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The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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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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.
Kazuo Hiramoto, Motoo Aoyama, Masaharu Sakagami, Renzo Takeda
Nuclear Technology | Volume 64 | Number 3 | March 1984 | Pages 243-248
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT84-A33354
Articles are hosted by Taylor and Francis Online.
Low density UO2 fuel pellets of an annular type are used to solve two problems related to high-discharge burnup: the enhancement of the pellet /cladding mechanical interaction, which increases cladding permanent strain, and the increase in average neutron energy due to high enrichment, which changes the core neutronic characteristics. As an example, the design concept is applied to boiling water reactor fuel rods having 57 effective full-power months (EFPMs). The fuel pellet density and the center hole diameter are determined to be 90% TD and 3.0 mm, respectively. The cladding permanent strain of the proposed fuel rod at EFPMs of 57 can be kept lower than the current fuel rod at 36 EFPMs. The EFPMs of 36 and 5 7 correspond respectively to the average discharge burnups of ∼30 and 50 GWd/ tonne U. With an enrichment of 4.5 wt%, the former rods provide the same neutronic characteristics as that of current rods with 2.8 wt% enrichment. Furthermore, power generation cost in the newly designed core is reduced by ∼10% from present cost levels.