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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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May 2024
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Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
Xiyang Zhang, Tiejun Xu, Lei Yin, Nanyu Mou, Yan Wang, Damao Yao
Fusion Science and Technology | Volume 80 | Number 1 | January 2024 | Pages 98-107
Research Article | doi.org/10.1080/15361055.2023.2198482
Articles are hosted by Taylor and Francis Online.
The China Fusion Engineering Test Reactor (CFETR) is a device developed to verify the engineering feasibility of a fusion reactor. For CFETR, the divertor is an important plasma-facing component, whose main function is to exclude impurities and remove plasma heat. In addition, the requirement for remote handling (RH) maintenance must be satisfied because of the level of radioactivity in the vacuum vessel after shutdown. The dome is an important component of the divertor, whose main function is to isolate impurity particles as well as to improve the ability of excluding particles. In the optional dome design, a hybrid divertor-blanket concept, a front-face RH compatible structure in plasma-facing units (PFUs), and a RH maintenance scheme for the main bolt are proposed. The vulnerable targets can be replaced directly and thus reduce the RH maintenance time. The dome needs to withstand the heat flux of 10 MW/m2 and nuclear heat in the condition of 1.5 GW of fusion power in the engineering design requirements. Because of the RH compatible structure, higher requirements are demanded for the design of the dome cooling system. In this study, the cooling system and the customized heat transfer structure of dome PFUs are designed to guarantee the maximum heat removal level. The steady-state thermal analysis shows that the cooling system fulfills the design requirements. The concept of the hybrid divertor-blanket and the front-face RH compatible structure for the divertor target have certain reference significance and value for the engineering design and RH maintenance research for the fusion reactor divertor in the future.
