Transactions | Volume 102 | Number 1 | June 2010 | Page iii
Meeting Officials, National Program Committee
Transactions | Volume 102 | Number 1 | June 2010 | Page v
Transactions | Volume 102 | Number 1 | June 2010 | Page vii
Transactions | Volume 102 | Number 1 | June 2010 | Page xvii
Opening Plenary: Nuclear Science and Technology - The Right Fit. The Right Time.
Transactions | Volume 102 | Number 1 | June 2010 | Page 3
Transactions | Volume 102 | Number 1 | June 2010 | Page 4
Nuclear Applications of Particle Accelerators: General
Transactions | Volume 102 | Number 1 | June 2010 | Page 7
Laser System for Inverse Compton Scattering Gamma-Ray Source for Photofission
Transactions | Volume 102 | Number 1 | June 2010 | Pages 9-10
Summary of Conclusions from the EUROTRANS Reactivity Monitoring Experiments at YALINA-Booster
Transactions | Volume 102 | Number 1 | June 2010 | Pages 11-12
Transactions | Volume 102 | Number 1 | June 2010 | Page 15
Irradiation to Control Quarantine Insects in Exported Fresh Commodities: Pioneering Generic Doses
Transactions | Volume 102 | Number 1 | June 2010 | Pages 17-18
Irradiation in Combined Treatments and Food Safety
Transactions | Volume 102 | Number 1 | June 2010 | Pages 19-20
A Mobile Food Irradiation Facility to Address Emergency Food Contamination Issues
Transactions | Volume 102 | Number 1 | June 2010 | Pages 21-22
Regulatory Update - Food Irradiation
Transactions | Volume 102 | Number 1 | June 2010 | Page 23
Food Irradiation in the United States: Empowering Food Industry Decision Makers
Transactions | Volume 102 | Number 1 | June 2010 | Pages 24-25
Transactions | Volume 102 | Number 1 | June 2010 | Page 26
Hot Topics and Emerging Issues
Transactions | Volume 102 | Number 1 | June 2010 | Page 29
Addressing Challenging Remote-Handled Deactivation and Decommissioning Wastes at ORNL
Transactions | Volume 102 | Number 1 | June 2010 | Pages 31-32
Trenchless Technologies for Minimizing Impacts for Pipeline Replacements in Radioactive Environments
Transactions | Volume 102 | Number 1 | June 2010 | Pages 33-34
Dismantling Nuclear Facilities for Reutilization: An Illustration on Marcoule UP1 Site
Transactions | Volume 102 | Number 1 | June 2010 | Pages 35-36
Development of Computer Program for Estimating Decommissioning Cost
Transactions | Volume 102 | Number 1 | June 2010 | Pages 37-38
Historic Preservation in Commercial Facility Decommissioning-Panel
Transactions | Volume 102 | Number 1 | June 2010 | Page 39
The Need for Nuclear Engineers with a Professional Engineering License-Papers/Panel
Transactions | Volume 102 | Number 1 | June 2010 | Page 43
Engineering Regulation - Evolution and Function
Transactions | Volume 102 | Number 1 | June 2010 | Pages 45-46
Professional Engineering Licensure: Opening Doors of Opportunity
Transactions | Volume 102 | Number 1 | June 2010 | Pages 47-48
Professional Engineering Registration Benefits: The Profession, the Public, the Person
Transactions | Volume 102 | Number 1 | June 2010 | Pages 49-50
Transactions | Volume 102 | Number 1 | June 2010 | Page 51
Training, Human Performance, and Workforce Development
Transactions | Volume 102 | Number 1 | June 2010 | Page 53
Regional Nuclear Workforce Development in the Central Savannah River Area
Transactions | Volume 102 | Number 1 | June 2010 | Pages 55-56
Knowledge Transfer and Peer Mentoring at SONGS
Transactions | Volume 102 | Number 1 | June 2010 | Pages 57-58
Needs Analysis of U.S. Nuclear Industry for Advanced/Senior Welding Technicians
Transactions | Volume 102 | Number 1 | June 2010 | Pages 59-60
Training on Scaling, Uncertainty, 3-D Coupled Calculations in Nuclear Technology
Transactions | Volume 102 | Number 1 | June 2010 | Pages 61-62
Innovations in Nuclear Engineering Education, Training, and Distance Learning
Transactions | Volume 102 | Number 1 | June 2010 | Page 63
An Assessment of a Game-Like 3-D Model for Training at NPPs
Transactions | Volume 102 | Number 1 | June 2010 | Pages 65-66
New Control Console for the Idaho State University AGN-201 Nuclear Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 67-68
Transactions | Volume 102 | Number 1 | June 2010 | Page 69
Focus on Communications: Credibility in a Digital Age-Panel
Transactions | Volume 102 | Number 1 | June 2010 | Page 70
Focus on Communications: Keeping Nuclear Communications Relevant-Panel
Transactions | Volume 102 | Number 1 | June 2010 | Page 71
Environmental Sciences: General
Transactions | Volume 102 | Number 1 | June 2010 | Page 75
New Meteorological Data for VENTSAR XL
Transactions | Volume 102 | Number 1 | June 2010 | Pages 77-78
An Economic Comparison of Nuclear and Natural Gas for Bitumen Extraction
Transactions | Volume 102 | Number 1 | June 2010 | Pages 79-80
Nuclear Assisted Coal and Gas to Liquids Production Analysis
Transactions | Volume 102 | Number 1 | June 2010 | Pages 81-82
Transactions | Volume 102 | Number 1 | June 2010 | Page 83
Hybrid Fission-Fusion Systems for Transmutation of Waste
Transactions | Volume 102 | Number 1 | June 2010 | Page 87
Nearer Term Fission-Fusion Hybrids: Status and Recent Results
Transactions | Volume 102 | Number 1 | June 2010 | Pages 89-90
The Laser Inertial Fusion Engine as a Weapons-Grade Plutonium Fuel Burner
Transactions | Volume 102 | Number 1 | June 2010 | Pages 91-92
The Georgia Tech SABR Studies of a Fusion-Fission Hybrid Fast Burner Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 93-94
A Conceptual Design of a Fusion-Fission Hybrid System
Transactions | Volume 102 | Number 1 | June 2010 | Pages 95-97
Transactions | Volume 102 | Number 1 | June 2010 | Page 98
Transactions | Volume 102 | Number 1 | June 2010 | Page 99
Methodology for Identifying Critical Fuel Cycle Parameters Governing Repository Capacity
Transactions | Volume 102 | Number 1 | June 2010 | Pages 101-102
Performance of Deep-Burn Spent Fuel in a Geological Repository
Transactions | Volume 102 | Number 1 | June 2010 | Pages 103-104
Development of Cermet High-Level Waste Forms
Transactions | Volume 102 | Number 1 | June 2010 | Pages 105-106
Evaluation of Radioactive Mineralized Waste Forms for Hanford Waste Treatment Plant Secondary Waste
Transactions | Volume 102 | Number 1 | June 2010 | Pages 107-108
Examination of Thermal Constraints on GTCC Waste Disposal
Transactions | Volume 102 | Number 1 | June 2010 | Pages 109-110
Safeguards, Nonproliferation, and Material Detection
Transactions | Volume 102 | Number 1 | June 2010 | Page 111
Design and Characterization of the Uranium Cylinder Assay System
Transactions | Volume 102 | Number 1 | June 2010 | Pages 113-114
Safeguards Verification with a Fissile Mass Flow Monitor in Gas Centrifuge Enrichment Plants
Transactions | Volume 102 | Number 1 | June 2010 | Pages 115-116
An Inverse Method for Locating a Radioactive Source Using a Distributed Array of Detectors
Transactions | Volume 102 | Number 1 | June 2010 | Pages 117-118
Time-Dependent Simulation of Neutron Detector Response
Transactions | Volume 102 | Number 1 | June 2010 | Pages 119-120
The Next-Generation Safeguards Professional Network
Transactions | Volume 102 | Number 1 | June 2010 | Page 121
Benchmarking UK National Nuclear Laboratory's Proliferation Resistance Assessment Methodology
Transactions | Volume 102 | Number 1 | June 2010 | Pages 122-123
Transactions | Volume 102 | Number 1 | June 2010 | Pages 124-125
Identification of Adequate Proliferation Resistance for a Closed Fuel Cycle
Transactions | Volume 102 | Number 1 | June 2010 | Pages 126-127
Transactions | Volume 102 | Number 1 | June 2010 | Page 128
New Developments in Advanced Fuel Cycles
Transactions | Volume 102 | Number 1 | June 2010 | Page 129
Development of an Analytical Fuel Cycle Model
Transactions | Volume 102 | Number 1 | June 2010 | Pages 131-132
Fuel Cycle Characteristics and Energy Policy Impacts of the Energy Multiplier Module (EM2) Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 133-134
Comprehensive Recycling of Used Nuclear Fuel - A Practical Alternative
Transactions | Volume 102 | Number 1 | June 2010 | Pages 135-136
Environmental Performance Analysis for the Korean Advanced Nuclear Fuel Cycle Concept
Transactions | Volume 102 | Number 1 | June 2010 | Pages 137-138
The DUROX Process: A Method to Reprocess Spent Nuclear Fuel
Transactions | Volume 102 | Number 1 | June 2010 | Pages 139-140
Uranium Resources for the Global Nuclear Renaissance
Transactions | Volume 102 | Number 1 | June 2010 | Pages 141-142
Behavior and Performance of Fuels for Advanced Fuel Cycles
Transactions | Volume 102 | Number 1 | June 2010 | Page 143
Actinide Transmutation Using Deep Burn in an Inert Matrix Fuel
Transactions | Volume 102 | Number 1 | June 2010 | Pages 145-146
Neutronics and Material Attractiveness Calculations for Thorium-Fueled PWRs
Transactions | Volume 102 | Number 1 | June 2010 | Pages 147-148
Lattice Expansion in Nuclear Fuels at High Burnups
Transactions | Volume 102 | Number 1 | June 2010 | Pages 149-150
Status Update on the NIFFTE High-Precision Fission Cross-Section Measurement Program
Transactions | Volume 102 | Number 1 | June 2010 | Pages 151-152
Analysis of Short- and Long-Term Behavior of Spent Fuel Decay Heat in a PWR
Transactions | Volume 102 | Number 1 | June 2010 | Pages 153-154
Human Factors, Instrumentation, and Controls: General
Transactions | Volume 102 | Number 1 | June 2010 | Page 157
Sliding Mode Estimation of Nuclear Systems - Point Reactor Model
Transactions | Volume 102 | Number 1 | June 2010 | Pages 159-160
Sliding Mode Estimation of Nuclear Systems - U-Tube Steam Generator
Transactions | Volume 102 | Number 1 | June 2010 | Pages 161-162
Feature Extraction for Data-Driven Fault Detection in Nuclear Power Plants
Transactions | Volume 102 | Number 1 | June 2010 | Pages 163-164
Situation Assessment Model for Nuclear Power Plant Operators and Its Application
Transactions | Volume 102 | Number 1 | June 2010 | Pages 165-166
Pulsed Eddy Current System for Monitoring the Wall Thinning of the Pipeline Covered with Insulator
Transactions | Volume 102 | Number 1 | June 2010 | Page 167
Nuclear Power Plant Productivity Improvement Opportunities with Extended Operating Life
Transactions | Volume 102 | Number 1 | June 2010 | Pages 168-169
NDMAS: Overview and Technical Details
Transactions | Volume 102 | Number 1 | June 2010 | Page 170
Neutron Beam Technique Developments and Utilizations at Research Reactors
Transactions | Volume 102 | Number 1 | June 2010 | Page 173
Transactions | Volume 102 | Number 1 | June 2010 | Pages 175-176
Transactions | Volume 102 | Number 1 | June 2010 | Pages 177-178
Further Development of TRIGSIMS Code System for Penn State Breazeale Reactor Fuel Management
Transactions | Volume 102 | Number 1 | June 2010 | Pages 179-180
An Assay of Uranium Ore with Compton-Suppressed Gamma Spectroscopy
Transactions | Volume 102 | Number 1 | June 2010 | Pages 181-182
Transactions | Volume 102 | Number 1 | June 2010 | Pages 183-184
Thermal-Hydraulic Modeling of Penn State Breazeale Reactor for Safety and Fuel Management Analysis
Transactions | Volume 102 | Number 1 | June 2010 | Pages 185-186
Transactions | Volume 102 | Number 1 | June 2010 | Pages 187-188
Isotopes and Radiation: General
Transactions | Volume 102 | Number 1 | June 2010 | Page 189
Application of Pattern Recognition Technique in Neutron-Based Elemental Analysis
Transactions | Volume 102 | Number 1 | June 2010 | Pages 191-192
Coincidence Counting Methods for Neutron Activation Analysis in Soil
Transactions | Volume 102 | Number 1 | June 2010 | Pages 193-194
Neutron Fluence Measurement Using Common PNP Transistors
Transactions | Volume 102 | Number 1 | June 2010 | Pages 195-196
Application of Queueing Theory for Detector Dead Time Estimation
Transactions | Volume 102 | Number 1 | June 2010 | Pages 197-198
Multi-Nuclide Decay Calculation and Recent Progresses in Methodology
Transactions | Volume 102 | Number 1 | June 2010 | Pages 199-200
A Demonstration of Self-Shielding for the Analysis of Gold with Neutron Activation Analysis
Transactions | Volume 102 | Number 1 | June 2010 | Pages 201-202
Current Issues in Computational Methods-Roundtable/Panel
Transactions | Volume 102 | Number 1 | June 2010 | Page 205
Transactions | Volume 102 | Number 1 | June 2010 | Page 207
Variable Change Technique Applied in Constrained Inverse Transport Applications
Transactions | Volume 102 | Number 1 | June 2010 | Pages 209-212
A Hybrid Differential Evolution/Levenberg-Marquardt Method for Solving Inverse Transport Problems
Transactions | Volume 102 | Number 1 | June 2010 | Pages 213-215
A Hybrid Monte Carlo-Deterministic Method for Global Binary Stochastic Medium Transport Problems
Transactions | Volume 102 | Number 1 | June 2010 | Pages 216-219
Enhanced Correlated Sampling by Source Biasing for Pin Diversion Analysis
Transactions | Volume 102 | Number 1 | June 2010 | Pages 220-221
Spatial Discretization Error Reduction in Thermal Radiative Transfer
Transactions | Volume 102 | Number 1 | June 2010 | Pages 222-223
Physics-Based Time Step Controller Improvements in Thermal Radiative Transfer
Transactions | Volume 102 | Number 1 | June 2010 | Pages 224-226
Uncertainty Quantification in Nuclear System Modeling and Simulation
Transactions | Volume 102 | Number 1 | June 2010 | Page 227
Uncertainty Methods and Approaches in Nuclear System Safety
Transactions | Volume 102 | Number 1 | June 2010 | Pages 229-230
Modeling of the Uncertainty of Nuclear Fuel Thermal Behavior
Transactions | Volume 102 | Number 1 | June 2010 | Pages 231-232
Transactions | Volume 102 | Number 1 | June 2010 | Pages 233-234
Using Automatic Differentiation in Sensitivity Analysis of Nuclear Simulation Models
Transactions | Volume 102 | Number 1 | June 2010 | Pages 235-237
Transactions | Volume 102 | Number 1 | June 2010 | Pages 238-239
Adjoint-Based Eigenvalue Sensitivity to Geometry Perturbations
Transactions | Volume 102 | Number 1 | June 2010 | Pages 240-243
Imprecise Probabilities as an Engineering Tool to Handle Uncertainties in Nuclear Safety Studies
Transactions | Volume 102 | Number 1 | June 2010 | Pages 244-245
Scenario Aggregation in Dynamic PRA Uncertainty Quantification
Transactions | Volume 102 | Number 1 | June 2010 | Pages 246-249
Explicit Uncertainty Analysis for Tritium Breeding in a Laser Inertial Fusion Engine
Transactions | Volume 102 | Number 1 | June 2010 | Pages 250-251
Computational Methods and Mathematical Modeling
Transactions | Volume 102 | Number 1 | June 2010 | Page 253
Some Considerations on Stochastic Neutron Populations
Transactions | Volume 102 | Number 1 | June 2010 | Pages 255-257
The Probability of Initiation in MCNP
Transactions | Volume 102 | Number 1 | June 2010 | Pages 258-260
Transactions | Volume 102 | Number 1 | June 2010 | Pages 261-263
A New Multiscale Approach to Nuclear Fuel Simulations: Atomistic Validation of Kinetic Method
Transactions | Volume 102 | Number 1 | June 2010 | Pages 264-265
Data, Analysis, and Operations in Nuclear Criticality Safety - I
Transactions | Volume 102 | Number 1 | June 2010 | Page 269
Criticality Safety Design Challenges at the MOX Fuel Fabrication Facility
Transactions | Volume 102 | Number 1 | June 2010 | Pages 271-272
Benchmark Evaluation of Uranium Metal Annuli and Cylinders with Beryllium Reflectors
Transactions | Volume 102 | Number 1 | June 2010 | Pages 273-274
Calculated Critical Masses of 242mAm for Unreflected Spherical Homogeneous Water Moderated Systems
Transactions | Volume 102 | Number 1 | June 2010 | Pages 275-277
Transactions | Volume 102 | Number 1 | June 2010 | Pages 278-280
Direct Perturbation Calculation for TSUNAMI Sensitivity Coefficient Validation
Transactions | Volume 102 | Number 1 | June 2010 | Pages 281-282
Validation of the SCALE Criticality Safety Codes and Data Using Reviewed Benchmark Models
Transactions | Volume 102 | Number 1 | June 2010 | Pages 283-286
Data, Analysis, and Operations in Nuclear Criticality Safety - II
Transactions | Volume 102 | Number 1 | June 2010 | Page 287
Application of Design-Basis Accident Analysis at Sellafield, United Kingdom
Transactions | Volume 102 | Number 1 | June 2010 | Page 289
The Revised OB-1 Method for Metal-Water Systems
Transactions | Volume 102 | Number 1 | June 2010 | Pages 290-291
Transactions | Volume 102 | Number 1 | June 2010 | Pages 292-294
Computational Advances in Criticality Safety Analysis
Transactions | Volume 102 | Number 1 | June 2010 | Page 295
Criticality Accident Alarm System Modeling Made Easy with SCALE 6.1
Transactions | Volume 102 | Number 1 | June 2010 | Pages 297-299
Reducing Errors: Developments at Sellafield to Aid the Criticality Assessor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 300-301
Revisiting the "K-effective of the World" Problem
Transactions | Volume 102 | Number 1 | June 2010 | Pages 302-304
COG - Special Features of Interest to Criticality Safety Practitioners
Transactions | Volume 102 | Number 1 | June 2010 | Pages 305-306
Bias Assessment of 233U Systems Using a SCALE TSURFER
Transactions | Volume 102 | Number 1 | June 2010 | Pages 307-311
Hazard Analysis of Nuclear Criticality Safety Evaluations-Tutorial - I
Transactions | Volume 102 | Number 1 | June 2010 | Page 312
Hazard Analysis of Nuclear Criticality Safety Evaluations-Tutorial - II
Transactions | Volume 102 | Number 1 | June 2010 | Page 313
Nuclear Criticality Safety Standards-Forum
Transactions | Volume 102 | Number 1 | June 2010 | Page 314
Proposed Solutions for SMR Generic Licensing Issues-Panel
Transactions | Volume 102 | Number 1 | June 2010 | Page 317
Severe Accident Analyses for Current and Advanced Reactors
Transactions | Volume 102 | Number 1 | June 2010 | Page 319
Reliability Evaluation for the Passive Residual Heat Removal System of SMART Integral Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 321-323
Spray Sensitivity Study Performed with the MELCOR Code
Transactions | Volume 102 | Number 1 | June 2010 | Pages 324-326
Evaluation of the Water Spray Impact on Premixed Hydrogen-Air-Steam Flames Propagation
Transactions | Volume 102 | Number 1 | June 2010 | Pages 327-328
Mitigation Effect of Feed-Bleed on In-Vessel Release of Fission Products
Transactions | Volume 102 | Number 1 | June 2010 | Pages 329-330
Plant-Specific Severe Accident Management Strategies Development for Pressurized Heavy Water Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Page 331
Progression of Severe Accidents in the U.S. EPR
Transactions | Volume 102 | Number 1 | June 2010 | Pages 332-333
Regulatory and Safety Analyses for Severe and Design-Basis Accidents
Transactions | Volume 102 | Number 1 | June 2010 | Page 335
The BEPU (Best Estimate Plus Uncertainty) Challenge in Current Licensing of Nuclear Reactors
Transactions | Volume 102 | Number 1 | June 2010 | Pages 337-338
Severe Accident Consequence Assessment Regulatory Guidance: A Critique
Transactions | Volume 102 | Number 1 | June 2010 | Page 339
Transactions | Volume 102 | Number 1 | June 2010 | Pages 340-341
A Probabilistic DNBR Analysis Method
Transactions | Volume 102 | Number 1 | June 2010 | Pages 342-343
Transactions | Volume 102 | Number 1 | June 2010 | Page 344
Advances in Safety Assessment Methods and Programs
Transactions | Volume 102 | Number 1 | June 2010 | Page 345
IAEA Safety Assessment Competency and Capacity Building Initiatives
Transactions | Volume 102 | Number 1 | June 2010 | Pages 347-348
Current IAEA Activities in Support of IRIDM and PSA
Transactions | Volume 102 | Number 1 | June 2010 | Pages 349-350
The Effects of ESFAS STI Extension on the Unavailability of ESF Actuated Components
Transactions | Volume 102 | Number 1 | June 2010 | Pages 351-352
Optimizing Transportation Parameters to Minimize the Risk of Hazardous Shipments
Transactions | Volume 102 | Number 1 | June 2010 | Pages 353-354
Development of Age-Dependent Failure Models for Incorporation into Existing NPP PRAs
Transactions | Volume 102 | Number 1 | June 2010 | Pages 355-356
Operations and Power: General - I
Transactions | Volume 102 | Number 1 | June 2010 | Page 359
Vermont Yankee License Renewal and the State of Vermont's Involvement
Transactions | Volume 102 | Number 1 | June 2010 | Pages 361-362
Emergency Planning Considerations for Small- and Medium-Sized Reactors
Transactions | Volume 102 | Number 1 | June 2010 | Pages 363-364
Hyperion Power Module, Safety and Operational Features for Reactor Operations
Transactions | Volume 102 | Number 1 | June 2010 | Pages 365-366
Remote Small-Modular Helium Reactor (RS-MHR)
Transactions | Volume 102 | Number 1 | June 2010 | Page 367
Operations and Power: General - II
Transactions | Volume 102 | Number 1 | June 2010 | Page 369
Best in Class SSC Life Cycle Management
Transactions | Volume 102 | Number 1 | June 2010 | Pages 371-372
Corrective Actions to Resolve the Check Valve Damage
Transactions | Volume 102 | Number 1 | June 2010 | Pages 373-374
Update on LWR Sustainability Program R&D Overview-Panel
Transactions | Volume 102 | Number 1 | June 2010 | Page 375
Challenges for New Plant Workforce Development and Training
Transactions | Volume 102 | Number 1 | June 2010 | Page 377
Estimating the Demand for the U.S. Nuclear Industry Workforce
Transactions | Volume 102 | Number 1 | June 2010 | Page 379
Will the New Plant Workforce Be in Place in Time?
Transactions | Volume 102 | Number 1 | June 2010 | Pages 380-381
Managing the Uncertainty in Delivering New Plant Projects
Transactions | Volume 102 | Number 1 | June 2010 | Pages 382-383
Operator Training Challenges for New Generation Reactors
Transactions | Volume 102 | Number 1 | June 2010 | Pages 384-385
Instructor Development During High-Volume New Reactor Training
Transactions | Volume 102 | Number 1 | June 2010 | Pages 386-387
Developing the Texas Nuclear Workforce of the Future
Transactions | Volume 102 | Number 1 | June 2010 | Pages 388-389
Plant Performance After Power Uprate-Panel
Transactions | Volume 102 | Number 1 | June 2010 | Page 390
Licensing of a Digital Upgrade - I
Transactions | Volume 102 | Number 1 | June 2010 | Page 391
Licensing of the Oconee Nuclear Station Digital Protection System
Transactions | Volume 102 | Number 1 | June 2010 | Pages 393-394
Wolf Creek's Single Platform Safety I&C Architecture
Transactions | Volume 102 | Number 1 | June 2010 | Pages 395-396
Developing Licensable FPGA-Based Safety Systems
Transactions | Volume 102 | Number 1 | June 2010 | Pages 397-398
Maintaining the Qualification of an I&C Platform
Transactions | Volume 102 | Number 1 | June 2010 | Pages 399-400
The 10 CFR 50.59 Rule and EPRI TR-102348/NEI 01-01 - Lessons Learned
Transactions | Volume 102 | Number 1 | June 2010 | Pages 401-404
Pilot Plant Experience with Interim Staff Guidance #6 - Licensing Process
Transactions | Volume 102 | Number 1 | June 2010 | Pages 405-407
Licensing of a Digital Upgrade - II-Panel
Transactions | Volume 102 | Number 1 | June 2010 | Page 408
Lessons Learned in the 10 CFR 52 Process: A Status Report-Panel
Transactions | Volume 102 | Number 1 | June 2010 | Page 409
Advanced/Generation-IV Reactors
Transactions | Volume 102 | Number 1 | June 2010 | Page 411
A Systematic Method to Reduce New Nuclear Capital Costs
Transactions | Volume 102 | Number 1 | June 2010 | Pages 413-414
Fluoride Salt Reactors (FHRs) and the Five Imperatives of Nuclear Energy
Transactions | Volume 102 | Number 1 | June 2010 | Page 415
Transactions | Volume 102 | Number 1 | June 2010 | Pages 416-417
Ultrasonic Linear Array for Under Sodium Viewing
Transactions | Volume 102 | Number 1 | June 2010 | Pages 418-419
Retrieval of Damaged Components from Experimental Fast Reactor Joyo Reactor Vessel
Transactions | Volume 102 | Number 1 | June 2010 | Pages 420-421
Current Topics in Radiation Protection and Shielding-Roundtable
Transactions | Volume 102 | Number 1 | June 2010 | Page 425
Modeling and Simulation Efforts for Nuclear Nonproliferation - I
Transactions | Volume 102 | Number 1 | June 2010 | Page 427
Three-Dimensional Source Localization Using Uncollimated Arrays
Transactions | Volume 102 | Number 1 | June 2010 | Pages 429-430
Transactions | Volume 102 | Number 1 | June 2010 | Pages 431-433
Burnup-Dependent Neutron Source Term for Gross Neutron Detection Techniques
Transactions | Volume 102 | Number 1 | June 2010 | Pages 434-436
Delayed Neutron Measurement System for Pu Mass Determination in Spent Fuel Assembly
Transactions | Volume 102 | Number 1 | June 2010 | Pages 437-438
Determining Plutonium Mass in Spent Fuel Using 252Cf Interrogation with Prompt Neutron
Transactions | Volume 102 | Number 1 | June 2010 | Pages 439-441
Transactions | Volume 102 | Number 1 | June 2010 | Pages 442-444
Modeling and Simulation Efforts for Nuclear Nonproliferation - II
Transactions | Volume 102 | Number 1 | June 2010 | Page 445
Modeling and Simulation's Role in Determining Plutonium Mass in Spent Fuel
Transactions | Volume 102 | Number 1 | June 2010 | Pages 447-448
Transactions | Volume 102 | Number 1 | June 2010 | Pages 449-450
Determining Fissile Content in PWR Assemblies Using a Passive Neutron Albedo Reactivity Technique
Transactions | Volume 102 | Number 1 | June 2010 | Pages 451-453
Transactions | Volume 102 | Number 1 | June 2010 | Pages 454-455
Delayed Gamma Instrument for Determining Plutonium Mass in Spent Nuclear Fuel
Transactions | Volume 102 | Number 1 | June 2010 | Pages 456-457
Modeling Higher Resolution Scintillators for Nonproliferation
Transactions | Volume 102 | Number 1 | June 2010 | Pages 458-459
Radiation Protection and Shielding: General
Transactions | Volume 102 | Number 1 | June 2010 | Page 461
Monte Carlo Modeling for Multivariate Optimization of Transformational Neutron Detectors
Transactions | Volume 102 | Number 1 | June 2010 | Pages 463-464
Neutron and Gamma Multiplicity Counting with STRAW Detectors
Transactions | Volume 102 | Number 1 | June 2010 | Pages 465-466
Prototype Neutron Energy Spectrometer
Transactions | Volume 102 | Number 1 | June 2010 | Pages 467-468
New Radiation Protection Material from the Recycling Materials
Transactions | Volume 102 | Number 1 | June 2010 | Pages 469-470
Computational Resources for Radiation Modeling
Transactions | Volume 102 | Number 1 | June 2010 | Page 471
Transactions | Volume 102 | Number 1 | June 2010 | Pages 473-474
A Comparative Analysis of MicroShield and RadSrc Libraries
Transactions | Volume 102 | Number 1 | June 2010 | Pages 475-476
The Helium-3 Shortage and the Future of Neutron Detection-Panel
Transactions | Volume 102 | Number 1 | June 2010 | Page 477
Point Kernel Shielding Techniques: A Tutorial on Quads/QAD MOD
Transactions | Volume 102 | Number 1 | June 2010 | Page 478
Current Issues in LWR Core Design and Reactor Engineering Support-Panel
Transactions | Volume 102 | Number 1 | June 2010 | Page 481
Transactions | Volume 102 | Number 1 | June 2010 | Page 483
Improving the Thermal Conductivity of UO2 Fuel with the Addition of Graphite Fibers
Transactions | Volume 102 | Number 1 | June 2010 | Pages 485-487
Magnesium Oxide: An Improved Reflector for Blanket-Free Fast Reactors
Transactions | Volume 102 | Number 1 | June 2010 | Pages 488-489
Fission Measurements in Support of Advanced Fuel Cycle Research
Transactions | Volume 102 | Number 1 | June 2010 | Pages 490-491
Empirical Diffusion Coefficients for Natural-Uranium CANDU Lattices
Transactions | Volume 102 | Number 1 | June 2010 | Pages 492-494
Monte Carlo Depletion Calculation for the AGR-1 TRISO Particle Irradiation Test
Transactions | Volume 102 | Number 1 | June 2010 | Pages 495-496
Minimization of the Decay Heat in an MHR for TRU Deep-Burn
Transactions | Volume 102 | Number 1 | June 2010 | Pages 497-498
Evaluation of Power Peaking Factor in VVER-1000 Using MCNP
Transactions | Volume 102 | Number 1 | June 2010 | Pages 499-500
Transactions | Volume 102 | Number 1 | June 2010 | Page 501
MCNP Calculations of Subcritical Fixed Source and Fission Multiplication Factors
Transactions | Volume 102 | Number 1 | June 2010 | Pages 503-505
Comparison of Resonance Parameter Covariance Generation Using CONRAD and SAMMY Computer Codes
Transactions | Volume 102 | Number 1 | June 2010 | Pages 506-508
Generation of Graphite Thermal Neutron Scattering Libraries Using Classical Molecular Dynamics
Transactions | Volume 102 | Number 1 | June 2010 | Pages 509-510
Transactions | Volume 102 | Number 1 | June 2010 | Page 511
Improved Capabilities of Whole-Core Transport Code DeCART for Prismatic VHTR Analysis
Transactions | Volume 102 | Number 1 | June 2010 | Pages 513-514
MCNP5 Analysis of the Fort St. Vrain High-Temperature Gas-Cooled Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 515-516
Comparison of CPM-3 Thorium Pin Cell Benchmark with Other Computer Codes
Transactions | Volume 102 | Number 1 | June 2010 | Pages 517-518
Coupled Nuclear-Thermal-Hydraulic Calculations for VHTRs
Transactions | Volume 102 | Number 1 | June 2010 | Pages 519-521
Transactions | Volume 102 | Number 1 | June 2010 | Page 523
Performance and Convergence Issue of Coarse-Mesh Methods for Diffusion Calculations
Transactions | Volume 102 | Number 1 | June 2010 | Pages 525-527
Overlap Local/Global Iteration Framework for Monte Carlo/Diffusion Nodal Calculations
Transactions | Volume 102 | Number 1 | June 2010 | Pages 528-532
Nonlinear Coarse Mesh Transport Using the Jacobian-Free Newton-Krylov Method
Transactions | Volume 102 | Number 1 | June 2010 | Pages 533-535
A Resonance Integral Table-Based Iteration Method for Resonance Treatment in Lattice Calculations
Transactions | Volume 102 | Number 1 | June 2010 | Pages 536-537
Comparison of Krylov and p-Multigrid Solutions of Orthogonal Response Matrix Equations
Transactions | Volume 102 | Number 1 | June 2010 | Pages 538-539
Response Matrix Acceleration Methods Based on Orthogonalization and Domain Decomposition
Transactions | Volume 102 | Number 1 | June 2010 | Pages 540-542
Development of a 1D Boiling Water Reactor Benchmark Specification
Transactions | Volume 102 | Number 1 | June 2010 | Pages 543-545
Development of a 1D Pressurized Water Reactor Benchmark Specification
Transactions | Volume 102 | Number 1 | June 2010 | Pages 546-548
Reactor Physics Design, Validation, and Operating Experience
Transactions | Volume 102 | Number 1 | June 2010 | Page 549
RERTR Fuel Plate Fission Power Deposition Estimation in ATR by MCNP Method
Transactions | Volume 102 | Number 1 | June 2010 | Pages 551-553
The Use of Perturbation Theory to Augment Advanced Test Reactor Modeling Capabilities
Transactions | Volume 102 | Number 1 | June 2010 | Pages 554-555
Preservation of FFTF Data Related to Passive Safety Testing
Transactions | Volume 102 | Number 1 | June 2010 | Pages 556-557
Assessment of Fuel Manufacturing Uncertainty Effect on NRAD Reactor Criticality
Transactions | Volume 102 | Number 1 | June 2010 | Pages 558-559
HFIR Post-Irradiation Curium Target Rod Nuclide Inventory Calculations
Transactions | Volume 102 | Number 1 | June 2010 | Pages 560-561
Recent Reload Design Experience of Digital PWR in Korea
Transactions | Volume 102 | Number 1 | June 2010 | Pages 562-563
Introduction of the Core Model Simulating Load-Follow Operation
Transactions | Volume 102 | Number 1 | June 2010 | Pages 564-565
Advances in Small- and Medium-Sized Reactor Designs
Transactions | Volume 102 | Number 1 | June 2010 | Page 567
Design Features, Economics, and Licensing of the 4S Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 569-570
ELECTRA - European Lead-Cooled Training Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 571-572
Nitride-Fueled Accelerator-Driven System with High Source Efficiency
Transactions | Volume 102 | Number 1 | June 2010 | Pages 573-574
A Preliminary Physics Study of a Long-Life Modular Gas-Cooled Fast Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 575-576
A Small Gas-Cooled Reactor for Space and Terrestrial Applications
Transactions | Volume 102 | Number 1 | June 2010 | Pages 577-578
Pebble-Bed System Features and Fuel Utilization
Transactions | Volume 102 | Number 1 | June 2010 | Pages 579-580
Conceptual Design of an Annular-Fueled Superheat Boiling Water Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 581-583
Impact of Small Modular Reactors in a Carbon Constrained Economy
Transactions | Volume 102 | Number 1 | June 2010 | Pages 584-585
Compact, Deployable Reactors for Power and Fuel in Remote Regions
Transactions | Volume 102 | Number 1 | June 2010 | Pages 586-587
Transactions | Volume 102 | Number 1 | June 2010 | Page 591
Three-Field Annular Flow Modeling Package - Part I: Interfacial Structure and Drag
Transactions | Volume 102 | Number 1 | June 2010 | Pages 593-595
Three-Field Annular Flow Modeling Package - Part II: Entrainment Rate Models
Transactions | Volume 102 | Number 1 | June 2010 | Pages 596-598
Numerical Analysis of the Effect of Two-Phase Flow Maldistribution on Heat Transfer Performance
Transactions | Volume 102 | Number 1 | June 2010 | Pages 599-600
Method of Characteristics for RELAP5 Simulations
Transactions | Volume 102 | Number 1 | June 2010 | Pages 601-602
Effect of Gap Nodalization on RELAP5 Heat Conduction Calculations
Transactions | Volume 102 | Number 1 | June 2010 | Pages 603-605
Transactions | Volume 102 | Number 1 | June 2010 | Page 607
Scaling Analysis for Depressurization of High-Temperature Test Facility
Transactions | Volume 102 | Number 1 | June 2010 | Pages 609-610
Scaling a Pressurized Conduction Cooldown Event in an HTGR
Transactions | Volume 102 | Number 1 | June 2010 | Pages 611-612
Scaling Analysis and Numerical Comparison for the Core in the High-Temperature Test Facility
Transactions | Volume 102 | Number 1 | June 2010 | Pages 613-614
Daily Thermal Results of the AGR-1 Experiment in the Advanced Test Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 615-616
RELAP5 Loss of Flow Analysis of Deep Burn High-Temperature Prismatic Reactor Core
Transactions | Volume 102 | Number 1 | June 2010 | Pages 617-618
Measurements of Graphite Particle Generation by Pebble Abrasion
Transactions | Volume 102 | Number 1 | June 2010 | Pages 619-620
Pressure Drop in a Pebble Bed Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 621-622
Transactions | Volume 102 | Number 1 | June 2010 | Pages 623-625
Computational Thermal Hydraulics
Transactions | Volume 102 | Number 1 | June 2010 | Page 627
Numerical Simulation of Exiting Coolant Flow in a Pool-Type Research Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 629-630
Large-Break LOCA Analysis of a Natural Circulation Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 631-633
PISO-SIMPLE-Type Algorithms for Transient Incompressible Turbulent Flows
Transactions | Volume 102 | Number 1 | June 2010 | Page 634
Numerical Simulation of Thermal Hydraulics of Supercritical Fluid in a 7-Rod Bundle
Transactions | Volume 102 | Number 1 | June 2010 | Pages 635-636
Numerical Computation of Intermittent Flow in Fuel Channel
Transactions | Volume 102 | Number 1 | June 2010 | Pages 637-638
Analysis of BR2 Loss of Flow Test C
Transactions | Volume 102 | Number 1 | June 2010 | Pages 639-640
CFD Prediction of Heat Transfer Deterioration to Supercritical Water
Transactions | Volume 102 | Number 1 | June 2010 | Pages 641-642
Thermal-Hydraulic System Analysis Input Parameters Adjustment for the IRIS Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 643-644
Scaling Analysis Techniques-Tutorial
Transactions | Volume 102 | Number 1 | June 2010 | Page 645
General Thermal Hydraulics - I
Transactions | Volume 102 | Number 1 | June 2010 | Page 647
CHF Enhancement in Flow Boiling Using Al2O3 Nano-Fluid and Al2O3 Nano-Particle Deposited Tube
Transactions | Volume 102 | Number 1 | June 2010 | Pages 649-650
Gas Void Fraction Determination Using an Innovative Two-Point Correlation Method
Transactions | Volume 102 | Number 1 | June 2010 | Pages 651-652
S-RELAP5 Best-Estimate Medium-Break LOCA Analysis for US EPR™ Plant
Transactions | Volume 102 | Number 1 | June 2010 | Pages 653-654
Transactions | Volume 102 | Number 1 | June 2010 | Pages 655-657
Impact of Power Uprate on BWR Thermal-Hydraulic Safety Margins
Transactions | Volume 102 | Number 1 | June 2010 | Pages 658-659
Investigation of Intermittent Flow Heat Transfer in Horizontal Fuel Channel
Transactions | Volume 102 | Number 1 | June 2010 | Pages 660-661
Predictability of Boron Transport Phenomenon in PWR Based on PKL Experimental Program
Transactions | Volume 102 | Number 1 | June 2010 | Pages 662-663
On the Cooling Technology of Nuclear Power Plants
Transactions | Volume 102 | Number 1 | June 2010 | Pages 664-666
Improvements to Reactor, Power, and Control Simulation (RPCSIM) Model Components
Transactions | Volume 102 | Number 1 | June 2010 | Pages 667-668
General Thermal Hydraulics - II
Transactions | Volume 102 | Number 1 | June 2010 | Page 669
Convective Heat Transfer in MHD Flows in Fusion Reactor Blankets
Transactions | Volume 102 | Number 1 | June 2010 | Pages 671-673
Inverse Heat Conduction Problem with Jet Cooling
Transactions | Volume 102 | Number 1 | June 2010 | Pages 674-675
Noncondensable Gases Effect on Steam Condensation Heat Transfer in Horizontal Tube Bundle
Transactions | Volume 102 | Number 1 | June 2010 | Pages 676-677
Enhancement of Passive Heat Removal for Add-On Shielding in a Spent Fuel Dry Storage System
Transactions | Volume 102 | Number 1 | June 2010 | Pages 678-679
Safety Margin Assessment Methodology Due to Aging-Induced Thermal-Hydraulic Effects
Transactions | Volume 102 | Number 1 | June 2010 | Page 680
Unsteady State Heat Transfer Analysis in a Magnesio-Thermic-Reduction Reactor for Uranium Production
Transactions | Volume 102 | Number 1 | June 2010 | Pages 681-682
Transactions | Volume 102 | Number 1 | June 2010 | Pages 683-684
Thermal Performance Analysis for Small Ion-Exchange Cesium Removal Process
Transactions | Volume 102 | Number 1 | June 2010 | Pages 685-687
Plenary - Research and Development to Bridge Science and Technology
Transactions | Volume 102 | Number 1 | June 2010 | Page 691
Fuels and Materials for Extended Lifetimes in Light Water Reactors
Transactions | Volume 102 | Number 1 | June 2010 | Page 693
The Department of Energy Light Water Reactor Sustainability Program
Transactions | Volume 102 | Number 1 | June 2010 | Pages 695-696
Transactions | Volume 102 | Number 1 | June 2010 | Page 697
Enabling Life Beyond 60: Materials Degradation Needs and Research
Transactions | Volume 102 | Number 1 | June 2010 | Page 698
Transactions | Volume 102 | Number 1 | June 2010 | Page 699
Development and Testing of Radiation Tolerant Clad Materials for Nuclear Fuels
Transactions | Volume 102 | Number 1 | June 2010 | Page 701
MAX Phases and Their Potential for Nuclear Reactor Applications
Transactions | Volume 102 | Number 1 | June 2010 | Pages 702-703
Welding Challenges in Generation IV Nuclear Systems
Transactions | Volume 102 | Number 1 | June 2010 | Pages 704-706
Transactions | Volume 102 | Number 1 | June 2010 | Pages 707-708
Transactions | Volume 102 | Number 1 | June 2010 | Page 709
Radiation Damage in Model FeCr Alloys and FM Steels
Transactions | Volume 102 | Number 1 | June 2010 | Pages 711-712
Deformation Mechanisms in Ferritic/Martensitic Steels
Transactions | Volume 102 | Number 1 | June 2010 | Pages 713-714
Radiation Induced Segregation in Ferritic-Martensitic Steels
Transactions | Volume 102 | Number 1 | June 2010 | Pages 715-716
Miniature Samples for Condition Based Monitoring in Nuclear Power Plants
Transactions | Volume 102 | Number 1 | June 2010 | Page 717
Transactions | Volume 102 | Number 1 | June 2010 | Page 719
Transactions | Volume 102 | Number 1 | June 2010 | Pages 721-722
Engineered Coatings for Ni Alloys in High-Temperature Reactors
Transactions | Volume 102 | Number 1 | June 2010 | Page 723
Aging and Environmental Effects on VHTR High-Temperature Alloys
Transactions | Volume 102 | Number 1 | June 2010 | Pages 724-725
Expediting ASME HTGR Code Rules
Transactions | Volume 102 | Number 1 | June 2010 | Page 726
Transactions | Volume 102 | Number 1 | June 2010 | Page 727
Transactions | Volume 102 | Number 1 | June 2010 | Page 729
Issues on the Evaluation of Creep-Fatigue Interaction
Transactions | Volume 102 | Number 1 | June 2010 | Page 730
High-Temperature Crack Growth Considerations for Next Generation Nuclear Reactors
Transactions | Volume 102 | Number 1 | June 2010 | Pages 731-732
Enabling Tools and Research Facilities
Transactions | Volume 102 | Number 1 | June 2010 | Page 733
The Advanced Test Reactor National Scientific User Facility
Transactions | Volume 102 | Number 1 | June 2010 | Pages 735-736
The HFIR Reactor As a Test Bed for Fast Neutron Fuels and Structural Materials
Transactions | Volume 102 | Number 1 | June 2010 | Pages 737-738
Transactions | Volume 102 | Number 1 | June 2010 | Pages 739-740
Advanced Photon Source Overview and Capabilities for Nuclear Fuels and Materials Research
Transactions | Volume 102 | Number 1 | June 2010 | Page 741
Irradiation Tests for the Development of FBR in Joyo
Transactions | Volume 102 | Number 1 | June 2010 | Pages 742-743
Atomic Scale Characterization of Nuclear Reactor Materials
Transactions | Volume 102 | Number 1 | June 2010 | Page 744
Transactions | Volume 102 | Number 1 | June 2010 | Page 745
Mesoscale Simulation of Microstructure Evolution in Irradiated Materials
Transactions | Volume 102 | Number 1 | June 2010 | Pages 747-748
Modeling Deep Burn Particulate Nuclear Fuel
Transactions | Volume 102 | Number 1 | June 2010 | Pages 749-750
Modeling of Ag Diffusion in TRISO Coated Fuel Particles
Transactions | Volume 102 | Number 1 | June 2010 | Pages 751-752
Spark Plasma Sintering as a Fabrication Process for Functional Oxides
Transactions | Volume 102 | Number 1 | June 2010 | Pages 753-755
Transactions | Volume 102 | Number 1 | June 2010 | Page 757
Transactions | Volume 102 | Number 1 | June 2010 | Pages 759-760
Fuel Cladding Chemical Interaction in Metallic Nuclear Fuels
Transactions | Volume 102 | Number 1 | June 2010 | Pages 761-762
Liquid-Metal-Bonded Hydride Fuels for LWRs
Transactions | Volume 102 | Number 1 | June 2010 | Pages 763-764
Irradiation Effects in UO2 and CeO2
Transactions | Volume 102 | Number 1 | June 2010 | Pages 765-766
Transactions | Volume 102 | Number 1 | June 2010 | Page 767
Development of TRU-TRISO Fuel for Deep Burn
Transactions | Volume 102 | Number 1 | June 2010 | Pages 769-770
Particle Fuel for Future Reactor Systems
Transactions | Volume 102 | Number 1 | June 2010 | Pages 771-772
HTR Fuel Testing in AVR and in MTRs
Transactions | Volume 102 | Number 1 | June 2010 | Page 773
New Generation Nuclear Fuel Structures: Dense Particles in Selectively Soluble Matrix
Transactions | Volume 102 | Number 1 | June 2010 | Page 774
Transactions | Volume 102 | Number 1 | June 2010 | Page 775
Radiation Chemistry of Water in Contact with Nuclear Fuels and Structural Materials
Transactions | Volume 102 | Number 1 | June 2010 | Page 777
Corrosion in a Supercritical Water-Cooled Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Page 778
Transactions | Volume 102 | Number 1 | June 2010 | Pages 779-780
Corrosion Studies of High-Temperature Alloys in Molten Chloride Salt
Transactions | Volume 102 | Number 1 | June 2010 | Pages 781-782
Alloys Compatibility in Molten Salt Fluorides: Kurchatov Institute Related Experience
Transactions | Volume 102 | Number 1 | June 2010 | Pages 783-784
Transactions | Volume 102 | Number 1 | June 2010 | Page 785
Ceramic Plasma-Sprayed Coating of Melting Crucible for Metal Fuel Slugs
Transactions | Volume 102 | Number 1 | June 2010 | Pages 787-788
Evaluations of Processing and Properties of HT-UPS Austenitic Stainless Steel
Transactions | Volume 102 | Number 1 | June 2010 | Page 789
Using Graphitic Foam as the Bonding Material in Metal Fuel Pins for Sodium Fast Reactors
Transactions | Volume 102 | Number 1 | June 2010 | Pages 790-792
Corrosion Behavior of Alloy 690 and Effects of Grain Boundary Engineering
Transactions | Volume 102 | Number 1 | June 2010 | Pages 793-794
Transactions | Volume 102 | Number 1 | June 2010 | Page 795
Hydrogen Permeability in VHTR Heat Exchanger Candidate Materials
Transactions | Volume 102 | Number 1 | June 2010 | Pages 796-797
Effect of Proton Irradiation on ZrC with Varied Stoichiometry
Transactions | Volume 102 | Number 1 | June 2010 | Pages 798-799
Microchemical Variations in Proton Irradiated 9 wt.% Chromium BCC Steels
Transactions | Volume 102 | Number 1 | June 2010 | Pages 800-801
Design of Alumina Forming FeCrAl Steels for Lead or Lead-Bismuth Cooled Fast Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 802-803
Corrosion of Ferritic-Martensitic Steels in Steam Compared to Supercritical Water
Transactions | Volume 102 | Number 1 | June 2010 | Pages 804-805
An Investigation of the Mechanical Properties of Fresh and Irradiated U-Mo Fuels
Transactions | Volume 102 | Number 1 | June 2010 | Pages 806-807
Characterization of Vanadium-Lined Fuel Cladding with Various Fabrication Parameters
Transactions | Volume 102 | Number 1 | June 2010 | Pages 808-809
Lead-Bismuth Eutectic Technology for HYPERION
Transactions | Volume 102 | Number 1 | June 2010 | Pages 810-811
Growth and Analysis of Thin Films of U3O8 and UO2 on Sapphire Substrates
Transactions | Volume 102 | Number 1 | June 2010 | Pages 812-813
Microstructure Study of U-7wt%Mo/Al-2wt%Si Dispersion Fuel Focusing on Bubble Evolution
Transactions | Volume 102 | Number 1 | June 2010 | Page 814
Measurement of Radiation Enhanced Diffusion of La in CeO2
Transactions | Volume 102 | Number 1 | June 2010 | Pages 815-816
TRISO Fuels: Ab Initio Study of Pd and SiC
Transactions | Volume 102 | Number 1 | June 2010 | Pages 817-818
Microstructural Development in an Irradiated Monolithic LEU U-Mo Fuel Plate
Transactions | Volume 102 | Number 1 | June 2010 | Pages 819-821
Fission Product Transport of Cesium and Silver in CVD-SiC
Transactions | Volume 102 | Number 1 | June 2010 | Pages 822-823
Phase Stability in Proton and Heavy Ion Irradiated Ferritic-Martensitic Alloys
Transactions | Volume 102 | Number 1 | June 2010 | Pages 824-825
Effect of Alloying Elements on Mechanical Properties of Ferritic/Martensitic Steels
Transactions | Volume 102 | Number 1 | June 2010 | Page 826
Transactions | Volume 102 | Number 1 | June 2010 | Pages 827-828
Reactions of U-Zr Alloys and Fe at 1003 K
Transactions | Volume 102 | Number 1 | June 2010 | Pages 829-830
Reaction of Rare Earth Elements with Iron-Base Alloy
Transactions | Volume 102 | Number 1 | June 2010 | Pages 831-832
Transactions | Volume 102 | Number 1 | June 2010 | Pages 833-835
Transactions | Volume 102 | Number 1 | June 2010 | Pages 836-837
Modeling of Inert Matrix Nitride Fuels for Generation IV Reactors
Transactions | Volume 102 | Number 1 | June 2010 | Page 838
Effect of Thermomechanical Treatment on 9% Cr Ferritic-Martensitic Steels
Transactions | Volume 102 | Number 1 | June 2010 | Pages 839-840
Modeling UZr Metallic Fuels: Coupling Thermodynamics with Microstructure
Transactions | Volume 102 | Number 1 | June 2010 | Pages 841-842
A Methodology for Quantitative Determination of Anisotropy of Pyrolytic Carbon
Transactions | Volume 102 | Number 1 | June 2010 | Pages 843-844
Modeling Gas Diffusion on a Microscopic Scale
Transactions | Volume 102 | Number 1 | June 2010 | Page 845
Response of Nanoclusters in Nanostructured Ferritic Alloys to Low-Dose Proton Irradiation
Transactions | Volume 102 | Number 1 | June 2010 | Pages 846-847
In Situ TEM Study of Gas Bubble Formation in Krypton-Implanted CeO2
Transactions | Volume 102 | Number 1 | June 2010 | Pages 848-849
Mechanism of Plastic Deformation of a Ni-Based Superalloy for VHTR Applications
Transactions | Volume 102 | Number 1 | June 2010 | Pages 850-851
Postirradiation Examination of Metallic Fuel for Minor Actinides Transmutation in Fast Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 852-854
Study of Irradiated Mod.9Cr-1Mo Steel by Synchrotron XAS
Transactions | Volume 102 | Number 1 | June 2010 | Page 855
Irradiation Damage on Fiber-Reinforced SiC
Transactions | Volume 102 | Number 1 | June 2010 | Page 856
Friction Stir Welding of Oxide Dispersion Strengthened Alloys
Transactions | Volume 102 | Number 1 | June 2010 | Pages 857-858
Volatile Species Retention During Metallic Fuel Casting
Transactions | Volume 102 | Number 1 | June 2010 | Pages 859-860
Strength of SiC/SiC Composites After Neutron Irradiation at up to 1300°C
Transactions | Volume 102 | Number 1 | June 2010 | Pages 861-862
Transactions | Volume 102 | Number 1 | June 2010 | Pages 863-864
Characterization of ZrC-TRISO Particles
Transactions | Volume 102 | Number 1 | June 2010 | Pages 865-866
Corrosion Behavior of an FeCrAl Alloy in Lead-Bismuth Eutectic
Transactions | Volume 102 | Number 1 | June 2010 | Pages 867-868
Minor-Actinide and Lanthanide Migration in the U-Zr Alloy Fuel
Transactions | Volume 102 | Number 1 | June 2010 | Pages 869-870
A Thermal Conductivity Measurement System for TRISO Fuel Compacts
Transactions | Volume 102 | Number 1 | June 2010 | Pages 871-872
Model-Based Breed and Burn Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Page 873
Thermal Analysis of High-Temperature Irradiation Modules in In-Core Sample Assembly
Transactions | Volume 102 | Number 1 | June 2010 | Pages 874-875
Transactions | Volume 102 | Number 1 | June 2010 | Page 876
Fabrication and Characterization of EBR-II Type Fuels for Irradiation in ATR
Transactions | Volume 102 | Number 1 | June 2010 | Page 877
Postirradiation Examination of Full-Sized Monolithic U-Mo Fuel at Low Temperatures
Transactions | Volume 102 | Number 1 | June 2010 | Pages 878-879
Uranium Powder Production Using a Hydride-Dehydride Process
Transactions | Volume 102 | Number 1 | June 2010 | Pages 880-881
Out-of-Pile Effects of Lanthanide Rare-Earth Elements on Fuel-Cladding Compatibility
Transactions | Volume 102 | Number 1 | June 2010 | Pages 882-883
Investigation of Multi-Scale Atomistic Simulations for Noble Fission Gas Diffusion in UO2
Transactions | Volume 102 | Number 1 | June 2010 | Pages 884-885
Structure of Oxide Layers Formed on HT-9 and T91 Steels in Flowing Lead-Bismuth
Transactions | Volume 102 | Number 1 | June 2010 | Pages 886-887
An Evaluation of the MATPRO Fuel Creep Model Using the FALCON Fuel Analysis Code
Transactions | Volume 102 | Number 1 | June 2010 | Pages 888-889
Statistical Analysis Support for Nuclear Fuel Performance Experimental Data Qualification
Transactions | Volume 102 | Number 1 | June 2010 | Pages 890-891
Understanding the Effects of Impurities in Liquid Sodium by Establishing Impure He Environments
Transactions | Volume 102 | Number 1 | June 2010 | Pages 892-893
In Situ Proton Irradiation Creep of Ferritic-Martensitic Steel T91
Transactions | Volume 102 | Number 1 | June 2010 | Pages 894-895
Role of Cr on Oxidation Mechanism of Ferritic-Martensitic Alloys in 600°C Supercritical Water
Transactions | Volume 102 | Number 1 | June 2010 | Pages 896-897
Leveraging Materials Progress for Next Generation Reactors
Transactions | Volume 102 | Number 1 | June 2010 | Page 899
ODS Materials for Fast Reactors
Transactions | Volume 102 | Number 1 | June 2010 | Page 901
Modeling the Radiation Stability of Nanoclusters in Ferritic Steels
Transactions | Volume 102 | Number 1 | June 2010 | Page 902
Grain Boundary Engineering for Structure Materials of Nuclear Reactor
Transactions | Volume 102 | Number 1 | June 2010 | Pages 903-904
Innovative SiCf/SiC Composite Materials for Fast Reactor Applications
Transactions | Volume 102 | Number 1 | June 2010 | Page 905