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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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
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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TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Keshav Chander, Bharatkumar N. Patil, Jayshree V. Kamat, Nandakumar B. Khedekar, Remani B. Manolkar, Surendranath G. Marathe
Nuclear Technology | Volume 78 | Number 1 | July 1987 | Pages 69-74
Technical Paper | Chemical Processing | doi.org/10.13182/NT87-A34010
Articles are hosted by Taylor and Francis Online.
Direct dissolution of uranium carbide was found to be very effective when it was refluxed with an 18 M H2SO4‾15 M HNO3 (1:1) mixture. Clear solutions could be obtained within 1 h. Uranium-plutonium carbide, as well as PuO2 could also be dissolved in 1 to 2 h in the same way. Other nuclear materials, UO2 + C and UO2 + PuO2 + C, needed longer duration for complete dissolution. When the proportion of H2SO4 in the H2SO4‾HNO3 mixture was increased to 2:1, these materials also dissolved within 2 h. Quantitativeness of the dissolution was checked by the potentiometric determination of uranium and/or plutonium contents in these solutions. The results were in good agreement (±0.5%) when compared with the values obtained by the well-established dissolution method. During the fabrication of fuel (plutonium-rich mixed carbide) for the fast breeder test reactor, a large number of fuel samples were analyzed by using the above method of dissolution for the chemical quality control. Presuming the possibility of formation of small amounts of oxalic and mellitic (benzene hexacarboxylic) acids during the process of dissolution of carbides, the effect of the presence of these organic species on the potentiometric determination of uranium and plutonium was studied.