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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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A webinar, and a new opportunity to take ANS’s CNP Exam
Applications are now open for the fall 2025 testing period for the American Nuclear Society’s Certified Nuclear Professional (CNP) exam. Applications are being accepted through October 14, and only three testing sessions are offered per year, so it is important to apply soon. The test will be administered from November 12 through December 16. To check eligibility and schedule your exam, click here.
In addition, taking place tomorrow (September 19) from 12:00 noon to 1:00 p.m. (CDT), ANS will host a new webinar, “How to Become a Certified Nuclear Professional.” More information is available below in this article.
Yuh-Ming Ferng, Chien-Hsiung Lee
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 19-33
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35309
Articles are hosted by Taylor and Francis Online.
The simulation capabilities of RELAP5/MOD3 are analyzed and assessed in comparison with the IIST experiments conducted to investigate the system response to the loss of the residual heat removal (RHR) system during midloop operation. Two IIST experiments are simulated; a one-loop test under closed system conditions and a three-loop test with a vent at the top of the pressurizer. Once the RHR cooling system is lost and if alternate heat sinks are not established in time, the primary system will be heated up by the decay power, causing core boiling, system pressurization, and potential core uncovery and fuel heatup. The predicted responses of system parameters by the current model show reasonable agreement with the experimental data. These key parameters consist of the system pressure transient, temperature histories, and variation in the active heat transfer length within the steam generator. The liquid flooding in the pressurizer and the steam generator can also be captured in the current simulation. A periodic fill-and-down cycle developed in the steam generator U-tubes has been observed in the IIST measured data of oscillatory differential pressure across the steam generator. This phenomenon is not simulated in the calculation. However, the calculated differential pressure will follow the experimental trend and agree qualitatively with the measured data averaged over one fill-and-down cycle. As shown in the comparison of the calculated and experimental data, the overall system responses to the loss-of-RHR system event during midloop operation can be appropriately simulated by the current RELAP5/MOD3 model.