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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
Zhi’ao Huang, Huifang Miao, Huai-En Hsieh, Yifen Chen, Ning Li (Xiamen Univ), Chao Guo (China General Nuclear Power Research Inst Co. Ltd.)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 379-387
Recently, with the development and application of full-scope level 2 probabilistic safety assessment (PSA) method around the world, severe accident phenomena during shutdown and low power conditions have aroused extensive attention in nuclear industry. And the shutdown severe accident management guideline is claimed to be developed, and the verification of the entry condition is the first consideration in this procedure. Diverse parameters have been monitored to identify their applicability as the alternative shutdown severe accident management guideline (SSAMG) entry conditions based on SBO scenarios in this paper, also the maximum core temperature 1350 K is chosen as the indicator of core damage instead of traditional peak cladding temperature 1024 ? which is thought to be much conservative. The results explain the complex severe accident progression during mid-loop operation in different scenarios and several parameters (i.e. mole fraction of H2 in containment and the mass of noble gas in containment. et.al) are identified to be useful as alternative SSAMG entry conditions in certain scenario. What’s more, the hot leg (in the loop with pressurizer) pipe surface temperature is identified to be the most appropriate parameter to be used as alternative SSAMG when the traditional entry conditions (core exit temperature and the radioactivity in containment) are not available, since it has strong relationship with the maximum core temperature.