Category of Content

Siting Experience Documents Only

Publication Date

Country

Keywords

Displaying 1 - 11 of 11

EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages

EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages

Author(s)
Paul L. Cloke
Publication Date
The Monitored Geologic Repository (MGR) Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating (CRWMS M&O) contractor performed calculations to provide input to the design of a waste package (WP). This document analyzes the degradation processes of two types of pressurized water reactor (PWR) spent nuclear fuel (SNF): • Fuel fabricated from low enriched uranium oxide, which has been used, or will ~ used, in commercial nuclear power plants.
criticality low-enriched uranium monitored geologic repository storage mox fuel waste package degradation pwr snf corrosion plutonium oxide geochemical analysis bba000000-01717-0210-00009 uranium oxide

OECD/NEA Burnup Credit Criticality Benchmarks Phase IIIB: Burnup Calculations of BWR Fuel Assemblies for Storage and Transport

OECD/NEA Burnup Credit Criticality Benchmarks Phase IIIB: Burnup Calculations of BWR Fuel Assemblies for Storage and Transport

Author(s)
Okuno, Hiroshi ,
Naito, Yoshitaka ,
Suyama, Kenya
Publication Date

The report describes the final results of the Phase IIIB Benchmark conducted by the
Expert Group on Burnup Credit Criticality Safety under the auspices of the Nuclear Energy
Agency (NEA) of the Organization for Economic Cooperation and Development (OECD).
The Benchmark was intended to compare the predictability of current computer code and
data library combinations for the atomic number densities of an irradiated BWR fuel
assembly model. The fuel assembly was irradiated under specific power of 25.6 MW/tHM

burnup credit criticality analysis nea jaeri nea/nsc/doc(2002)/2 composition calculations

Program on Technology Innovation: Readiness of Existing and New U.S. Reactors for Mixed-Oxide (MOX) Fuel

Program on Technology Innovation: Readiness of Existing and New U.S. Reactors for Mixed-Oxide (MOX) Fuel

Author(s)
Electric Power Research Institute
Publication Date

Expanding interest in nuclear power and advanced fuel cycles indicate that use of mixed-oxide (MOX) fuel in the current and new U.S. reactor fleet could become an option for utilities in the coming decades. In light of this renewed interest, EPRI has reviewed the substantial knowledge base on MOX fuel irradiation in light water reactors (LWRs). The goal was to evaluate the technical feasibility of MOX fuel use in the U.S. reactor fleet for both existing and advanced LWR designs (Generation III/III+).

nuclear fuel cycle plutonium recycling light water reactor advanced fuel cycle mox fuel plutonium oxide

Burn-up Credit Criticality Safety Benchmark - Phase VII, UO2 Fuel: Study of Spent Fuel Compositions for Long-term Disposal

Burn-up Credit Criticality Safety Benchmark - Phase VII, UO2 Fuel: Study of Spent Fuel Compositions for Long-term Disposal

Author(s)
Wagner, J. C. ,
Radulescu, G.
Publication Date
burnup credit spent fuel isbn 978-92-64-99172-9 nea no. 6998 criticality analysis spent fuel composition nea wpncs egbuc used fuel

Criticality Analysis of Pu and U Accumulations in a Tuff Fracture Network

Criticality Analysis of Pu and U Accumulations in a Tuff Fracture Network

Author(s)
CRWMS
Publication Date

The objective of this analysis is to evaluate accumulations within the thermally altered tuff surrounding a drift. The evaluation examines accumulation of uranium minerals (soddyite), plutonium oxide (Pu01), and combinations of these materials. A hypothetical model of the tuff is used to provide insight into the factors that affect criticality for this near-field scenario. The factors examined include: the size of the accumulation, the fissile composition of the accumulation, the water or clayey material fraction in the accumulation and the water fraction in the tuff

tuff criticality analysis storage near field interactions fissile material accumulation mcnp repository drifts plutonium oxide uranium minerals soddyite

Stakeholder Confidence in Radioactive Waste Management: An Annotated Glossary of Key Terms

Stakeholder Confidence in Radioactive Waste Management: An Annotated Glossary of Key Terms

Author(s)
OECD
Publication Date

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.

public perception nea radioactive waste 6988 waste management stakeholders

The Partnership Approach to Siting and Developing Radioactive Waste Management Facilities

SED Publication Type

The Partnership Approach to Siting and Developing Radioactive Waste Management Facilities

Author
NEA
Publication Date

History shows that the search for sites for radioactive waste management facilities has been marred by conflicts and delays. Affected communities have often objected that their concerns and interests were not addressed. In response, institutions have progressively turned away from the traditional “decide, announce and defend” model, and are learning to “engage, interact and co-operate”. This shift has fostered the emergence of partnerships between the proponent of the facility and the potential host community, as shown in a recent NEA study.

public perception nea waste management siting community interaction
Disclaimer: Note that this page contains links to external sites. When leaving the CURIE site, please note that the U.S. Department of Energy and Pacific Northwest National Laboratory do not control or endorse the content or ads on these sites.
Sponsored by: