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The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
2020 ANS Annual Meeting
June 8–11, 2020
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Nuclear Science and Engineering
Fusion Science and Technology
When a nuclear plant closes
Theresa Knickerbocker, the mayor of the village of Buchanan, N.Y., where the Indian Point nuclear power plant is located, is not happy. What has gotten Ms. Knickerbocker’s ire up is the fact that Indian Point’s Unit 2 was closed on April 30, and Unit 3 is scheduled to close in 2021. The village, population 2,300, is about 1.3 square miles total, with the Indian Point site comprising 240 acres along the Hudson River, 30 miles upstream of Manhattan. Unit 2 was a 1,028-MWe pressurized water reactor; Unit 3 is a 1,041-MWe PWR.
The nuclear plant provides the revenue for half of Buchanan’s annual $6-million budget, Knickerbocker told Nuclear News. That’s $3 million in tax revenues each year that eventually will go away. How will that revenue be replaced? Where will the replacement power come from?
Chenglong Wang, Kaichao Sun, Lin-wen Hu, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G. H. Su
Nuclear Technology | Volume 198 | Number 1 | April 2017 | Pages 1-16
Technical Paper | dx.doi.org/10.1080/00295450.2017.1294011
Articles are hosted by Taylor and Francis Online.
A transportable fluoride-salt-cooled high-temperature reactor (TFHR) design with 20-MW(thermal) rated power and 18-month fuel cycle is proposed for off-grid applications. One of the design goals of the compact reactor core is potential transport by truck, rail, or air. Full-core thermal-hydraulic analyses and improvements using three-dimensional computational fluid dynamics (CFD) were performed previously to demonstrate the feasibility of a TFHR design at a nominal power of 20 MW(thermal). In this paper, the best-estimate system code Reactor Excursion Leak Analysis Program (RELAP5-3D) is adopted to study the transient behavior of this TFHR design and the safety characteristics of the primary loop system during accident conditions. The modeling results of the steady state were verified using CFD results with consideration of radial heat conduction between heat transfer unit cells. Four most challenging accidents of anticipated transient without scram were analyzed, as well as parametric studies of some key factors. These accidents include unprotected reactivity insertion accident (URIA), unprotected loss of heat sink (ULOHS), unprotected loss of flow (ULOF), and a combination accident of ULOF and ULOHS. The results indicate that transient temperature limits are not exceeded during the most severe accidents. They indicate satisfactory transient performance of the TFHR design. The transient temperature limit of structure material Hastelloy N, based on embrittlement phenomena, poses the most limiting constraint due to the small temperature margin of about 20 K in the accident combination of ULOF and ULOHS. Overall, TFHR is a sound reactor design from a thermal-hydraulic viewpoint.