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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.
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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
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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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Fusion Science and Technology
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.
F. Andritsos, M. Zucchetti
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2046-2050
Safety, Recycling, and Waste Management | doi.org/10.13182/FST92-A30022
Articles are hosted by Taylor and Francis Online.
The thermal transient in ITER, following a total LOCA accident, has been studied by means of a combined neutronic-thermal model. A complete (inboard and outboard) sector of the machine has been modelled. It turns out that, at short term, the transient is dominated by the redistribution of the high initial temperature of the plasma facing components. At medium term, the intense afterheat generation dominates the transient. The cold components act as a heat sink, and the process remains adiabatic for all practical purposes. At long term, weak afterheat generation and heat dissipation towards the environment dominate, and a temperature peak is found only several weeks after the accident. The temperatures that are obtained do not affect in any way the structural integrity or the containment of ITER.