Preclosure Consequence Analyses

Preclosure Consequence Analyses

The purpose of this calculation is to demonstrate that the preclosure performance objectives specified in 10 CFR 63.111(a) and 10 CFR 63.111(b) (Reference 2.2.1) have been met for the proposed design and operations in the geologic repository operations area (GROA) during normal operations and Category 1 event sequences, and following Category 2 event sequences. Category 1 event sequences are those natural and human-induced event sequences that are expected to occur one or more times before permanent closure of the repository.

N-Reactor Spent Nuclear Fuel Criticality Calculations

N-Reactor Spent Nuclear Fuel Criticality Calculations

The purpose of this calculation is to characterize the criticality safety aspects of N-Reactor fuel stored in a Department of Energy spent nuclear fuel (DOE-SNF) canister that contains four Multi-Canister Overpacks (MCO's). These calculations will be done to support the analysis that will be done to demonstrate concept viability related to pre-emplacement storage and use in the Monitored Geologic Repository (MGR) environment for the pre-closure time frame.

Fast Flux Test Facility (FFTF) Reactor Fuel Criticality Calculations

Fast Flux Test Facility (FFTF) Reactor Fuel Criticality Calculations

The purpose of these calculations is to characterize the criticality safety concerns for the storage of Fast Flux Test Facility (FFTF) nuclear fuel in a Department of Energy spent nuclear fuel (DOE SNF) canister in a co-disposal waste package. These results will be used to support the analysis that will be done to demonstrate concept viability related to use in the Monitored Geologic Repository (MGR) environment.

Preclosure Criticality Safety Analysis

Preclosure Criticality Safety Analysis

The means to prevent and control criticality must be addressed as part of the Preclosure Safety Analysis (PCSA) required for compliance with 10 CFR Part 63 [DIRS 180319], where the preclosure period covers the time prior to permanent closure activities. This technical report presents the nuclear criticality safety evaluation that documents the achievement of this objective.

Final 10 CFR 960: General Guidelines for the Preliminary Screening of Potential Sites for a Nuclear Waste Repository

These guidelines were developed in accordance with the requirements of Section 112(a) of the Nuclear Waste Policy Act of 1982 for use by the Secretary of Energy in evaluating the suitability of sites. The guidelines will be used for suitability evaluations and determinations made pursuant to Section 112(b). The guidelines set forth in this part are intended to complement the requirements set forth in the Act, 10 CFR part 60, and 40 CFR part 191. The DOE recognizes NRC jurisdiction for the resolution of differences between the guidelines and 10 CFR part 60.

Site Selection and Characterization Processes for Deep Geologic Disposal of High Level Nuclear Waste

In this paper, the major elements of the site selection and characterization processes used in the U.S. high level waste program are discussed. While much of the evolution of the site selection and characterization processes have been driven by the unique nature of the U.S. program, these processes, which are well-defined and documented, could be used as an initial basis for developing site screening, selection, and characterization programs in other countries. Thus, this paper focuses more on the process elements than the specific details of the U.S. program.

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