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Program on Technology Innovation: Advanced Fuel Cycles - Impact on High-Level Waste Disposal

This report presents the results of a dynamic simulation analysis for deployment of advanced light water reactors (LWRs) and fast burner reactors, as proposed by the Global Nuclear Energy Partnership (GNEP) program. Conditions for the analysis were selected for their potential to challenge the nuclear fuel simulation codes that were used, due to the large variations in nuclear fuel composition for the burner reactors before equilibrium conditions are approached. The analysis was performed in a U.S.

Nuclear Fuel Cycle Cost Comparison Between Once-Through and Plutonium Multi-Recycling in Fast Reactors

This report presents results from a parametric study of equilibrium fuel cycle costs for a closed fuel cycle with multi-recycling of plutonium in fast reactors (FRs) compared to an open, once-through fuel cycle using PWRs. The study examines the impact on fuel cycle costs from changes in the unit costs of uranium, advanced PUREX reprocessing of discharged uranium dioxide (UO2) fuel and fast-reactor mixed-oxide (FR-MOX) fuel, and FR-MOX fuel fabrication.

Advanced Nuclear Fuel Cycles -- Main Challenges and Strategic Choices

This report presents the results of a critical review of the technological challenges to the growth of nuclear energy, emerging advanced technologies that would have to be deployed, and fuel cycle strategies that could conceivably involve interim storage, plutonium recycling in thermal and fast reactors, reprocessed uranium recycling, and transmutation of minor actinide elements and fission products before eventual disposal of residual wastes.

Program on Technology Innovation: Advanced Fuel Cycles—Impact on High-Level Waste Disposal: Analysis of Deployment Scenarios of Fast Burner Reactors in the U.S. Nuclear Fleet

This report presents the results of a dynamic simulation analysis for deployment of advanced light water reactors (LWRs) and fast burner reactors, as proposed by the Global Nuclear Energy Partnership (GNEP) program. Conditions for the analysis were selected for their potential to challenge the nuclear fuel simulation codes that were used, due to the large variations in nuclear fuel composition for the burner reactors before equilibrium conditions are approached. The analysis was performed in a U.S.

Enrico Fermi Fast Reactor Spent Nuclear Fuel Criticality Calculations: Degraded Mode

The objective of this calculation is to characterize the nuclear criticality safety concerns
associated with the codisposal of the Department of Energy’s (DOE) Enrico Fermi (EF) Spent
Nuclear Fuel (SNF) in a 5-Defense High-Level Waste (5-DHLW) Waste Package (WP) and
placed in a Monitored Geologic Repository (MGR). The scope of this calculation is limited to
the determination of the effective neutron multiplication factor (keff) for the degraded mode
internal configurations of the codisposal WP. The results of this calculation and those of Ref. 8

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