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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
J. E. Till, E. S. Bomar, L. E. Morse, V. J. Tennery
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 328-339
Technical paper | Fuel | doi.org/10.13182/NT78-A31998
Articles are hosted by Taylor and Francis Online.
A radiological assessment was performed for a reprocessing plant handling advanced liquid-metal fast breeder reactor (LMFBR) fuels, and the results were compared with those for reference oxide fuel. Candidate advanced fuels analyzed included l(U,Pu)Cl and f(U,Pu)Nj with selected concentrations of i5N. Core neutronics and designs appropriate to advanced-fueled LMFBRs were used with the ORIGEN computer code to calculate compositions of spent core and blanket fuel equivalent to 50 GW-yr of electrical energy generation. Confinement factors, specific to each radionuclide released to the atmosphere at the reprocessing plant, were used to calculate source terms describing the emission of radionuclides. Radiological impact within a 80-km radius of the facility was determined with the AIRDOS-II computer code, while the dose to the world population from 14C released at the reprocessing plant was estimated with a multicompartment global carbon cycling model. For carbide fuel, the calculated dose commitment to the total body of the maximally exposed individual was ∼2.8 mrem. Corresponding dose commitments when nitride fuels were substituted ranged between 59 and 3.4 mrem, as the 14N content in fuel was varied from 99.64%, the natural abundance of 14N, to zero (i.e., 100% enrichment with 15N), respectively. Dose commitment to the world population from l4C produced in nitride fuel made with natural nitrogen may prohibit use of this fuel from an environmental standpoint. However, a combination of ,SN enrichment in the fuel and confinement of at least part of the 14C at the reprocessing plant can significantly reduce both the amount of 14C ultimately released to the atmosphere and the global impact from 14C. It was concluded that no major differences exist in the radiological impact when carbide fuel is substituted for oxide fuel at the reprocessing plant. The use of nitride fuel may, however, require substantial enrichment with 15N or significant improvement in effluent treatment techniques proposed for 14 C retention.
