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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
P. K. Kuroda, M. P. Menon
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 70-74
Technical Paper | doi.org/10.13182/NSE61-A25932
Articles are hosted by Taylor and Francis Online.
The occurrence of a number of fission products in pitchblende and in nonirradiated natural and depleted U salts with 10-4 dis/sec/g-U, was recently reported by Kuroda and co-workers. The following nuclides were detected: Sr89, 90, 91, 92, Mo99, I131, 132, 133, 134, 135, and Ba140. These fission products are formed predominantly by the spontaneous fission of U238, and it is possible to obtain the general shape of the mass-yield curve for the spontaneous fission of U238 from the equilibrium activities of the fission products found in nonirradiated U salts. The spontaneous fission half-life of U238 can also be calculated from these data. Radiochemical procedures have been developed for the determination of each fission product, in which a quantity ranging from 0.1 to 1 disintegration/sec of the fission product activity is isolated from kilogram quantities of U salts, purified, and then counted. Where the half-life of the fission product was several months, U minerals instead of U salts, were used. Removal of the bulk of the U by a liquid extraction method was found to be necessary and/or advantageous in most cases, although it was possible to precipitate certain fission products directly from a concentrated solution of the U salts. A new procedure is currently under investigation for the isolation and quantitative determination of the isotopes of Ce by a liquid-liquid extraction method. Ce(IV) can be extracted from a 10 M HNO3 solution by a 1 to 4 mixture of TBP and CCl4 with high extraction efficiency, and further purified by a combination of oxidation-reduction and liquid-liquid extraction procedures.
