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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
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.
