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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!
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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.
Kong Xiaoning, Chen Jun, Liu Dongqi, Li Jian, Sun Qionghua (SNPTC/SPIC)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 1041-1049
COSINE is a self-reliant development code package of China which is a core and system integrated engine used for NPP’s design and analysis. cosCSLOCA is a sub-program among the thermal hydraulic design and safety analysis codes in COSINE software package. It is applicable to analyze the loss of coolant accidents(LOCA) in nuclear power plants and use the conservative models recommended in appendix K of NRC 10cfr50.46. And cosBELOCA is the loss of coolant accident best estimation analysis code which is also included in COSINE .
The Post-CHF heat transfer is an important phenomenon to predict the peak cladding temperature during a LOCA. This paper listed the correlations of Post-CHF heat transfer adopted in these two codes and introduced the flowchart of development in cosCSLOCA. In addition, the ORNL THTF tests have been used for the verification of the Post-CHF models in both cosCSLOCA and cosBELOCA. Comparisons are made between the experimental results, the results calculated by relap5/3.3, cosCSLOCA and cosBELOCA. The results show that the results of the three codes had the same trend with experiment, and the calculated cladding temperatures using cosCSLOCA are higher than cosBELOCA and relap5/3.3.Through the separate effect assessments, the conservative of the post-CHF heat transfer model in cosCSLOCA were verified.