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Division Spotlight
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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Latest News
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.
Simcha Stroes-Gascoyne, Lawrence H. Johnson, Dennis M. Sellinger
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 320-330
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A33972
Articles are hosted by Taylor and Francis Online.
Safety assessment of the used fuel disposal concept requires a study of the integrity of used fuel in contact with groundwater. In this context, the initial release of 137Cs and I29I from used Canada deuterium uranium fuel segments, exposed to water at 25°C, has been studied as a function of fuel irradiation history. Percentages of inventories released after 5 days of leaching are compared to stable xenon fuel-sheath gap inventories. Cesium-137/xenon and 129I/xenon release ratios average ∼0.2 for low linear power rating (LLPR) fuel. For high linear power rating fuel, ratios are considerably larger and may approach 1. For LLPR fuel, the ratios become larger when the leaching time is increased. It is proposed that these differences are related to the microstructure of used fuel. The results indicate that the source term for the instantaneous release of isotopes of cesium and iodine should include all of the fuel-sheath gap inventory. Power history data and calculated gas release data can be used to accurately estimate the contribution of the fuel-sheath gap inventory to the source term for radionuclide release.
