Calculation of the radionuclides in PWR spent fuel samples for SFR experiment planning.

Technical Report · Tue Jun 01 04:00:00 EDT 2004

DOI:https://doi.org/10.2172/919122· OSTI ID:919122

Naegeli, Robert Earl

This report documents the calculation of radionuclide content in the pressurized water reactor (PWR) spent fuel samples planned for use in the Spent Fuel Ratio (SPR) Experiments at Sandia National Laboratories, Albuquerque, New Mexico (SNL) to aid in experiment planning. The calculation methods using the ORIGEN2 and ORIGEN-ARP computer codes and the input modeling of the planned PWR spent fuel from the H. B. Robinson and the Surry nuclear power plants are discussed. The safety hazards for the calculated nuclide inventories in the spent fuel samples are characterized by the potential airborne dose and by the portion of the nuclear facility hazard category 2 and 3 thresholds that the experiment samples would present. In addition, the gamma ray photon energy source for the nuclide inventories is tabulated to facilitate subsequent calculation of the direct and shielded dose rates expected from the samples. The relative hazards of the high burnup 72 gigawatt-day per metric ton of uranium (GWd/MTU) spent fuel from H. B. Robinson and the medium burnup 36 GWd/MTU spent fuel from Surry are compared against a parametric calculation of various fuel burnups to assess the potential for higher hazard PWR fuel samples.

• Research Organization: Sandia National Laboratories
• Sponsoring Organization: USDOE
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 919122
• Report Number(s): SAND2004-2757
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CALCULATION METHODS
COMPUTER CODES
DOSE RATES
ENERGY SOURCES
EXPERIMENT PLANNING
NEW MEXICO
NUCLEAR POWER PLANTS
PWR TYPE REACTORS
Pressurized water reactors.
Radionuclide migration-Calculations.
SANDIA NATIONAL LABORATORIES
SPENT FUELS