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Volume 187

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Number 1

The SABrR Concept for A Fission-Fusion Hybrid 238U-to-239Pu Fissile Production Reactor

C. L. Stewart, W. M. Stacey

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 1-14

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-102

Resolution of Fission and Fusion Technology Integration Issues: An Upgraded Design Concept for the Subcritical Advanced Burner Reactor

W. M. Stacey, C. L. Stewart, J.-P. Floyd, T. M. Wilks, A. P. Moore, A. T. Bopp, M. D. Hill, S. Tandon, and A. S. Erickson

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 15-43

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-96

Effects of Shape and Size on Countercurrent Flow Limitation in Flow Channels Simulating A PWR Hot Leg

Ikuo Kinoshita, Michio Murase, Yoichi Utanohara, Dirk Lucas, Christophe Vallée, and Akio Tomiyama

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 44-56

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-32

Clogging of HEPA Filters By Soot During Fire Events in Nuclear Fuel Cycle Facilities

Takashi Ishibashi, Susumu Tsuchino, Shiro Matsumoto, and Fumio Kasahara

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 57-68

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-94

Efficient Digital Implementation of Signal Processing Algorithms in State-Of-The-Art Field-Programmable Gate Arrays for Gamma-Ray Spectroscopy

Fateme Fahiman, Mahdi Kafaee, Ali Moussavi-Zarandi, and Meisam Fahiman

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 69-81

Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-65

Deployment Strategies for Wireless Sensor Networks in Nuclear Power Plants

Ataul Bariand Jin Jiang

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 82-95

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT13-1

Computer-Based Investigative Techniques: A Comparison of Dose Using the MCNP Code for Optically Stimulated Light Dosimeters

Thomas B. Rezentes, Mark A. Prelas, Eric Lukosi, Matthew L. Watermann, Jack Crawford, and Richard H. Olsher

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 96-102

Technical Note / Radiation Transport and Protection / dx.doi.org/10.13182/NT11-105

Impact of Local Burnup on Prediction of Power Density in the NIST Research Reactor

Nicholas R. Brown, Albert L. Hanson, and David J. Diamond

Nuclear Technology / Volume 187 / Number 1 / July 2014 / Pages 103-116

Technical Note / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-20

Number 2

Two-Phase Flow Modeling With Tough2-Mp of A Deep Geological Repository Within the First Benchmark of the FORGE Project

Manuel Lorenzo Sentís

Nuclear Technology / Volume 187 / Number 2 / August 2014 / Pages 117-130

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-84

Extension and Tuning of TOUGH2-MP EOS7R for the Assessment of Deep Geological Repositories for Nuclear Waste: Hydrogen, Arbitrarily Long Decay Chains, and Solubility Limits

Th. U. Kaempfer, Y. Mishin, J. Brommundt, J. Roger, E. Treille, and N. Hubschwerlen

Nuclear Technology / Volume 187 / Number 2 / August 2014 / Pages 131-146

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-80

Modeling Two-Phase-Flow Interactions Across a Bentonite Clay and Fractured Rock Interface

Benoît Dessirier, Jerker Jarsjö, Andrew Frampton

Nuclear Technology / Volume 187 / Number 2 / August 2014 / Pages 147-157

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT13-77

The Effect of Stress on Flow and Transport in Fractured Rock Masses Using an Extended Multiple Interacting Continua Method with Crack Tensor Theory

Zhen Wang, Jonny Rutqvist, Yuan Wang, Colin Leung, Andrew Hoch, Ying Dai

Nuclear Technology / Volume 187 / Number 2 / August 2014 / Pages 158-168

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT13-76

Modeling Transport of Water, Ions, and Chemical Reactions in Compacted Bentonite: Comparison Among Toughreact, Numerrin, and Comsol Multiphysics

Aku Itälä, Mika Laitinen, Merja Tanhua-Tyrkkö, Markus Olin

Nuclear Technology / Volume 187 / Number 2 / August 2014 / Pages 169-174

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT13-79

T2GGM: A Coupled Gas Generation Model for Deep Geologic Disposal of Radioactive Waste

John Avis, Paul Suckling, Nicola Calder, Robert Walsh, Paul Humphreys, Fraser King

Nuclear Technology / Volume 187 / Number 2 / August 2014 / Pages 175-187

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT13-83

Optimizing the Modeling Performance for Safety Assessments of Nuclear Waste Repositories By Approximating Two-Phase Flow and Transport by Single-Phase Transport Simulations

Philipp Schaedle, Nicolas Hubschwerlen, Holger Class

Nuclear Technology / Volume 187 / Number 2 / August 2014 / Pages 188-197

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-82

Design Study on a Fast Reactor Metal Fuel Attaining Very High Burnup

Hirokazu Ohta, Takanari Ogata, Toru Obara

Nuclear Technology / Volume 187 / Number 2 / August 2014 / Pages 198-207

Regular Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-105

New Numerical Algorithm Method Considering the Self-Absorption of the Spherical Radioactive Sources Matrix to Calibrate a System of Two Nai Gamma Detectors

Mohamed E. Krar, Ahmed M. El-Khatib, Mohamed S. Badawi

Nuclear Technology / Volume 187 / Number 2 / August 2014 / Pages 208-219

Regular Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT13-109

Number 3

Analysis of the Limiting Safety System Settings of a Fluoride Salt–Cooled High-Temperature Test Reactor

Yao Xiao, Lin-Wen Hu, Charles Forsberg, Suizheng Qiu, Guanghui Su, Kun Chen, Naxiu Wang

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 221-234

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-93

Modeling the Detection of Delayed Neutron Signatures in MCNP6 and Comparisons with Measurements of 233U, 235U, and 239Pu

M. T. Andrews, J. T. Goorley, E. C. Corcoran, D. G. Kelly

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 235-242

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-72

Application of an Improved Mechanical Shim Control Strategy for AP1000 Reactor

Pengfei Wang, Jiashuang Wan, Shoujun Yan, Yang Liu, Fuyu Zhao

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 243-259

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-111

Preliminary Economic Evaluation of Thorium-Based Fuels in PWRs

M. H. Du Toit, A. C. Cilliers

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 260-269

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-134

An Examination of CANDU Fuel Performance Margins Derived from a Statistical Assessment of Industrial Manufacturing Data

Travis A. Cunning, Paul Chan, Mahesh D. Pandey, Aniket Pant

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 270-281

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-126

Experimental Investigation of a Scaled Water-Cooled Reactor Cavity Cooling System

Rodolfo Vaghetto, Yassin A. Hassan

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 282-293

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-130

Thermal Modeling of High-Level Nuclear Waste Disposal in a Salt Repository

Dylan R. Harp, Philip H. Stauffer, Phoolendra K. Mishra, Daniel G. Levitt, Bruce A. Robinson

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 294-307

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-110

In-Core Flux Sensor Evaluations at the ATR Critical Facility

Troy Unruh, Benjamin Chase, Joy Rempe, David Nigg, George Imel, Jason Harris, Todd Sherman, Jean-François Villard

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 308-315

Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT13-122

Cesium Isotope Composition in Fukushima Daiichi Units After Boiling Water Reactor Accident

Masato Takahashi, Kenichi Yoshioka

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 316-327

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT13-114

Probability Correction Approach to Calibrate High-Purity Germanium Cylindrical Detectors Using Parallelepiped Sources

Sherif S. Nafee

Nuclear Technology / Volume 187 / Number 3 / September 2014 / Pages 328-336

Technical Note / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-106

 
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