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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Latest News
Wyoming as a hub for new nuclear manufacturing and microreactor deployment?
A 60-year-old Wyoming industrial machinery company is partnering with nuclear innovator BWX Technologies to deploy 50-megawatt microreactors in America’s heartland over the coming years to provide carbon-free heat and power for industrial users.
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.