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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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!
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Jack K. Boshoven
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 33-39
Technical Paper | Burnup Credit / Nuclear Criticality Safety | doi.org/10.13182/NT95-A35094
Articles are hosted by Taylor and Francis Online.
General Atomics (GA) is developing two legal weight truck casks for shipping spent fuel from both pressurized water reactors (PWRs) and boiling water reactors (BWRs). The GA-4 (4 PWR) and GA-9 (9 BWR) casks are high-capacity legal weight truck casks designed to transport light water reactor spent-fuel assemblies. The GA-9 cask can meet the criticality safety requirements using the “fresh fuel” assumption. To maintain a capacity of four PWR spent-fuel assemblies, the GA-4 cask uses burnup credit as part of the criticality control for initial enrichments >2.9 wt% 235U. Using the U.S. Department of Energy Burnup Credit Program as a basis, GA has performed burnup credit analysis for the GA-4 cask. The approach to calculating the minimum burnup requirement takes into account all of the key parameters affecting keff. It is based on technically sound principles and conservatively increases the burnup requirement for a given enrichment to account for all uncertainties and biases associated with the calculations.