Disposal criticality analysis methodology for fissile waste forms

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Description

A general methodology has been developed to evaluate the criticality potential of the wide range of waste forms planned for geologic disposal. The range of waste forms include commercial spent fuel, high level waste, DOE spent fuel (including highly enriched), MOX using weapons grade plutonium, and immobilized plutonium. The disposal of these waste forms will be in a container with sufficiently thick corrosion resistant barriers to prevent water penetration for up to 10,000 years. The criticality control for DOE spent fuel is primarily provided by neutron absorber material incorporated into the basket holding the individual assemblies. For the immobilized plutonium, ... continued below

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7 p.

Creation Information

Davis, J.W. & Gottlieb, P. March 1, 1998.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this report can be viewed below.

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  • Davis, J.W. Framatome Cogema Fuels, Las Vegas, NV (United States)
  • Gottlieb, P. TRW Environmental Safety Systems, Las Vegas, NV (United States)

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Description

A general methodology has been developed to evaluate the criticality potential of the wide range of waste forms planned for geologic disposal. The range of waste forms include commercial spent fuel, high level waste, DOE spent fuel (including highly enriched), MOX using weapons grade plutonium, and immobilized plutonium. The disposal of these waste forms will be in a container with sufficiently thick corrosion resistant barriers to prevent water penetration for up to 10,000 years. The criticality control for DOE spent fuel is primarily provided by neutron absorber material incorporated into the basket holding the individual assemblies. For the immobilized plutonium, the neutron absorber material is incorporated into the waste form itself. The disposal criticality analysis methodology includes the analysis of geochemical and physical processes that can breach the waste package and affect the waste forms within. The basic purpose of the methodology is to guide the criticality control features of the waste package design, and to demonstrate that the final design meets the criticality control licensing requirements. The methodology can also be extended to the analysis of criticality consequences (primarily increased radionuclide inventory), which will support the total performance assessment for the respository.

Physical Description

7 p.

Notes

INIS; OSTI as DE98005822

Source

  • Other Information: PBD: Mar 1998

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  • Other: DE98005822
  • Report No.: DOE/RW--98005822
  • DOI: 10.2172/658246 | External Link
  • Office of Scientific & Technical Information Report Number: 658246
  • Archival Resource Key: ark:/67531/metadc707118

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Creation Date

  • March 1, 1998

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • May 18, 2016, 5:41 p.m.

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Davis, J.W. & Gottlieb, P. Disposal criticality analysis methodology for fissile waste forms, report, March 1, 1998; United States. (digital.library.unt.edu/ark:/67531/metadc707118/: accessed August 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.