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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.
A. A. Farooq Ansari, Kevin J. Burns, Douglas K. Beller, Quazi A. Haque, Stephen P. Schultz
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 205-211
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33191
Articles are hosted by Taylor and Francis Online.
The steady-state operating limit for boiling water reactors (BWRs) is determined by calculating the transient change in the critical power ratio (CPR). To determine the operating limit CPR, a method for calculating the ΔCPR during transients is needed. The RETRAN code can be used as a tool in the evaluation of transient CPRs for determining the operating margin for BWRs. Since the RETRAN code does not contain a critical power calculation, the ΔCPR cannot be obtained directly from RETRAN. Therefore, a program, TCPYA01, designed to evaluate transient CPR (and ΔCPR) based on the GEXL correlation using time-dependent conditions from RETRAN was used. The justification for using the RETRAN code is provided by predicting transient boiling transition data taken at the GE-ATLAS loop facility. Results of the sensitivity studies performed on nodalization, void models, and time-step size are also provided.
