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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.
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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
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.
Virgil E. Schrock
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 323-331
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32334
Articles are hosted by Taylor and Francis Online.
Heating from the decay of radioactive nuclides in shutdown reactors plays an important role in the safety evaluation of nuclear power plants. Although there are many other important uses for this information, the need for more accurate data for the analysis of hypothetical reactor accident scenarios has been the main impetus for recent research activity that has led to a major revision of the Draft American Nuclear Society 5.1 Standard, “Decay Energy Release Rates Following Shutdown of Uranium Fueled Reactors” (published in 1971). The 1978 revised standard, titled “Decay Heat Power in Light Water Reactors,” is based on new experiments and summation calculations. Very accurate determination of the decay heat is now possible for light water reactors, especially within the first 101 s after shutdown, where the influence of neutron capture in fission products may be treated as a small correction to the idealized zero capture case. The new standard accounts for differences among fuel nuclides. It covers cooling times to 109 s, but provides only an “upper bound” on the capture correction in the interval from 104 to 109 s.