ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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.
