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Monitored Retrievable Storage Facility Design Criteria Policy Document - 2nd Draft
Monitored Retrievable Storage Facility Design Criteria Policy Document - 2nd Draft
Nuclear Criticality Calculations for Canister-Based Facilities - DOE SNF
Nuclear Criticality Calculations for Canister-Based Facilities - DOE SNF
The purpose of this calculation is to perform waste-form specific nuclear criticality safety calculations to aid in establishing criticality safety design criteria, and to identify design and process parameters that are potentially important to the criticality safety of Department of Energy (DOE) standardized Spent Nuclear Fuel (SNF) canisters.
Storage of Spent Nuclear Fuel (Specific Safety Guide)
Storage of Spent Nuclear Fuel (Specific Safety Guide)
This Safety Guide provides recommendations and guidance on the storage of spent nuclear fuel. It covers all types of storage facilities and all types of spent fuel from nuclear power plants and research reactors. It takes into consideration the longer storage periods that have become necessary owing to delays in the development of disposal facilities and the decrease in reprocessing activities. It also considers developments associated with nuclear fuel, such as higher enrichment, mixed oxide fuels and higher burnup.
Radionuclide Screening
Radionuclide Screening
The waste forms under consideration for disposal in the repository at Yucca Mountain contain scores of radionuclides. It would be impractical and highly inefficient to model all of these radionuclides in a total system performance assessment (TSPA). Thus, the purpose of this radionuclide screening analysis is to remove from further consideration (screen out) radionuclides that are unlikely to significantly contribute to radiation dose to the public from a nuclear waste repository at Yucca Mountain.
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.
Canister Handling Facility Criticality Safety Calculations
Canister Handling Facility Criticality Safety Calculations
This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC (Bechtel SAIC Company) 2004 (DIRS 167614).
Nuclear Criticality Calculations for Canister-Based Facilities - Commercial SNF
Nuclear Criticality Calculations for Canister-Based Facilities - Commercial SNF
The purpose of this calculation is to perform waste-form specific nuclear criticality safety calculations to aid in establishing criticality safety design criteria, and to identify design and process parameters that are potentially important to the criticality safety of the transportation, aging and disposal (TAD) canister-based systems.
Local Liaison Committees and National Association of Local Liaison Committees: the French experience
Local Liaison Committees and National Association of Local Liaison Committees: the French experience
In the context of the governance of nuclear activities, especially in the field of the radioactive waste management, the self-structuring of civil society is a necessary condition of the citizens’ action. The experience of French “Commissions Locales d’Information” (CLIs) and their national federation the “Association Nationale des Commissions Locales d’Information” (ANCLI) represent an interesting and original example of local actors empowerment. In France, Local Information Commissions (CLI) are attached to most of the nuclear sites.
LONG-TERM ENVIRONMENTAL SURVEILLANCE AND HEALTH RISK ASSESSMENT
LONG-TERM ENVIRONMENTAL SURVEILLANCE AND HEALTH RISK ASSESSMENT
This research brief is addressing the governance issues associated with the practical implementation of long-term environmental surveillance systems on the one hand, and the health impact assessment related to radioactive waste disposal installations on the other hand. Based on feedback experiences associated with the surveillance of nuclear installations, the analysis is focused on governance stakes (how to involve local stakeholders, which information is meaningful, how to transfer the surveillance system between generations...) according to the expectations of the local stakeholders.
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada (40 CFR Part 197) -- Final Rule Response to Comments Document
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada (40 CFR Part 197) -- Final Rule Response to Comments Document
EPA held a 90-day public comment period for the proposed radiation protection standards for Yucca Mountain (August 27, 1999 through November 26, 1999). Sixty-nine (69) sets of written comments were submitted to EPAÕs Air Docket regarding the proposed standards, although some commenters submitted more than one set of written comments. In addition, the Agency received oral testimony on the proposed standards from 28 speakers during public hearings that were held in Washington, DC; Las Vegas, NV; Amargosa Valley, NV; and Kansas City, MO.
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada; Final Rule
Public Health and Environmental Radiation Protection Standards for Yucca Mountain, Nevada; Final Rule
We, the Environmental Protection Agency (EPA), are promulgating public health and safety standards for radioactive material stored or disposed of in the potential repository at Yucca Mountain, Nevada. Section 801 of the Energy Policy Act of 1992 (EnPA, Pub. L. 102Ð486) directs us to develop these standards. Section 801 of the EnPA also requires us to contract with the National Academy of Sciences (NAS) to conduct a study to provide findings and recommendations on reasonable standards for protection of the public health and safety.
Structuring local communities and development of local democracy for engagement in Radioactive Waste Management governance
Structuring local communities and development of local democracy for engagement in Radioactive Waste Management governance
Engagement of local communities and actors in the decision-making processes is traditionally motivated by the fact they are impacted by the decision taken. This traditional rationale for engagement of local communities and actors is driven not only by ethical concerns, but also by the necessity for public authorities to comply with national or international legal frameworks which give to stakeholders, concerned by a decision having environmental impacts, the right to be informed and participate in the decision (e.g.
Brief 3: Community Benefits and Support Packages
Brief 3: Community Benefits and Support Packages
The Brief introduces the concept of ‘Community Benefit and Support Packages’ following requests from a number of National Stakeholder Groups (NSGs) for more information on this issue. During the development of the Brief presentations were made to NSG meetings in Romania (June 2009), Slovenia (October 2009) and the UK (September 2008, September 2009). Some information specific to the UK from the Brief was also presented in Spain (November 2008).
Final 40 CFR 19: Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes
Final 40 CFR 19: Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes
Final 40 CFR 40 Ruling on Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel , High-Level and Transuranic Radioactive Wastes