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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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
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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.
Hiroshi Maekawa, Yukio Oyama, Tomoo Suzuki, Yujiro Ikeda, Tomoo Nakamura
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1165-1170
Neutronics and Shielding | doi.org/10.13182/FST83-A23016
Articles are hosted by Taylor and Francis Online.
Angle-dependent neutron leakage spectra above 0.5 MeV from Li2O slab assemblies were measured accurately by the time-of-flight method. The measured angles were 0°, 12.2°, 24.9°, 41.8° and 66.8°. The sizes of Li2O assemblies were 31.4 em in equivalent radius and 5.06, 20.24 and 40.48 em in thickness. The data were analyzed by a new transport code “BERMUDA-2DN”. Time-independent transport equation is solved for two-dimensional, cylindrical, multi-regional geometry using the direct integration method in a multi-group model. The group transfer kernels are accurately obtained from the double-differential cross section data without using Legendre expansion. The results were compared absolutely. While there exist discrepancies partially, the calculational spectra agree well with the experimental ones as a whole. The BERMUDA code was demonstrated to be useful for the analyses of the fusion neutronics and shielding.
