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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
Framatome signs contracts with Sizewell C
French nuclear developer Framatome is slated to deliver key equipment for Sizewell C Ltd.’s two large reactors planned for the United Kingdom’s Suffolk coast.
The agreement, reportedly worth multiple billions of euros, was announced this week and will involve Framatome from the design phase until commissioning. The company also agreed to a long-term fuel supply deal. Framatome is 80.5 percent owned by France’s EDF and 19.5 percent owned by Mitsubishi Heavy Industries.
Liang-Che Dai, Chung-Yu Yang, Yng-Ruey Yuann, Bau-Shei Pei, Chun-Kuan Shih
Nuclear Science and Engineering | Volume 182 | Number 1 | January 2016 | Pages 96-103
Technical Paper | Special Issue on the RELAP5-3D Computer Code | doi.org/10.13182/NSE14-145
Articles are hosted by Taylor and Francis Online.
According to “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants” (NUREG-0800) of the U.S. Nuclear Regulatory Commission, the homogeneous and thermal equilibrium critical flow model (HEM model) is acceptable for pressure and temperature analysis of the subcompartment of the containment. However, it was not built into the RELAP5-3D code. In order to provide the blowdown boundary conditions that meet the acceptance criteria for the subcompartment pressure and temperature response analysis, Institute of Nuclear Energy Research implemented and assessed the Moody HEM model of RELAP5-3D. The assessment phase was subsequent to the implementation of the Moody HEM model of RELAP5-3D. Three experiments of Marviken critical flow tests (CFTs) were selected as the assessment cases. They were CFT 15, CFT 22, and CFT 24. The assessment input decks of RELAP5-3D had been modified from the appendixes of the references. Additional comparisons with the results of the RELAP5-3D built-in Ransom-Trapp and Henry-Fauske critical flow models were also included. The comparisons of the calculated blowdown mass flow rate with the test data assessed the newly implemented model, which gave good prediction. Moreover, the comparisons between the results of the critical flow models of RELAP5-3D and the test data provided a measure of the relative conservatism of the critical flow calculations.