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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
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. De Volpi, C. L. Fink, G. E. Marsh, E. A. Rhodes, G. S. Stanford
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 141-188
Technical Paper | Analyses | doi.org/10.13182/NT82-1
Articles are hosted by Taylor and Francis Online.
For fuel-motion surveillance in Transient Reactor Test Facility experiments, the fast-neutron hodoscope has advanced beyond its initial ability to provide time, location, and velocity data: its quantitative mass results are now routinely used in liquid-metal fast breeder reactor accident projections. (Mass normalization is based on initial fuel inventory.) The material and radiation surroundings of the test section affect hodoscope detectors in intrinsic and instrumental ways that necessitate detailed corrections. Depending on the experiment, count rate compensation with as little as 5% total imprecision is usually desired for dead time, power-level changes, nonlinear response, efficiency, and background. In addition, systematic effects ranging up to 20% may occur, from such causes as self-shielding, self-multiplication, self-attenuation, and flux depression. For one- to seven-pin bundles, the hodoscope has achieved 1-ms time resolution, 0.25-mm lateral- and 5-mm axial-motion displacement detection, and 50-mg single-pin, 350-mg seven-pin mass resolution—not all, however, simultaneously, since resolution and statistical precision are inversely related. The experimental and theoretical foundation for that performance is now well established.