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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
Morris F. Osborne, Jack L. Collins, Richard A. Lorenz
Nuclear Technology | Volume 78 | Number 2 | August 1987 | Pages 157-169
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT87-A33994
Articles are hosted by Taylor and Francis Online.
Fission product release from fully irradiated light water reactor fuel under accident conditions and the chemical forms and behavior of the released material have been studied at high temperatures. This work has emphasized release from commercial fuels, but tracer-level tests using specific fission product species have been used in efforts to clarify chemical behavior. The specimens were heated in an induction furnace in flowing steam at temperatures of 1700 to 2300 K. The fractional releases of krypton, iodine, and cesium increased with temperature, reaching maxima of nearly 60% in 20 min. The release of tellurium varied strongly with the extent of cladding oxidation and approached that of cesium for completely oxidized cladding. In addition to some structural material, the major chemical forms in the furnace effluent appeared to include CsI, CsOH, silver, antimony, and tellurides of cesium and tin. The fractional releases of the volatile fission products correlated with the amount of fuel porosity, and the masses of aerosol collected increased with test temperature and oxidation. Comparison of our results with several fission product release models showed agreement ranging from good to poor.