Criticality safety evaluation report for the multi-canister overpack

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Description

This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both KE and KW Basins, and loaded into multiple canister overpack (MCO) containers with specially built baskets containing a maximum of either 54 Mark 1V or 48 Mark IA fuel assemblies. The criticality evaluations include loading baskets into the cask-MCO, operations at the Cold Vacuum Drying Facility, and storage in the Canister Storage Building. Many conservatisms have been built into this analysis, the primary one being the selection of the k{sub eff} = 0.95 criticality safety limit. Additional analyses in this revision include partial fuel ... continued below

Physical Description

135 pages

Creation Information

KESSLER, S.F. May 21, 1999.

Context

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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  • Hanford Site (Wash.)
    Publisher Info: HNF Hanford Site (United States)
    Place of Publication: United States

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Description

This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both KE and KW Basins, and loaded into multiple canister overpack (MCO) containers with specially built baskets containing a maximum of either 54 Mark 1V or 48 Mark IA fuel assemblies. The criticality evaluations include loading baskets into the cask-MCO, operations at the Cold Vacuum Drying Facility, and storage in the Canister Storage Building. Many conservatisms have been built into this analysis, the primary one being the selection of the k{sub eff} = 0.95 criticality safety limit. Additional analyses in this revision include partial fuel basket loadings, loading 26.1 inch Mark IA fuel assemblies into Mark IV fuel baskets, and the revised fuel and scrap basket designs. The MCO MCNP model was revised to include the shield plug assembly.

Physical Description

135 pages

Notes

INIS; OSTI as DE00782361

Source

  • Other Information: PBD: 21 May 1999

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Identifier

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  • Report No.: HNF--SD--SNF-CSER-005--REV4
  • Grant Number: AC06-96RL13200
  • DOI: 10.2172/782361 | External Link
  • Office of Scientific & Technical Information Report Number: 782361
  • Archival Resource Key: ark:/67531/metadc723496

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Office of Scientific & Technical Information Technical Reports

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Creation Date

  • May 21, 1999

Added to The UNT Digital Library

  • Sept. 29, 2015, 5:31 a.m.

Description Last Updated

  • April 27, 2016, 4:01 p.m.

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Citations, Rights, Re-Use

KESSLER, S.F. Criticality safety evaluation report for the multi-canister overpack, report, May 21, 1999; United States. (digital.library.unt.edu/ark:/67531/metadc723496/: accessed August 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.