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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.
H. Albrecht, V. Matschoss, H. Wild
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 559-565
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32366
Articles are hosted by Taylor and Francis Online.
The most relevant open questions combined with activity release during hypothetical core meltdown accidents refer to the chemical behavior of the highly reactive elements iodine, cesium, and tellurium, to the release characteristics of the medium-volatile fission and activation products, to the properties of the resulting aerosol particles, and to various phenomena during steam explosion and melt/concrete interaction. To answer some of these questions, experiments are conducted at the melting facility SASCHA in which a representative core material mixture (corium) is induction-heated to temperatures of 3000 K. The released material is analyzed by use of gamma-ray spectrometry and electron scanning microscopy. Some results of the first series of experiments in air are given below: