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.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
The newest era of workforce development at ANS
As most attendees of this year’s ANS Annual Conference left breakfast in the Grand Ballroom of the Chicago Downtown Marriott to sit in on presentations covering everything from career pathways in fusion to recently digitized archival nuclear films, 40 of them made their way to the hotel’s fifth floor to take part in the second offering of Nuclear 101, a newly designed certification course that seeks to give professionals who are in or adjacent to the industry an in-depth understanding of the essentials of nuclear energy and engineering from some of the field’s leading experts.
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.