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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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.