ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Mar 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
April 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Nuclear materials testing project brings U.S. and U.K. expertise together
As nations look to nuclear energy as a source of reliable electricity and heat, researchers and industry are developing a new generation of nuclear reactors to fill the need. These advanced nuclear reactors will provide safe, efficient, and economical power that go beyond what the current large light water reactors can do.
But before large-scale deployment of advanced reactors, researchers need to understand and test the safety and performance of the technologies—especially the coolants and materials—that make them possible.
Now, the United States and the United Kingdom have teamed up to test hundreds of advanced nuclear materials.
Technical Session
Wednesday, November 10, 2021|8:00–10:00AM EST
Session Chair:
Enrique Melendez Asensio (Consejo de Seguridad Nuclear)
Alternate Chair:
Man Cheol Kim (TBD)
Session Organizer:
Session Producer:
Sam Brewer
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Internal Explosion Level 1 PSA: Probabilistic Assessment of Hydrogen Risk in French Nuclear Power Plants
8:00–8:30AM EST
Yannick Lefebvre (EDF), Cécile Luzoir (EDF), Hugo Jadot (EDF), Jérémy Gaudron (EDF)
Paper
Addressing Loss of Room Cooling in PRA Modeling
8:30–9:00AM EST
Joshua S. Beckton (Westinghouse Electric Co.)
Development of SAMG-FT/ET Model for Level 2 PRA of OPR-1000 NPPs
9:00–9:30AM EST
Sang Hun Lee (KAERI), Jaehyun Cho (KAERI), Jaewhan Kim (KAERI)
Presentation Video (Visible to Attendees)
Attachment — short bio to the chairman
Modeling Portable Equipment in Probabilistic Safety Assessment of Nuclear Power Plants
9:30–10:00AM EST
Ji Suk Kim (Chung-Ang Univ.), Man Cheol Kim (Chung-Ang Univ.), Kibeom Son (Kyung Hee Univ.), Gyunyoung Heo (Kyung Hee Univ.), Gayoung Park (Chosun Univ.), Jonghyun Kim (Chosun Univ.), Meejeong Hwang (KAERI), Moosung Jae (Hanyang Univ.)
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