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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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
Oklo to collaborate with Atomic Alchemy on isotope production
Fast reactor developer Oklo, which recently went public on the New York Stock Exchange, announced on May 13 that it has signed a memorandum of understanding with Atomic Alchemy to cooperate on the production of radioisotopes for medical, energy, industry, and science applications.
Ara Go, Daesik Yook, Kyuhwan Jeong, GyeongMi Kim, GunHee Jung, Ser Gi Hong
Nuclear Technology | Volume 205 | Number 4 | April 2019 | Pages 605-623
Technical Paper | doi.org/10.1080/00295450.2018.1500795
Articles are hosted by Taylor and Francis Online.
The Basic Plan for High-Level Radioactive Waste Management (national WM plan) was established and promulgated, taking into consideration national and international trends on policy and technology development. In order to evaluate the safety for a facility in accordance with the national WM plan, it is essential to evaluate the spent nuclear fuel (SNF) source term. The objective of this study was to analyze Korea SNF characteristics; to propose reference SNF; and to evaluate generation amounts, radioactivity, thermal power, and isotopic composition of SNF in compliance with the national WM plan in order to provide basic information for safety research in Korea. The Automatic Multi-batch ORIGEN Runner for Evaluation of Spent fuel program (AMORES) was developed and used to evaluate inventory, radioactivity, and thermal power. Generation amounts, radioactivity, thermal power, and isotopic composition of SNF for milestones in the national WM plan were evaluated using a pressurized water reactor SNF database (DB) through 2015, and future SNF generation was estimated by taking into consideration the distribution of initial enrichment and burnup for each power plant unit. As a result, radioactivity, thermal power, and isotopic composition at each site in 2015, 2052, and 2082 differed significantly depending on the presence of new nuclear power plants. In addition, a reference SNF was proposed through statistical analysis of the SNF DB in order to utilize it for safety analysis based on various scenarios when actual SNF data cannot be available. In order to perform a more realistic safety assessment, radionuclide inventories using reference SNF and time-integrated SNF nuclide inventories using actual data were compared, and then, the best-fit reference SNF for each site and year was suggested.