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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nuclear Technology
August 2024
Fusion Science and Technology
Latest News
Taking shape: Fusion energy ecosystems built with public-private partnerships
It’s possible to describe fusion in simple terms: heat and squeeze small atoms to get abundant clean energy. But there’s nothing simple about getting fusion ready for the grid.
Private developers, national lab and university researchers, suppliers, and end users working toward that goal are developing a range of complex technologies to reach fusion temperatures and pressures, confounded by science and technology gaps linked to plasma behavior; materials, diagnostics, and electronics for extreme environments; fuel cycle sustainability; and economics.
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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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2018.1471296
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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2018.1499338
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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2018.1501977