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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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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2024: The Year in Nuclear—July through September
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from July through September 2024.
Stay tuned for the top stories from the rest of the past year.
James F. Harrison
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 310-324
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34144
Articles are hosted by Taylor and Francis Online.
An assessment of RETRAN’s ability to provide best-estimate reference information for the qualification of full-scope power plant training simulators is provided. Analyses that compare RETRAN predictions to plant data or to test facility data are summarized. The relationship between the RETRAN qualification studies and the simulator test matrix presented in Electric Power Research Institute NP-4243, Analytic Simulator Qualification Methodology, and the requirements of ANSI/ANS-3.5 are discussed. Thirty-one boiling water reactor transient analyses and 50 pressurized water reactor analyses have been evaluated. The evaluation shows that RETRAN models have experienced essentially all of the “dynamic states” required for the qualification of power plant training simulators. The rating for the magnitude, timing, and trend measures indicates that the predictions using RETRAN models are either completely acceptable or acceptable with some reservations most of the time. The magnitude performance varies depending on the type of event, whereas the trend and timing performance is nearly the same for all event types. The ratings for the RETRAN transient predictions show that RETRAN models are capable of predicting the important system parameters with the fidelity required for the qualification of training simulators.