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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
Chang Yong Jin, Young Seok Bang (KINS)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 887-892
Since the design of Advanced Power Reactor 1400MWe (APR1400) has a deep loop seal geometry, loop seal reformation during Small Break Loss-Of-Coolant Accident (SBLOCA) has been concerned due to its possible effect on core uncovery and significant cladding temperature rise. Therefore it has been an important safety issue of SBLOCA and it has been vital to understand the effect of loop seal clearing and reformation on the core uncovery and cladding temperature.
In this study, SBLOCA of APR1400 was analyzed with MARS-KS (KINS Standard version of Multi-dimensional Analysis of Reactor Safety) code to investigate the thermal-hydraulic behavior including loop seal clearing and reformation. The break spectrum analysis was performed to identify the effect of break size to confirm the limiting case leading to Peak Cladding Temperature (PCT). The limiting case of MARS-KS calculation was compared with that of SPACE (Safety and Performance Analysis CodE). Particularly the thermal-hydraulic parameters including the system pressure and the water level of core and downcomer were identified in detail.