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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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Seconds Matter: Rethinking Nuclear Facility Security for the Modern Threat Landscape
In today’s rapidly evolving threat environment, nuclear facilities must prioritize speed and precision in their security responses—because in critical moments, every second counts. An early warning system serves as a vital layer of defense, enabling real-time detection of potential intrusions or anomalies before they escalate into full-blown incidents. By providing immediate alerts and actionable intelligence, these systems empower security personnel to respond decisively, minimizing risk to infrastructure, personnel, and the public. The ability to anticipate and intercept threats at the earliest possible stage not only enhances operational resilience but also reinforces public trust in the safety of nuclear operations. Investing in such proactive technologies is no longer optional—it’s essential for modern nuclear security.
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.
