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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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Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Jie Li, Jie Zhang, Yang Qiu, Liangliang Zhang, Changle Liu, Xiang Gao
Fusion Science and Technology | Volume 76 | Number 1 | January 2020 | Pages 70-77
Technical Note | doi.org/10.1080/15361055.2019.1610320
Articles are hosted by Taylor and Francis Online.
The breeding material ratio (BMR) makes a significant impact on the tritium breeding ratio (TBR) to the fusion blanket due to the material fraction influence inside the blanket interior. The qualitative study on the BMR-related TBR issues are focused on the two cases of water-cooled blanket modules: the mixture blanket structure and the multilayer blanket case. The study indicates that TBR is a unique value in accordance with one BMR value in the mixture blanket. Moreover, a systematic scheme on TBR estimation based on multiple variable combinations is carried out for the multilayer model. It is found that the blanket local TBR would vary along with BMR increasing, and that high TBRs are obtained at BMR in the range of 0.08 to 0.12 for the two cases. In particular, the maximum TBR occurs when the BMR is in the range of 0.09 to 0.1. Furthermore, TBR variation due to BMR change induced by blanket macrofactors, like material type, material ratio, material structure, etc., is defined using the universal function solution. These results would be more important to the breeding blanket design and optimization since they would affect the blanket structure concepts and their TBR estimations. Hence, the blanket BMR issues are important concerns on the road toward an advanced blanket system for the Chinese Fusion Engineering Test Reactor (CFETR) at the present pre-engineering stages.
