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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Fusion Science and Technology
Latest News
Zap Energy hits 37-million-degree electron temperatures in compact fusion device
Zap Energy announced April 23 that it has reached 1-3 keV plasma electron temperatures—roughly the equivalent of 11 to 37 million degrees Celsius—using its sheared-flow-stabilized Z-pinch approach to fusion. Reaching temperatures above that of the sun’s core (which is 10 million degrees Celsius temperature) is just one hurdle required before any fusion confinement concept can realistically pursue net gain and fusion energy.
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.