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

Technical Report · Mon Jun 19 00:00:00 EDT 1995

DOI:https://doi.org/10.2172/149989· OSTI ID:149989

Chandler, M C ^[1]; Ketusky, E T; Thoman, D C ^[2]

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1. Westinghouse Savannah River Co., Aiken, SC (United States)
2. SAIC (United States)

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.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 149989
• Report Number(s): WSRC-TR-94-0456; ON: DE96003205; TRN: 96:001411
• Resource Relation: Other Information: PBD: 19 Jun 1995
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
40 CHEMISTRY
SAVANNAH RIVER PLANT
SPENT FUELS
RADIOACTIVE WASTES
REPROCESSING
SLUDGES
RADIOCHEMICAL ANALYSIS
TARGETS
FISSION PRODUCTS
RADIOISOTOPES
DISTRIBUTION FUNCTIONS
RADIOACTIVE WASTE STORAGE
ACTINIDES
S CODES
G CODES
RADIATION DOSES
INGESTION
INHALATION
RADIONUCLIDE KINETICS
ENVIRONMENTAL EXPOSURE PATHWAY
TANKS
INVENTORIES