ANS / Publications / Journals / Nuclear Technology

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT13-A16998

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT12-141

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT13-A19440

Volume 183 Indexes

Nuclear Technology / Volume 183 / Number 3 / September 2013 / Pages 543-546

Departments / dx.doi.org/10.13182/NT13-A19441