Transactions | Volume 106 | Number 1 | June 2012 | Page iii
Meeting Officials, National Program Committee
Transactions | Volume 106 | Number 1 | June 2012 | Page v
Transactions | Volume 106 | Number 1 | June 2012 | Page xix
Transactions | Volume 106 | Number 1 | June 2012 | Page 3
Special Sessions
ANS President's Special Session: Low-Level Radiation and Its Implications for Fukushima Recovery
Transactions | Volume 106 | Number 1 | June 2012 | Page 4
Special Sessions
A Review of Radiation Protection of Patients Received Proton Radiotherapy
Transactions | Volume 106 | Number 1 | June 2012 | Pages 9-10
Accelerator Applications | Accelerators and Detectors Used in Medical Therapy
Advances in Accelerator Technology for Hadron Therapy
Transactions | Volume 106 | Number 1 | June 2012 | Pages 11-12
Accelerator Applications | Accelerators and Detectors Used in Medical Therapy
Overview of Accelerator Advances in Particle Therapy
Transactions | Volume 106 | Number 1 | June 2012 | Page 13
Accelerator Applications | Accelerators and Detectors Used in Medical Therapy
Detection Techniques for Fast Neutron Spectroscopy
Transactions | Volume 106 | Number 1 | June 2012 | Pages 14-15
Accelerator Applications | Accelerators and Detectors Used in Medical Therapy
Transactions | Volume 106 | Number 1 | June 2012 | Pages 19-20
Accelerator Applications | Acceleration Applications: General
The Fermilab Project-X: Nuclear Energy Application
Transactions | Volume 106 | Number 1 | June 2012 | Page 21
Accelerator Applications | Acceleration Applications: General
Reliability Analysis of a Proton Linac for ADS Applications
Transactions | Volume 106 | Number 1 | June 2012 | Pages 22-25
Accelerator Applications | Acceleration Applications: General
US Spent Nuclear Fuel Inventory Disposal Utilizing Accelerator Driven Systems
Transactions | Volume 106 | Number 1 | June 2012 | Pages 26-27
Accelerator Applications | Acceleration Applications: General
Impact of Different Physics Models in MCNPX Code on the Neutron and Proton Heating in ADS
Transactions | Volume 106 | Number 1 | June 2012 | Pages 28-31
Accelerator Applications | Acceleration Applications: General
Identifying the Elemental Composition of Dust Particles Using Photon Activation Analysis
Transactions | Volume 106 | Number 1 | June 2012 | Pages 32-33
Accelerator Applications | Acceleration Applications: General
Preliminary Results of a Focusing Beamline for a PETtrace Cyclotron
Transactions | Volume 106 | Number 1 | June 2012 | Pages 34-36
Accelerator Applications | Acceleration Applications: General
Review of Modern Dosimetric Modeling Methods of Bracytherapy Sources
Transactions | Volume 106 | Number 1 | June 2012 | Pages 41-42
Biology and Medicine | Modeling and Simulation of Brachytherapy Sources and Biology and Medicine: General
Challenges in Clinical Brachytherapy Source Modeling: Going Beyond Schematics
Transactions | Volume 106 | Number 1 | June 2012 | Pages 43-44
Biology and Medicine | Modeling and Simulation of Brachytherapy Sources and Biology and Medicine: General
Brachytherapy with a Grid-Based Boltzmann Solver: Sources, Boundaries, Applicators, Heterogeneities
Transactions | Volume 106 | Number 1 | June 2012 | Pages 45-47
Biology and Medicine | Modeling and Simulation of Brachytherapy Sources and Biology and Medicine: General
Investigation of Discrete Ordinates Code for Unsealed Sources in Brachytherapy
Transactions | Volume 106 | Number 1 | June 2012 | Pages 48-49
Biology and Medicine | Modeling and Simulation of Brachytherapy Sources and Biology and Medicine: General
Unstructured Mesh Human Phantoms with MCNP
Transactions | Volume 106 | Number 1 | June 2012 | Pages 50-51
Biology and Medicine | Modeling and Simulation of Brachytherapy Sources and Biology and Medicine: General
Proton CT for Improved Stopping Power Determination in Proton Therapy
Transactions | Volume 106 | Number 1 | June 2012 | Pages 55-58
Biology and Medicine | Proton Imaging Technology for Proton Therapy
Overview of the LLUMC/UCSC/CSUSB Phase 2 Proton CT Project
Transactions | Volume 106 | Number 1 | June 2012 | Pages 59-62
Biology and Medicine | Proton Imaging Technology for Proton Therapy
The Phase I Proton CT Scanner and Test Beam Results at LLUMC
Transactions | Volume 106 | Number 1 | June 2012 | Pages 63-66
Biology and Medicine | Proton Imaging Technology for Proton Therapy
Overview of the NIU/Fermilab Phase 2 Proton CT Project
Transactions | Volume 106 | Number 1 | June 2012 | Page 67
Biology and Medicine | Proton Imaging Technology for Proton Therapy
Theoretical Aspects of Image Reconstruction in Proton Computed Tomography
Transactions | Volume 106 | Number 1 | June 2012 | Pages 68-69
Biology and Medicine | Proton Imaging Technology for Proton Therapy
High-Performance Multiple-CPU/GPU Proton Computed Tomography
Transactions | Volume 106 | Number 1 | June 2012 | Pages 70-72
Biology and Medicine | Proton Imaging Technology for Proton Therapy
Fast Superiorization Using a Dual Perturbation Scheme for Proton Computed Tomography
Transactions | Volume 106 | Number 1 | June 2012 | Pages 73-76
Biology and Medicine | Proton Imaging Technology for Proton Therapy
Measurements of the Prompt Gamma Signal in a Clinical Proton Therapy Environment
Transactions | Volume 106 | Number 1 | June 2012 | Pages 77-79
Biology and Medicine | Proton Imaging Technology for Proton Therapy
Preliminary Results on Lung and Liver Tumor Tracking with Carbon and Proton Radiography
Transactions | Volume 106 | Number 1 | June 2012 | Pages 80-82
Biology and Medicine | Proton Imaging Technology for Proton Therapy
Preliminary Results of a Scintillating Fibers Detector for Proton Radiography
Transactions | Volume 106 | Number 1 | June 2012 | Pages 83-84
Biology and Medicine | Proton Imaging Technology for Proton Therapy
Nuclear Technician Education and Training-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 87
Education, Training, and Workforce Development
Visual Recognition of Objects with Sparse Texture and Specular Reflectivity
Transactions | Volume 106 | Number 1 | June 2012 | Pages 91-94
Education, Training, and Workforce Development | Research by U.S. DOE NEUP-Sponsored Students
Construction and Installation of the Colorado School of Mines Neutron Imaging Facility
Transactions | Volume 106 | Number 1 | June 2012 | Pages 95-99
Education, Training, and Workforce Development | Research by U.S. DOE NEUP-Sponsored Students
A Laser-Based Method for Ultrasonic Characterization of Nuclear Grade Graphites
Transactions | Volume 106 | Number 1 | June 2012 | Pages 100-102
Education, Training, and Workforce Development | Research by U.S. DOE NEUP-Sponsored Students
Numerical and Experimental Studies of Heat Transfer Coefficients in a RCCS
Transactions | Volume 106 | Number 1 | June 2012 | Pages 103-104
Education, Training, and Workforce Development | Research by U.S. DOE NEUP-Sponsored Students
Boron Filling of Deep Holes for Solid-State Neutron Detector Applications
Transactions | Volume 106 | Number 1 | June 2012 | Pages 105-106
Education, Training, and Workforce Development | Research by U.S. DOE NEUP-Sponsored Students
Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications
Transactions | Volume 106 | Number 1 | June 2012 | Pages 107-108
Education, Training, and Workforce Development | Research by U.S. DOE NEUP-Sponsored Students
Transactions | Volume 106 | Number 1 | June 2012 | Pages 109-111
Education, Training, and Workforce Development | Research by U.S. DOE NEUP-Sponsored Students
Science in Politics: Getting Scientists Elected-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 112
Education, Training, and Workforce Development | Research by U.S. DOE NEUP-Sponsored Students
Communication Workshop on Nuclear Industry and Women's Issues-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 113
Education, Training, and Workforce Development | Research by U.S. DOE NEUP-Sponsored Students
The University of Tennessee Institute for Nuclear Security
Transactions | Volume 106 | Number 1 | June 2012 | Page 117
Education, Training, and Workforce Development | Bridging the Gap Between Technology and Policy in Education and Training-Paper/Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 118
Education, Training, and Workforce Development | Bridging the Gap Between Technology and Policy in Education and Training-Paper/Panel
Teaching Across and Through the Curriculum: Enhancing Student Performance in Online Education
Transactions | Volume 106 | Number 1 | June 2012 | Pages 121-122
Education, Training, and Workforce Development | Education, Training, and Workforce Development: General
Teaching Online Nuclear Engineering Courses Improves Your In-Class Teaching
Transactions | Volume 106 | Number 1 | June 2012 | Pages 123-124
Education, Training, and Workforce Development | Education, Training, and Workforce Development: General
The Continued Evolution of a Revolutionary Curriculum in Nuclear Environmental Engineering
Transactions | Volume 106 | Number 1 | June 2012 | Pages 125-127
Education, Training, and Workforce Development | Education, Training, and Workforce Development: General
Nuclear Forensic Science Educational Needs - A Student Perspective
Transactions | Volume 106 | Number 1 | June 2012 | Pages 128-129
Education, Training, and Workforce Development | Education, Training, and Workforce Development: General
Development of Web Based Thermal-Hydraulics Modules for Nuclear Engineering Minor
Transactions | Volume 106 | Number 1 | June 2012 | Page 130
Education, Training, and Workforce Development | Education, Training, and Workforce Development: General
A Simple Educational Tool for In-Core Fuel Management
Transactions | Volume 106 | Number 1 | June 2012 | Pages 131-132
Education, Training, and Workforce Development | Education, Training, and Workforce Development: General
Design of the U-PANTHER Desktop Nuclear Plant Simulator
Transactions | Volume 106 | Number 1 | June 2012 | Pages 133-135
Education, Training, and Workforce Development | Education, Training, and Workforce Development: General
Novel Reactor Simulator Using Natural Interfacing
Transactions | Volume 106 | Number 1 | June 2012 | Pages 136-137
Education, Training, and Workforce Development | Education, Training, and Workforce Development: General
Health Effects of Radiation-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 141
Environmental Sciences
Fast Nuclear Fission Technology: Past Experience and IFR - I-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 142
Environmental Sciences
Fast Nuclear Fission Technology: IFR - The Path Forward - II-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 143
Environmental Sciences
A Comprehensive Radiological and Chemical Risk Assessment of the Open Nuclear Fuel Cycle
Transactions | Volume 106 | Number 1 | June 2012 | Pages 147-148
Environmental Sciences | Environmental Sciences: General
Transactions | Volume 106 | Number 1 | June 2012 | Page 149
Environmental Sciences | Environmental Sciences: General
Transactions | Volume 106 | Number 1 | June 2012 | Pages 150-151
Environmental Sciences | Environmental Sciences: General
Effect of the Synergistic Biomass-Nuclear Process on the Global Carbon Budget
Transactions | Volume 106 | Number 1 | June 2012 | Pages 152-153
Environmental Sciences | Environmental Sciences: General
Impact of Renewable Electricity Standards on Nuclear Generation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 154-156
Environmental Sciences | Environmental Sciences: General
Monitoring Plant Conditions with Radio Frequency Devices
Transactions | Volume 106 | Number 1 | June 2012 | Pages 157-158
Environmental Sciences | Environmental Sciences: General
Gamma Ray Mapping Systems for Ground Surface Characterization
Transactions | Volume 106 | Number 1 | June 2012 | Page 159
Environmental Sciences | Environmental Sciences: General
A Model for Recovering Uranium from Scrap Monolithic Uranium Molybdenum Alloy by Electrorefining
Transactions | Volume 106 | Number 1 | June 2012 | Pages 165-166
Fuel Cycle and Waste Management | Development of Advanced Fuel Recycle Methods
The Direct Dissolution and Electrochemical Study of U3O8 in Ionic Liquid
Transactions | Volume 106 | Number 1 | June 2012 | Pages 167-169
Fuel Cycle and Waste Management | Development of Advanced Fuel Recycle Methods
Possibility of Co-deposition of U and Pu at a Solid Cathode in Pyro-chemical Processing
Transactions | Volume 106 | Number 1 | June 2012 | Pages 170-171
Fuel Cycle and Waste Management | Development of Advanced Fuel Recycle Methods
Plutonium and Minor Actinide Transmutation Target Fuel Evaluation for PWRs
Transactions | Volume 106 | Number 1 | June 2012 | Pages 172-175
Fuel Cycle and Waste Management | Development of Advanced Fuel Recycle Methods
Increasing Inert Matrix Fuel Burnup
Transactions | Volume 106 | Number 1 | June 2012 | Pages 176-177
Fuel Cycle and Waste Management | Development of Advanced Fuel Recycle Methods
Technology Advancement for Recycle of Zirconium from Used Nuclear Fuel Cladding
Transactions | Volume 106 | Number 1 | June 2012 | Pages 181-182
Fuel Cycle and Waste Management | Used Fuel Component Recycle and Off-Gas Issues
Conceptual Design of a Simplified Head-End Process for the Recycling of Used Nuclear Fuel
Transactions | Volume 106 | Number 1 | June 2012 | Pages 183-184
Fuel Cycle and Waste Management | Used Fuel Component Recycle and Off-Gas Issues
Utilization of LWR Nuclear Waste Transuranium/Nat-Uranium Mixed Fuel in CANDU Reactors
Transactions | Volume 106 | Number 1 | June 2012 | Pages 185-188
Fuel Cycle and Waste Management | Used Fuel Component Recycle and Off-Gas Issues
Transactions | Volume 106 | Number 1 | June 2012 | Pages 189-190
Fuel Cycle and Waste Management | Used Fuel Component Recycle and Off-Gas Issues
Transactions | Volume 106 | Number 1 | June 2012 | Page 191
Fuel Cycle and Waste Management | Used Fuel Component Recycle and Off-Gas Issues
Transactions | Volume 106 | Number 1 | June 2012 | Pages 192-194
Fuel Cycle and Waste Management | Used Fuel Component Recycle and Off-Gas Issues
Extended Storage and Transportation of Spent Nuclear Fuel - I-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 195
Fuel Cycle and Waste Management | Used Fuel Component Recycle and Off-Gas Issues
Extended Storage and Transportation of Spent Nuclear Fuel - II-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 196
Fuel Cycle and Waste Management | Used Fuel Component Recycle and Off-Gas Issues
The United States Support Program: 35 Years of Safeguards Enhancements
Transactions | Volume 106 | Number 1 | June 2012 | Pages 199-200
Fuel Cycle and Waste Management | Nuclear Nonproliferation Issues
Aboveground Antineutrino Detectors for Reactor Monitoring and Safeguards
Transactions | Volume 106 | Number 1 | June 2012 | Pages 201-204
Fuel Cycle and Waste Management | Nuclear Nonproliferation Issues
Development of Path Search Toolkit for Nuclear Non-Proliferation Applications
Transactions | Volume 106 | Number 1 | June 2012 | Pages 205-206
Fuel Cycle and Waste Management | Nuclear Nonproliferation Issues
Incentivizing Timely Detection: Game Theoretic Modeling of Trade-Offs
Transactions | Volume 106 | Number 1 | June 2012 | Pages 207-208
Fuel Cycle and Waste Management | Nuclear Nonproliferation Issues
Neuro-Fuzzy Methodology for Geospatial and Time Interpolation on Gamma Ray Spectroscopy Data
Transactions | Volume 106 | Number 1 | June 2012 | Pages 209-210
Fuel Cycle and Waste Management | Nuclear Nonproliferation Issues
Fuzzy Logic Radio-Isotope Identifier for Gamma Spectra Analysis in Source Search Applications
Transactions | Volume 106 | Number 1 | June 2012 | Pages 211-212
Fuel Cycle and Waste Management | Nuclear Nonproliferation Issues
Report on a DOE Nuclear Separations Workshop and the Path Forward
Transactions | Volume 106 | Number 1 | June 2012 | Pages 215-216
Fuel Cycle and Waste Management | Fuel Cycle and Waste Management: General - I
Update on DOE's Safety and Regulatory Crosscut Work
Transactions | Volume 106 | Number 1 | June 2012 | Pages 217-218
Fuel Cycle and Waste Management | Fuel Cycle and Waste Management: General - I
Arizona's Suitability as an Interim Recyclable Fuel Storage Facility Site
Transactions | Volume 106 | Number 1 | June 2012 | Pages 219-220
Fuel Cycle and Waste Management | Fuel Cycle and Waste Management: General - I
Fuel Cycle Strategies Utilizing Single Isotope Separation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 221-223
Fuel Cycle and Waste Management | Fuel Cycle and Waste Management: General - I
A Comparative Study of CANDLE Reactor Based U.S. Nuclear Fuel Cycles
Transactions | Volume 106 | Number 1 | June 2012 | Pages 224-225
Fuel Cycle and Waste Management | Fuel Cycle and Waste Management: General - I
MR Reactor Decommissioning in NRC "Kurchatov Institute": Results of Preparatory Work Phase
Transactions | Volume 106 | Number 1 | June 2012 | Pages 229-230
Fuel Cycle and Waste Management | Fuel Cycle and Waste Management: General - II
Irradiation Effects on Actinide Containing U-Pu-Zr Metallic Fuels at Several Burnups
Transactions | Volume 106 | Number 1 | June 2012 | Pages 231-234
Fuel Cycle and Waste Management | Fuel Cycle and Waste Management: General - II
Building Confidence in LLW Performance Assessments Through Risk Evaluation Analysis
Transactions | Volume 106 | Number 1 | June 2012 | Pages 235-236
Fuel Cycle and Waste Management | Fuel Cycle and Waste Management: General - II
X-Ray Backscatter Imaging of Nuclear Fuel Rods
Transactions | Volume 106 | Number 1 | June 2012 | Pages 237-238
Fuel Cycle and Waste Management | Fuel Cycle and Waste Management: General - II
Transformation Enthalpies of Uranium-Zirconium Alloy System
Transactions | Volume 106 | Number 1 | June 2012 | Pages 239-241
Fuel Cycle and Waste Management | Fuel Cycle and Waste Management: General - II
Bismuth Impurity Effects on Copper Nuclear Waste Containers
Transactions | Volume 106 | Number 1 | June 2012 | Pages 242-245
Fuel Cycle and Waste Management | Fuel Cycle and Waste Management: General - II
Agent Based Simulation of the Nuclear Fuel Cycle
Transactions | Volume 106 | Number 1 | June 2012 | Pages 249-251
Fuel Cycle and Waste Management | Modeling and Simulation in the Fuel Cycle
Modeling Spent Fuel Storage Options in Fuel Cycle Systems Simulation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 252-253
Fuel Cycle and Waste Management | Modeling and Simulation in the Fuel Cycle
Transient Thermal Modeling of a Deep Borehole Repository
Transactions | Volume 106 | Number 1 | June 2012 | Pages 254-257
Fuel Cycle and Waste Management | Modeling and Simulation in the Fuel Cycle
Transactions | Volume 106 | Number 1 | June 2012 | Pages 258-259
Fuel Cycle and Waste Management | Modeling and Simulation in the Fuel Cycle
Numerical Calibration of an Analytical Generic Nuclear Repository Heat Transfer Model
Transactions | Volume 106 | Number 1 | June 2012 | Pages 260-263
Fuel Cycle and Waste Management | Modeling and Simulation in the Fuel Cycle
U-Pu-Zr Fuel Properties and Thermal Performance Modeling for Sodium Fast Reactors
Transactions | Volume 106 | Number 1 | June 2012 | Page 264
Fuel Cycle and Waste Management | Modeling and Simulation in the Fuel Cycle
Development of a Neutron Evaporation Theory Code for U-235 Thermal Fission
Transactions | Volume 106 | Number 1 | June 2012 | Pages 269-270
Isotopes and Radiation | Isotopes and Radiation: General
Experimental Verification of Wavelet Method of Analysis of Neutron Induced Gamma Spectra
Transactions | Volume 106 | Number 1 | June 2012 | Pages 271-272
Isotopes and Radiation | Isotopes and Radiation: General
Background Spectrum Estimation for Low Count Spectra Using Kernel-Modeled Gaussian Processes
Transactions | Volume 106 | Number 1 | June 2012 | Pages 273-274
Isotopes and Radiation | Isotopes and Radiation: General
Enhancement of Nuclide Identification Using Transforms
Transactions | Volume 106 | Number 1 | June 2012 | Pages 275-277
Isotopes and Radiation | Isotopes and Radiation: General
Analysis of Lanthanum Bromide Spectra for Identification of Depleted Uranium
Transactions | Volume 106 | Number 1 | June 2012 | Pages 278-280
Isotopes and Radiation | Isotopes and Radiation: General
Plutonium Holdup Measurement Using Fast Neutron Signatures
Transactions | Volume 106 | Number 1 | June 2012 | Pages 283-284
Isotopes and Radiation | Innovations in Radiation Detectors: New Designs, Improvements, and Applications
Improvements in Extractive Ligands to Enhance Sample Preparation for Alpha Spectrometry
Transactions | Volume 106 | Number 1 | June 2012 | Pages 285-286
Isotopes and Radiation | Innovations in Radiation Detectors: New Designs, Improvements, and Applications
Neutron Spectrometry Utilizing Neutron PODs and Source Location Determination
Transactions | Volume 106 | Number 1 | June 2012 | Pages 287-288
Isotopes and Radiation | Innovations in Radiation Detectors: New Designs, Improvements, and Applications
High Temperature SiC Alpha-Particle Detectors for Pyroprocessing
Transactions | Volume 106 | Number 1 | June 2012 | Pages 289-290
Isotopes and Radiation | Innovations in Radiation Detectors: New Designs, Improvements, and Applications
Comparison of Traditional and Hybrid Dead Time Models for Radiation Detector
Transactions | Volume 106 | Number 1 | June 2012 | Pages 291-292
Isotopes and Radiation | Innovations in Radiation Detectors: New Designs, Improvements, and Applications
Development of Detector Response Functions for LaBr3 Scintillator
Transactions | Volume 106 | Number 1 | June 2012 | Pages 293-294
Isotopes and Radiation | Innovations in Radiation Detectors: New Designs, Improvements, and Applications
Production of 37Ar Through the Irradiation of Ca-Containing Compounds
Transactions | Volume 106 | Number 1 | June 2012 | Pages 297-298
Isotopes and Radiation | University Research Reactors and Nuclear Science Programs - I
Neutronic Analysis of the New Penn State Breazeale Reactor Core Design Using MCNP5 Code
Transactions | Volume 106 | Number 1 | June 2012 | Pages 299-300
Isotopes and Radiation | University Research Reactors and Nuclear Science Programs - I
Transactions | Volume 106 | Number 1 | June 2012 | Pages 301-302
Isotopes and Radiation | University Research Reactors and Nuclear Science Programs - I
Transactions | Volume 106 | Number 1 | June 2012 | Pages 303-304
Isotopes and Radiation | University Research Reactors and Nuclear Science Programs - I
A Literature Review of Potential Low Enrichment U-10wt%Mo Fuel Failures
Transactions | Volume 106 | Number 1 | June 2012 | Pages 305-307
Isotopes and Radiation | University Research Reactors and Nuclear Science Programs - I
Development of Online Reactor Experiments Software at Penn State
Transactions | Volume 106 | Number 1 | June 2012 | Pages 308-309
Isotopes and Radiation | University Research Reactors and Nuclear Science Programs - I
Electron Emission Following 157Gd Neutron Capture
Transactions | Volume 106 | Number 1 | June 2012 | Pages 313-314
Isotopes and Radiation | University Research Reactors and Nuclear Science Programs - II
Reactor Based Production and Purification of 64Cu and 67Cu
Transactions | Volume 106 | Number 1 | June 2012 | Pages 315-316
Isotopes and Radiation | University Research Reactors and Nuclear Science Programs - II
Neutronic Simulation of Penn State Breazeale Nuclear Reactor Core Using MURE
Transactions | Volume 106 | Number 1 | June 2012 | Pages 317-319
Isotopes and Radiation | University Research Reactors and Nuclear Science Programs - II
Modeling Transient Mechanisms for Penn State Breazeale Nuclear Reactor Core Neutronic Analysis
Transactions | Volume 106 | Number 1 | June 2012 | Pages 320-323
Isotopes and Radiation | University Research Reactors and Nuclear Science Programs - II
A Neutron Beam Monitor for a Neutron Depth Profiling Facility
Transactions | Volume 106 | Number 1 | June 2012 | Pages 324-325
Isotopes and Radiation | University Research Reactors and Nuclear Science Programs - II
Betavoltaic Batteries from Irradiated Lithium Intercalated Graphite
Transactions | Volume 106 | Number 1 | June 2012 | Pages 326-328
Isotopes and Radiation | University Research Reactors and Nuclear Science Programs - II
Transactions | Volume 106 | Number 1 | June 2012 | Page 331
Mathematics and Computation
A Residual Monte Carlo Method for Spatially Discrete, Angularly Continuous Radiation Transport
Transactions | Volume 106 | Number 1 | June 2012 | Pages 335-338
Mathematics and Computation | Transport Methods
Transactions | Volume 106 | Number 1 | June 2012 | Pages 339-341
Mathematics and Computation | Transport Methods
Transactions | Volume 106 | Number 1 | June 2012 | Pages 342-345
Mathematics and Computation | Transport Methods
Efficient Monte Carlo Solution for Uncertainty Propagation with Stochastic Collocation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 346-349
Mathematics and Computation | Transport Methods
A New Source Biasing Approach in ADVANTG
Transactions | Volume 106 | Number 1 | June 2012 | Pages 350-353
Mathematics and Computation | Transport Methods
Cross Section Recondensation as a Spectral Correction for Non-Fissionable Regions of VHTR Cores
Transactions | Volume 106 | Number 1 | June 2012 | Pages 354-357
Mathematics and Computation | Transport Methods
An Homotopy Continuation Method Applied to SN Transport
Transactions | Volume 106 | Number 1 | June 2012 | Pages 358-361
Mathematics and Computation | Transport Methods
A Moment-Preserving SN Discretization for the One-Dimensional Fokker-Planck Equation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 362-365
Mathematics and Computation | Transport Methods
On the Evaluation of Ray Effects in Multidimensional and Time-Dependent Transport Problems
Transactions | Volume 106 | Number 1 | June 2012 | Pages 369-371
Mathematics and Computation | Computational Methods and Mathematical Modeling
Transactions | Volume 106 | Number 1 | June 2012 | Pages 372-374
Mathematics and Computation | Computational Methods and Mathematical Modeling
Transactions | Volume 106 | Number 1 | June 2012 | Pages 375-377
Mathematics and Computation | Computational Methods and Mathematical Modeling
GPU/CUDA-Ready Parallel Monte Carlo Codes for Reactor Analysis and Other Applications
Transactions | Volume 106 | Number 1 | June 2012 | Pages 378-379
Mathematics and Computation | Computational Methods and Mathematical Modeling
A Parallel Computational Approach to Nuclear Fuel Assembly Simulations
Transactions | Volume 106 | Number 1 | June 2012 | Pages 380-383
Mathematics and Computation | Computational Methods and Mathematical Modeling
A Projection Approach for the Immersed Finite Element Method
Transactions | Volume 106 | Number 1 | June 2012 | Pages 384-387
Mathematics and Computation | Computational Methods and Mathematical Modeling
An Adaptive Natural Multigroup for Neutron Slowing Down
Transactions | Volume 106 | Number 1 | June 2012 | Pages 388-391
Mathematics and Computation | Computational Methods and Mathematical Modeling
A Multilevel Methodology for Coupling Neutronics with the Heat Transfer Equation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 395-397
Mathematics and Computation | Transport and Computational Methods
Comparison of Two p Preconditioned GMRES Algorithms for Variational Nodal Multigroup System
Transactions | Volume 106 | Number 1 | June 2012 | Pages 398-400
Mathematics and Computation | Transport and Computational Methods
A Novel Krylov Adjoint Method for the Computation of Sensitivities in Eigenvalue Problems
Transactions | Volume 106 | Number 1 | June 2012 | Pages 401-404
Mathematics and Computation | Transport and Computational Methods
Preconditioning Multiple Right Sides for the Time Dependent Neutron Diffusion Equation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 405-409
Mathematics and Computation | Transport and Computational Methods
Implementing a Discrete Maximum Principle for the IMC Equations
Transactions | Volume 106 | Number 1 | June 2012 | Pages 410-411
Mathematics and Computation | Transport and Computational Methods
Temporal Convergence of Coarse Mesh Finite Difference Accelerated Monte Carlo
Transactions | Volume 106 | Number 1 | June 2012 | Pages 412-415
Mathematics and Computation | Transport and Computational Methods
Reduced Variance for Material Sources in Implicit Monte Carlo
Transactions | Volume 106 | Number 1 | June 2012 | Pages 416-417
Mathematics and Computation | Transport and Computational Methods
A More Implicit Temperature Estimate for the IMC Method of Photon Transport
Transactions | Volume 106 | Number 1 | June 2012 | Pages 418-421
Mathematics and Computation | Transport and Computational Methods
Using Source Biasing in Implicit Monte Carlo to Reduce Numerical Artifacts and Variance
Transactions | Volume 106 | Number 1 | June 2012 | Pages 422-425
Mathematics and Computation | Transport and Computational Methods
Second-Order Sensitivity Analysis of Godiva and Jezebel Experimental Benchmarks
Transactions | Volume 106 | Number 1 | June 2012 | Pages 429-432
Mathematics and Computation | Uncertainty Quantification, Sensitivity Analysis, and Reduced Order Modeling
Revisiting Boundary Perturbation Theory for Inhomogeneous Transport Equations
Transactions | Volume 106 | Number 1 | June 2012 | Pages 433-436
Mathematics and Computation | Uncertainty Quantification, Sensitivity Analysis, and Reduced Order Modeling
Reduced Order Approximations in Uncertainty Analysis of Nuclear Engineering Applications
Transactions | Volume 106 | Number 1 | June 2012 | Pages 437-438
Mathematics and Computation | Uncertainty Quantification, Sensitivity Analysis, and Reduced Order Modeling
Reduced Order Modeling of the Forward Eigenvalue Problem
Transactions | Volume 106 | Number 1 | June 2012 | Pages 439-441
Mathematics and Computation | Uncertainty Quantification, Sensitivity Analysis, and Reduced Order Modeling
The Zeus Copper/Uranium Critical Experiment at NCERC
Transactions | Volume 106 | Number 1 | June 2012 | Pages 447-449
Nuclear Criticality Safety | Data Analysis in Nuclear Criticality Safety - I
Transactions | Volume 106 | Number 1 | June 2012 | Pages 450-455
Nuclear Criticality Safety | Data Analysis in Nuclear Criticality Safety - I
Criticality Safety Validation of SCALE 6.1 with ENDF/B-VII.0 Libraries
Transactions | Volume 106 | Number 1 | June 2012 | Pages 456-460
Nuclear Criticality Safety | Data Analysis in Nuclear Criticality Safety - I
Transactions | Volume 106 | Number 1 | June 2012 | Pages 461-464
Nuclear Criticality Safety | Data Analysis in Nuclear Criticality Safety - I
Transactions | Volume 106 | Number 1 | June 2012 | Pages 465-468
Nuclear Criticality Safety | Data Analysis in Nuclear Criticality Safety - I
Cross Section Data Benchmarking Using Automated Criticality Benchmarks in MCNP6 and Partisn
Transactions | Volume 106 | Number 1 | June 2012 | Pages 471-474
Nuclear Criticality Safety | Data Analysis in Nuclear Criticality Safety - II
Benchmark Evaluation of GROTESQUE, a Complex Arrangement of HEU Metal Pieces
Transactions | Volume 106 | Number 1 | June 2012 | Pages 475-478
Nuclear Criticality Safety | Data Analysis in Nuclear Criticality Safety - II
Radiation Damage to Neutron Absorber Materials for Cask Spent Fuel Storage
Transactions | Volume 106 | Number 1 | June 2012 | Pages 479-482
Nuclear Criticality Safety | Data Analysis in Nuclear Criticality Safety - II
Transactions | Volume 106 | Number 1 | June 2012 | Pages 483-486
Nuclear Criticality Safety | Data Analysis in Nuclear Criticality Safety - II
Comparison of HEU Measurements Using Measured and Simulated Data
Transactions | Volume 106 | Number 1 | June 2012 | Pages 487-489
Nuclear Criticality Safety | Data Analysis in Nuclear Criticality Safety - II
An Evaluation of Monte Carlo Simulations of Neutron Multiplicity Measurements of Plutonium Metal
Transactions | Volume 106 | Number 1 | June 2012 | Pages 490-493
Nuclear Criticality Safety | Data Analysis in Nuclear Criticality Safety - II
Methods for Detector Placement and Analysis of Criticality Accident Alarm Systems
Transactions | Volume 106 | Number 1 | June 2012 | Pages 497-500
Nuclear Criticality Safety | Advancing Criticality Safety Capabilities in a Growing Nuclear World
Continuous-S(
,
) Capability in MCNP
Transactions | Volume 106 | Number 1 | June 2012 | Pages 501-504
Nuclear Criticality Safety | Advancing Criticality Safety Capabilities in a Growing Nuclear World
The Double Contingency Principle and Subcriticality Revisited
Transactions | Volume 106 | Number 1 | June 2012 | Pages 505-507
Nuclear Criticality Safety | Advancing Criticality Safety Capabilities in a Growing Nuclear World
Continuous-Estimator Representation for Monte Carlo Criticality Diagnostics
Transactions | Volume 106 | Number 1 | June 2012 | Pages 508-511
Nuclear Criticality Safety | Advancing Criticality Safety Capabilities in a Growing Nuclear World
Evaluation of Computing c-Eigenvalues with Monte Carlo
Transactions | Volume 106 | Number 1 | June 2012 | Pages 512-515
Nuclear Criticality Safety | Advancing Criticality Safety Capabilities in a Growing Nuclear World
Benchmarking Experiments for Criticality Safety and Reactor Physics Applications - I-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 516
Nuclear Criticality Safety | Advancing Criticality Safety Capabilities in a Growing Nuclear World
Benchmarking Experiments for Criticality Safety and Reactor Physics Applications - II-Tutorial
Transactions | Volume 106 | Number 1 | June 2012 | Page 517
Nuclear Criticality Safety | Advancing Criticality Safety Capabilities in a Growing Nuclear World
Nuclear Criticality Safety Standards-Forum
Transactions | Volume 106 | Number 1 | June 2012 | Page 518
Nuclear Criticality Safety | Advancing Criticality Safety Capabilities in a Growing Nuclear World
Reliability Modeling of Passive Systems Under Multiple Failure Processes
Transactions | Volume 106 | Number 1 | June 2012 | Pages 523-524
Nuclear Installations Safety | Emerging Issues in Nuclear Facility Safety
Short Term Analysis of MSLB for PWR Type Containment
Transactions | Volume 106 | Number 1 | June 2012 | Pages 525-526
Nuclear Installations Safety | Emerging Issues in Nuclear Facility Safety
Radionuclides for Unique Identification of Nuclear Fuel from Fabrication to Grave
Transactions | Volume 106 | Number 1 | June 2012 | Pages 527-528
Nuclear Installations Safety | Emerging Issues in Nuclear Facility Safety
A Mechanism of Concrete Degradation in Reactor Concrete Structures from Groundwater Infiltration
Transactions | Volume 106 | Number 1 | June 2012 | Pages 529-532
Nuclear Installations Safety | Emerging Issues in Nuclear Facility Safety
Analyses of Data from the KATE-FIRE Kerite® Cable Tests
Transactions | Volume 106 | Number 1 | June 2012 | Pages 535-537
Nuclear Installations Safety | Current Fire Research Activities: Strengthening Safety Through Research
Uncertainty Analysis of Input Parameters in Fire Modeling Using Fire Dynamic Simulator
Transactions | Volume 106 | Number 1 | June 2012 | Pages 538-539
Nuclear Installations Safety | Current Fire Research Activities: Strengthening Safety Through Research
Dynamic Considerations in the Performance of Fire PRA
Transactions | Volume 106 | Number 1 | June 2012 | Pages 540-542
Nuclear Installations Safety | Current Fire Research Activities: Strengthening Safety Through Research
Transactions | Volume 106 | Number 1 | June 2012 | Pages 545-548
Nuclear Installations Safety | Nuclear Installations Safety: General
MELCOR Model of the Spent Fuel Pool of Fukushima Dai-ichi Unit 4
Transactions | Volume 106 | Number 1 | June 2012 | Pages 549-551
Nuclear Installations Safety | Nuclear Installations Safety: General
MELCOR Sensitivity Study for a PWR Containment
Transactions | Volume 106 | Number 1 | June 2012 | Pages 552-554
Nuclear Installations Safety | Nuclear Installations Safety: General
Unreviewed Safety Question Analysis for the New Neutron Imaging Facility at the USGS TRIGA Reactor
Transactions | Volume 106 | Number 1 | June 2012 | Pages 555-558
Nuclear Installations Safety | Nuclear Installations Safety: General
Fracture Toughness Analysis for Different Materials with Leak-Before-Break Applications
Transactions | Volume 106 | Number 1 | June 2012 | Pages 559-560
Nuclear Installations Safety | Nuclear Installations Safety: General
Blackstone: An Irradiation Project for AGR Life Time Extension
Transactions | Volume 106 | Number 1 | June 2012 | Pages 563-566
Nuclear Installations Safety | Irradiation Assisted Degradation of Reactor Vessel Internals/NRC-Sponsored Environmentally Assisted Fatigue Research Activities
Ligament Rupture and Burst Pressures of Flawed SG U-bends
Transactions | Volume 106 | Number 1 | June 2012 | Pages 567-568
Nuclear Installations Safety | Irradiation Assisted Degradation of Reactor Vessel Internals/NRC-Sponsored Environmentally Assisted Fatigue Research Activities
Cracking Behavior of Irradiated 316-Ti Stainless Steel in Simulated LWR Environments
Transactions | Volume 106 | Number 1 | June 2012 | Pages 569-570
Nuclear Installations Safety | Irradiation Assisted Degradation of Reactor Vessel Internals/NRC-Sponsored Environmentally Assisted Fatigue Research Activities
Transactions | Volume 106 | Number 1 | June 2012 | Page 571
Nuclear Installations Safety | Irradiation Assisted Degradation of Reactor Vessel Internals/NRC-Sponsored Environmentally Assisted Fatigue Research Activities
Update on NQA-1: Quality Assurance Requirements for Nuclear Facility Applications-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 572
Nuclear Installations Safety | Irradiation Assisted Degradation of Reactor Vessel Internals/NRC-Sponsored Environmentally Assisted Fatigue Research Activities
Solving the Spent Fuel Dilemma-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 575
Operations and Power
New Nuclear Construction Around the World Status Report-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 576
Operations and Power
Fukushima: Evaluation and Impacts-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 577
Operations and Power
A Three-Component Model on Gas Transport in a Defective Fuel Rod
Transactions | Volume 106 | Number 1 | June 2012 | Pages 581-583
Operations and Power | Operations and Power: General
Recovery of Damaged Components in Reactor Vessel of the Experimental Fast Reactor Joyo
Transactions | Volume 106 | Number 1 | June 2012 | Pages 584-585
Operations and Power | Operations and Power: General
Statistic Trend Analysis of Incidents and Failures Focused on Commissioning Stage of KSNP
Transactions | Volume 106 | Number 1 | June 2012 | Pages 586-587
Operations and Power | Operations and Power: General
The Advanced Test Reactor National Scientific User Facility
Transactions | Volume 106 | Number 1 | June 2012 | Pages 588-589
Operations and Power | Operations and Power: General
Licensing and Design of Mixed Cores for US Light Water Cooled Reactors
Transactions | Volume 106 | Number 1 | June 2012 | Pages 590-591
Operations and Power | Operations and Power: General
IRWST Elevation Design for Passive ECCS and IVR Strategy
Transactions | Volume 106 | Number 1 | June 2012 | Page 592
Operations and Power | Operations and Power: General
Initial Split-Flow Operations of a Supercritical-CO2 Recompression Brayton Cycle
Transactions | Volume 106 | Number 1 | June 2012 | Pages 593-596
Operations and Power | Operations and Power: General
Analysis of Supercritical CO2 Brayton Cycles for Pertinent Compressor Inlet Conditions
Transactions | Volume 106 | Number 1 | June 2012 | Pages 597-598
Operations and Power | Operations and Power: General
Update on Emergency Preparedness and Planning Post-Fukushima-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 599
Operations and Power | Operations and Power: General
The Business Case for Islanded Small Modular Reactors
Transactions | Volume 106 | Number 1 | June 2012 | Page 603
Operations and Power | SMR: Progression and Status
Progress on Privately Funded Energy Multiplier Module (EM2) Program
Transactions | Volume 106 | Number 1 | June 2012 | Pages 604-605
Operations and Power | SMR: Progression and Status
Westinghouse SMR Program Progress
Transactions | Volume 106 | Number 1 | June 2012 | Page 606
Operations and Power | SMR: Progression and Status
Simulator Assisted Design for a Multi-Module Small Modular Reactor Plant
Transactions | Volume 106 | Number 1 | June 2012 | Pages 607-608
Operations and Power | SMR: Progression and Status
Transactions | Volume 106 | Number 1 | June 2012 | Pages 611-613
Operations and Power | Advanced Reactors
In-Situ Performance of Optical Fibers Heated to 600°C During Gamma Irradiation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 614-615
Operations and Power | Advanced Reactors
In-Situ Performance of Silica Optical Fibers Heated to 1000°C
Transactions | Volume 106 | Number 1 | June 2012 | Pages 616-617
Operations and Power | Advanced Reactors
PARFUME Modeling Status Update
Transactions | Volume 106 | Number 1 | June 2012 | Pages 618-621
Operations and Power | Advanced Reactors
ADS Windowless Spallation Target Design: An Experimental and Computational Approach
Transactions | Volume 106 | Number 1 | June 2012 | Pages 622-625
Operations and Power | Advanced Reactors
3D In-Core Monitoring in Advanced Reactor Environments
Transactions | Volume 106 | Number 1 | June 2012 | Pages 626-627
Operations and Power | Advanced Reactors
Simulations of Dynamics and Control of Advanced Reactor Systems Using Artificial Neural Networks
Transactions | Volume 106 | Number 1 | June 2012 | Pages 628-629
Operations and Power | Advanced Reactors
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors
Transactions | Volume 106 | Number 1 | June 2012 | Pages 630-632
Operations and Power | Advanced Reactors
The Conceptual Design of Integrated Passive Safety System
Transactions | Volume 106 | Number 1 | June 2012 | Page 633
Operations and Power | Advanced Reactors
Radiation Protection and Shielding-Roundtable
Transactions | Volume 106 | Number 1 | June 2012 | Page 637
Radiation Protection and Shielding
Verification of the Local Monte Carlo Modeling Approach for Fusion Neutronics Applications in ITER
Transactions | Volume 106 | Number 1 | June 2012 | Pages 641-644
Radiation Protection and Shielding | Radiation Protection and Shielding: General
Overview on SNS Beam Lines Shielding Analyses
Transactions | Volume 106 | Number 1 | June 2012 | Pages 645-647
Radiation Protection and Shielding | Radiation Protection and Shielding: General
A Database for Effective Dose from External Photon Exposures Using Voxel Phantoms and ICRP 103
Transactions | Volume 106 | Number 1 | June 2012 | Pages 648-649
Radiation Protection and Shielding | Radiation Protection and Shielding: General
Transactions | Volume 106 | Number 1 | June 2012 | Pages 650-651
Radiation Protection and Shielding | Radiation Protection and Shielding: General
Portable Neutron Sensors for Emergency Response Operations
Transactions | Volume 106 | Number 1 | June 2012 | Pages 652-655
Radiation Protection and Shielding | Radiation Protection and Shielding: General
Uncollided Surface and Cell Tallies in Monte Carlo Codes
Transactions | Volume 106 | Number 1 | June 2012 | Pages 659-661
Radiation Protection and Shielding | Computational Tools for Radiation Protection and Shielding
Transactions | Volume 106 | Number 1 | June 2012 | Pages 662-665
Radiation Protection and Shielding | Computational Tools for Radiation Protection and Shielding
Transactions | Volume 106 | Number 1 | June 2012 | Pages 666-668
Radiation Protection and Shielding | Computational Tools for Radiation Protection and Shielding
Validating Scale6.1/MAVRIC with Two Reactor Pressure Vessel Dosimetry Benchmarks
Transactions | Volume 106 | Number 1 | June 2012 | Pages 669-671
Radiation Protection and Shielding | Computational Tools for Radiation Protection and Shielding
Reactor Pressure Vessel Neutron Exposure Monitoring-Tutorial
Transactions | Volume 106 | Number 1 | June 2012 | Page 672
Radiation Protection and Shielding | Computational Tools for Radiation Protection and Shielding
MCNP/MCNPX Tutorial for Homeland Security
Transactions | Volume 106 | Number 1 | June 2012 | Page 673
Radiation Protection and Shielding | Computational Tools for Radiation Protection and Shielding
Current Capabilities, Issues in LWR Core Design and Reactor Engineering Support-Panel
Transactions | Volume 106 | Number 1 | June 2012 | Page 677
Reactor Physics
Challenges in HTGR Modeling and Simulation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 681-684
Reactor Physics | Characterization and Applications of Advanced Reactors and Fuels
Improvement of DeCART Depletion Calculation for VHTR Fuel Elements
Transactions | Volume 106 | Number 1 | June 2012 | Pages 685-688
Reactor Physics | Characterization and Applications of Advanced Reactors and Fuels
A Neutronics Feasibility Study of Using FCM on a LWR
Transactions | Volume 106 | Number 1 | June 2012 | Pages 689-691
Reactor Physics | Characterization and Applications of Advanced Reactors and Fuels
Transactions | Volume 106 | Number 1 | June 2012 | Pages 692-694
Reactor Physics | Characterization and Applications of Advanced Reactors and Fuels
233U Production by Fusion Driven Systems Using Slurry Fuel Carrier
Transactions | Volume 106 | Number 1 | June 2012 | Pages 695-696
Reactor Physics | Characterization and Applications of Advanced Reactors and Fuels
Study of Space-Time Evolution of Flux in a Long-Life Traveling Wave Reactor
Transactions | Volume 106 | Number 1 | June 2012 | Pages 697-699
Reactor Physics | Characterization and Applications of Advanced Reactors and Fuels
A Large-Scale Sodium Loop for Coupling to the Sandia National Laboratories S-CO2 Brayton Cycle
Transactions | Volume 106 | Number 1 | June 2012 | Pages 700-702
Reactor Physics | Characterization and Applications of Advanced Reactors and Fuels
A Doppler Broadening and Monte Carlo Coupling Code for Temperature-Dependent Problems
Transactions | Volume 106 | Number 1 | June 2012 | Pages 705-707
Reactor Physics | Reactor Analysis Methods - I
Progress with On-The-Fly Neutron Doppler Broadening in MCNP
Transactions | Volume 106 | Number 1 | June 2012 | Pages 708-710
Reactor Physics | Reactor Analysis Methods - I
Transactions | Volume 106 | Number 1 | June 2012 | Pages 711-714
Reactor Physics | Reactor Analysis Methods - I
Analysis of Erbia-Loaded Critical Experiments in KUCA Using AEGIS Cross Section Library
Transactions | Volume 106 | Number 1 | June 2012 | Pages 715-718
Reactor Physics | Reactor Analysis Methods - I
Transactions | Volume 106 | Number 1 | June 2012 | Pages 719-722
Reactor Physics | Reactor Analysis Methods - I
SCALE Continuous-Energy Monte Carlo Depletion with Parallel KENO in TRITON
Transactions | Volume 106 | Number 1 | June 2012 | Pages 723-725
Reactor Physics | Reactor Analysis Methods - I
Integrated Radiation Transport and Thermo-Mechanics Simulation of a PWR Assembly
Transactions | Volume 106 | Number 1 | June 2012 | Pages 726-731
Reactor Physics | Reactor Analysis Methods - I
Discrete Ordinate Calculation of the k-Eigenvalue of an IFBA Pin Using Unstructured Meshes in 2D
Transactions | Volume 106 | Number 1 | June 2012 | Pages 732-735
Reactor Physics | Reactor Analysis Methods - I
Development and Comparison of High Flux Isotope Reactor Actinide Target Models
Transactions | Volume 106 | Number 1 | June 2012 | Pages 736-738
Reactor Physics | Reactor Analysis Methods - I
A 3D Neutron Transport Calculation Method for ITER Test Blanket Module
Transactions | Volume 106 | Number 1 | June 2012 | Pages 741-742
Reactor Physics | Reactor Analysis Methods - II
Kinetic Calculation Method in Space-Time Frame Using Characteristic Line
Transactions | Volume 106 | Number 1 | June 2012 | Pages 743-746
Reactor Physics | Reactor Analysis Methods - II
Calculation of Incremental Control Rod Reactivity Worth Using COMET
Transactions | Volume 106 | Number 1 | June 2012 | Pages 747-749
Reactor Physics | Reactor Analysis Methods - II
Parallel Iterative Method for Solving the Continuous Energy Slowing-Down Equations
Transactions | Volume 106 | Number 1 | June 2012 | Pages 750-753
Reactor Physics | Reactor Analysis Methods - II
A Quadrature Set for a Characteristics-Based Response Matrix Method
Transactions | Volume 106 | Number 1 | June 2012 | Pages 754-756
Reactor Physics | Reactor Analysis Methods - II
Evaluation of Indirect Effect in Sensitivity Coefficients by SAINT-II
Transactions | Volume 106 | Number 1 | June 2012 | Pages 757-758
Reactor Physics | Reactor Analysis Methods - II
High-Order Response Moments for Model Uncertainty Quantification and Validation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 759-762
Reactor Physics | Reactor Analysis Methods - II
Application of GPT-Free Method to Sensitivity Analysis in Monte Carlo Models
Transactions | Volume 106 | Number 1 | June 2012 | Pages 763-766
Reactor Physics | Reactor Analysis Methods - II
Transactions | Volume 106 | Number 1 | June 2012 | Pages 767-770
Reactor Physics | Reactor Analysis Methods - II
Release of the ENDF/B-VII.1 Evaluated Nuclear Data File
Transactions | Volume 106 | Number 1 | June 2012 | Pages 773-776
Reactor Physics | ENDF/B-VII.1: Data Measurements, Evaluation, Processing, and Initial Experience
Decay Data Sub-library Developed for ENDF/B-VII.1
Transactions | Volume 106 | Number 1 | June 2012 | Pages 777-778
Reactor Physics | ENDF/B-VII.1: Data Measurements, Evaluation, Processing, and Initial Experience
Transactions | Volume 106 | Number 1 | June 2012 | Pages 779-783
Reactor Physics | ENDF/B-VII.1: Data Measurements, Evaluation, Processing, and Initial Experience
ORNL Resonance Evaluation for ENDF/B-VII.1
Transactions | Volume 106 | Number 1 | June 2012 | Pages 784-785
Reactor Physics | ENDF/B-VII.1: Data Measurements, Evaluation, Processing, and Initial Experience
ICSBEP Criticality Benchmark Eigenvalues with ENDF/B-VII.1 Cross Sections
Transactions | Volume 106 | Number 1 | June 2012 | Pages 786-788
Reactor Physics | ENDF/B-VII.1: Data Measurements, Evaluation, Processing, and Initial Experience
Benchmarking ENDF/B-VII.1, JENDL-4.0 and JEFF-3.1.1 with MCNP6
Transactions | Volume 106 | Number 1 | June 2012 | Pages 789-791
Reactor Physics | ENDF/B-VII.1: Data Measurements, Evaluation, Processing, and Initial Experience
Benchmark Testing of the ENDF/B-VII.1 Nuclear Data Library
Transactions | Volume 106 | Number 1 | June 2012 | Pages 792-795
Reactor Physics | ENDF/B-VII.1: Data Measurements, Evaluation, Processing, and Initial Experience
Uncertainty Quantification in Monte Carlo Criticality Calculations with ENDF/B-VII.1 Covariance Data
Transactions | Volume 106 | Number 1 | June 2012 | Pages 796-797
Reactor Physics | ENDF/B-VII.1: Data Measurements, Evaluation, Processing, and Initial Experience
Transactions | Volume 106 | Number 1 | June 2012 | Pages 798-800
Reactor Physics | ENDF/B-VII.1: Data Measurements, Evaluation, Processing, and Initial Experience
Role of Experimental Correlations for Validation of Neutron Cross-Sections Libraries
Transactions | Volume 106 | Number 1 | June 2012 | Pages 801-802
Reactor Physics | ENDF/B-VII.1: Data Measurements, Evaluation, Processing, and Initial Experience
Development of IDAT: IRPhE Database and Analysis Tool
Transactions | Volume 106 | Number 1 | June 2012 | Pages 805-807
Reactor Physics | Reactor Physics Design, Validation, and Operating Experience
Status of Validating Core-Reload and Safety Analysis of the Advanced Test Reactor Using HELIOS
Transactions | Volume 106 | Number 1 | June 2012 | Pages 808-810
Reactor Physics | Reactor Physics Design, Validation, and Operating Experience
MCNP5 Version 1.60 Adjoint-Weighted Kinetics Parameters Option Validation in ATR
Transactions | Volume 106 | Number 1 | June 2012 | Pages 811-812
Reactor Physics | Reactor Physics Design, Validation, and Operating Experience
A Preliminary Comparison of MCNP6 Delayed Neutron Emission from 235U and Experimental Measurements
Transactions | Volume 106 | Number 1 | June 2012 | Pages 813-816
Reactor Physics | Reactor Physics Design, Validation, and Operating Experience
Determination of Hot Channel of Missouri S&T Nuclear Reactor
Transactions | Volume 106 | Number 1 | June 2012 | Pages 817-818
Reactor Physics | Reactor Physics Design, Validation, and Operating Experience
Relicensing Analysis for the Geological Survey TRIGA Reactor
Transactions | Volume 106 | Number 1 | June 2012 | Pages 819-823
Reactor Physics | Reactor Physics Design, Validation, and Operating Experience
KIPT Neutron Source Facility Configuration Using Beryllium-Graphite Reflector
Transactions | Volume 106 | Number 1 | June 2012 | Pages 824-825
Reactor Physics | Reactor Physics Design, Validation, and Operating Experience
Conceptual Design of a Small Nuclear Reactor for NTD-Si Using Short PWR Fuel Assemblies
Transactions | Volume 106 | Number 1 | June 2012 | Pages 826-829
Reactor Physics | Reactor Physics Design, Validation, and Operating Experience
Traveling Wave Reactor Core Design Using Massively Parallel Precomputation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 830-833
Reactor Physics | Reactor Physics Design, Validation, and Operating Experience
Preliminary Design of a FHR Test Reactor Core
Transactions | Volume 106 | Number 1 | June 2012 | Pages 834-835
Reactor Physics | Reactor Physics Design, Validation, and Operating Experience
Reconciliation of Anomalous TMI-1 Radiochemical Assays
Transactions | Volume 106 | Number 1 | June 2012 | Pages 836-838
Reactor Physics | Reactor Physics Design, Validation, and Operating Experience
IAEA Support of Research Reactor HEU to LEU Fuel Conversion
Transactions | Volume 106 | Number 1 | June 2012 | Pages 841-844
Reactor Physics | Experiences and Challenges in RERTR Core Redesign
Design of a Low-Enriched Uranium Fuel for the High Flux Isotope Reactor - Reactor Physics Analyses
Transactions | Volume 106 | Number 1 | June 2012 | Pages 845-848
Reactor Physics | Experiences and Challenges in RERTR Core Redesign
Neutronic Modeling of the MIT Reactor LEU Conversion
Transactions | Volume 106 | Number 1 | June 2012 | Pages 849-852
Reactor Physics | Experiences and Challenges in RERTR Core Redesign
Transactions | Volume 106 | Number 1 | June 2012 | Pages 853-856
Reactor Physics | Experiences and Challenges in RERTR Core Redesign
Transactions | Volume 106 | Number 1 | June 2012 | Pages 857-860
Reactor Physics | Experiences and Challenges in RERTR Core Redesign
Additional Benchmark Evaluation of the NRAD Reactor LEU Core Conversion
Transactions | Volume 106 | Number 1 | June 2012 | Pages 861-864
Reactor Physics | Experiences and Challenges in RERTR Core Redesign
Prompt Neutron Lifetime for the NBSR Reactor
Transactions | Volume 106 | Number 1 | June 2012 | Pages 865-868
Reactor Physics | Experiences and Challenges in RERTR Core Redesign
Transactions | Volume 106 | Number 1 | June 2012 | Pages 869-871
Reactor Physics | Experiences and Challenges in RERTR Core Redesign
Transactions | Volume 106 | Number 1 | June 2012 | Pages 872-874
Reactor Physics | Experiences and Challenges in RERTR Core Redesign
Selection and Application of Dosimetry Cross Sections for Nuclear Applications
Transactions | Volume 106 | Number 1 | June 2012 | Pages 877-880
Reactor Physics | Research Applications of Neutron Spectrometry and Dosimetry
The Role of the Prior Covariance Matrix in Least-Squares Neutron Spectrum Adjustment
Transactions | Volume 106 | Number 1 | June 2012 | Pages 881-883
Reactor Physics | Research Applications of Neutron Spectrometry and Dosimetry
Transactions | Volume 106 | Number 1 | June 2012 | Pages 884-887
Reactor Physics | Research Applications of Neutron Spectrometry and Dosimetry
Neutron Dosimetry in Containment at the Dominion Kewaunee Power Station
Transactions | Volume 106 | Number 1 | June 2012 | Pages 888-889
Reactor Physics | Research Applications of Neutron Spectrometry and Dosimetry
Transactions | Volume 106 | Number 1 | June 2012 | Pages 890-893
Reactor Physics | Research Applications of Neutron Spectrometry and Dosimetry
The p-D2O Generator Neutron Spectrum Determination by Multi-foil Activation Method
Transactions | Volume 106 | Number 1 | June 2012 | Pages 894-896
Reactor Physics | Research Applications of Neutron Spectrometry and Dosimetry
Test Fidelity at Research Reactors
Transactions | Volume 106 | Number 1 | June 2012 | Pages 897-899
Reactor Physics | Research Applications of Neutron Spectrometry and Dosimetry
Thermal Neutron Scattering Cross Sections for Reactor-Grade Graphite
Transactions | Volume 106 | Number 1 | June 2012 | Pages 903-904
Reactor Physics | Reactor Physics: General
Transactions | Volume 106 | Number 1 | June 2012 | Pages 905-908
Reactor Physics | Reactor Physics: General
Particle Tracking Development for a Fission Time Projection Chamber
Transactions | Volume 106 | Number 1 | June 2012 | Pages 909-911
Reactor Physics | Reactor Physics: General
An Analysis of the Antineutrino Rate During CANDU Reactor Startup
Transactions | Volume 106 | Number 1 | June 2012 | Pages 912-914
Reactor Physics | Reactor Physics: General
Reconsideration of Inherent Neutron Sources in Liquid Fuel of Molten Salt Reactors
Transactions | Volume 106 | Number 1 | June 2012 | Pages 915-918
Reactor Physics | Reactor Physics: General
Numerical Simulation of the Two Phase Flow and Investigation of the Induced Neutron Noise
Transactions | Volume 106 | Number 1 | June 2012 | Pages 919-921
Reactor Physics | Reactor Physics: General
A Mechanistic Approach to Iodine-Influenced Stress Corrosion Cracking (ISCC)
Transactions | Volume 106 | Number 1 | June 2012 | Pages 922-926
Reactor Physics | Reactor Physics: General
Heater Controller Module for Simulating Reactivity Feedback
Transactions | Volume 106 | Number 1 | June 2012 | Pages 927-930
Reactor Physics | Reactor Physics: General
Development of Reactor Core Neutronics and Thermal Physics for the U-PANTHER Simulator
Transactions | Volume 106 | Number 1 | June 2012 | Pages 931-934
Reactor Physics | Reactor Physics: General
Stack Characterization System Development - Status and Path Forward
Transactions | Volume 106 | Number 1 | June 2012 | Pages 939-942
Robotics and Remote Systems | Robotics and Remote Systems: General
COINS: A New Computer Assisted Method for Non Destructive Rod Analysis
Transactions | Volume 106 | Number 1 | June 2012 | Pages 943-944
Robotics and Remote Systems | Robotics and Remote Systems: General
Statistics and Discrete-Event Modeling of Remote Operations with a TRU Pipe Connector
Transactions | Volume 106 | Number 1 | June 2012 | Pages 945-946
Robotics and Remote Systems | Robotics and Remote Systems: General
Needs for Robotic Assessments of Nuclear Disasters
Transactions | Volume 106 | Number 1 | June 2012 | Pages 947-948
Robotics and Remote Systems | Robotics and Remote Systems: General
Tube Sheet Runner (TSR) PWR Steam Generator Inspection Manipulator
Transactions | Volume 106 | Number 1 | June 2012 | Pages 949-950
Robotics and Remote Systems | Robotics and Remote Systems: General
Advanced Manufacturing Concepts Using Hybrid Laser Welding
Transactions | Volume 106 | Number 1 | June 2012 | Pages 951-952
Robotics and Remote Systems | Robotics and Remote Systems: General
Spectral Analysis of Turbulent Bubbly Flows Based on Direct Numerical Simulation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 957-959
Thermal Hydraulics | General Two-Phase Flow
Transactions | Volume 106 | Number 1 | June 2012 | Pages 960-961
Thermal Hydraulics | General Two-Phase Flow
3-D Simulation of Rising Bubble in a Viscous Liquid Using the Lattice Boltzmann Method
Transactions | Volume 106 | Number 1 | June 2012 | Pages 962-964
Thermal Hydraulics | General Two-Phase Flow
PWR Core Analysis with COBRA-TF/PARCSv2.7 Coupled Code
Transactions | Volume 106 | Number 1 | June 2012 | Pages 965-968
Thermal Hydraulics | General Two-Phase Flow
Temporal Convergence Criteria for the COBRA-TF Subchannel Analysis Code
Transactions | Volume 106 | Number 1 | June 2012 | Pages 971-974
Thermal Hydraulics | Computational Thermal Hydraulics - I
Use of RELAP5/MOD3.3 Code to Get Fluid Dynamic Stability Maps
Transactions | Volume 106 | Number 1 | June 2012 | Pages 975-978
Thermal Hydraulics | Computational Thermal Hydraulics - I
RELAP5-3D Simulations of the Reactor Cavity Cooling System Experimental Facility
Transactions | Volume 106 | Number 1 | June 2012 | Pages 979-981
Thermal Hydraulics | Computational Thermal Hydraulics - I
A Sensitivity Analysis of the Safety Features in a 600 MWe Demonstration Fast Reactor
Transactions | Volume 106 | Number 1 | June 2012 | Pages 982-983
Thermal Hydraulics | Computational Thermal Hydraulics - I
Space-Time Convergence Study Based on OECD Ringhals-1 Stability Benchmark
Transactions | Volume 106 | Number 1 | June 2012 | Pages 984-987
Thermal Hydraulics | Computational Thermal Hydraulics - I
Assessment of Regularization Methods for the 1D Two-Fluid Model
Transactions | Volume 106 | Number 1 | June 2012 | Pages 988-991
Thermal Hydraulics | Computational Thermal Hydraulics - I
Validation of Heat Transfer Predictions by Turbulence Models and Heat Transfer Correlations
Transactions | Volume 106 | Number 1 | June 2012 | Pages 992-994
Thermal Hydraulics | Computational Thermal Hydraulics - I
Dynamic Bias Error Analysis for Multi-Phase Flow
Transactions | Volume 106 | Number 1 | June 2012 | Pages 995-996
Thermal Hydraulics | Computational Thermal Hydraulics - I
CFD Analysis of Two-Group IATE Models for Bubbly-Cap Flows with the EAGLE Code
Transactions | Volume 106 | Number 1 | June 2012 | Pages 999-1002
Thermal Hydraulics | Computational Thermal Hydraulics - II
Verification of COBRA-TF Boron Tracking Model with STAR-CD
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1003-1005
Thermal Hydraulics | Computational Thermal Hydraulics - II
Assessment of a Computational Fluid Dynamic (CFD) Model for the IPR-R1 TRIGA Research Reactor
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1006-1009
Thermal Hydraulics | Computational Thermal Hydraulics - II
SHARP Reactor Performance and Safety Analysis Simulation Suite
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1013-1016
Thermal Hydraulics | Next Generation Safety Analysis Code
Best-Estimate Plus Uncertainty Approach in Licensing of Current Reactors
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1017-1019
Thermal Hydraulics | Next Generation Safety Analysis Code
Requirement Analysis and Primary Design of COSINE Code
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1020-1023
Thermal Hydraulics | Next Generation Safety Analysis Code
Correlation for Nucleate Boiling on a Downward Facing Surface Under IVR-ERVC Conditions
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1027-1028
Thermal Hydraulics | Thermal Hydraulics in Severe Accidents
Simulation of FARO Corium Coolant Interaction Experiment with TEXAS-VI
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1029-1031
Thermal Hydraulics | Thermal Hydraulics in Severe Accidents
Prediction of Local Hydrogen Concentrations in PWR Containment Using GOTHIC Code
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1032-1035
Thermal Hydraulics | Thermal Hydraulics in Severe Accidents
A Feasibility Study for MELCOR DB Construction and Uncertainty Analysis
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1036-1037
Thermal Hydraulics | Thermal Hydraulics in Severe Accidents
Study of CHF Characteristics with a Downward-Facing Plane for IVR
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1038-1040
Thermal Hydraulics | Thermal Hydraulics in Severe Accidents
Characterization of Turbine Stop Valve Closing Time
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1043-1045
Thermal Hydraulics | General Thermal Hydraulics - I
Critical Heat Flux in Vertical Channels at Zero Flow Condition
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1046-1048
Thermal Hydraulics | General Thermal Hydraulics - I
Intermediate BLOCA Scenarios - Sensitivity Analysis with TRACE5
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1049-1052
Thermal Hydraulics | General Thermal Hydraulics - I
Analysis of Reactor Water Level Fluctuations in BWRs
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1053-1054
Thermal Hydraulics | General Thermal Hydraulics - I
Measurement of Whole Temperature Field in Refrigerant Using Two-Color/Single-Dye LIF
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1057-1059
Thermal Hydraulics | General Thermal Hydraulics - II
Acoustic Analysis of Pump-Induced Vibrations in Reactor Recirculation Piping
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1060-1063
Thermal Hydraulics | General Thermal Hydraulics - II
Study of Thermal Mixing Characteristics with T-Junction Piping System
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1064-1067
Thermal Hydraulics | General Thermal Hydraulics - II
Critical Heat Flux Under Natural and Forced Convection
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1068-1070
Thermal Hydraulics | General Thermal Hydraulics - II
Design of a Scaled-Down Low-Temperature DRACS Test Facility for an AHTR
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1071-1074
Thermal Hydraulics | General Thermal Hydraulics - II
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1075-1077
Thermal Hydraulics | General Thermal Hydraulics - II
Investigation on Hydrodynamic Cavitation of a Restriction Orifice on Crud-Like Deposits
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1078-1080
Thermal Hydraulics | General Thermal Hydraulics - II
Heat Transfer Characterization of a Scaled-Down Air-Ingress Accident Test Facility
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1081-1084
Thermal Hydraulics | General Thermal Hydraulics - II
Effect of Fuel Assembly Grouping on Instability of Chinshan NPP
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1085-1087
Thermal Hydraulics | General Thermal Hydraulics - II
Transactions | Volume 106 | Number 1 | June 2012 | Page 1091
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012)
General Chairs' Special Session
Transactions | Volume 106 | Number 1 | June 2012 | Page 1092
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012)
An Assessment of Nitride Test Data and its Use in SMRs
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1095-1097
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I
Chemical Stabilization of Metallic Nuclear Fuels
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1098-1101
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I
Development of Advanced Ultra-High Burnup SFR Metallic Fuel Concept - Project Overview
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1102-1105
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I
Fully Ceramic Microencapsulated Fuels for LWRs
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1106-1107
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - I
The EBR-II X447 High Temperature U-10Zr Metal Alloy Experiment
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1111-1112
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - II
Mg as a Matrix for Low-Enriched U-Mo Dispersion Fuel Plates
Transactions | Volume 106 | Number 1 | June 2012 | Page 1113
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - II
Irradiation Behavior of Oxide Ceramics for Inert Matrices
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1114-1116
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - II
Development and Properties of Uranium Nitride Fuels: Oxide Conversion and Thermochemistry
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1117-1118
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Fuel - II
Mechanisms of Ag Diffusion in TRISO Coated Fuel Particles
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1121-1122
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Clad/Fuel
Effects of Structure and Processing on the Thermal Conductivity of SiC-SiC Composites
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1123-1125
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Clad/Fuel
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1126-1127
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Advanced Clad/Fuel
Sodium Fast Reactor Fuels and Materials: Research Needs
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1131-1132
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Fast Reactor Materials
HT9 Development for the Traveling Wave Reactor
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1133-1135
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Fast Reactor Materials
Corrosion of Zirconium Alloy in Flowing Sodium
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1136-1138
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Fast Reactor Materials
Burnup Predictions for Metal Fuel Tests in the Fast Flux Test Facility
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1139-1141
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Fast Reactor Materials
Materials Performance for High Temperature Gas-Cooled Reactors
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1145-1146
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | High Temperature Materials - I
Oxidation Investigation of NBG-18 Nuclear-Grade Graphite
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1147-1148
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | High Temperature Materials - I
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1149-1152
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | High Temperature Materials - I
Creep Behaviors of Alloy 617 in High Temperature Steam Environments
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1153-1154
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | High Temperature Materials - I
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1157-1158
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | High Temperature Materials - II
Local Atomic Structure of Irradiated ZrC and ZrN
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1159-1160
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | High Temperature Materials - II
Creep-Fatigue Interaction in Advanced Ferritic-Martensitic Steels
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1161-1162
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | High Temperature Materials - II
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1163-1164
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | High Temperature Materials - II
The Center for Material Science of Nuclear Fuel
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1167-1168
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Extreme Environment - I: Nanoscale Effects
Irradiation Effects in Nanocrystalline Ceria, Zirconia and Thoria
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1169-1172
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Extreme Environment - I: Nanoscale Effects
Thermal Stability and Radiation Tolerance of Ultrafine Grained Austenitic Stainless Steel
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1173-1176
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Extreme Environment - I: Nanoscale Effects
Characterization of Nanocomposite Materials Using Synchrotron Radiation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1177-1180
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Extreme Environment - I: Nanoscale Effects
Radiation Enhanced Diffusion of Nd in Single Crystal Thin Film UO2
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1183-1186
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Extreme Environment - II: Kinetics and Transport
Evaluation of Gas Release Behavior of Minor Actinide-Containing Metal Fuel
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1187-1188
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Extreme Environment - II: Kinetics and Transport
Oxidation of Candidate Ferritic LWR Cladding Materials at High Temperatures
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1189-1190
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Extreme Environment - II: Kinetics and Transport
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1191-1193
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Extreme Environment - II: Kinetics and Transport
Multiscale Fuel Performance Modeling: Coupling Atomic, Meso and Continuum Level Simulations
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1197-1198
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Modeling - I: Thermomechanics and Transport
Lattice Dynamics and Boltzmann Transport Equation Simulations of Thermal Conductivity in UO2
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1199-1200
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Modeling - I: Thermomechanics and Transport
Fuel Performance Assessment of the Lead-Bismuth-Cooled MYRRHA Reactor
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1201-1204
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Modeling - I: Thermomechanics and Transport
Thermo-Mechanical Modeling of U-Pu-Zr Metallic Fuel
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1205-1206
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Modeling - I: Thermomechanics and Transport
Issues in Modeling Metallic Fuel Systems with HT9 Clad
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1207-1208
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Modeling - I: Thermomechanics and Transport
A Continuum Thermodynamic Approach to Radiation Effects in Materials
Transactions | Volume 106 | Number 1 | June 2012 | Page 1211
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Modeling - II: Radiation Effects
Molecular Dynamics Simulations of Swift Heavy Ion Interactions in UO2
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1212-1213
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Modeling - II: Radiation Effects
Calculation of the Displacement Energy in b.c.c. U at 800 K
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1214-1215
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Modeling - II: Radiation Effects
Fast Radiation Tolerant Dynamics at Interfaces
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1216-1218
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Modeling - II: Radiation Effects
A European Roadmap on Materials for Nuclear Energy Technology
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1221-1224
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Hydrogen-Helium Synergy in Bubbles in BCC Iron
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1225-1227
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
An Atomistic Simulation Study of the Substitution of Pu and Am in UO2 Lattice
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1228-1229
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Formation of a Magnetic Phase in Irradiated Model Austenitic Alloys
Transactions | Volume 106 | Number 1 | June 2012 | Page 1230
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Simulation of Injection Casting for Metal Fuel Fabrication
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1231-1232
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
SiC Oxidation in Steam Environments at Elevated Temperature and Pressure
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1233-1234
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
An Inter-Laboratory Comparison of Graphite Testing Procedures
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1235-1237
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Thermal and Oxygen Transport in UO2 Fuel Elements: Impact of Thermal Conductivity
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1238-1239
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1240-1241
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
In-Situ TEM Study of Gas Bubble Formation in Xenon-Implanted CeO2
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1242-1243
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Effect of the Forming Conditions on the Mechanical and Physical Properties of Fuel Elements for HTGR
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1244-1245
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Neutron Irradiation Effects on the Tensile Properties of FBR Structural Materials
Transactions | Volume 106 | Number 1 | June 2012 | Page 1246
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Thermal-Hydraulic Analysis of LWR Hydride Fuel Irradiation Experiment in MITR
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1247-1250
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1251-1252
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Behavior of Binder Materials in Graphite Matrix Powder for HTGR Fuel Compact
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1253-1255
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Thermal Properties of U-Zr Alloys for SFR Fuel by Gravity Casting
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1256-1257
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Resintering Behavior of MnO-Al2O3-Doped UO2 Annular Pellet for Dual Cooled Fuel
Transactions | Volume 106 | Number 1 | June 2012 | Page 1258
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Resintering Behavior of Cr2O3-Doped UO2 Pellets
Transactions | Volume 106 | Number 1 | June 2012 | Page 1259
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Compatibility of Welds and 12 Cr ODS with Oxygen Containing Liquid Pb
Transactions | Volume 106 | Number 1 | June 2012 | Page 1260
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
High Temperature Materials Testing Capsule for Irradiation Experiments in PULSTAR Reactor
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1261-1262
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Microstructure and High Temperature Mechanical Behaviour of UO2 Fuel
Transactions | Volume 106 | Number 1 | June 2012 | Page 1263
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Preliminary Evaluation of Fission Product Release from AGR-1 Coated Particles
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1264-1267
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Clustering and Nucleation of Point Defects in Stoichiometric and Non-stoichiometric UO2
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1268-1269
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Study of Interfacial Interactions Using Thin Film Surface Modification
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1270-1271
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Analysis of Nuclear Fuel Reliability Under Steam Generator Tube Rupture Accident Conditions
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1272-1275
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Towards Improving the Fracture Characteristics of Nanostructured Ferritic Alloys
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1276-1277
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Microstructural Studies of Nuclear Graphite (NBG 18)
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1278-1281
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Thermal Simulation Data Analysis for AGR Experiments
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1282-1283
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Multicomponent Diffusion in Molten LiCl-KCl Mixture
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1284-1286
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1287-1289
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1290-1291
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Modeling of Fission-Gas-Induced Swelling in U-Mo Alloy Fuels
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1292-1293
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
In-situ Raman Spectroscopic Analysis of Ni-Base Alloy/LAS Dissimilar Metal Weld Interfaces
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1294-1295
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Spatially Resolved Positron Annihilation Spectroscopy of Nuclear Fuels
Transactions | Volume 106 | Number 1 | June 2012 | Page 1296
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Kinetic Parameters Influencing the Oxidation of Alloy 800H in Impure Helium at 850°C
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1297-1300
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Metal Matrix Microencapsulated Fuels for LWRs
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1301-1302
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
In-Pile Thermal Conductivity Measurement of Uranium-Zirconium Hydride Fuel
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1303-1304
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
A Study of Fuel Cladding Design Parameters for Ultra-Long Cycle Fast Reactors
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1305-1306
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Graphite Crucible of Ceramic Plasma-Sprayed Coating Layer Evaluation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1307-1308
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Initial APT Analysis of Irradiated MA957
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1309-1310
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Fabrication and Characterization of Ferritic/Martensitic Steel Cladding Tubes for SFR
Transactions | Volume 106 | Number 1 | June 2012 | Page 1311
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1312-1313
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1314-1315
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
In-Situ Characterization of NF616 Steel Using High Energy X-rays
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1316-1317
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Experiment Design of UO2 Irradiation in the Advanced Test Reactor
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1318-1319
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
A Robust Powered Remote Manipulator for Use in Waste Sorting, Processing, and Packaging
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1320-1322
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Graphite Reactor Decommissioning
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1323-1325
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Use of Retrieval Manipulator Systems in Nuclear Decommissioning
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1326-1328
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Neutron Irradiation Effect on Mechanical Properties of NITE SiC/SiC Composites
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1329-1330
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Microstructural Effect on Neutron Irradiation Response of Alloy 800H
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1331-1332
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
A Chemical Method to Immobilize Fission Product Lanthanides in Metallic Fast Reactor Fuel
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1333-1334
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Porous Silicon Carbide Composites for LWR Cladding
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1335-1336
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Microstructural Development in Silicon Carbide Composite During Neutron Irradiation
Transactions | Volume 106 | Number 1 | June 2012 | Page 1337
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Experimental Characterization of UO2 Oxidation in Water Vapor
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1338-1339
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Sintering and Final Microstructure of New UO2 Model Powders
Transactions | Volume 106 | Number 1 | June 2012 | Page 1340
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1341-1342
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Safety in the Synthesis of Nitride and Carbide Fuels
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1343-1344
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Irradiation Creep and Microstructure of F-M Steel T91
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1345-1347
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Thermodynamic Modeling of the Spinel Phase in the Fe-Ni-Cr-Zn-O System
Transactions | Volume 106 | Number 1 | June 2012 | Page 1348
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Advanced Metallic Fuel for Ultra-High Burnup: Irradiation Tests in ATR
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1349-1351
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Properties of Nuclear-Grade Silicon Carbide Continuous Fiber Composites
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1352-1353
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Thermal Aging Effects in Advanced Ferritic-Martensitic and Austenitic Steels
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1354-1355
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Fluidity Testing of Molten Uranium Alloys
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1356-1357
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
A Method for In-Situ Studies of Irradiation-Accelerated Corrosion
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1358-1360
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Microstructure and Surface Analysis of SiC Ceramics Oxidized in Helium Environments
Transactions | Volume 106 | Number 1 | June 2012 | Page 1361
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1362-1363
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Neutron Powder Diffraction Study of Irradiated Reactor Grade Graphite
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1364-1365
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Post Irradiation Examination of FFTF Irradiated MFF-3 and MFF-5 Fuel Pins
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1366-1367
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Hot-Roll-Processing of 9CrODS Steels for Na-Cooled Fast Reactors
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1368-1369
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Fission Gas Venting for Ultra-high Burnup SFR Metallic Fuel Pin Design
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1370-1373
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Multiscale Simulation Models of Xe Bubble Formation in Irradiated Mo
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1374-1375
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Status of Development of Metal Fuel Performance Code, PUMA
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1376-1377
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Investigation of the Effects of Alloying Additions to U-Zr Fuel via Atomistic Simulation
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1378-1380
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Vibrations and Anisotropic Heat Transport in Graphite
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1381-1383
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session
Computational Thermodynamics in the Advanced Multi-Physics Code
Transactions | Volume 106 | Number 1 | June 2012 | Pages 1384-1386
Embedded Topical Meeting: Nuclear Fuel and Structural Materials for the Next Generation Nuclear Reactors (NFSM 2012) | Poster Session