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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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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, KHNP to investigate producing Lu-177 in South Korea
Framatome and Korea Hydro & Nuclear Power (KHNP) announced the signing of a memorandum of understanding to explore the possibility of producing the medical isotope Lutetium-177 at KHNP’s Wolsong nuclear power plant in South Korea. The companies also will investigate the feasibility of using the plant to support Korean production of medical radioisotopes in the future.
Kevin John Connolly, Alexander J. Huning, Farzad Rahnema, Srinivas Garimella
Nuclear Science and Engineering | Volume 184 | Number 2 | October 2016 | Pages 228-243
Technical Paper | doi.org/10.13182/NSE15-105
Articles are hosted by Taylor and Francis Online.
A newly developed coupled neutronic–thermal-hydraulic method for prismatic high-temperature gas reactors (HTGRs) is presented with accompanying results for several prismatic core configurations and numerical sensitivity studies. The principal advantage of the new method is the determination of coupled, whole-core temperature and pin power distributions with reduced computational effort over other available codes. The coarse-mesh radiation transport method (COMET), which relies solely on radiation transport, is the component of the new method used to compute neutronic parameters. A three-dimensional unit-cell–based thermal fluids solver is used to compute steady-state thermal-hydraulic parameters. For both component methods, no geometric approximations or averaging schemes are necessary. Convergence of the neutronic and thermal-hydraulic components and the coupled method is discussed, and coupled analyses are presented. The calculation of whole-core solutions allows for unique insights not possible with limited domain tools such as computational fluid dynamics. Results from one such unique study, near-critical control rod movements, are presented in this paper. Comparisons between coupled and uncoupled analyses are also presented.