ANS / Publications / Journals / Nuclear Technology

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