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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
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Cesare Frepoli
Nuclear Science and Engineering | Volume 194 | Number 8 | August-September 2020 | Pages 825-832
Technical Note | doi.org/10.1080/00295639.2020.1753419
Articles are hosted by Taylor and Francis Online.
Integral systems test (IST) facilities, which are sometimes referred to as integral effects tests (IETs), play a key role in the design, assessment, and certification of innovative reactor designs. Data obtained using such facilities have been used to benchmark the best-estimate safety analysis computer codes used to evaluate nuclear plant safety. They have also been used to assess the effectiveness of safety system functions under simulated accident conditions. Scaling analyses are an important component in determining the applicability of an evaluation model for its intended purpose. Evaluation models can only approximate the physical behavior of postulated events on a prototype, and the judgment of their adequacy relies heavily on their capability in predicting IETs that were designed to simulate the events analyzed. With few exceptions, all ISTs are subscale representations of the power plants they are built to represent. As thermal-hydraulic computer codes are benchmarked to an IST database, the most important challenge for the analyst is the development of convincing scaling similarities between the IST and the plant. Unless such rules are clearly identified, it would not be possible to extend conclusions from the assessment of the tools against subscale data to the plant scenario time and geometry scales.