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Under-Sodium Endurance Experiment of Selector Valve in Failed-Fuel Detection and Location System of JSFR
Kosuke Aizawa, Kaoru Fujita, Shingo Hirata, Naoto Kasahara
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 1-12
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A16988
Characteristics of Composite Silicon Carbide Fuel Cladding After Irradiation Under Simulated PWR Conditions
John D. Stempien, David M. Carpenter, Gordon Kohse, Mujid S. Kazimi
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 13-29
Technical Paper | Fuel Cycle and Management/Materials for Nuclear Systems | doi.org/10.13182/NT12-86
Behavior of Transuranic Mixed-Oxide Fuel in a CANDU-900 Reactor
A. C. Morreale, M. R. Ball, D. R. Novog, J. C. Luxat
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 30-44
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A16990
Entropy-Based Nuclear Fuel Cycle Sensitivities and Covariances
Anthony M. Scopatz, Erich A. Schneider, Jun Li, Man-Sung Yim
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 45-61
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A16991
Verification and Validation of One-Dimensional Flow-Accelerated Corrosion Evaluation Code
Hiroaki Suzuki, Shunsuke Uchida, Masanori Naitoh, Hidetoshi Okada, Souji Koikari, Yukihiko Nagaya, Akira Nakamura, Seiichi Koshizuka, Derek H. Lister
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 62-74
Technical Paper | Thermal Hydraulics/Materials for Nuclear Systems | doi.org/10.13182/NT13-A16992
Study on the Behavior of an Asymmetrically Heated Reactor Cavity Cooling System with Water in Single Phase
D. D. Lisowski, T. C. Haskin, A. Tokuhiro, M. H. Anderson, M. L. Corradini
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 75-87
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-A16993
Predictions of the Heat Transfer Coefficient by Correlations and Turbulence Models
Constantine P. Tzanos
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 88-100
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-A16994
Advantages of MCNPX-Based Lattice Tally over Mesh Tally in High-Speed Monte Carlo Dose Reconstruction for Proton Radiotherapy
Rui Zhang, Jonas D. Fontenot, Dragan Mirkovic, John S. Hendricks, Wayne D. Newhauser
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 101-106
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT13-A16995
Software Failure Probability Assessment by Bayesian Inference
Gee-Yong Park, Heung-Seop Eom, Seung Cheol Jang, Hyun Gook Kang
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 107-118
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT13-A16996
Determination of Electrochemical Corrosion Potential Along the JMTR In-Pile Loop - I: Evaluation of ECP of Stainless Steel in High-Temperature Water as a Function of Oxidant Concentrations and Exposure Time
Shunsuke Uchida, Satoshi Hanawa, Yutaka Nishiyama, Takehiko Nakamura, Tomonori Satoh, Takashi Tsukada, Jan Kysela
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 119-135
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT13-A16997
Determination of Electrochemical Corrosion Potential Along the JMTR In-Pile Loop - II: Validation of ECP Electrodes and the Extrapolation of Measured ECP Data
Satoshi Hanawa, Takehiko Nakamura, Shunsuke Uchida, Pavel Kus, Rudolf Vsolak, Jan Kysela, Masanori Sakai
Nuclear Technology | Volume 183 | Number 1 | July 2013 | Pages 136-148
Technical Paper | Reprocessing | doi.org/10.13182/NT13-A16998

Number 2

Table of Contents
Long-Term Electrochemical Criteria for Crevice Corrosion in Concentrated Chloride Solutions (T. Ahn, H. Jung, P. Shukla, X. He)

Measurement of Silver Diffusion in VHTR Graphitic Materials
Thomas R. Boyle, Robert V. Tompson, Sudarshan K. Loyalka, Tushar K. Ghosh, Michael L. Reinig, Jr.
Nuclear Technology | Volume 183 | Number 2 | August 2013 | Pages 149-159
Technical Paper | Fission Reactors/Materials for Nuclear Systems | doi.org/10.13182/NT13-A18108
A Market-Clearing Model of the Uranium and Enrichment Industries
E. A. Schneider, U. B. Phathanapirom, R. Eggert, E. Segal
Nuclear Technology | Volume 183 | Number 2 | August 2013 | Pages 160-177
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A18109
Development of Erbia-Credit Super-High-Burnup Fuel: Assessment of Fuel Cycle Economics
Masatoshi Yamasaki, Hironobu Unesaki, Akio Yamamoto, Toshikazu Takeda, Masaaki Mori
Nuclear Technology | Volume 183 | Number 2 | August 2013 | Pages 178-193
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A18110
Risk Evaluation of Flow-Accelerated Corrosion Based on One-Dimensional FAC Code
Hiroaki Suzuki, Shunsuke Uchida, Masanori Naitoh, Hidetoshi Okada, Soji Koikari, Kunio Hasegawa, Fumio Kojima, Seiichi Koshizuka, Derek H. Lister
Nuclear Technology | Volume 183 | Number 2 | August 2013 | Pages 194-209
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A18111
Safety Assessment of SiC Cladding Oxidation Under Loss-of-Coolant Accident Conditions in Light Water Reactors
Youho Lee, Thomas J. McKrell, Chao Yue, Mujid S. Kazimi
Nuclear Technology | Volume 183 | Number 2 | August 2013 | Pages 210-227
Technical Paper | Fuel Cycle and Management/Materials for Nuclear Systems | doi.org/10.13182/NT12-122
Failure Probability Evaluation of a Near-Surface Radioactive Waste Repository Due to Water Infiltration
L. A. Aguiar, P. F. Frutuoso e Melo, A. C. M. Alvim
Nuclear Technology | Volume 183 | Number 2 | August 2013 | Pages 228-247
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT13-A18113
Zirconium Effect on the Corrosion Behavior of 316L Stainless Steel Alloy and Hastelloy-N Superalloy in Molten Fluoride Salt
Wei-Jen Cheng, Robert S. Sellers, Mark H. Anderson, Kumar Sridharan, Chaur-Jeng Wang, Todd R. Allen
Nuclear Technology | Volume 183 | Number 2 | August 2013 | Pages 248-259
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT12-125
The Development and Testing of a Much-Improved RadBall: A Small Deployable 360-deg-View Radiation Hot-Spot Imaging Device
Steven J. Stanley, Kat Lennox, Alex Jenkins
Nuclear Technology | Volume 183 | Number 2 | August 2013 | Pages 260-269
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT12-141

Number 3

Macroscopic and Microscopic Packing Properties of Experimental and Computational Pebble Beds
Gert Jan Auwerda, Jan-Leen Kloosterman, Danny Lathouwers, Tim H. J. J. Van Der Hagen
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 272-286
Technical Paper | Fission Reactors and Heat Transfer | doi.org/10.13182/NT13-A19417
Trade-Off Study on the Power Capacity of a Prototype Sodium-Cooled Fast Reactor in Korea
Min-Ho Baek, Sang-Ji Kim, Jaewoon Yoo, In-Ho Bae
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 287-297
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A19418
Dryout Methodology with New Steady-State Criterion and More-Accurate Statistical Treatment of Channel Bow
Uffe C. Bergmann, Simon Baumgartner, Roger Bieli
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 298-307
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-A19419
Core Design, Spent-Fuel Characteristics Assessment, and Fuel Cycle Analysis for Thorium-Uranium Breeding Recycle in Pressurized Water Reactors
Guangwen Bi, Shengyi Si, Chanyun Liu
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 308-320
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A19420
Analysis of Pin Removal Experiments Conducted in a Supercritical Light Water Reactor-Like Test Lattice
Rakesh Chawla, Dominik Rätz, Kelly A. Jordan, Gregory Perret
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 321-330
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A19421
Neutronics and Depletion Methods for Multibatch Fluoride Salt-Cooled High-Temperature Reactors with Slab Fuel Geometry
Anselmo T. Cisneros, Dan Ilas
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 331-340
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A19422
Transition to CASMO-5M and SIMULATE-3K for Stability Analyses of the Swiss Boiling Water Reactors
Abdelhamid Dokhane, Stefano Canepa, Hakim Ferroukhi
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 341-353
Technical Paper | Fission Reactors / Radiation Transport and Protection | doi.org/10.13182/NT13-A19423
Simulation of In-Core Neutron Noise Measurements for Axial Void Profile Reconstruction in Boiling Water Reactors
V. Dykin, I. Pázsit
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 354-366
Technical Paper | Fission Reactors / Thermal Hydraulics | doi.org/10.13182/NT13-A19424
Reactivity Effects of Spatial Homogenization of Thermal Feedback Regions in Monte Carlo Reactor Calculations
Benjamin R. Hanna, Daniel F. Gill, David P. Griesheimer
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 367-378
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A19425
SCALE Code Validation for Prismatic High-Temperature Gas-Cooled Reactors
Dan Ilas
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 379-390
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A19426
Verification of a Depletion Method in SCALE for the Advanced High-Temperature Reactor
Ryan Kelly, Dan Ilas
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 391-397
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A19427
WIMS/PANTHER Analysis of UO₂/MOX Cores Using Embedded Supercells
Martin Knight, Paul Bryce, Sheldon Hall
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 398-408
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A19428
Application of Radiogenic Lead with Dominant Content of ²⁰⁸Pb for Long Prompt Neutron Lifetime in Fast Reactor
Anatoly N. Shmelev, Gennady G. Kulikov, Eduard F. Kryuchkov, Vladimir A. Apse, Evgeny G. Kulikov
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 409-426
Technical Paper | Enrichment | doi.org/10.13182/NT13-A19429
Design of Ultralong-Cycle Fast Reactor Employing Breed-and-Burn Strategy
Taewoo Tak, Deokjung Lee, T. K. Kim
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 427-435
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A19430
Pressurized Water Reactor ENDF/B-VII Cross-Section Libraries for ORIGEN-ARP
Carolyn McGraw, Germina Ilas
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 436-445
Technical Paper | Fission Reactors / Radiation Transport and Protection | doi.org/10.13182/NT13-A19431
Features of Hybrid Core Calculations at BFS-62-3A Experiments
E. F. Mitenkova, N. V. Novikov, A. I. Blokhin
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 446-454
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A19432
Strain-Rate Sensitivity Analysis for Ni Alloys to be Used in Very High Temperature Reactors
Kun Mo, Hsiao-Ming Tung, Xiang Chen, Yang Zhao, Jon Hansen, James F. Stubbins
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 455-463
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT13-A19433
Effects of Nuclear Data Uncertainties on the NEA/OECD PWR MOX/UO₂ Core Rod Ejection Benchmark
Ihor Pasichnyk, Markus Klein, Kiril Velkov, Winfried Zwermann, Andreas Pautz
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 464-472
Technical Paper | Hydraulic Reactor Safety / Fission Reactors | doi.org/10.13182/NT183-464
Reactivity Impact of ¹⁶O Thermal Elastic-Scattering Nuclear Data for Some Numerical and Critical Benchmark Systems
Ken S. Kozier, Dan Roubtsov, Arjan J. M. Plompen, Stefan Kopecky
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 473-483
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A19435
Coupled 3-D Neutronics/Thermal-Hydraulics Optimization Study for Improving the Response of a 3600 MW(thermal) SFR Core to an Unprotected Loss-of-Flow Accident
Kaichao Sun, Aurelia Chenu, Jiri Krepel, Konstantin Mikityuk, Rakesh Chawla
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 484-503
Technical Paper | Fission Reactors / Thermal Hydraulics | doi.org/10.13182/NT13-A19436
Validation of the U.S. NRC Coupled Code System TRITON/TRACE/PARCS Using the Special Power Excursion Reactor Test III
Raymond C. Wang, Yunlin Xu, Nathanael Hudson, Thomas J. Downar
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 504-514
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-A19437
A Statistical Sampling Method for Uncertainty Analysis with SCALE and XSUSA
M. L. Williams, G. Ilas, M. A. Jessee, B. T. Rearden, D. Wiarda, W. Zwermann, L. Gallner, M. Klein, B. Krzykacz-Hausmann, A. Pautz
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 515-526
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-112
Development of a Three-Dimensional Pseudo Pin-by-Pin Calculation Methodology in ANC
Baocheng Zhang, Larry Mayhue, Harish Huria, Boyan Ivanov
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 527-534
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A19439
Coupled Thermal-Hydraulic/Neutronics/Crud Framework in Prediction of Crud-Induced Power Shift Phenomenon
Ling Zou, Hongbin Zhang, Jess Gehin, Brendan Kochunas
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 535-542
Technical Paper | Fission Reactors / Thermal Hydraulics | doi.org/10.13182/NT13-A19440
Volume 183 Indexes
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 543-546
Departments | doi.org/10.13182/NT13-A19441

Volume 183

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