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Volume 192

Number 1 | Number 2 | Number 3

Number 1

Functionalization of the Discontinuity Factor in the Albedo-Corrected Parameterized Equivalence Constants (APEC) Method

Woosong Kim, Kyunghoon Lee, Yonghee Kim

Nuclear Science and Engineering / Volume 192 / Number 1 / October 2018 / Pages 1-20

Technical Paper / dx.doi.org/10.1080/00295639.2018.1497396

The RAPID Fission Matrix Approach to Reactor Core Criticality Calculations

William J. Walters, Nathan J. Roskoff, Alireza Haghighat

Nuclear Science and Engineering / Volume 192 / Number 1 / October 2018 / Pages 21-39

Technical Paper / dx.doi.org/10.1080/00295639.2018.1497395

A 2D/1D Algorithm for Effective Cross-Section Generation in Fast Reactor Neutronic Transport Calculations

Bastien Faure, Pascal Archier, Jean-François Vidal, Laurent Buiron

Nuclear Science and Engineering / Volume 192 / Number 1 / October 2018 / Pages 40-51

Technical Paper / dx.doi.org/10.1080/00295639.2018.1480190

Prediction of the Prompt Neutron Multiplicity Distribution ν(A) for 235U(n,f) and 239Pu(n,f) in the Incident Energy Range of Multichance Fission

Anabella Tudora, Franz-Josef Hambsch, Viorel Tobosaru

Nuclear Science and Engineering / Volume 192 / Number 1 / October 2018 / Pages 52-69

Technical Paper / dx.doi.org/10.1080/00295639.2018.1497394

Analytical Studies of Three-Dimensional Evaluation of Radionuclide Distribution in Zeolite Wastes Through Gamma Scanning of Adsorption Vessels

Taichi Matsumura, Ryuji Nagaishi, Jun-ichi Katakura, Masahide Suzuki

Nuclear Science and Engineering / Volume 192 / Number 1 / October 2018 / Pages 70-79

Technical Paper / dx.doi.org/10.1080/00295639.2018.1493856

SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, keff, and α Using PARTISN

Jeffrey A. Favorite

Nuclear Science and Engineering / Volume 192 / Number 1 / October 2018 / Pages 80-114

Computer Code Abstract / dx.doi.org/10.1080/00295639.2018.1471296

Number 2

Calculating Alpha Eigenvalues and Eigenfunctions with a Markov Transition Rate Matrix Monte Carlo Method

Benjamin R. Betzler, Brian C. Kiedrowski, William R. Martin, Forrest B. Brown

Nuclear Science and Engineering / Volume 192 / Number 2 / November 2018 / Pages 115-152

Technical Paper / dx.doi.org/10.1080/00295639.2018.1497397

Application of Krylov Acceleration Technique in Method of Characteristics–Based Neutron Transport Code

Tanay Mazumdar, Anurag Gupta

Nuclear Science and Engineering / Volume 192 / Number 2 / November 2018 / Pages 153-188

Technical Paper / dx.doi.org/10.1080/00295639.2018.1499340

The Discontinuous Asymptotic Telegrapher’s Equation (P1) Approximation

Avner P. Cohen, Roy Perry, Shay I. Heizler

Nuclear Science and Engineering / Volume 192 / Number 2 / November 2018 / Pages 189-207

Technical Paper / dx.doi.org/10.1080/00295639.2018.1499339

A Coarse-Mesh Diffusion Synthetic Acceleration Method with Local hp Adaptation for Neutron Transport Calculations

Tseelmaa Byambaakhuu, Dean Wang, Sicong Xiao

Nuclear Science and Engineering / Volume 192 / Number 2 / November 2018 / Pages 208-217

Technical Paper / dx.doi.org/10.1080/00295639.2018.1499338

Number 3

Improved Accuracy in the 2-D/1-D Method with Anisotropic Transverse Leakage and Cross-Section Homogenization

Michael Jarrett, Brendan Kochunas, Edward Larsen, Thomas Downar

Nuclear Science and Engineering / Volume 192 / Number 3 / December 2018 / Pages 219-239

Technical Paper / dx.doi.org/10.1080/00295639.2018.1507186

Flux Region Assignment Method Using Ray Trace Information for the Method of Characteristics to Improve Cache Efficiency

Akio Yamamoto, Akinori Giho, Tomohiro Endo

Nuclear Science and Engineering / Volume 192 / Number 3 / December 2018 / Pages 240-253

Technical Paper / dx.doi.org/10.1080/00295639.2018.1501978

Contributon-Based Mesh-Reduction Methodology for Hybrid Deterministic-Stochastic Particle Transport Simulations Using Block-Structured Grids

Timothy Flaspoehler, Bojan Petrovic

Nuclear Science and Engineering / Volume 192 / Number 3 / December 2018 / Pages 254-274

Technical Paper / dx.doi.org/10.1080/00295639.2018.1507185

Transient Simulations of CPR1000 Nuclear Power Plant Implementing Advanced Mechanical Shim Control System

Shifa Wu, Jiashuang Wan, Hongbing Song, Xinyu Wei, Fuyu Zhao, Shripad Revankar

Nuclear Science and Engineering / Volume 192 / Number 3 / December 2018 / Pages 275-297

Technical Paper / dx.doi.org/10.1080/00295639.2018.1501976

Three Loading Patterns for 99Tc Transmutation in PWR Burnable Poison Rods

Bin Liu, Juan Fu, Xuefeng Lyu, Wenqiang Li, Jinsheng Han

Nuclear Science and Engineering / Volume 192 / Number 3 / December 2018 / Pages 298-310

Technical Paper / dx.doi.org/10.1080/00295639.2018.1509570

Improvements of the Embedded Self-Shielding Method with Pseudo-Resonant Isotope Model on the Multifuel Lattice System

Qian Zhang, Qiang Zhao, Zhijian Zhang, Liang Liang, Won Sik Yang, Hongchun Wu, Liangzhi Cao

Nuclear Science and Engineering / Volume 192 / Number 3 / December 2018 / Pages 311-327

Technical Note / dx.doi.org/10.1080/00295639.2018.1501977

 
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