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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
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.
J. W. Davidson, M. E. Battat
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 2007-2015
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29636
Articles are hosted by Taylor and Francis Online.
A precise calculational analysis of the INEL manganese bath experiment to measure beryllium neutron multiplication has been performed. The goal throughout the analysis was the minimization of all sources of error due to the calculational model and method. An extremely detailed three-dimensional Monte Carlo geometry model was developed for use with the code MCNP. Calculations were performed for a bare-source and four beryllium sample configurations for both DT and 252Cf neutron sources. The primary objective of the analysis was the calculation of various neutron-economy parameters applied as experimental corrections, either directly or as verification of measured values. The most significant of these were the tank leakage, duct streaming, structural absorption, fractional bath capture in manganese, high-energy parasitic bath absorption, neutron multiplication in other materials, and indirect absorption and multiplication in beryllium.