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Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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January 2025
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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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
