ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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!
Latest Magazine Issues
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
High-temperature plumbing and advanced reactors
The use of nuclear fission power and its role in impacting climate change is hotly debated. Fission advocates argue that short-term solutions would involve the rapid deployment of Gen III+ nuclear reactors, like Vogtle-3 and -4, while long-term climate change impact would rely on the creation and implementation of Gen IV reactors, “inherently safe” reactors that use passive laws of physics and chemistry rather than active controls such as valves and pumps to operate safely. While Gen IV reactors vary in many ways, one thing unites nearly all of them: the use of exotic, high-temperature coolants. These fluids, like molten salts and liquid metals, can enable reactor engineers to design much safer nuclear reactors—ultimately because the boiling point of each fluid is extremely high. Fluids that remain liquid over large temperature ranges can provide good heat transfer through many demanding conditions, all with minimal pressurization. Although the most apparent use for these fluids is advanced fission power, they have the potential to be applied to other power generation sources such as fusion, thermal storage, solar, or high-temperature process heat.1–3
Jump to:
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
