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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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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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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Latest News
Siting of Canadian repository gets support of tribal nation
Canada’s Nuclear Waste Management Organization (NWMO) announced that Wabigoon Lake Ojibway Nation has indicated its willingness to support moving forward to the next phase of the site selection process to host a deep geological repository for Canada’s spent nuclear fuel.
Tim D. Bohm, Mohamed E. Sawan
Fusion Science and Technology | Volume 77 | Number 7 | November 2021 | Pages 813-828
Technical Paper | doi.org/10.1080/15361055.2021.1908783
Articles are hosted by Taylor and Francis Online.
In the design of fusion reactors, determining radiation levels due to neutrons and photons (gammas) throughout the reactor and its surroundings is important. Radiation transport codes need to have accurate cross-section libraries in order to produce accurate results. The Fusion Evaluated Nuclear Data Library (FENDL) is an international effort coordinated by the International Atomic Energy Agency, Nuclear Data Section, that assembles a collection of the best nuclear data for fusion applications. In the current FENDL-3.1d data library, neutron cross sections for 65 of the 180 isotopes present in the library come from ENDF/B-VII.1.
Monte Carlo–based neutronics calculations using cross-section libraries from FENDL (versions 2.1 and 3.1d), ENDF/B (versions VII.1 and VIII.0), and candidate new evaluations for key structural elements/isotopes such as iron and chromium were performed. The calculations were performed in reactor-relevant models including a one-dimensional (1-D) cylindrical model of ITER, a three-dimensional (3-D) computer-aided design (CAD)–based model of ITER, and a 3-D CAD-based model of the U.S. Fusion Energy System Studies Fusion Nuclear Science Facility (FNSF).
The results show that neutron fluxes calculated with different cross-section libraries can be as much as 12% higher and as much as 8% lower than those calculated with the reference cross-section library (FENDL-2.1). Nuclear heating calculated with different cross-section libraries can be as much as 14% higher and as much as 8% lower than those calculated with the reference cross-section library. Iron displacements per atom calculated with different cross-section libraries can be as much as 9% higher and as much as 9% lower than those calculated with the reference cross-section library. Helium production calculated with different cross-section libraries can be as much as 19% higher and as much as 2% lower than those calculated with the reference cross-section library. Tritium production in the ITER 1-D model’s nonbreeding regions calculated with different cross-section libraries can be as much as 246% higher and as much as 5% lower than those calculated with the reference cross-section library. The tritium breeding ratio in the FNSF 3-D model calculated with different cross-section libraries averaged 1% higher at the inboard and 1.4% higher at the outboard than those calculated with the reference cross-section library.