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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
Canhui Sun, Zhaocan Meng, Yaodong Chen (State Power Investment Corp. Research Inst)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1153-1160
Rapid industrialization and urbanization in the last 30 years in China have caused severe air pollution. In order to meet the new challenges on the energy and environment, a new conceptual design of nuclear heating reactor (HAPPY200) is developed. HAPPY200 is a two-loop low pressure water reactor with low thermal parameters and passive safety systems. It can be used for heating, cooling, desalination and other process heat applications. Based on large volume pool completely passive technologies, HAPPY200 safety system can provide an inherent technical guarantee for the safety of the reactor.
The thermal-hydraulic behavior analysis is necessary for the safety and economy of the design. Subchannel analysis is the basic thermal-hydraulic analysis method used to predict the coolant enthalpy, quality, density, mass velocity rate, liquid temperature, vapor void fraction, pressure distribution, and the resulting DNBR distributions.
In this study, the analysis of thermal-hydraulic behavior for low pressure reactor is worked. Some problems are discussed for low pressure reactor, and the subchannel object model is established by subchannel code. Some low pressure CHF correlations developed for other fuel assemblies are analyzed. The thermal diffusion coefficient for reduced-height rod bundle is obtained compared with full-height rod bundle using CFD code. The value of reduced-height rod bundle can be used in the preliminary analysis of HAPPY200. According to the subchannel results, all the values satisfy conceptual design criteria.
