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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.
Tai-Hung Wu, De-Cheng Chen
Nuclear Technology | Volume 205 | Number 6 | June 2019 | Pages 867-880
Technical Note | doi.org/10.1080/00295450.2018.1533320
Articles are hosted by Taylor and Francis Online.
Station blackout (SBO) sequences for a Westinghouse-designed three-loop pressurized water reactor (PWR) with large dry containment are investigated. Recovery of alternating-current power is considered under two separate headings in event trees of loss of off-site power: recovery of the off-site power and recovery of the emergency diesel generators (EDGs) or diesel generator 5. A reactor coolant pump seal leakage model under SBO conditions for a Westinghouse PWR with high-temperature O-rings is used. Seal failure mechanisms, including popping open, binding, and O-ring extrusion, are considered. Success criteria are established based on the results of thermal-hydraulic calculations via the MELCOR and/or RELAP-5 codes. Furthermore, the WinNUPRA software package is used for sequence quantification.
Three primary models are addressed: Basic, WOG2000, and Ultimate Response Guideline (URG). The core damage frequency (CDF) of SBO sequences for the Basic model is found to be very optimistic and underestimated. The improvement on CDF by introducing the URG model is found to be dependent primarily on the reliability of plant operators in performing the procedure URG under SBO situations.
Two sensitivity analyses on the passive shutdown seal (PSDS) are performed: WOG2000 (PSDS) and URG (PSDS). The low-failure-probability PSDS results in a >94% improvement in CDF due to SBO since the CDF contribution from long-term SBO sequences becomes negligible. Furthermore, the URG strategies are shown to have a significant impact on the reduction of CDF since seal leakage is no longer a concern in the presence of the PSDS.
The way that power recovered is distinguished from off-site power or on-site EDGs and the way that SBO CDF is assessed make the present study more realistic than general SBO models.
A key analysis of the confidence bands of the SBO CDF with the aid of the uncertainty measure is also performed to observe the induced effects by the probabilistic seal failure modes and PSDS.