This report puts forth a number of options and recommendations for how to engage
stakeholders and other members of the public in the storage and management of spent
nuclear fuel and high level waste in the United States. The options are generated from a
scientific review of existing publications proposing criteria for assessing past efforts to
engage publics and stakeholders in decision-making about risky technologies. A set of
nine principles are derived for evaluating cases of public and stakeholder engagement with

This report puts forth a number of options and recommendations for how to engage
stakeholders and other members of the public in the storage and management of spent
nuclear fuel and high level waste in the United States. The options are generated from a
scientific review of existing publications proposing criteria for assessing past efforts to
engage publics and stakeholders in decision-making about risky technologies. A set of
nine principles are derived for evaluating cases of public and stakeholder engagement with

The Blue Ribbon Commission staff requested this paper cataloging innovative stakeholder involvement programs within the Department of Energy (DOE). I reviewed a variety of material on public involvement, including papers and presentations on stakeholder involvement in DOE programs, published presentations and comments to the BRC, and research reports on stakeholder and public involvement.

The objective of this calculation is to establish an isotopic database to represent commercial spent nuclear fuel (CSNF) from pressurized water reactors (PWRs) 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 (YMP 2000).

The purpose of this calculation is to evaluate the transient behavior and consequences of a worst- case criticality event involving intact pressurized water reactor (PWR) mixed-oxide (MOX) spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR waste package (WP). This calculation will provide information necessary for demonstrating that the consequences of a worst-case criticality event involving intact PWR MOX SNF are insignificant in their effect on the overall radioisotopic inventory and on the integrity of the repository.

This report puts forth a number of options and recommendations for how to engage
stakeholders and other members of the public in the storage and management of spent
nuclear fuel and high level waste in the United States. The options are generated from a
scientific review of existing publications proposing criteria for assessing past efforts to
engage publics and stakeholders in decision-making about risky technologies. A set of
nine principles are derived for evaluating cases of public and stakeholder engagement with

The purpose of this activity is to develop a representative “limiting” axial burnup profile for pressurized water reactors (PWRs), which would encompass the isotopic axial variations caused by different assembly irradiation histories, and produce conservative isotopics with respect to criticality. The effect that the low burnup regions near the ends of spent fuel have on system reactivity is termed the “end-effect”. This calculation will quantify the end-effects associated with Pressurized Water Reactor (PWR) fuel assemblies emplaced in a hypothetical 21 PWR waste package.

The purpose of this analysis is to evaluate the transient behavior and consequences of a worst case criticality event involving intact pressurized water reactor (PWR) spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR assembly waste package (WP). The objective of this analysis is to demonstrate that the consequences of a worst case criticality event involving intact PWR SNF are insignificant in their effect on the overall radioisotopic inventory in a WP. An internal WP criticality is modeled in a manner analogous to transient phenomena in a nuclear reactor core.

The purpose of this activity is to develop a representative “limiting” axial burnup profile for pressurized water reactors (PWRs), which would encompass the isotopic axial variations caused by different assembly irradiation histories, and produce conservative isotopics with respect to

The OECD Nuclear Energy Agency (NEA) Forum on Stakeholder Confidence (FSC) acts as a centre for informed exchange of knowledge and experience regarding stakeholder interaction and public participation in radioactive waste management. It promotes an open discussion among members and stakeholders, across institutional boundaries, and between technical and non-technical actors, in an atmosphere of trust and mutual respect. As such, the FSC is, first and foremost, a learning organisation.

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department to describe the latest version of the probabilistic criticality analysis methodology and its application to the entire commercial waste stream of commercial pressurized water reactor (PWR) spent nuclear fuel (SNF) expected to be emplaced in the repository. The purpose of this particular application is to evaluate the 21 assembly PWR absorber plate waste package (WP) with respect to degradedmode criticality performance.