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10 CFR Part 960 - General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories
10 CFR Part 960 - General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories
The Department of Energy, Office of Civilian Radioactive Waste Management, today proposes to amend its General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. The DOE is proposing these amendments to clarify and focus the Guidelines to be used in evaluating the suitability of the Yucca Mountain site in Nevada for development as a repository.
10 CFR Part 963 - Yucca Mountain Site Suitability Guidelines
10 CFR Part 963 - Yucca Mountain Site Suitability Guidelines
Revising America's Nuclear Waste Policy
Revising America's Nuclear Waste Policy
With the first 100 days of the Obama Administration behind us, the Institute for 21st Century Energy presents this nuclear waste policy document that recounts the history of the country’s nuclear waste policy, discusses the mechanics of the issue, and offers specific recommendations to the Obama Administration and the U.S. Congress.
Underlying Yucca Mountain: The Interplay of Geology and Policy in Nuclear Waste Disposal
Underlying Yucca Mountain: The Interplay of Geology and Policy in Nuclear Waste Disposal
Nuclear waste disposal in the USA is a difficult policy issue infused with science, technology, and politics. This issue provides an example of the co-production of scientific knowledge and politics through public policy. The proponents of a repository site at Yucca Mountain, Nevada, argue that their decision to go ahead with the site is based on ‘sound science’, but the science they use to uphold their decision is influenced by politics. In turn, the politics of site selection has been altered by the scientific knowledge produced.
Regulatory History
Regulatory History
The Way Forward in the US: Nuclear Waste Management
The Way Forward in the US: Nuclear Waste Management
Development of a High-Level Radioactive Waste Regulatory Structure
Development of a High-Level Radioactive Waste Regulatory Structure
Slides - Blue Ribbon Commission Disposal Subcommittee, Site Evaluation & Management Lessons Learned from Yucca Mountain
Slides - Blue Ribbon Commission Disposal Subcommittee, Site Evaluation & Management Lessons Learned from Yucca Mountain
Site Evaluation and Management Lessons Learned from Yucca Mountain
Technical Basis Report For Surface Characteristics, Preclosure Hydrology, And Erosion
Technical Basis Report For Surface Characteristics, Preclosure Hydrology, And Erosion
This study presents a synthesis of information and interpretations relevant to surficial processes at the Yucca Mountain Site. The report is part of the technical basis which will be used to evaluate the suitability of Yucca Mountain, Nevada, as a site for a mined geologic repository for the permanent disposal of high-level radioactive waste and spent nuclear fuel. It provides a description of the surface characteristics, preclosure hydrology, and erosion at the Yucca Mountain Site. This report will provide the technical basis to evaluate three technical guidelines from the U.S.
TECHNICAL BASIS REPORT FOR SURFACE CHARACTERISTICS, PRECLOSURE HYDROLOGY, AND EROSION PUBLIC SUMMARY
TECHNICAL BASIS REPORT FOR SURFACE CHARACTERISTICS, PRECLOSURE HYDROLOGY, AND EROSION PUBLIC SUMMARY
Frequency of SNF Misload for Uncanistered Fuel Waste Package
Frequency of SNF Misload for Uncanistered Fuel Waste Package
The purpose of this engineering calculation is to estimate the frequency of misloading spent nuclear fuel (SNF) assemblies that would result in exceeding the criticality design basis of a waste package (WP). This type of misload - a reactivity misload - results from the incorrect placement of one or more fuel assemblies into a waste package such that the criticality controls do not match the required controls for the fuel assemblies. An actual criticality event can not occur in a WP unless a moderator (e.g. water) is present.
In-Drift Precipitates/Salts Model
In-Drift Precipitates/Salts Model
This report documents the development and validation of the in-drift precipitates/salts (IDPS) process model. The IDPS process model is a geochemical model designed to predict the postclosure effects of evaporation and deliquescence on the chemical composition of water within the Engineered Barrier System (EBS) in support of the total system performance assessment (TSPA). Application of the model in support of TSPA is documented in Engineered Barrier System: Physical and Chemical Environment (BSC 2005 [DIRS 175083]).
PWR Axial Burnup Profile Analysis
PWR Axial Burnup Profile Analysis
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.
EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages
EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages
The Monitored Geologic Repository (MGR) Waste Package Operations (WPO) of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Shippingport Pressurized Water Reactor (PWR) (Ref. 1). The Shippingport PWR SNF has been considered for disposal at the proposed Yucca Mountain site.
Isotopic Generation and Confirmation of the BWR Appl. Model
Isotopic Generation and Confirmation of the BWR Appl. Model
The objective of this calculation is to establish an isotopic database to represent commercial spent nuclear fuel (CSNF) from boiling water reactors (BWRs) in criticality analyses performed for the proposed Monitored Geologic Repository at Yucca Mountain, Nevada. Confirmation of the conservatism with respect to criticality in the isotopic concentration values represented by this isotopic database is performed as described in Section 3.5.3.1.2 of the Disposal Criticality Analysis Methodology Topical Report (Reference 7.1).
Evaluation of Potential Economic Impacts of 40 CFR Part 197: Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada
Evaluation of Potential Economic Impacts of 40 CFR Part 197: Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada
The information presented in this EIA has demonstrated that the design of a repository for disposal of radioactive wastes at Yucca Mountain has evolved without having been affected by the EPA standards. The standards have been demonstrated to have no impact on repository program costs, and nominal performance for the current repository design would result in no radiation doses for more than 10,000 years. Additionally, the difference between a 25 mrem/yr dose standard and a 15 mrem/yr standard is insignificant to program costs and performance evaluations.
Letter from Mississippi Governor Phil Bryant
Letter from Mississippi Governor Phil Bryant
Governor Bryant sent a letter to Pete Lyons, Assistant Secretary for Nuclear Energy regarding the state hosting a geologic repository for spent nuclear fuel as an alternative to the Yucca Mountain repository . Although some communities may have expressed interest to DOE, Governor Bryant is opposed to hosting a repository and asks DOE to consider any state other than Mississippi.
Letter on siting from Governor Rick Perry
Letter on siting from Governor Rick Perry
Texas Governor Rick Perry wrote a letter to the Texas Congressional delegation regarding new solutions to the long term handling of spent nuclear fuel and high-level radioactive waste.
One Step at a Time: The Staged Development of Geologic Repositories for High-Level Radioactive Waste - Summary
One Step at a Time: The Staged Development of Geologic Repositories for High-Level Radioactive Waste - Summary
A new report from the National Academies proposes a management approach called “adaptive staging” as a promising means to develop geologic repositories for high-level waste such as the proposed repository at Yucca Mountain, Nevada. Adaptive staging is a learn-as-you-go process that enables project managers to continuously reevaluate and adjust the program in response to new knowledge and stakeholder input.
Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences
Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences
Performance objectives for the geologic repository operations area through permanent closure in 10 CFR 63.111 identify compliance with regulatory dose limits for workers and members of the public as a design objective. The purpose of this design calculation is to determine direct radiation dose consequences for Category 1 and 2 event sequences. It does not include worker dose assessment for recovery operations following Category 1 event sequences.
WHF and RF Thermal Evaluation
WHF and RF Thermal Evaluation
The purpose of this analysis is to estimate the peak fuel assembly cladding temperature within the transportation casks that will be received in the WHF and RF, and to compare this value with established temperature limits. Thermally limiting scenarios are evaluated for both normal and off-normal operating conditions, with the off-normal condition defined as a loss of active ventilation.
Radiation Effects of Isotopic Uncertainty for Burnup Credit Validation
Radiation Effects of Isotopic Uncertainty for Burnup Credit Validation
The objective of this calculation is to provide the uncertainty term for fission product and minor actinides which contributes to the determination of the critical limit for burnup credit calculations. The scope of this calculation covers PWR and BWR spent nuclear fuel. This activity supports the Criticality Department's validation of burnup credit. The intended use of these results is in future Criticality Department calculations and analyses.
DSNF and Other Waste Form Degradation Abstraction
DSNF and Other Waste Form Degradation Abstraction
Several hundred distinct types of DOE-owned spent nuclear fuel (DSNF) may potentially be disposed in the Yucca Mountain repository. These fuel types represent many more types than can be viably individually examined for their effect on the Total System Performance Assessment for the License Application (TSPA-LA). Additionally, for most of these fuel types, there is no known direct experimental test data for the degradation and dissolution of the waste form in repository groundwaters.