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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
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.