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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 Technology
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Latest News
NRC updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
Teruya Tanaka, Hiroyuki Noto, Fuminobu Sato, Yoshimitsu Hishinuma, Hiroyuki A. Sakaue, Masahito Yoshino
Fusion Science and Technology | Volume 75 | Number 8 | November 2019 | Pages 1076-1083
Technical Paper | doi.org/10.1080/15361055.2019.1658039
Articles are hosted by Taylor and Francis Online.
To examine the impact of nuclear transmutation in K-type and N-type thermocouples on temperature measurements in a fusion reactor, thermocouples with altered compositions were fabricated, and their responses were obtained at up to 800°C. The compositions of the thermocouples were altered according to transmutation calculations simulating the 3.5-, 4.6-, and 7-year use at the first wall and 40-year use at the front surface of the radiation shield. Comparison of the responses with commercial thermocouples at 800°C showed that the K-type and N-type thermocouples with altered composition simulating the 7-year use at the first wall indicate 20% to 25% lower temperatures. In this condition, the weight ratio of additive powders for simulation of transmuted elements was ~3%. The differences of responses between the commercial thermocouples and thermocouples simulating transmutation are dependent on the weight ratio of the additive powders. The present data could be used for estimation of response degradation of thermocouples used for long-term operation in a fusion reactor.