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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
2022 ANS Winter Meeting and Technology Expo
November 13–17, 2022
Phoenix, AZ|Arizona Grand 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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Latest News
CNSC vendor design review of eVinci microreactor to begin
Westinghouse's eVinci microreactor (Image: Westinghouse)
Westinghouse Electric Company has signed a service agreement with the Canadian Nuclear Safety Commission (CNSC) to bring the eVinci microreactor closer to commercialization, the company announced Tuesday. The agreement initiates a vendor design review (VDR)—a prelicensing technical assessment of a company’s reactor technology.
The objective of a VDR, according to the CNSC, is to verify the acceptability of a nuclear power plant design with respect to Canadian nuclear regulatory requirements and expectations, as well as Canadian codes and standards. The review also aims to identify fundamental barriers to licensing a new design in Canada and to assure that a resolution path exists for any design issues identified.
Seonghee Hong, Myunghyun Kim
Fusion Science and Technology | Volume 75 | Number 6 | August 2019 | Pages 466-478
Technical Paper | dx.doi.org/10.1080/15361055.2019.1609820
Articles are hosted by Taylor and Francis Online.
To enhance the practical application of a fusion-driven subcritical reactor, a system with constant fusion power by online feeding of molten salt fuel was designed. The system satisfies multiple purposes including waste transmutation, tritium breeding (TB), and energy multiplication (EM) through constant fusion power. All neutronic calculations were performed by SERPENT2.1.29 with the ENDF/B-VII.0 neutron cross-section library in order to simulate the online-feeding process.
A constant k-eff is maintained by the amount of the feeding being larger than the amount of the removed fission products. However, system performance is significantly improved by just reducting the reactivity swing with the feeding. Compared to a once-through cycle (OTC), the performance of TB and EM is significantly improved as the feeding rate increases. However, there is no deep burning effect like the OTC for waste transmutation.
The performance of waste transmutation is changed in the feeding scenarios. For the scenario with a high plutonium ratio, transmutation with plutonium is increased. On the other hand, for the feeding scenario with a high minor actinide ratio, transuranic waste is burned. However, the transmutation performance is degraded due to a low fission-to-capture ratio.
