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      Webinar: MC&A and safety in advanced reactors in focus

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      Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.

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Annual Meeting 2006 / Volume 94

  • ANS Officers

    Transactions | Volume 94 | Number 1 | June 2006 | Page iii

  • Meeting Officials, National Program Committee

    Transactions | Volume 94 | Number 1 | June 2006 | Page v

  • Contents

    Transactions | Volume 94 | Number 1 | June 2006 | Pages vii-xxiv

  • Cross-Reference of Divisions with Tracks

    Transactions | Volume 94 | Number 1 | June 2006 | Pages xvii-xviii

  • Author Index

    Transactions | Volume 94 | Number 1 | June 2006 | Pages xix-xxiii

  • ANS Plenary: A Brilliant Future: Nexus of Public Support in Nuclear Technology

    Transactions | Volume 94 | Number 1 | June 2006 | Page 3

    Track 1: A Brilliant Future: Nexus of Public Support in Nuclear Technology

  • ANS President's Special Session: The Hydrogen Economy: Partnering with Nuclear for the Future

    Transactions | Volume 94 | Number 1 | June 2006 | Page 4

    Track 1: A Brilliant Future: Nexus of Public Support in Nuclear Technology

  • Focus on Communications: Pronuclear Communications-Panel

    Transactions | Volume 94 | Number 1 | June 2006 | Page 5

    Track 1: A Brilliant Future: Nexus of Public Support in Nuclear Technology

  • Focus on Communications: Speaking with the Media-Panel

    Transactions | Volume 94 | Number 1 | June 2006 | Page 6

    Track 1: A Brilliant Future: Nexus of Public Support in Nuclear Technology

  • Training, Human Performance, and Workforce Development

    Transactions | Volume 94 | Number 1 | June 2006 | Page 9

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Vertical Evaluations - A Technique for Training Program Review

    Kent W. Hamlin (INPO)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 11

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Threaded Discussions a Powerful Asynchronous Online Learning Tool

    Lorraine F. NewHaven (Westinghouse)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 12-13

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Cultivating and Training the Next Generation of Startup Engineers

    Richard Holman, Leonard Bond, William Phoenix (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 14-15

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Virtual Reality for Improved Maintenance Training

    Angelia Sebok (Micro Analysis & Design), Terje Johnsen (OECD Halden Reactor Proj)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 16-17

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Maintenance and Dynamics of Human Factors

    Transactions | Volume 94 | Number 1 | June 2006 | Page 19

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Enabling Successful Supply Chain Team Performance to Achieve Outage Goals

    D. Kevin Cantrell (American Tank & Fabricating)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 21-23

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • SCWE Produces Bottom Line Results

    Victor Chrjapin (Washington Grp Int)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 24-25

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Worker Familiarity and Industrial Safety Outcomes

    Mark Friedmann (Day & Zimmermann NPS)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 26-27

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Continuous Improvement Processes and Impact on Maintenance

    Mark Friedmann, Chuck Lepisto (Day & Zimmermann NPS)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 28

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Low Power and Shutdown Operations: Observations, Trends, and Future Action-Panel

    Transactions | Volume 94 | Number 1 | June 2006 | Page 29

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • The Licensing Process and Status of Small Power Reactors-Panel

    Transactions | Volume 94 | Number 1 | June 2006 | Page 30

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Education and Training: General

    Transactions | Volume 94 | Number 1 | June 2006 | Page 31

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Distance Reactor Laboratory and Virtual Tours

    Eric Edwards, Adam Sweet, Michelle Blanchard, Robert Agasie (Univ of Wisconsin-Madison), Prashant Jain, Rizwan-uddin (Univ of Illinois)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 33-35

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Collaborative Decision-Making Strategies to Gain Public Support

    Mark D. Radonich (Cultural Effect Consulting)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 36-37

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Nuclear Power Engineering Education in India

    Prabhat Munshi (Indian Inst of Technol Kanpur)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 38-39

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • The Interactive Nucleus: Students Take Control of the Atom

    William Wabbersen (ANS-Savannah River Section)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 40-41

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • International Training Program: 3D S.UN.COP - Scaling, Uncertainty and 3D Thermal-Hydraulics/Neutron-Kinetics Coupled Codes Seminar

    A. Petruzzi, F. D'Auria (Univ of Pisa), T. Bajs (Univ of Zagreb), F. Reventos (UPC-SEN)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 42-44

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Tools and Concepts Related to the Human Machine Interface and Overall Safety Culture

    Transactions | Volume 94 | Number 1 | June 2006 | Page 45

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • An Analysis on Visual Search and EEG During Complex Diagnostic Tasks in NPPs

    Jun-Su Ha, Poong-Hyun Seong (KAIST)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 47-48

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • An Empirical Analysis of Human Performance and Nuclear Safety Culture

    Jeffrey C. Joe, Larry G. Blackwood (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 49-50

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Advances in HFE Methods and Their Implications for Regulatory Reviews

    John O'Hara (BNL), J. Persensky, Autumn Szabo (NRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 51-52

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • HUPESS: Human Performance Evaluation Support System

    Jun-Su Ha, Poong-Hyun Seong (KAIST)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 53-54

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Safety Culture Enhancements to the Reactor Oversight Process

    J. Persensky, I. Schoenfeld, V. Barnes (NRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 55

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Development of V&V Facility for the Advanced Man-Machine Interface of Advanced Power Reactor in Korea

    Man-Woo Kim, Jong-Jae Choi, Moon-Jae Choi, Il-Nam Choe (KOPEC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 56-57

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Addressing Aging and Obsolescence Issues with Printed Circuit Boards-Papers/Panel

    Transactions | Volume 94 | Number 1 | June 2006 | Page 59

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Considerations of Electronic Circuit Board Aging

    G. William Hannaman, C. Dan Wilkinson (SAIC), Joseph Naser (EPRI)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 61-62

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • An Approach to Printed Circuit Board Test Data Management

    John Beatty, W. Merle Horner, Nicola Arlia, James Kisic (Westinghouse)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 63-64

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Panel Discussion

    Transactions | Volume 94 | Number 1 | June 2006 | Page 65

    Track 2: Technology, Management, Operations, and New Construction of Nuclear Systems

  • Implementing the Spent Fuel Recycling Initiative: Fuel Cycle Requirements and the Role of the Nuclear Power Utilities-Panel

    Transactions | Volume 94 | Number 1 | June 2006 | Page 69

    Track 3: Nuclear Fuel Cycle Technologies

  • Nuclear Issues in South Asia-Panel

    Transactions | Volume 94 | Number 1 | June 2006 | Page 70

    Track 3: Nuclear Fuel Cycle Technologies

  • Fuel Cycle and Spent Fuel Modeling

    Transactions | Volume 94 | Number 1 | June 2006 | Page 71

    Track 3: Nuclear Fuel Cycle Technologies

  • The IAEA International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO): Study on Opportunities and Challenges of Large-Scale Nuclear Energy Development

    M. Khoroshev (IAEA), S. Subbotin (Russian Research Ctr)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 73-75

    Track 3: Nuclear Fuel Cycle Technologies

  • DESAE Integrated Computer Model for Global Analysis in INPRO Assessment Studies

    V. Tsibulskiy, S. Subbotin (Russian Research Ctr), M. Khoroshev (IAEA)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 76-77

    Track 3: Nuclear Fuel Cycle Technologies

  • Simulation Institute for Nuclear Energy Modeling and Analyses (SINEMA): Developing a GENIUS

    Christopher A. Juchau, Mary Lou Dunzik-Gougar (Idaho State Univ), Kemal Pasamehmetoglu (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 78-79

    Track 3: Nuclear Fuel Cycle Technologies

  • Pinhole Breaches in Spent Fuel Containers: Some Modeling Considerations

    Andrew M. Casella, Sudarshan K. Loyalka (Univ of Missouri-Columbia), Brady D. Hanson (PNNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 80-81

    Track 3: Nuclear Fuel Cycle Technologies

  • Canister Loading Monitor for CANDU Spent Fuel Dry Storage

    Sang-Yoon Lee, Michael C. Miller (LANL), Il-Jin Park, Gyung-Sik Min (Natl Nucl Mgt & Control Agency)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 82-83

    Track 3: Nuclear Fuel Cycle Technologies

  • Evaluation of Recent Transmutation Scenarios for Partitioning/Transmutation of Actinides and Heat-Generating Fission Products

    Transactions | Volume 94 | Number 1 | June 2006 | Page 85

    Track 3: Nuclear Fuel Cycle Technologies

  • Thorium-Based Fuels for Enhancing Plutonium Transmutation in Light Water Reactors

    Reuben T. Sorensen, Jeffrey C. Davis, John C. Lee (Univ of Michigan)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 87-88

    Track 3: Nuclear Fuel Cycle Technologies

  • Transmutation Characteristics of Thorium-Based Fuel in a Multiple-Tier Fuel Cycle

    Jeffrey C. Davis, Reuben T. Sorensen, John C. Lee, Ronald F. Fleming (Univ of Michigan)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 89-90

    Track 3: Nuclear Fuel Cycle Technologies

  • Transmutation of Americium and Curium Using Z-Pinch Fusion

    B. B. Cipiti (SNL), P. P. H. Wilson (Univ of Wisconsin-Madison)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 91-92

    Track 3: Nuclear Fuel Cycle Technologies

  • Potential of Minor Actinides to Enhance VHTR Performance Characteristics

    Pavel V. Tsvetkov, Ayodeji B. Alajo (Texas A&M)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 93-94

    Track 3: Nuclear Fuel Cycle Technologies

  • Comparison of Proliferation Resistance of Once-Through, MOX, and DUPIC Fuel Cycles

    Jun Li, Man-Sung Yim, David McNelis (NCSU)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 95-96

    Track 3: Nuclear Fuel Cycle Technologies

  • Conceptual Design of Accelerator Driven Fast/Thermal Spectrum Subcritical System

    Xiaofeng Jiang, Hao Huang (Shanghai Jiao Tong Univ), Z. S. Xie (Xi'an Jiaotong Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 97-98

    Track 3: Nuclear Fuel Cycle Technologies

  • Advanced Head-End Improvements for Processing Spent Nuclear Fuels

    Transactions | Volume 94 | Number 1 | June 2006 | Page 99

    Track 3: Nuclear Fuel Cycle Technologies

  • Advanced Head-End Processing of Spent Fuel: A Progress Report on a Pyrochemical Front-End

    Guillermo D. Del Cul, Rodney D. Hunt, Barry B. Spencer, Emory D. Collins (ORNL), Brian Westphal, Karen Howden (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 101-102

    Track 3: Nuclear Fuel Cycle Technologies

  • Recent Progress in the DEOX Process

    B. R. Westphal, K. J. Bateman, R. P. Lind, D. L. Wahlquist (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 103

    Track 3: Nuclear Fuel Cycle Technologies

  • Processing of Spent TRISO-Coated Reactor Fuels: Milling of Fuel to Support a Grind-Leach Process

    Barry B. Spencer, Guillermo D. Del Cul, Catherine H. Mattus, Emory D. Collins (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 104-105

    Track 3: Nuclear Fuel Cycle Technologies

  • Electrochemical Dissolution of Spent EBR-II Driver Fuel in Molten Salt Electrolyte

    S. X. Li, D. Vaden, R. W. Benedict, K. M. Goff (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 106-107

    Track 3: Nuclear Fuel Cycle Technologies

  • CFD Study of Turbulence in an Annular Centrifugal Contactor

    Kent E. Wardle, Todd R. Allen, Ross Swaney (Univ of Wisconsin-Madison)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 108-109

    Track 3: Nuclear Fuel Cycle Technologies

  • Environmental Impact Assessment for the DFDF Under a Normal Operation

    Ho-Hee Lee, Jang-Jin Park, Jin-Myeong Shin, Ki-ho Kim, In-Ha Jung, Myung-Seung Yang (KAERI)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 110

    Track 3: Nuclear Fuel Cycle Technologies

  • Emerging Topics in Nuclear Installations Safety

    Transactions | Volume 94 | Number 1 | June 2006 | Page 113

    Track 4: Nuclear and Criticality Safety Technologies

  • The Boron Concentration Measurement: A New Concept to Follow the Boron 10 Depletion in PWRs

    Jean-Pierre Burel, Patrick Pirat (Data Sys & Sol), Cécile Masson, Jean-Pierre Mégard (EDF-SEPTEN), Martial Berger (EDF-CNEN)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 115

    Track 4: Nuclear and Criticality Safety Technologies

  • Time-Limited Aging Analysis of BWR Reactor Vessel Components in License Renewal

    Linh Tran, Robert Hsu, Ken Chang (NRC), Amy Hull (ANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 116-117

    Track 4: Nuclear and Criticality Safety Technologies

  • Fault Tolerant Reactor Protection System Technology

    J. Troy Martel (Invensys-Triconex), Jadu G. Das (Washington Grp Int)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 118-120

    Track 4: Nuclear and Criticality Safety Technologies

  • Nuclear Criticality Safety Related to TA-18 Relocation

    Transactions | Volume 94 | Number 1 | June 2006 | Page 121

    Track 4: Nuclear and Criticality Safety Technologies

  • Disassembly of the Godiva Critical Assembly Machine

    Joetta M. Goda (LANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 123-124

    Track 4: Nuclear and Criticality Safety Technologies

  • Criticality Safety for Godiva Pre-Disassembly Operations

    John A. Miller, James S. Baker (LANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 125-126

    Track 4: Nuclear and Criticality Safety Technologies

  • Criticality Safety Above a Multiplication of 20 (The Godiva Disassembly)

    John A. Miller, James S. Baker (LANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 127-128

    Track 4: Nuclear and Criticality Safety Technologies

  • Clad Embrittlement Criterion for Revised 10 CFR 50.46 Design Basis Accidents

    Transactions | Volume 94 | Number 1 | June 2006 | Page 129

    Track 4: Nuclear and Criticality Safety Technologies

  • Technical Basis for Revision of LOCA Embrittlement Criteria

    Ralph O. Meyer (NRC), Michael C. Billone (ANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 131-132

    Track 4: Nuclear and Criticality Safety Technologies

  • Impact of Pre-Transient Hydrogen and Cooling Rate on the Post-LOCA Cladding Ductility - Recent CEA-EDF-Framatome Test Results

    Nicolas Waeckel (EDF-SEPTEN), Jean-Paul Mardon (AREVA Framatome ANP), Jean-Christophe Brachet, Valérie Maillot (CEA-Saclay)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 133

    Track 4: Nuclear and Criticality Safety Technologies

  • Effect of Irradiation on Post-LOCA Cladding Behavior

    R. O. Montgomery, J. M. Alvis (ANATECH), R. Yang, O. Ozer (EPRI)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 134-135

    Track 4: Nuclear and Criticality Safety Technologies

  • Prototypical Experiments on Air Oxidation of Zircaloy Cladding at High Temperatures

    Martin Steinbrück (FZK)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 136-137

    Track 4: Nuclear and Criticality Safety Technologies

  • Semi-Mechanistic Approach for Evaluation of Zr Oxidation Experiments

    G. Schanz (FZK)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 138-139

    Track 4: Nuclear and Criticality Safety Technologies

  • A QUENCH Experiment Including an Air Ingress Phase Prior to Flooding

    L. Sepold (FZK), Z. Hózer (KFKI), G. Schanz, U. Stegmaier, M. Steinbrück, J. Stuckert (FZK)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 140-141

    Track 4: Nuclear and Criticality Safety Technologies

  • Data, Analysis, and Operations for Nuclear Criticality Safety

    Transactions | Volume 94 | Number 1 | June 2006 | Page 143

    Track 4: Nuclear and Criticality Safety Technologies

  • Criticality Potential of Waste Packages Containing DOE SNF Affected by Igneous Intrusion

    Darby S. Kimball (Bechtel Natl), Charlotta E. Sanders (Bechtel SAIC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 145-146

    Track 4: Nuclear and Criticality Safety Technologies

  • HTC Experimental Programme

    F. Fernex, E. Letang (IRSN), P. Fouillaud (CEA), J. F. Thro (AREVA/COGEMA)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 147-149

    Track 4: Nuclear and Criticality Safety Technologies

  • Calculation of Critical Experiments Involving U(37)O2F2 Solution

    K. L. Goluoglu, A. W. Krass (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 150-151

    Track 4: Nuclear and Criticality Safety Technologies

  • CSLEPs and Quick Screens: Answers to Expedited Processing of Legacy Criticality Safety Limits and Evaluations

    David G. Erickson, Hans Toffer (Fluor Hanford), Robert E. Wilson (DOE)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 152-153

    Track 4: Nuclear and Criticality Safety Technologies

  • Comparison Between GEMER and KENO V.a on Heterogeneous System Simulation

    Qi Ao, Lon E. Paulson (GNF)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 154-155

    Track 4: Nuclear and Criticality Safety Technologies

  • Alternative Source Term Applications to Improve Power Reactor Safety Analysis-Papers/Panel

    Transactions | Volume 94 | Number 1 | June 2006 | Page 157

    Track 4: Nuclear and Criticality Safety Technologies

  • Implementation of Reactor Accident Alternative Source Term

    Jay Y. Lee (NRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 159-160

    Track 4: Nuclear and Criticality Safety Technologies

  • Alternative Source Term Application for McGuire Nuclear Station

    Franklin J. Verbos, Jr., Melissa S. Moran (Duke Energy)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 161-162

    Track 4: Nuclear and Criticality Safety Technologies

  • Important Isotopes to Post-Accident BWR Shielding Analyses with the Alternative Source Term

    Gregory E. Broadbent (Entergy)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 163-164

    Track 4: Nuclear and Criticality Safety Technologies

  • MELCOR 1.8.5 Benchmark for Alternative Source Term Technical Basis

    Scott G. Ashbaugh, Randall O. Gauntt (SNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 165-166

    Track 4: Nuclear and Criticality Safety Technologies

  • Panel Discussion

    Transactions | Volume 94 | Number 1 | June 2006 | Page 167

    Track 4: Nuclear and Criticality Safety Technologies

  • Integrating New Technology and Innovation Within Nuclear Criticality Safety

    Transactions | Volume 94 | Number 1 | June 2006 | Page 169

    Track 4: Nuclear and Criticality Safety Technologies

  • The Application of Recent Developments in Distributed Parametric Searches for Criticality Assessment Using the CodeMore Program

    Paul Hulse, David Dewar (British Nucl Grp)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 171-172

    Track 4: Nuclear and Criticality Safety Technologies

  • Economic Impact of Criticality Safety Innovation at GNF-A

    Lon E. Paulson (GNF)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 173-174

    Track 4: Nuclear and Criticality Safety Technologies

  • Probabilistic Risk Assessment

    Transactions | Volume 94 | Number 1 | June 2006 | Page 175

    Track 4: Nuclear and Criticality Safety Technologies

  • Treatment of Uncertainties in Modeling the Failure of Major RCS Components in Severe Accident Analysis

    Aram Hakobyan, Richard Denning, Tunc Aldemir (Ohio State), Sean Dunagan, David Kunsman (SNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 177-179

    Track 4: Nuclear and Criticality Safety Technologies

  • Quantification of Minimal Cutset Truncation Errors in Fault Tree Analysis

    Jong Soo Choi (KINS), Nam Zin Cho (KAIST)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 180-182

    Track 4: Nuclear and Criticality Safety Technologies

  • A Graphical Tool for the Analysis of Event Trees

    Kyle Metzroth, Umit Catalyurek, Tunc Aldemir (Ohio State), Sean Dunagan, Dave Kunsman (SNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 183-185

    Track 4: Nuclear and Criticality Safety Technologies

  • Software Quality Assurance for Analytical Codes

    Steven A. Arndt (NRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 186-188

    Track 4: Nuclear and Criticality Safety Technologies

  • SMV Model-Based Safety Analysis of Software Requirements

    Kwang Yong Koh, Poong Hyun Seong (KAIST)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 189-190

    Track 4: Nuclear and Criticality Safety Technologies

  • Transnational Nuclear Liability: Issues and Developments

    Blake J. Nelson (Akin, Gump, Strauss, Hauer & Feld)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 191-192

    Track 4: Nuclear and Criticality Safety Technologies

  • Mathematical Fire Modeling and Its Application to Nuclear Power Plants

    Transactions | Volume 94 | Number 1 | June 2006 | Page 193

    Track 4: Nuclear and Criticality Safety Technologies

  • Use of Fire Models in Regulatory Decisions

    Naeem Iqbal, Sunil Weerakkody (NRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 195-197

    Track 4: Nuclear and Criticality Safety Technologies

  • Validating Fire Models for Nuclear Power Plant Applications

    Kevin McGrattan, Richard Peacock (NIST)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 198-199

    Track 4: Nuclear and Criticality Safety Technologies

  • Experimental Uncertainty in the Validation of Fire Models for Nuclear Power Plant Applications

    Anthony Hamins (NIST)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 200-201

    Track 4: Nuclear and Criticality Safety Technologies

  • Predicting Fire-Induced Core Damage Frequencies - A Simple "Sanity Check"

    Raymond H. V. Gallucci (NRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 202-204

    Track 4: Nuclear and Criticality Safety Technologies

  • Consensus Standards for the Evaluation of Fire Models for Nuclear Power Plant Applications

    Richard Peacock (NIST)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 205-206

    Track 4: Nuclear and Criticality Safety Technologies

  • Current Fire Modeling Activities at U.S. NRC Office of Nuclear Regulatory Research

    Jason Dreisbach (NRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 207-208

    Track 4: Nuclear and Criticality Safety Technologies

  • Fire Modeling Activities at Electric Power Research Institute

    Robert P. Kassawara (EPRI), Bijan Najafi, Francisco Joglar (SAIC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 209-211

    Track 4: Nuclear and Criticality Safety Technologies

  • Tutorial on the Proposed ANSI/ANS 8.24 Standard: Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations

    Transactions | Volume 94 | Number 1 | June 2006 | Page 212

    Track 4: Nuclear and Criticality Safety Technologies

  • Nuclear Installations Safety: General

    Transactions | Volume 94 | Number 1 | June 2006 | Page 213

    Track 4: Nuclear and Criticality Safety Technologies

  • Nuclear Power Plant Qualified Halogen Free Cables

    Lukas von Laue, Tristan Cerosky (Nexans)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 215

    Track 4: Nuclear and Criticality Safety Technologies

  • Defense-in-Depth as an Analogue of Fault Tolerance

    N. Prasad Kadambi (NRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 216-217

    Track 4: Nuclear and Criticality Safety Technologies

  • Computerized Severe Accident Management Operator Support "SAMOS"

    G. Vayssier (NSC Netherlands), P. Fantoni (IFE Halden), L. Borondo (Iberinco), R. Martinez (Tecnatom), B. Krajnc (NEK), N. Dessars (Westinghouse Europe), J. Husarcek (UJD), J. Bahna (VUJE)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 218

    Track 4: Nuclear and Criticality Safety Technologies

  • Nuclear Facility Security: How Much is Enough?

    Matias F. Travieso-Diaz, Paul A. Gaukler (Pillsbury Winthrop Shaw Pittman)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 219-220

    Track 4: Nuclear and Criticality Safety Technologies

  • Key Aspects of RBMK Deterministic Safety Technology

    F. D'Auria (Univ of Pisa), S. Soloviev (NIKIET)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 221-222

    Track 4: Nuclear and Criticality Safety Technologies

  • Preliminary Study on the Development of Chinese PWR SAMG

    Kun Zhang, Xue-Wu Cao (Shanghai Jiao Tong Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 223-224

    Track 4: Nuclear and Criticality Safety Technologies

  • Nuclear Criticality Safety Standards-Forum

    Transactions | Volume 94 | Number 1 | June 2006 | Page 225

    Track 4: Nuclear and Criticality Safety Technologies

  • Environmental Monitoring and Modeling at Nuclear Facilities

    Transactions | Volume 94 | Number 1 | June 2006 | Page 229

    Track 5: Environmental Science and Technologies

  • Transfer Factors for Small Mammals Collected from a 137Cs Contaminated Reservoir

    Michael H. Paller, G. Timothy Jannik, Lynn D. Wike (SRNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 231-232

    Track 5: Environmental Science and Technologies

  • Methodology for Modeling 2-D Groundwater Motion in a Geographic Information System (GIS)

    James S. Bollinger (SRNL), John K. Reed (Geological Consultant)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 233-235

    Track 5: Environmental Science and Technologies

  • Tritium Transport in South Atlantic Coastal Waters

    Alfred J. Garrett, James S. Bollinger, Larry D. Koffman, David W. Hayes (SRNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 236-238

    Track 5: Environmental Science and Technologies

  • Dynamic Subsidence Modeling Studies of Low-Level Waste in Nevada

    George Danko, Tyler Cluff (Univ of Nevada, Reno)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 239-240

    Track 5: Environmental Science and Technologies

  • Long-Term Sustainability of Nuclear Fission Energy - I-Panel

    Transactions | Volume 94 | Number 1 | June 2006 | Page 241

    Track 5: Environmental Science and Technologies

  • Long-Term Sustainability of Nuclear Fission Energy - II-Paper/Panel

    Transactions | Volume 94 | Number 1 | June 2006 | Page 243

    Track 5: Environmental Science and Technologies

  • Why We Should Use Nuclear Energy for Transportation

    Robert E. Uhrig (Univ of Tennessee)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 245-246

    Track 5: Environmental Science and Technologies

  • Panel Discussion

    Transactions | Volume 94 | Number 1 | June 2006 | Page 247

    Track 5: Environmental Science and Technologies

  • Environmental Aspects of New Site Selection- Papers/Panel

    Transactions | Volume 94 | Number 1 | June 2006 | Page 249

    Track 5: Environmental Science and Technologies

  • Reactor Siting in Southeastern Coastal Plain Settings: Hydrostratigraphy and Lithostratigraphy

    Douglas Wyatt (Washington SMS), Randolph Cumbest (Washington SRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 251-252

    Track 5: Environmental Science and Technologies

  • Site Selection and Environmental Requirements for Commercial Nuclear Power Plants Under 10 CFR 52

    Kevin Bryson, John Downing (Shaw Grp)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 253-254

    Track 5: Environmental Science and Technologies

  • Panel Discussion

    Transactions | Volume 94 | Number 1 | June 2006 | Page 255

    Track 5: Environmental Science and Technologies

  • Environmental Sciences: General

    Transactions | Volume 94 | Number 1 | June 2006 | Page 257

    Track 5: Environmental Science and Technologies

  • High Resolution Hand-Held Gamma Spectrometer

    Sanjoy Mukhopadhyay (Bechtel Nevada)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 259-261

    Track 5: Environmental Science and Technologies

  • Adiabatic Heat of Hydration Calorimetric Measurements for Reference Saltstone Waste

    James S. Bollinger (SRNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 262-264

    Track 5: Environmental Science and Technologies

  • Statistical Analysis of Fissile Mass

    N. J. Devaser, J. A. March-Leuba, B. R. Upadhyaya (Univ of Tennessee)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 265-266

    Track 5: Environmental Science and Technologies

  • Turning Effluent Processing Plants to Remediation Leaders

    Ian D. MacPherson, Iain A. Irving (British Nucl Grp)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 267-268

    Track 5: Environmental Science and Technologies

  • Development of INPRO Methodology in the Area of Environment

    Masanao Moriwaki (IAEA), Roberto Dones (Paul Scherrer Inst), Sergey Fesenko (IAEA), W. Eberhard Falck (Consultant), Akira Omoto (IAEA)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 269-271

    Track 5: Environmental Science and Technologies

  • Decommissioning, Decontamination, and Reutilization Technological Advancements

    Transactions | Volume 94 | Number 1 | June 2006 | Page 275

    Track 6: Waste Management and Decommissioning Technologies

  • Diamond Shaving of Contaminated Concrete Surfaces

    Robert M. Hulick (Bluegrass Concrete Cutting)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 277-278

    Track 6: Waste Management and Decommissioning Technologies

  • Proven Advancements and Advantages of Subsurface Sampling and Characterization of Nuclear Facilities Being Decommissioned

    G. Charters, S. Aggarwal (NMNT)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 279

    Track 6: Waste Management and Decommissioning Technologies

  • Decontamination of Large Metal Objects

    Raymond Durante (INTEK Technol)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 280

    Track 6: Waste Management and Decommissioning Technologies

  • Regulatory Issues in Decommissioning

    Transactions | Volume 94 | Number 1 | June 2006 | Page 281

    Track 6: Waste Management and Decommissioning Technologies

  • An Overview of the U.S. Nuclear Regulatory Commission Role and Activities Related to Incidental Waste Determinations

    Larry Camper, Anna H. Bradford, A. Christianne Ridge, David W. Esh, Scott Flanders, Rateb (Boby) Abu-Eid (NRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 283-284

    Track 6: Waste Management and Decommissioning Technologies

  • Status of NRC Decommissioning Program Rulemaking and Decommissioning Guidance

    J. Shepherd, R. L. Johnson, T. Fredrichs, D. Schmidt, K. Banovac (NRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 285-286

    Track 6: Waste Management and Decommissioning Technologies

  • Update on the Implementation of the Memorandum of Understanding Between the United States Nuclear Regulatory Commission and the United States Environmental Protection Agency on Decommissioning Sites

    Rafael L. Rodriguez, Derek A. Widmayer (NRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 287

    Track 6: Waste Management and Decommissioning Technologies

  • It Is Not Just About the LTP - Integrating Regulatory Programs and Securing Approvals to Support Site Closure at Yankee Rowe

    J. A. Hamilton (CLF Ventures), J. R. Lynch (Yankee Atomic Electric)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 288

    Track 6: Waste Management and Decommissioning Technologies

  • Complex Dose Modeling Analysis for Decommissioning - A Case Study

    Rateb (Boby) Abu Eid, Mark Thaggard (NRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 289-291

    Track 6: Waste Management and Decommissioning Technologies

  • Best of Decommissioning, Decontamination, and Reutilization 2005

    Transactions | Volume 94 | Number 1 | June 2006 | Page 293

    Track 6: Waste Management and Decommissioning Technologies

  • Decontamination and Recycling of Radioactive Material from Retired Components

    Chris Wood, Sean Bushart (EPRI), David Bradbury, George Elder (Bradtec Decon Technol)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 295-296

    Track 6: Waste Management and Decommissioning Technologies

  • Addressing Environmental Issues During D&D of a Former Fuel Cycle Facility

    Elaine Hammick (ABB)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 297-298

    Track 6: Waste Management and Decommissioning Technologies

  • Orientations for the Final Decommissioning of the RAPSODIE Fast Breeder Reactor

    Jean Fontaine, Jean-Marc Goubot, Xavier Berson, Michel Soucille (CEA)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 299-300

    Track 6: Waste Management and Decommissioning Technologies

  • The Reform of Near Term and Lifecycle Planning for the Sellafield Group of Sites and the Associated Reorganisation of the UK Nuclear Industry

    David Reed (British Nucl Grp)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 301

    Track 6: Waste Management and Decommissioning Technologies

  • Efficient Treatment of Bulk Materials from D&D

    J. J. Shonka, M. R. Marcial, J. L. Kelley (Shonka Research Assoc)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 302-303

    Track 6: Waste Management and Decommissioning Technologies

  • Stakeholder Outreach as a Project Risk Management Tool in Support of Site Closure - Lessons from Connecticut Yankee and Yankee Rowe

    J. A. Hamilton (CLF Ventures), J. R. Lynch (Yankee Atomic Electric)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 304

    Track 6: Waste Management and Decommissioning Technologies

  • Transport and Storage of Commercial Spent Nuclear Fuel

    Transactions | Volume 94 | Number 1 | June 2006 | Page 305

    Track 6: Waste Management and Decommissioning Technologies

  • New Methods for Applying Fuel-Depletion Code Bias in Burnup-Credit Criticality Analyses

    James E. Hopf (BNG Fuel Sol)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 307-308

    Track 6: Waste Management and Decommissioning Technologies

  • U.S. Department of Energy Cleanup and International Program Update

    Transactions | Volume 94 | Number 1 | June 2006 | Page 309

    Track 6: Waste Management and Decommissioning Technologies

  • DOE and Fluor Hanford Continue to Make Progress on Cleanup of Hanford

    Michael B. Lackey (Fluor Hanford)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 311

    Track 6: Waste Management and Decommissioning Technologies

  • Source Term Remediation and Demolition Strategy for the Hanford K-Area Spent Fuel Basins

    Glen B. Chronister, Peter M. Knollmeyer (Fluor Hanford)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 312-313

    Track 6: Waste Management and Decommissioning Technologies

  • Retrieval and Transfer of Decladding Process Sludge at the Marcoule Site (France)

    Eric Tchemitcheff (COGEMA-Richland), Marcel Delrieux (SGN, AREVA), Jean Luc Lecollier (Technicatome, AREVA), Grégoire Piot (SGN/HRB, AREVA), Hervé Comole (COGEMA)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 314

    Track 6: Waste Management and Decommissioning Technologies

  • Clean-Up and Dismantling Operations at the Marcoule Site

    Jean Fontaine, Michèle Tallec, Gérard Calmes, Jean-Louis Garcia (CEA)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 315-316

    Track 6: Waste Management and Decommissioning Technologies

  • Decommissioning Operations at French INB 52 ATUE Facility

    E. Gouhier, D. Seisson (CEA)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 317-318

    Track 6: Waste Management and Decommissioning Technologies

  • Decommissioning Operations at French INB41 HARMONIE Reactor

    Eric Gouhier, Sandra Paradis (CEA)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 319-320

    Track 6: Waste Management and Decommissioning Technologies

  • Decommissioning, Decontamination, and Reutilization Hot Topics and Emerging Issues-Papers/Panel

    Transactions | Volume 94 | Number 1 | June 2006 | Page 321

    Track 6: Waste Management and Decommissioning Technologies

  • Design of Nuclear Power Plants to Facilitate Decommissioning

    Richard H. Meservey (Battelle Energy Alliance)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 323

    Track 6: Waste Management and Decommissioning Technologies

  • DD&R Issues if Nuclear Plants Are Sited Underground

    Wes Myers, Ned Elkins (LANL), Jay Kunze, James Mahar (Idaho State Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 324-325

    Track 6: Waste Management and Decommissioning Technologies

  • Panel Discussion

    Transactions | Volume 94 | Number 1 | June 2006 | Page 326

    Track 6: Waste Management and Decommissioning Technologies

  • High-Level Waste Management

    Transactions | Volume 94 | Number 1 | June 2006 | Page 327

    Track 6: Waste Management and Decommissioning Technologies

  • Thermal Loading Perspective on U.S. Nuclear Waste Repository Needs

    Mike P. Stahala, Man-Sung Yim (NCSU), David McNelis (Univ of North Carolina at Chapel Hill)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 329-330

    Track 6: Waste Management and Decommissioning Technologies

  • The Influence of Fuel Cycle and Spent Fuel Characteristics on Repository Heat Loads

    Jeff Preston, Jeff Clark, Gary Sweder, F. R. Mynatt, L. F. Miller (Univ of Tennessee)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 331-332

    Track 6: Waste Management and Decommissioning Technologies

  • Design of a Radioactive Waste Immobilisation Plant: An Engineering Challenge

    Alamin Hossain, Dylan Buckley (ANSTO)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 333-334

    Track 6: Waste Management and Decommissioning Technologies

  • State, Tribal, and Federal Interactions Relative to Spent Nuclear Fuel Transportation - Transportation Emergency Preparedness Program

    Ella McNeil (DOE)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 335-336

    Track 6: Waste Management and Decommissioning Technologies

  • State, Tribal, and Federal Interactions Relative to Spent Nuclear Fuel Transportation

    Corinne Macaluso (DOE), Elizabeth Helvey (Bechtel SAIC), Julie Offner (Booz Allen Hamilton)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 337-338

    Track 6: Waste Management and Decommissioning Technologies

  • Small-Angle X-Ray Scattering Measurements of Helium Bubble Formation in Borosilicate Glass

    Brent J. Heuser, Alexander Terekhov, Maria Okuniewski (Univ of Illinois)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 339-340

    Track 6: Waste Management and Decommissioning Technologies

  • Current Topics for Reactor Engineers-Panel

    Transactions | Volume 94 | Number 1 | June 2006 | Page 343

    Track 7: Nuclear Science and Engineeting

  • Radiation Protection and Shielding: General

    Transactions | Volume 94 | Number 1 | June 2006 | Page 345

    Track 7: Nuclear Science and Engineeting

  • Response Functions of Semiconductor Slow Neutron Detectors for Spectrometry

    Qi Lou (Univ of Illinois), Raymond T. Klann, Patrick M. DeLurgio (ANL), James F. Stubbins (Univ of Illinois)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 347-348

    Track 7: Nuclear Science and Engineeting

  • Dose to Salivary Glands and Extrathoracic Airways for External Photon

    Choonsik Lee, Choonik Lee, Wesley Bolch (Univ of Florida)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 349-350

    Track 7: Nuclear Science and Engineeting

  • Accurate Mathematical Determination of the Well-Type Detector's Efficiencies

    M. I. Abbas (Alexandria Univ), S. S. Nafee (Alexandria Univ, NIST), L. R. Karam (NIST), Y. S. Selim (Alexandria Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 351-352

    Track 7: Nuclear Science and Engineeting

  • Compactible Results for Capsular Cylindrical Shielding Using Analytical Methods and MCNP

    E. V. Steinfelds, S. K. Loyalka, M. A. Prelas (Univ of Missouri-Columbia)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 353-355

    Track 7: Nuclear Science and Engineeting

  • Current Issues in Computational Methods-Roundtable

    Transactions | Volume 94 | Number 1 | June 2006 | Page 356

    Track 7: Nuclear Science and Engineeting

  • Thermal Hydraulics in Generation IV Systems

    Transactions | Volume 94 | Number 1 | June 2006 | Page 357

    Track 7: Nuclear Science and Engineeting

  • Assessment of PBMR Analysis Using the MELCOR Code

    K. J. Hogan, K. Vierow, S. T. Revankar (Purdue Univ), R. K. Cole, Jr., R. O. Gauntt, S. Rodriguez (SNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 359-360

    Track 7: Nuclear Science and Engineeting

  • Restructuring RELAP5-3D for Next Generation Nuclear Plant Analysis

    Donna Post Guillen, George L. Mesina (INL), Joshua M. Hykes (Penn State)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 361-362

    Track 7: Nuclear Science and Engineeting

  • RELAP5-3D Model Validation and Benchmark Exercises for Advanced Gas Cooled Reactor Application

    Eugene Moore, Y. A. Hassan (Texas A&M)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 363-366

    Track 7: Nuclear Science and Engineeting

  • Experimental Measurement of Flow Phenomena in a VHTR Lower Plenum Model

    Hugh M. McIlroy, Jr., Donald M. McEligot, Glenn C. McCreery, Keith G. Condie, Robert J. Pink (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 367-368

    Track 7: Nuclear Science and Engineeting

  • Investigation of Material Relocation in TIB of CEFR

    Z. Wang, X. W. Cao (Shanghai Jiao Tong Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 369-370

    Track 7: Nuclear Science and Engineeting

  • Performance of a Printed Circuit Heat Exchanger in an Air Open Test Loop

    Sung Chu Song, Hee Cheon No (KAIST), Cheol Shin Lee (KOPEC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 371-372

    Track 7: Nuclear Science and Engineeting

  • Reactor Physics: General

    Transactions | Volume 94 | Number 1 | June 2006 | Page 373

    Track 7: Nuclear Science and Engineeting

  • Analysis of the Unmoderated Zeus Critical Experiment

    Russell D. Mosteller, Peter J. Jaegers (LANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 375-377

    Track 7: Nuclear Science and Engineeting

  • Homogenization of Research Reactor Fuel for Discrete Ordinates Transport Calculations

    Ryanne Kennedy, Tunc Aldemir (Ohio State)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 378-380

    Track 7: Nuclear Science and Engineeting

  • IRIS Full MOX Core Evaluation

    F. Franceschini, B. Petrovic (Westinghouse)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 381-382

    Track 7: Nuclear Science and Engineeting

  • Physical Similarity in the Reactivity-Equivalent Physical Transformation

    Yonghee Kim, Jae Man Noh (KAERI)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 383-384

    Track 7: Nuclear Science and Engineeting

  • Analysis of Decay Heat Measurements for BWR Fuel Assemblies

    Germina Ilas, Ian C. Gauld (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 385-387

    Track 7: Nuclear Science and Engineeting

  • Optimization of a Refueling Simulation for a CANDU Reactor by Using an Evolutionary Algorithm

    Quang Binh Do (Vietnam Atomic Energy Agency), Gyuhong Roh, Hangbok Choi (KAERI)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 388-389

    Track 7: Nuclear Science and Engineeting

  • A Hybrid Optimization Method for Loading Pattern Search

    Tao Wang (Shanghai Jiao Tong Univ), Zhongsheng Xie (Xi'an Jiaotong Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 390-391

    Track 7: Nuclear Science and Engineeting

  • Research by U.S. Department of Energy-Sponsored Students

    Transactions | Volume 94 | Number 1 | June 2006 | Page 393

    Track 7: Nuclear Science and Engineeting

  • Evaluation of a Simple System for Radiation Treatment Positioning

    William H. Miller, Amenyedu Adovor, Andrew Andreassen, Yu-Wen Chang, Nithin Polasani (Univ of Missouri-Columbia)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 395-398

    Track 7: Nuclear Science and Engineeting

  • MCNP Study of Concrete Activation Due to Beam Port Penetration of the Illinois TRIGA Reactor

    J'Tia Patrice Taylor, Brent J. Heuser (Univ of Illinois)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 399-400

    Track 7: Nuclear Science and Engineeting

  • Spallation Target Moderators for the Los Alamos Neutron Science Center

    Daniel P. Speaker (NCSU), Erich A. Schneider (Univ of Texas at Austin)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 401-402

    Track 7: Nuclear Science and Engineeting

  • Analysis of the Pebble-Bed VHTR Spectrum Shifting Capabilities for Advanced Fuel Cycles

    Pavel V. Tsvetkov, Megan L. Pritchard, David E. Ames II, Ayodeji B. Alajo (Texas A&M)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 403-404

    Track 7: Nuclear Science and Engineeting

  • Computational Medical Physics Benchmarks

    Transactions | Volume 94 | Number 1 | June 2006 | Page 405

    Track 7: Nuclear Science and Engineeting

  • Experimental Transport Benchmarks for Physical Dosimetry to Support Development of Fast-Neutron Therapy with Neutron Capture Augmentation

    D. W. Nigg, J. K. Hartwell, J. R. Venhuizen, C. A. Wemple (INL), R. Risler, G. E. Laramore (Univ of Washington), W. Sauerwein, G. Hüdepohl (Univ of Essen), A. Lennox (NIU Inst for Neutron Therapy, FNAL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 407-409

    Track 7: Nuclear Science and Engineeting

  • Isodose Mapping Using Coincidence Measurement of Annihilation Photons

    Amol Patil (Univ of Missouri-Rolla), Dramane Konate (Univ of Cincinnati), Thomas P. Goter, Shoaib Usman (Univ of Missouri-Rolla)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 410-411

    Track 7: Nuclear Science and Engineeting

  • Determination of Optimum Source Position in Radiotherapy Inverse Planning Using MCNP-4C

    Fouad A. Abolaban, Youssef A. Shatilla (King Abdulaziz Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 412-415

    Track 7: Nuclear Science and Engineeting

  • Thermal Hydraulics: General - I

    Transactions | Volume 94 | Number 1 | June 2006 | Page 417

    Track 7: Nuclear Science and Engineeting

  • Thermal-Hydraulic Analysis of Electron Targets for Neutron Generation in a Subcritical System

    Tanju Sofu, Yousry Gohar, David W. Pointer (ANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 419

    Track 7: Nuclear Science and Engineeting

  • Vortex Identification in a Channel Flow with Microbubbles

    C. del C. Gutierrez-Torres (IPN), Y. A. Hassan (Texas A&M), J. A. Jiménez-Bernal (IPN)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 420-421

    Track 7: Nuclear Science and Engineeting

  • Coherent Structure Evolution Due to Microbubbles Injection in Turbulent Flow

    Ling Zhen, Yassin A. Hassan (Texas A&M)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 422-423

    Track 7: Nuclear Science and Engineeting

  • Simulation of Molecular Phase Localized Deposition Patterns in Lung Bifurcations

    V. R. Gutti, R. V. Tompson, S. K. Loyalka (Univ of Missouri-Columbia)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 424-425

    Track 7: Nuclear Science and Engineeting

  • Effect of LES Subgrid Scale Model on Flow Through Bends

    V. Vishnu Karthik, Y. A. Hassan, A. R. McFarland (Texas A&M)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 426-427

    Track 7: Nuclear Science and Engineeting

  • Computational Fluid Dynamic Simulation of Liquid Inside a Cyclone

    Shishan Hu, A. R. McFarland, Y. A. Hassan (Texas A&M)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 428-429

    Track 7: Nuclear Science and Engineeting

  • Thermal Hydraulics: General - II

    Transactions | Volume 94 | Number 1 | June 2006 | Page 431

    Track 7: Nuclear Science and Engineeting

  • Natural Convection Heat Transfer in an Internally Heated Semicircular Water Pool

    Seung D. Lee, Jong G. Lee, Kune Y. Suh (Seoul Natl Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 433-434

    Track 7: Nuclear Science and Engineeting

  • An Experiment Study on Thermo Hydraulic Characteristics Under FCI Conditions

    Xiaoyan Li, Yanhua Yang, Jijun Xu (Shanghai Jiao Tong Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 435-436

    Track 7: Nuclear Science and Engineeting

  • Strategy for Experimental Studies on Safety and Efficiency of New Design NPPs with VVER

    Vladimir Blinkov, Oleg Melikhov (Electrogorsk Research and Eng Ctr on NPP Safety)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 437-438

    Track 7: Nuclear Science and Engineeting

  • Improved Model of Heat Transfer in Porous Crud Layers

    Ling Zou, Barclay G. Jones (Univ of Illinois)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 439-440

    Track 7: Nuclear Science and Engineeting

  • Two-Phase Flow Structures Under Simulated Microgravity Condition

    S. Vasavada (Purdue Univ), X. Sun (Ohio State), M. Ishii (Purdue Univ), W. Duval (NASA Glenn Research Ctr)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 441-443

    Track 7: Nuclear Science and Engineeting

  • 2D Spectra Evaluation for Single and Two Phase Flows

    Jose A. Jimenez-Bernal (IPN), Yassin A. Hassan (Texas A&M), Claudia del C. Gutierrez-Torres (IPN)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 444-445

    Track 7: Nuclear Science and Engineeting

  • Thermal Hydraulics: General - III

    Transactions | Volume 94 | Number 1 | June 2006 | Page 447

    Track 7: Nuclear Science and Engineeting

  • Development of OECD/NRC BFBT Benchmark for Validation and Improvement of Two-Phase Flow Modeling

    B. Neykov, F. Aydogan, L. E. Hochreiter, K. Ivanov (Penn State), H. Utsuno (Japan Nucl Energy Safety Org), E. Sartori (OECD-NEA), G. Rhee (NRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 449-451

    Track 7: Nuclear Science and Engineeting

  • Evaluation of the Downcomer Boiling Test (DOBO) Using RELAP5 and TRACE Codes

    B. G. Huh (KINS), D. J. Euh, B. J. Yun (KAERI), Y. J. Cho, I. G. Kim (KINS), C.-H. Song (KAERI)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 452-453

    Track 7: Nuclear Science and Engineeting

  • Inactive Loop Flow Stagnation During Natural Circulation Cooldown

    Daren Chang (STP Nucl Operating)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 454-455

    Track 7: Nuclear Science and Engineeting

  • CIAU Method to Evaluate the Uncertainty in System Thermal-Hydraulics Calculations. Key Applications

    A. Petruzzi, F. D'Auria (Univ of Pisa)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 456-458

    Track 7: Nuclear Science and Engineeting

  • The BEMUSE Programme: Best-Estimate Methods Uncertainty and Sensitivity Evaluation - Phase 2

    A. Petruzzi, F. D'Auria (Univ of Pisa)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 459-461

    Track 7: Nuclear Science and Engineeting

  • Non-Dimensional Analysis of Static Bifurcation in a Natural Circulation Loop

    Lili Tong (Shanghai Jiao Tong Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 462-463

    Track 7: Nuclear Science and Engineeting

  • Student/Professional Collaborations in Reactor Physics

    Transactions | Volume 94 | Number 1 | June 2006 | Page 465

    Track 7: Nuclear Science and Engineeting

  • Benchmark Analysis for a 2x2 Array Highly Enriched Uranium (HEU) and Iron Critical Experiment

    Daniel Gehman, David Loaiza (LANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 467-468

    Track 7: Nuclear Science and Engineeting

  • PBMR 400 Coupled Code Benchmark: Challenges and Successes with NEM-THERMIX

    Javier Ortensi, Hans Gougar (INL), Peter Mkhabela, James Han, Bismark Tyobeka, Kostadin Ivanov (Penn State)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 469-470

    Track 7: Nuclear Science and Engineeting

  • Coarse-Mesh Finite-Difference Acceleration in the NEWT Generalized-Geometry Lattice Physics Package

    Zhaopeng Zhong (Purdue Univ), Mark D. DeHart (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 471-472

    Track 7: Nuclear Science and Engineeting

  • Parallelization of the SCALE Continuous-Energy Resonance Processing Module GEMINEWTRN

    Zhaopeng Zhong, Thomas J. Downar (Purdue Univ), Mark D. DeHart, Mark L. Williams (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 473-475

    Track 7: Nuclear Science and Engineeting

  • Westinghouse Nuclear Fuel Engineering Collaborations with Nuclear Engineering Departments

    Duncan Robinson, Elise Malek, Baard Johansen (Westinghouse)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 476-477

    Track 7: Nuclear Science and Engineeting

  • Integrating Students' Research into IRIS Design Development

    B. Petrovic, M. Carelli (Westinghouse), M. Ricotti (Polytechnic of Milan), N. Todreas (MIT), F. Oriolo (Univ of Pisa), N. Cavlina (Univ of Zagreb), H. Ninokata (Tokyo Inst of Technol)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 478-479

    Track 7: Nuclear Science and Engineeting

  • University of Cincinnati and LLNL Collaboration: PWR Fuel Pin Diversion Study

    C. Yin, J. Burdo, G. Ivan Maldonado (Univ of Cincinnati), Young S. Ham (LLNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 480-482

    Track 7: Nuclear Science and Engineeting

  • University of Cincinnati and Westinghouse Collaboration: PHOENIX-4 Lattice Physics Studies

    C. Yin, J. D. Galloway, G. Ivan Maldonado (Univ of Cincinnati), Emilio Fuentes, Juan Casal (Westinghouse)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 483-485

    Track 7: Nuclear Science and Engineeting

  • Young Professional Thermal Hydraulics Research Competition

    Transactions | Volume 94 | Number 1 | June 2006 | Page 487

    Track 7: Nuclear Science and Engineeting

  • Fast Neutron Gamma-Insensitive Centrifugally-Tensioned Metastable Fluid Detector

    P. Smagacz, J. Lapinskas, A. Horn, Y. Xu, R. P. Taleyarkhan (Purdue Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 489-490

    Track 7: Nuclear Science and Engineeting

  • Fast Neutron Gamma-Insensitive Continuous Operation Tension Metastable Fluid Detector

    J. Lapinskas, P. Smagacz, J. Webster, P. Shaw, Y. Xu, R. P. Taleyarkhan (Purdue Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 491-492

    Track 7: Nuclear Science and Engineeting

  • Thermal Hydraulic Differences in Application of ASTRUM to 2-, 3-, and 4-Loop Plants

    Jeffrey Kobelak, Cesare Frepoli (Westinghouse)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 493-494

    Track 7: Nuclear Science and Engineeting

  • Emergency Diesel Generator Start Time Effects on Pressurizer Surge Line Break

    S. Y. Antoine (Westinghouse)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 495-496

    Track 7: Nuclear Science and Engineeting

  • Flow Visualization in a Packed Bed Reactor Using PIV and Refractive Index Matching

    E. E. Dominguez-Ontiveros, R. B. Barner, C. E. Estrada-Perez, Y. A. Hassan, S. Abdel-Fattah (Texas A&M)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 497-498

    Track 7: Nuclear Science and Engineeting

  • CFD Simulation on a Slit Virtual Impactor

    Sridhar Hari, Y. A. Hassan (Texas A&M)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 499-505

    Track 7: Nuclear Science and Engineeting

  • Instability Research of Two Phase Flow Using Fractal Image Coding

    Zhi Shang, Jun Zhao, Shuo Chen (Shanghai Jiao Tong Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 506-507

    Track 7: Nuclear Science and Engineeting

  • Transport Methods: General

    Transactions | Volume 94 | Number 1 | June 2006 | Page 509

    Track 7: Nuclear Science and Engineeting

  • Fourier Analysis of Parallel Inexact Block-Jacobi Splitting in Slab Geometry

    Massimiliano Rosa (Penn State), James S. Warsa, Jae H. Chang (LANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 511-513

    Track 7: Nuclear Science and Engineeting

  • Coupled Space-Angle Adaptivity for Radiation Transport Modeling

    HyeongKae Park, Cassiano R. E. de Oliveira (Georgia Tech)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 514-516

    Track 7: Nuclear Science and Engineeting

  • Asymptotically Correct Angular Distributions for Monte Carlo-Diffusion Interfaces

    Gregory Davidson (Univ of Michigan), Jeffery D. Densmore (LANL), Anil K. Prinja (Univ of New Mexico), Jim E. Morel (Texas A&M)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 517-520

    Track 7: Nuclear Science and Engineeting

  • The Boundary Element Formulation of the One Group 1D Nodal Equations

    B. D. Ganapol (Univ of Arizona), A. M. Ougouag (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 521-524

    Track 7: Nuclear Science and Engineeting

  • A One Group-One-Dimensional Transport Benchmark in Cylindrical Geometry

    B. D. Ganapol (Univ of Arizona)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 525-527

    Track 7: Nuclear Science and Engineeting

  • University Research Reactor and Nuclear Science Programs

    Transactions | Volume 94 | Number 1 | June 2006 | Page 529

    Track 7: Nuclear Science and Engineeting

  • Impact of INIE on the Oregon State TRIGA Reactor and Other Radiation Center Facilities

    Steven R. Reese, Stephen E. Binney (Oregon State Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 531-532

    Track 7: Nuclear Science and Engineeting

  • University of Wisconsin Supercritical Water Loop Radiation Energy Deposition Calibration

    Eric J. Edwards, Paul P. H. Wilson, Mark Anderson (Univ of Wisconsin-Madison), David Bartels, Simon Pimblott (Univ of Notre Dame), Benjamin Schmitt, Daniel Ludwig, Joseph Prazak, Timothy Setter (Univ of Wisconsin-Madison)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 533-534

    Track 7: Nuclear Science and Engineeting

  • A High LET Neutron Irradiation Facility for Biological Samples at the MUTR

    Eric Burgett, C.-K. Wang, Xin Zhang (Georgia Tech), Mohamad Al-Sheikhly, Ian Gifford, Vince Adams (Univ of Maryland)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 535-536

    Track 7: Nuclear Science and Engineeting

  • Addition of Hydrogen to Ni-Ti Multilayers: Implications for Improved Neutron Supermirror Performance

    Hyunsu Ju, Brent J. Heuser (Univ of Illinois)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 537-538

    Track 7: Nuclear Science and Engineeting

  • NISP Optimization of a SANS Instrument at the IUCF LENS

    Giovanna Danagoulian, Brent J. Heuser (Univ of Illinois)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 539-540

    Track 7: Nuclear Science and Engineeting

  • Graphical Methods of Teaching Monte Carlo Simulation

    Alexander G. Atwood (Suffolk County Community Coll)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 541-542

    Track 7: Nuclear Science and Engineeting

  • Comparison of Gamma-Ray Detectors for Neutron-Based Explosives Detection Systems

    Alexander Barzilov, Phillip Womble (Western Kentucky Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 543

    Track 7: Nuclear Science and Engineeting

  • Training and Research in Energy Sciences & Engineering: Towards a Better Understanding of Nuclear Sciences and Innovative Concepts

    O. K. Bouhelal (ENIM)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 544-550

    Track 7: Nuclear Science and Engineeting

  • Reactor Analysis Methods

    Transactions | Volume 94 | Number 1 | June 2006 | Page 551

    Track 7: Nuclear Science and Engineeting

  • The AFEN Method in Cylindrical (r,,z) Geometry for Pebble Bed Reactors - Extension to Multigroup Form and Treatment of Voids

    Nam Zin Cho, Joo Hee Lee, Jaejun Lee, Gil Soo Lee (KAIST)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 553-555

    Track 7: Nuclear Science and Engineeting

  • Reactivity Biases in the Simulation of the Random Dispersal of Fuel: The Case of VHTR Fuel Compacts

    Felix C. Difilippo (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 556-557

    Track 7: Nuclear Science and Engineeting

  • Simulation of a University Reactor Using MCNP Transport Code

    Michael L. Lampe, Matthew L. Dennis (Univ of Missouri-Rolla)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 558-559

    Track 7: Nuclear Science and Engineeting

  • Implementation of Uncertainty Analysis in Evaluation of Small Disturbances

    Plamen V. Petkov (Kozloduy NPP)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 560-561

    Track 7: Nuclear Science and Engineeting

  • A Convergence Problem of Nodal Methods

    Ziyong Li, Shaohong Zhang (Shanghai Jiao Tong Univ), Y. A. Chao (Westinghouse)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 562-564

    Track 7: Nuclear Science and Engineeting

  • Fast-Running Loading Pattern Evaluation Method Based on Low-Order Harmonics Expansion

    Dong Lv, Shaohong Zhang, Tao Wang (Shanghai Jiao Tong Univ), Y. A. Chao (Westinghouse)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 565-566

    Track 7: Nuclear Science and Engineeting

  • Tests of a Flow-Levitated Absorber for GFR LOF and LOCA Mitigation

    M. J. Driscoll, C. S. Handwerk (MIT)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 567-568

    Track 7: Nuclear Science and Engineeting

  • Computational Methods: General

    Transactions | Volume 94 | Number 1 | June 2006 | Page 569

    Track 7: Nuclear Science and Engineeting

  • A Fast RSA Method for Fuel Particle Packing

    Forrest B. Brown (LANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 571-573

    Track 7: Nuclear Science and Engineeting

  • Real Variance Estimation Using Inter-Cycle Correlation of Fission Source Distribution in Monte Carlo Eigenvalue Calculations

    Hyung Jin Shim, Chang Hyo Kim (Seoul Natl Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 574-576

    Track 7: Nuclear Science and Engineeting

  • Atomic-Scale Modeling of Dislocation-Radiation Defects Interaction

    Yuri N. Osetsky, Roger E. Stoller (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 577-578

    Track 7: Nuclear Science and Engineeting

  • Degradation Monitoring Through Unscented Kalman Filtering

    Bulent Alpay, John C. Lee (Univ of Michigan)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 579-580

    Track 7: Nuclear Science and Engineeting

  • Development and Benchmarking of Robust Non-Parametric Sequential Probability Ratio Tests

    Adrian Miron (Univ of Cincinnati), Randall L. Bickford (Expert MicroSystems)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 581-582

    Track 7: Nuclear Science and Engineeting

  • The Problem of Prompt Gamma Emission for Water Prospecting in Martian Regolith

    Shikha Prasad, Natallia Pinchuk, Katie Woch, James Paul Holloway (Univ of Michigan)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 583-584

    Track 7: Nuclear Science and Engineeting

  • Reactor Physics Design, Validation, and Operating Experience

    Transactions | Volume 94 | Number 1 | June 2006 | Page 585

    Track 7: Nuclear Science and Engineeting

  • A Process for Analyzing Channel-Control Blade Interference

    Atul A. Karve, Gerald A. Potts, Robert A. Rand, Gerry M. Latter, Mark A. Dubecky (GE/GNF)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 587-588

    Track 7: Nuclear Science and Engineeting

  • MOX and MOX with 237Np/241Am Inert Gas Generation Comparison in ATR

    G. S. Chang, M. Robel, W. J. Carmack, D. J. Utterbeck (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 589-590

    Track 7: Nuclear Science and Engineeting

  • Lifetime Predictions for Three Fuel Reloading Scenarios in the PULSTAR Reactor at NCSU

    Matthew L. F. Miller, R. E. Pevey, L. F. Miller (Univ of Tennessee), A. I. Hawari (NCSU)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 591-593

    Track 7: Nuclear Science and Engineeting

  • Neutronic Design Study of a TRU Transmutation Core Using Void Duct Assemblies

    Ser Gi Hong, Yeong Il Kim, Sang Ji Kim (KAERI)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 594-596

    Track 7: Nuclear Science and Engineeting

  • Configuration Adjustment Potential of the VHTR Prismatic Cores with Advanced Actinide Fuels

    Pavel V. Tsvetkov, David E. Ames II, Ayodeji B. Alajo (Texas A&M)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 597-598

    Track 7: Nuclear Science and Engineeting

  • Radiation Damage Study at First Wall Structures of a Hybrid Type Magnetic Fusion Reactor

    Mustafa Übeyli, Teyfik Demir (TOBB ETU)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 599-600

    Track 7: Nuclear Science and Engineeting

  • Neutronic Analysis of a Magnetic Fusion Reactor with Heavy Metal Salt

    Sümer Sahin (Gazi Univ), Mustafa Übeyli (TOBB ETU)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 601-602

    Track 7: Nuclear Science and Engineeting

  • MCNP5 Simulations of ZrH Scattering Experiments

    Yan Cao (Univ of Michigan), Tong Zhou, Iyad I. Al-Qasir, Ayman I. Hawari (NCSU), Ronald F. Fleming, John C. Lee (Univ of Michigan)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 603-604

    Track 7: Nuclear Science and Engineeting

  • Emerging Technologies Related to Hydrogen

    Transactions | Volume 94 | Number 1 | June 2006 | Page 607

    Track 8: Emerging Nuclear Technologies

  • Nuclear Power's Role in Breaking America's Addiction to Foreign Oil

    Donn D. Dears (TSAugust)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 609-610

    Track 8: Emerging Nuclear Technologies

  • Coupling of a Nuclear Heating Reactor with LT-MED Desalination Process

    Deng Jian, X. W. Cao (Shanghai Jiao Tong Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 611-612

    Track 8: Emerging Nuclear Technologies

  • The Development of Autocatalytic Structural Materials for Use in the Sulfur-Iodine Process for the Production of Hydrogen

    K. K. Miu, R. G. Ballinger (MIT), N. Li (LANL), J. Y. Lim, D. A. Rigual (MIT)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 613-614

    Track 8: Emerging Nuclear Technologies

  • Dose and Damage to Personnel and Electrodes from O(,n)Ne Reactions

    Kyle Maloy, Alex Misner, Todd S. Palmer, Richard Peterson, Qiao Wu (Oregon State Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 615-616

    Track 8: Emerging Nuclear Technologies

  • Thermal Hydraulics of Nuclear Hydrogen Systems

    Transactions | Volume 94 | Number 1 | June 2006 | Page 617

    Track 8: Emerging Nuclear Technologies

  • Effects of Interstage Cooling on Brayton Cycle Efficiency

    Chang H. Oh (INL), Robert Barner (Texas A&M)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 619-620

    Track 8: Emerging Nuclear Technologies

  • Thermal Hydraulic Analysis of HTGR Coupled with Hydrogen Plant

    Chang H. Oh, Cliff Davis, Steven Sherman (INL), Robert Barner (Texas A&M)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 621-622

    Track 8: Emerging Nuclear Technologies

  • Simplified Model to Couple SI Cycle to Nuclear Heat Transport System

    Shripad T. Revankar, Seungmin Oh, Nicholas Brown, Karen Vierow (Purdue Univ), Salvador Rodriguez, Randall Cole, Jr., Randall Gauntt (SNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 623-624

    Track 8: Emerging Nuclear Technologies

  • Assessment of Sulfur Iodine Thermochemical Water Splitting Process Flowsheet with ASPEN Code

    Seungmin Oh, Shripad T. Revankar, Nicholas Brown, Karen Vierow (Purdue Univ), Salvador Rodriguez, Randall Cole, Jr., Randall Gauntt (SNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 625-626

    Track 8: Emerging Nuclear Technologies

  • Fusion Energy Using Lunar-Mined Helium

    Transactions | Volume 94 | Number 1 | June 2006 | Page 627

    Track 8: Emerging Nuclear Technologies

  • MilliWatt Radioisotope Power System Performance Enhancement

    Luca Gratton (MGT Tech Consulting)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 629-630

    Track 8: Emerging Nuclear Technologies

  • A Strategy for D-3He Fusion Development

    J. F. Santarius, G. L. Kulcinski (Univ of Wisconsin-Madison), G. H. Miley (Univ of Illinois)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 631-633

    Track 8: Emerging Nuclear Technologies

  • On Use of D-3He in Fusion Space Propulsion

    G. H. Miley (Univ of Illinois, NPL Assoc), H. Momota, P. J. Shrestha (NPL Assoc), J. F. Santarius (Univ of Wisconsin-Madison)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 634-635

    Track 8: Emerging Nuclear Technologies

  • A Bi-Modal Fusion Propulsion System for He3 Mining of the Planets

    T. Kammash, R. Tang (Univ of Michigan), B. Cassenti (Pratt & Whitney)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 636-637

    Track 8: Emerging Nuclear Technologies

  • Carbon Nanotubes in IEC Fusion Reactors

    S. Krupakar Murali (Micron Technol), Rick Nebel, Jaeyoung Park (LANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 638-639

    Track 8: Emerging Nuclear Technologies

  • Fuels and Materials for Very-High-Temperature Reactors (VHTR)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 643

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Fuel Characteristics and Requirements for the Advanced High-Temperature Reactor

    Charles W. Forsberg (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 645-647

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • SIROCCO: The CEA and AREVA Irradiation Programme of VHTR Fuel

    M. Phélip (CEA), P. Guillermier (Framatome ANP), S. Bendotti (CEA)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 648

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • The CRP-6 Benchmark on HTGR Fuel Behavior Under Accident Conditions

    Karl Verfondern (FZJ), Yumin Mao (Fachhochschule Aachen)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 649-650

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Burn-Leach: The Most Important Test in the Manufacture of HTGR Fuel

    Heinz Nabielek (FZJ), Chunhe Tang (INET), Shohei Ueta (JAEA), Karl Verfondern (FZJ)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 651

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • The CRP-6 Benchmark on HTGR Fuel Behavior Under Normal Operation

    Mayeul Phélip (CEA), Igor Kadarmetov (A. A. Bochvar All-Russian Research Inst of Inorganic Materials), David Petti (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 652-653

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Use of Friction Stir Welding and Friction Stir Processing for Advanced Nuclear Fuels and Materials Joining Applications

    J. I. Cole, C. R. Clark, J. F. Jue (INL), D. A. Cullen (Arizona State Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 654-655

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Effects of Accelerated Irradiation on Coated Particle Fuel Performance

    David A. Petti, John T. Maki, Darrell L. Knudson, Gregory K. Miller (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 656

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Growth of SiC Whiskers in SiCf/SiC Composites and Its Effect on Mechanical Properties

    Weon-Ju Kim, Seok Min Kang, Ji Yeon Park, Woo-Seog Ryu (KAERI)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 657

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Statistical Approach of HTR Fuel Particle Failure

    C. Cannaméla, F. Michel (CEA)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 658-659

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • ATLAS, a Code for V/HTR Fuel Performance Evaluation

    Frédéric Michel (CEA), Pierre Mailhe (Framatome ANP)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 660-661

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Pyrocarbon Materials for High Temperature Reactor Fuels

    D. Hélary (Univ of Bordeaux, CEA), V. Basini (CEA), F. Cellier (Framatome ANP)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 662-663

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • BWXT Capabilities and Experience Relevant to Generation IV Reactor Fuel Development

    S. W. Scoles, W. C. Richardson (BWXT)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 664-665

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Effect of High Temperature Processing on UCO Fuel Kernel Characteristics

    D. L. Husser (BWXT), M. A. Ebner (INL), T. B. Lindemer (Harbach Eng and Sol)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 666

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Development of a Continuous CVD Process for TRISO Coating for AGR Fuel

    Joseph T. Keeley, Bruce L. Tomlin (BWXT)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 667

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Degradation of Triso Fuel in a Repository Environment

    Joshua Peterson, Mary Lou Dunzik-Gougar (Idaho State Univ)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 668-669

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Experiment and Model Development on the Effect of Burn-Off for Graphite Oxidation

    Eung Soo Kim, Hee Cheon No (KAIST)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 670-671

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Studying TRISO Fuel Failure Using Passive Gamma-Ray Spectrometry

    J. M. Harp, E. H. Martin, A. I. Hawari, M. A. Bourham (NCSU)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 672-673

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Structural Ceramic Composites for the VHTR

    W. E. Windes (INL), Y. Katoh, L. Snead (ORNL), C. Henager (PNNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 674-675

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Characterization Methods for Quality Control Analysis of Coated Particles and Fuel Compacts for the Advanced Gas Reactor Fuel Development and Qualification Program

    John D. Hunn (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 676

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Carbon Fiber Composites for Harsh Nuclear Environments

    Lance L. Snead (ORNL), Will Windes (INL), James Klett, Yutai Katoh (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 677-678

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Handbook on SiC and ZrC Properties for Fuel Performance Modeling

    Lance L. Snead, Yutai Katoh, Takashi Nozawa (ORNL), David Petti (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 679

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Fracture Stress of SiC Layer in Coated Particle Fuel

    T. S. Byun, S. G. Hong, L. L. Snead, Y. Katoh (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 680-681

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Stress Analysis of Composite Control Rod Tubes for Gen IV Reactor

    Seong-Gu Hong (KAIST, ORNL), Yutai Katoh (ORNL), Will Windes (INL), Lance Snead, James Klett (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 682-683

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Qualification Programs for the Materials Envisioned in VHTRs

    Bernard Riou, Claude Escaravage, Odile Gelineau (Framatome ANP)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 684

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Coated Particle Fuel for the Advanced Gas Reactor

    R. A. Lowden, J. H. Miller, J. C. McLaughlin, J. D. Hunn (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 685-686

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Development of a TRISO Particle Overcoating and Compacting Process for the VHTR

    P. J. Pappano, M. P. Trammell, M. R. Rogers (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 687-688

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Generation IV Reactor Integrated Materials Program

    William R. Corwin (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 689

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Final Post-Irradiation Examinations of FMDP Weapons-Derived MOX Fuel

    R. N. Morris, C. A. Baldwin, N. H. Packan (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 690-691

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Creep Response of Alloy 617 in Impure Helium for VHTR Applications

    P. S. Shankar, K. Natesan, D. L. Rink (ANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 692

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Material Challenges for Hydrogen Production from Nuclear Systems

    P. S. Pickard (SNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 693

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • An Update on the DOE Advanced Gas Reactor (AGR) Fuel Development and Qualification Program

    David Petti (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 694-695

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Fuel Performance Modeling for Coated Particle Fuel: The PARFUME Code

    David Petti, John Maki, Greg Miller, Darrell Knudson (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 696-697

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Environmental Resistance of Alloys in the Next Generation Nuclear Plant

    Richard N. Wright (INL), Dane F. Wilson (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 698-699

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Overview of Fuel and Materials Development for the AREVA HTR

    Lewis Lommers (AREVA)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 700

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Design and Materials Aspects of the PBMR

    Mark N. Mitchell, Kobus Smit, Mary Fechter, Shahed Fazluddin (PBMR)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 701

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Graphite for Next Generation Reactors

    T. D. Burchell, J. P. Strizak (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 702-703

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • High Temperature MHR Design, Technology and Applications

    Arkal Shenoy, Donald McEachern, John Saurwein (General Atomics)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 704

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Present Status of ZrC Coated Fuel Particle Development for Very High Temperature Reactors in JAEA

    Kazuhiro Sawa, Shouhei Ueta, Jun Aihara (JAEA)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 705

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Fuels and Materials for Gas-Cooled Fast Reactors (GFR)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 707

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Gas-Fast Reactor Fuel Fabrication

    Randall Fielding, Mitch Meyer, Jan-Fong Jue, Jian Gan (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 709-710

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Thermophysical Characterization of Nitrides: Preliminary Results

    A. Ciriello, V. V. Rondinella, D. Staicu, J. Somers (European Commission, JRC, Inst for Transuranium Elements)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 711-712

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Thermomechanics of Candidate Coatings for Advanced Gas Reactor Fuels

    A. Nosek, J. Conzen, H. Doesscher, C. Martin, J. Blanchard (Univ of Wisconsin-Madison)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 713

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Characterization of Uranium Carbide Spheres for Gas-Cooled Fast Reactors

    Jan-Fong Jue, Randall Fielding (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 714-715

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Radiation Resistance of Ceramic Candidates for Generation IV Gas-Cooled Reactors

    B. D. Miller, C. A. Dickerson, H. J. Yount, T. R. Allen (Univ of Wisconsin-Madison)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 716

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Burn-Up Capability Optimization for Deep Burn Modular Helium Reactor

    Di Yun, Thomas A. Patten, Bei Ye, James F. Stubbins (Univ of Illinois)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 717-718

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Materials Testing in Supercritical CO2

    Jeongyoun Lim (MIT), Ning Li (LANL), Ronald Ballinger (MIT)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 719

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Fission Product Interactions with Carbides and Nitrides

    Paul A. Demkowicz, David A. Petti, Karen Wright (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 720-721

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Fuel Development for Gas-Cooled Fast Reactors

    M. K. Meyer (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 722

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Outlines of the CEA's Materials R&D Program for the Gas Cooled Systems

    Philippe Billot, Jean-Louis Séran, Lionel Gosmain, Hélène Burlet (CEA)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 723-724

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Fuels and Materials for Supercritical Water-Cooled Reactors (SCWR)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 725

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Improved Creep Properties of Grain Boundary Engineered 9Cr-1Mo-Nb-V (T91) Steel

    Gaurav Gupta, Gary S. Was (Univ of Michigan)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 727-728

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Status of Supercritical Water Reactor Design

    T. Schulenberg (FZK), D. Bittermann (Framatome ANP)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 729-730

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Irradiation Induced Microstructure and Irradiation Assisted Stress Corrosion Cracking in Supercritical Water

    S. Teysseyre, E. West, Z. Jiao, G. S. Was (Univ of Michigan)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 731-732

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Facility for Conducting Stress Corrosion Cracking of Neutron Irradiated Specimens in Supercritical Water

    S. Teysseyre, Q. Peng, C. Becker, G. S. Was (Univ of Michigan)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 733

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Zirconium Alloys for Supercritical Water Reactor Applications: Challenges and Possibilities

    Arthur Motta, Aylin Yilmazbayhan, Marcelo Silva (Penn State), Robert J. Comstock (Westinghouse), Gary Was, Eric Gartner, Quinja Peng (Univ of Michigan), Yong Hwan Jeong, Jeong Yong Park (KAERI)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 734-735

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Corrosion and Stress Corrosion Cracking in Supercritical Water

    Gary S. Was, Pantip Ampornrat, Gaurav Gupta, Sebastien Teysseyre (Univ of Michigan)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 736-737

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Temperature Dependence of Oxidation of Ferritic-Martensitic Alloys in Supercritical Water

    Pantip Ampornrat, Gary S. Was (Univ of Michigan)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 738-739

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Corrosion of 9Cr Oxide Dispersion Strengthened Steel in Supercritical Water Environment

    Y. Chen, K. Sridharan, T. R. Allen (Univ of Wisconsin-Madison)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 740-741

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Zirconium Metal Inert Matrix Fuel Fabrication

    Randall Fielding, Jan-Fong Jue, James Stuart (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 742-743

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Grain Boundary Engineering of FCC and BCC Alloys

    L. Tan, K. Sridharan, T. R. Allen (Univ of Wisconsin-Madison)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 744

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Oxidation Behavior of HCM12A Exposed in Harsh Environments

    L. Tan, M. T. Machut, K. Sridharan, T. R. Allen (Univ of Wisconsin-Madison)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 745

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Fuels and Materials for Lead-Cooled Fast Reactors (LFR)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 747

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Corrosion Resistance of Ferritic/Martensitic ODS Alloys in LBE Environment and Application of MA956

    Peter Hosemann (Univ of Leoben, LANL), Felix Olivas, Ning Li (LANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 749

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Modeling of Corrosion Mechanisms of Steels for Lead-Alloy Cooled Reactors

    McLean Machut, Kumar Sridharan (Univ of Wisconsin-Madison), Ning Li (LANL), Todd Allen (Univ of Wisconsin-Madison)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 750-751

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Fast Spectrum Nitride Transmutation Fuels for the Futurix-FTA Irradiation Experiment

    Stewart Voit, Kenneth McClellan, Christopher Stanek (LANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 752-753

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • An EBSD Investigation on Flow Localization of 316L Stainless Steel

    Xianglin Wu, Xiao Pan, James C. Mabon (Univ of Illinois), Meimei Li (ORNL), James F. Stubbins (Univ of Illinois)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 754-755

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Steel Corrosion in Heavy Liquid Metals

    Ning Li (LANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 756-757

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Structural Materials for Fast Spectrum Reactors to Transmute Spent Nuclear Fuel

    S. A. Maloy (LANL), M. B. Toloczko (PNNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 758

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Effects of Chromium and Silicon on Iron-Alloy Corrosion in Pb-Bi Eutectic

    J. Lim, R. G. Ballinger, P. W. Stahle (MIT), N. Li (LANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 759-760

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • The Development and Production of Functionally Graded Composite Cladding and Structural Materials for Lead-Bismuth Service

    R. G. Ballinger, J. Lim (MIT), N. Li (LANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 761

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Preliminary Study on Polonium Filter for Lead Alloy Cooled Reactors

    Toru Obara, Takeru Koga, Terumitsu Miura, Hiroshi Sekimoto (Tokyo Inst of Technol)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 762

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Swelling, Creep, and Embrittlement of Three Russian Ferritic-Martensitic Steels Irradiated in the BN-350 Fast Reactor

    S. I. Porollo, A. M. Dvoriashin, S. P. Shulepin, Yu. V. Konobeev (IPPE), N. I. Budylkin, E. G. Mironova, M. V. Leontyeva-Smirnova, A. G. Ioltukhovsky (A. A. Bochvar All-Russian Research Inst of Inorganic Materials), F. A. Garner (PNNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 763-764

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Modeling Advanced Materials

    Wolfgang Hoffelner, Maria Samaras (Paul Scherrer Inst)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 765

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Fuels and Materials for Sodium-Cooled Fast Reactors (SFR)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 767

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Design Challenges for Sodium-Cooled Fast Reactors

    Mamoru Konomura, Masakazu Ichimiya (JAEA)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 769-770

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Measurement of the Fuel Pin Deflection in an Assembly Irradiated in FBR "JOYO"

    Kozo Katsuyama, Tsuyoshi Nagamine, Yasuo Nakamura, Shin-ichiro Matsumoto, Takeo Asaga, Hirotaka Furuya (JAEA)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 771-772

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Postirradiation Examination of AFCI Metallic Transmutation Fuels at 8 at.%

    Bruce A. Hilton, Douglas L. Porter, Steven L. Hayes (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 773-774

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Chemical Interactions Between Metallic SFR Fuel and Advanced Claddings

    Dennis D. Keiser, Jr., James I. Cole (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 775-776

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Postirradiation Examination of AFCI Nitride and Oxide Transmutation Fuels at 8 at.%

    Bruce A. Hilton, Douglas L. Porter, Steven L. Hayes (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 777-779

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Pyrometallurgical Production of U-Pu Alloy and Injection Casting of U-Pu-Zr

    Kinya Nakamura, Takeshi Yokoo (CRIEPI), Yasuo Arai (JAEA)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 780

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Advanced Fuel Cycle Initiative Fuel Development Program Overview

    William J. Carmack (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 781-785

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Development of Optimized Martensitic 9Cr-ODS Steel Cladding

    S. Ukai, T. Kaito, S. Ohtsuka, T. Narita, H. Sakasegawa (JAEA)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 786-787

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • The Strong Influence of Atomic Displacement Rate on Neutron-Induced Void Swelling of Structural Alloys

    F. A. Garner (PNNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 788-790

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Fuels for Sodium-Cooled Fast Reactors

    Douglas C. Crawford, Douglas L. Porter, Steven L. Hayes (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 791-792

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • An Approach to Fuel Development and Qualification

    Douglas C. Crawford, Douglas L. Porter, Steven L. Hayes, Kemal Pasamehmetoglu (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 793-794

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • An Approach to Fuel Safety Testing

    Douglas C. Crawford (INL), Arthur E. Wright, James E. Cahalan (ANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 795-796

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Review of HT-9 Cladding Creep Correlations for Advanced Liquid Metal Fast Reactors

    Ho Jin Ryu, A. M. Yacout, Yeon Soo Kim, G. L. Hofman (ANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 797-798

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Structural and Cladding Aspects of Fast Reactors

    T. R. Allen (Univ of Wisconsin-Madison)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 799-800

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Fuel and Core Structural Materials for Commercial Fast Sodium Reactor in Russia: State-of-Art and Prospects

    L. M. Zabudko, A. A. Kamaev (IPPE)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 801-802

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Fuels and Materials for Molten Salt-Cooled Reactors (MSR)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 803

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Experimental Design for Testing Materials Corrosion in Molten Fluoride Salt

    Luke Olson, James Ambrosek, Kumar Sridharan, Mark Anderson, Todd Allen, Dave Williams, Dane Wilson (Univ of Wisconsin-Madison)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 805-806

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • High-Temperature Design Methodology

    Transactions | Volume 94 | Number 1 | June 2006 | Page 807

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • NRC and ACRS Technical Issues Relating to Clinch River Breeder Reactor (CRBR)

    William J. O'Donnell (O'Donnell Consulting Eng)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 809-810

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Elevated Temperature Structural Design Criteria - Background and Issues for GEN IV/VHTR

    Robert Jetter (Consultant)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 811-812

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Evaluation of the ASME-NH B-1 Test for Very High Temperature Application

    Timothy E. McGreevy (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 813-814

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • The Reference Stress Concept - An Alternative Approach to Stress Classification

    Douglas L. Marriott (Stress Eng Svc)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 815-817

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Simplified Inelastic Analysis Method Based on r-Factor

    Saurin Majumdar (ANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 818-819

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Next Generation Nuclear Plant Technical Issues and Safety Research Needs - NRC Staff Views

    Stuart Rubin (NRC)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 820

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Microstructural Modeling

    Transactions | Volume 94 | Number 1 | June 2006 | Page 821

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Stochastic Deformations and Bubble Density Evolution in Nuclear Materials

    Ray B. Stout (RhoBetaSigma Affaires)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 823

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Materials for Radiation Service

    Transactions | Volume 94 | Number 1 | June 2006 | Page 825

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Fabrication of Dual Phase Magnesia-Zirconia Ceramics Doped with Plutonia and Erbia

    P. G. Medvedev, J. F. Jue, S. M. Frank (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 827-828

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Radiation Response of a 9 Cr Oxide Dispersion Strengthened ODS to Heavy Ion Irradiation

    T. R. Allen (Univ of Wisconsin-Madison), J. Gan, J. I. Cole (ANL), S. Ukai (JAEA), S. Shutthanandan, S. Thevuthasan (PNNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 829-830

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Ferritic Steels for Next-Generation Reactors

    R. L. Klueh, A. T. Nelson (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 831-832

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Thermal Analysis of LWR-2 Experiment in the Advanced Test Reactor

    Grant L. Hawkes (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 833-834

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Neutronic Performance of the LANSCE Materials Test Station

    Michael R. James (LANL), Erich A. Schneider (Univ of Texas at Austin), Guenter Muhrer, Eric J. Pitcher (LANL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 835-836

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Irradiation Effects of Helium and Hydrogen in BCC Single Crystal Iron

    Maria A. Okuniewski (Univ of Illinois), Chaitanya S. Deo, Srivilliputhur G. Srinivasan, Michael I. Baskes, Michael R. James, Stuart A. Maloy (LANL), James F. Stubbins (Univ of Illinois)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 837

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • MOX Fuel Fabrication for the AFCI Program

    Paul A. Lessing, Timothy A. Hyde (INL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 838-839

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Shear Properties at the PyC/SiC Interface of TRISO-Coating

    Takashi Nozawa, Lance L. Snead, Yutai Katoh, James H. Miller (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 840

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Development of Nanostructured Ferritic Alloys for Advanced Fission and Fusion Energy Applications

    G. R. Odette, T. Yamamoto, P. Miao (Univ of California, Santa Barbara), M. J. Alinger (Univ of California, Santa Barbara/Berkeley, GE Research), B. D. Wirth (Univ of California, Berkeley), D. T. Hoelzer, N. Hashimoto (ORNL), R. J. Kurtz, D. S. Gelles, B. M. Oliver (PNNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 841-842

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Effects of Neutron Irradiation on Temperature Dependence of Yield Stress of Molybdenum

    Meimei Li, T. S. Byun, N. Hashimoto, L. L. Snead, S. J. Zinkle (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 843-844

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Four Decades of Fast Reactor Structural Materials: Experience and Questions for the Future

    J. T. Busby, P. J. Maziasz, E. E. Bloom (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 845-846

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • Refractory Alloys for Nuclear Applications

    S. J. Zinkle, J. T. Busby, K. J. Leonard, L. L. Snead, D. T. Hoelzer, T. S. Byun, M. Li (ORNL)

    Transactions | Volume 94 | Number 1 | June 2006 | Pages 847-848

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

  • International Research Cooperation in Next Generation Reactors: A Path to Non-Proliferation Through ISTC

    José Ignacio Pradas-Poveda (ISTC)

    Transactions | Volume 94 | Number 1 | June 2006 | Page 849

    Embedded Topical Meeting: Nuclear Fuels and Structural Materials for the Next Generation Nuclear Reactors

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