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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island 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
Feinstein Institutes to research novel radiation countermeasure
The Feinstein Institutes for Medical Research, home of the research institutes of New York’s Northwell Health, announced it has received a five-year, $2.9 million grant from the National Institutes of Health to investigate the potential of human ghrelin, a naturally occurring hormone, as a medical countermeasure against radiation-induced gastrointestinal syndrome (GI-ARS).
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.
