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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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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.
E.U. Bashlakova, V.V. Ignatiev, S.V. Kirillov, V.M. Novikov, A.V. Puzirev
Fusion Science and Technology | Volume 20 | Number 4 | December 1991 | Pages 620-626
Advanced Fission Reactors | doi.org/10.13182/FST91-A11946908
Articles are hosted by Taylor and Francis Online.
In providing nuclear power plant safety the priority is currently given to reactor self-protection by means of inherent features and passive means. The problems of self-protection for molten-salt fuel reactor (MSR) and molten-salt cooled coated particle fuel graphite reactor (HTMSR) have been studied. The following ways to reach a high level of self-protection are investigated: a) high level of natural circulation (100% for MSR and 10% for HTMSR); b) integrated layout; c) minimization of reactivity changes during fuel burn-up; d) decrease of maximum operative temperature. Calculations of transient processes during heavy accidents without scram are presented. It is shown that maximum temperatures of the primary circuit materials do not reach critical values under such accidents. For the high hypothetical case with the damage of the reactor and guard vessels in MSR the fission products yield from the fuel salt into gas-phase of MSR containment is investigated.
