Category of Content

Siting Experience Documents Only

Publication Date

Subject Matter

Keywords

Displaying 1 - 25 of 63

Probabilistic External Criticality Evaluation

Probabilistic External Criticality Evaluation

Author(s)
P. Gottlieb ,
J. R. Massari
Publication Date
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department to provide a probabilistic evaluation of the potential for criticality of fissile material which has been transported from a geologic repository containing breached waste packages of commercial spent nuclear fuel (SNF). This analysis is part of a continuing investigation of the probability of criticality resulting from the emplacement of spent nuclear fuel in a geologic repository.
criticality safety mined geologic repository external criticality breached waste package

The Likelihood of Criticality Following Disposal of SF/HLW/HEU/Pu

The Likelihood of Criticality Following Disposal of SF/HLW/HEU/Pu

Author(s)
T.W. Hicks ,
T.D. Baldwin ,
J.M. Solano ,
Galson Sciences Ltd ,
D.G. Bennett ,
TerraSalus Ltd
Publication Date
The Radioactive Waste Management Directorate (RWMD) is responsible for implementing geological disposal of the UK’s higher-activity radioactive wastes. RWMD’s research into geological disposal considers safety during waste transport to a disposal facility, during waste disposal operations, and once the facility has been closed. The wastes for disposal comprise a wide range of materials and include some fissile radionuclides.
disposal criticality criticality safety heu used fuel disposition hlw geologic disposal facility gdf sf rwmd/003/001 17293-tr-022

Computational Benchmark for Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit

Computational Benchmark for Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit

Author(s)
Mueller, D. E. ,
Scaglione, J. M. ,
Wagner, J. C. ,
Bowman, S. M.
Publication Date

This report proposes and documents a computational benchmark for the estimation of the
additional reactivity margin available in spent nuclear fuel (SNF) from fission products and minor
actinides in a burnup-credit storage/transport environment, relative to SNF compositions
containing only the major actinides. The benchmark problem/configuration is a generic burnupcredit
cask designed to hold 68 boiling water reactor (BWR) spent nuclear fuel assemblies. The
purpose of this computational benchmark is to provide a reference configuration for the

burnup credit bwr fission products criticality safety computational benchmark minor actinides nureg/cr-7157 ornl/tm-2012/96 estimated reactivity margin storage

Review and Prioritization of Technical Issues Related to Burnup Credit for BWR Fuel

Review and Prioritization of Technical Issues Related to Burnup Credit for BWR Fuel

Author(s)
Mueller, D. E. ,
Bowman, S. M. ,
Marshall, W. J. ,
Scaglione, J. M.
Publication Date

This report has been prepared to support technical discussion of and planning for future
research supporting implementation of burnup credit for boiling-water reactor (BWR) spent fuel
storage in spent fuel pools and storage and transport cask applications. The review and
discussion in this report are based on knowledge and experience gained from work performed
in the United States and other countries, including experience with burnup credit for
pressurized-water reactor (PWR) spent fuel. Relevant physics and analysis phenomena are

burnup credit bwr criticality safety nureg/cr-7158 ornl/tm-2012/261 storage

Criticality Risks During Transportation of Spent Nuclear Fuel

Criticality Risks During Transportation of Spent Nuclear Fuel

Author(s)
Electric Power Research Institute
Publication Date

This report presents a best-estimate probabilistic risk assessment (PRA) to quantify the frequency of criticality accidents during railroad transportation of spent nuclear fuel casks. The assessment is of sufficient detail to enable full scrutiny of the model logic and the basis for each quantitative parameter contributing to criticality accident scenario frequencies. The report takes into account the results of a 2007 peer review of the initial version of this probabilistic risk assessment, which was published as EPRI Technical Report 1013449 in December 2006.

burnup credit spent fuel criticality safety misloading rail risk assessment accident testing railroad transportation spent fuel transportation

Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term Disposal Criticality Safety

Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term Disposal Criticality Safety

Author(s)
DeHart, M. D.
Publication Date

Utilization of burnup credit in criticality safety analysis for long-term disposal of spent
nuclear fuel allows improved design efficiency and reduced cost due to the large mass of fissile
material that will be present in the repository. Burnup-credit calculations are based on depletion
calculations that provide a conservative estimate of spent fuel contents (in terms of criticality
potential), followed by criticality calculations to assess the value of the effective neutron

burnup credit pwr spent fuel criticality safety ornl/tm-1999/99 parametric analysis depletion parameters used fuel

Nuclide Importance to Criticality Safety, Decay Heating, and Source Terms Related to Transport and Interim Storage of High-Burnup LWR Fuel

Nuclide Importance to Criticality Safety, Decay Heating, and Source Terms Related to Transport and Interim Storage of High-Burnup LWR Fuel

Author(s)
Ryman, J. C. ,
Gauld, I. C.
Publication Date

This report investigates trends in the radiological decay properties and changes in relative nuclide importance associated with increasing enrichments and burnup for spent LWR fuel as they affect the areas of criticality safety, thermal analysis (decay heat), and shielding analysis of spent fuel transport and storage casks. To facilitate identifying the changes in the spent fuel compositions that most directly impact these application areas, the dominant nuclides in each area have been identified and ranked by importance.

burnup credit criticality safety nureg/cr-6700 ornl/tm-2000/284 decay heating source terms high burnup

slides - CFD Best Practice Guidelines (NUREG-2152), Thermal Modeling Issues, and Generic Communications Related to Vacuum Drying Operations

slides - CFD Best Practice Guidelines (NUREG-2152), Thermal Modeling Issues, and Generic Communications Related to Vacuum Drying Operations

Author(s)
Solis, J.
Publication Date

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013

slides nei used fuel management meeting cfd thermal modeling vacuum drying
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: