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Program on Technology Innovation: Readiness of Existing and New U.S. Reactors for Mixed-Oxide (MOX) Fuel
Program on Technology Innovation: Readiness of Existing and New U.S. Reactors for Mixed-Oxide (MOX) Fuel
Expanding interest in nuclear power and advanced fuel cycles indicate that use of mixed-oxide (MOX) fuel in the current and new U.S. reactor fleet could become an option for utilities in the coming decades. In light of this renewed interest, EPRI has reviewed the substantial knowledge base on MOX fuel irradiation in light water reactors (LWRs). The goal was to evaluate the technical feasibility of MOX fuel use in the U.S. reactor fleet for both existing and advanced LWR designs (Generation III/III+).
Criticality Analysis of Pu and U Accumulations in a Tuff Fracture Network
Criticality Analysis of Pu and U Accumulations in a Tuff Fracture Network
The objective of this analysis is to evaluate accumulations within the thermally altered tuff surrounding a drift. The evaluation examines accumulation of uranium minerals (soddyite), plutonium oxide (Pu01), and combinations of these materials. A hypothetical model of the tuff is used to provide insight into the factors that affect criticality for this near-field scenario. The factors examined include: the size of the accumulation, the fissile composition of the accumulation, the water or clayey material fraction in the accumulation and the water fraction in the tuff
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report for Uruguay
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report for Uruguay
There are no nuclear power stations and no nuclear fuel cycle activities in Uruguay. There are only disused radioactive sources from medical and industrial practices and there is a disused conditioned neutron Pu-239 source with 185 TBq, waiting for its reshipment to the United States. This material is stored in the building in which it was an old research reactor. The application of the Convention is limited to radioactive waste arising from the medical, industrial and research applications of radioisotopes.