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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
June 2024
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Latest News
ANS Standards Committee publishes joint ASME/ANS standard for Level 1/large early release frequency PRA
ANSI/ASME/ANS RA-S-1.1-2024, Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, has been published by the American Nuclear Society. The document, which is a joint standard developed with the American Society of Mechanical Engineers by the ANS/ASME Joint Committee on Nuclear Risk Management, received the approval of the American National Standards Institute on February 29, 2024, and was issued on March 15, 2024.
Odile Petit, Yannick Pénéliau, Yi-Kang Lee
Nuclear Science and Engineering | Volume 198 | Number 2 | February 2024 | Pages 476-485
Research Article | doi.org/10.1080/00295639.2023.2194209
Articles are hosted by Taylor and Francis Online.
A specific simulation mode has been implemented in the TRIPOLI-4® Monte Carlo code to deal with subcritical or critical configurations together with the use of variance reduction techniques usually dedicated to shielding studies. This multiple mode enables a coupling between the fixed-source criticality (or the criticality) mode with the shielding mode, within the Monte Carlo code, with the aims to simplify the calculation and help users run the code. Test cases with a fuel assembly in borated water are presented to illustrate the use of this feature in a subcritical case. An experimental setup is then investigated in a critical case. It is based on the Criticality Accident Alarm System benchmark experiment conducted in the SILENE critical assembly facility. Stability and efficiency issues are examined, and promising results are presented and discussed in both cases.
