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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.
M.R. Tanaka, C. Fong, K.M. Kalyanam, S.K. Sood, M. Delisle, A. Natalizio
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 970-975
Tritium Safety | Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30531
Articles are hosted by Taylor and Francis Online.
The Tritium Enclosure Model (TEM) has been developed as a user friendly interface to facilitate the application of the previously validated, verified and ITER approved TMAP4 Code. TEM (and TMAP4) dynamically analyzes the movement of tritium through structures, between structures and adjoining enclosures. Credible ITER relevant accident scenarios were developed and analyzed. The analyses considered the scenario with the cleanup system active or inactive, with and without the surface interactions. For surface interaction cases, the epoxy characteristics reported in the TMAP4 User Manual were used. Typical applications for TEM are the estimation of time-dependent tritium inventories in enclosures, as well as emissions to the environment following an accidental spill into any set of enclosures connected to cleanup systems. This paper outlines the various features of TEM and reports on the application of TEM to determine environmental source terms for the ITER Fuel Cycle and Cooling Systems, under chronic and accidental tritium releases.
