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Division Spotlight
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.
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.
Abdellatif M. Yacout, Stefano Salvatores, Yuri Orechwa
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 177-189
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35187
Articles are hosted by Taylor and Francis Online.
Failure times of components are traditionally used to evaluate their reliability. An alternate approach is to analyze the degradation data accumulated during the component’s testing or during its normal operation. Degradation analysis is particularly useful when it is not possible to observe a significant number of failures. This is the case for metallic Integral Fast Reactor fuel pins irradiated in Experimental Breeder Reactor II, where failures have not taken place under normal operating conditions. A degradation analysis methodology is presented and applied to these pins. The time-to-failure distribution for the fuel pins is estimated based on a fixed threshold failure model. The confidence intervals of the distribution are calculated using a parametric bootstrap method.