Computed isotopic inventory and dose assessment for SRS fuel and target assemblies

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Past studies have identified and evaluated important radionuclide contributors to dose from reprocessed spent fuel sent to waste for Mark 16B and 22 fuel assemblies and for Mark 31 A and 31B target assemblies. Fission-product distributions after a 5- and 15-year decay time were calculated for a ``representative`` set of irradiation conditions (i.e., reactor power, irradiation time, and exposure) for each type of assembly. The numerical calculations were performed using the SHIELD/GLASS system of codes. The sludge and supernate source terms for dose were studied separately with the significant radionuclide contributors for each identified and evaluated. Dose analysis considered both ... continued below

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56 p.

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Chandler, M.C.; Ketusky, E.T. & Thoman, D.C. June 19, 1995.

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Description

Past studies have identified and evaluated important radionuclide contributors to dose from reprocessed spent fuel sent to waste for Mark 16B and 22 fuel assemblies and for Mark 31 A and 31B target assemblies. Fission-product distributions after a 5- and 15-year decay time were calculated for a ``representative`` set of irradiation conditions (i.e., reactor power, irradiation time, and exposure) for each type of assembly. The numerical calculations were performed using the SHIELD/GLASS system of codes. The sludge and supernate source terms for dose were studied separately with the significant radionuclide contributors for each identified and evaluated. Dose analysis considered both inhalation and ingestion pathways: The inhalation pathway was analyzed for both evaporative and volatile releases. Analysis of evaporative releases utilized release fractions for the individual radionuclides as defined in the ICRP-30 by DOE guidance. A release fraction of unity was assumed for each radionuclide under volatile-type releases, which would encompass internally initiated events (e.g., fires, explosions), process-initiated events, and externally initiated events. Radionuclides which contributed at least 1% to the overall dose were designated as significant contributors. The present analysis extends and complements the past analyses through considering a broader spectrum of fuel types and a wider range of irradiation conditions. The results provide for a more thorough understanding of the influences of fuel composition and irradiation parameters on fission product distributions (at 2 years or more). Additionally, the present work allows for a more comprehensive evaluation of radionuclide contributions to dose and an estimation of the variability in the radionuclide composition of the dose source term that results from the spent fuel sent to waste encompassing a broad spectrum of fuel compositions and irradiation conditions.

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56 p.

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INIS; OSTI as DE96003205

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  • Other Information: PBD: 19 Jun 1995

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  • Other: DE96003205
  • Report No.: WSRC-TR--94-0456
  • Grant Number: AC09-89SR18035
  • DOI: 10.2172/149989 | External Link
  • Office of Scientific & Technical Information Report Number: 149989
  • Archival Resource Key: ark:/67531/metadc624121

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  • June 19, 1995

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • Feb. 9, 2016, 8 p.m.

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Chandler, M.C.; Ketusky, E.T. & Thoman, D.C. Computed isotopic inventory and dose assessment for SRS fuel and target assemblies, report, June 19, 1995; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc624121/: accessed July 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.