Calculations of the Skyshine Gamma-Ray Dose Rates from Independent Spent Fuel Storage Installations (ISFSI) under Worst Case Accident Conditions

Technical Report · Mon Sep 01 00:00:00 EDT 1980

DOI:https://doi.org/10.2172/5203797· OSTI ID:5203797

Pace, III, J. V. ^[1]; Cramer, S. N. ^[1]; Knight, J. R. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Calculations of the skyshine gamma-ray dose rates from three spent fuel storage pools under worst case accident conditions have been made using the discrete ordinates code DOT-IV and the Monte Carlo code MORSE and have been compared to those of two previous methods. The DNA 37N-21G group cross-section library was utilized in the calculations, together with the Claiborne-Trubey gamma-ray dose factors taken from the same library. Plots of all results are presented. It was found that the dose was a strong function of the iron thickness over the fuel assemblies, the initial angular distribution of the emitted radiation, and the photon source near the top of the assemblies.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USNRC; USDOE
• DOE Contract Number: AC05-84OR21400; W-7405-ENG-26
• OSTI ID: 5203797
• Report Number(s): NUREG/CR--0723; ORNL/NUREG/TM--316; ON: TI86000143
• Country of Publication: United States
• Language: English

Related Subjects

052002* -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
61 RADIATION PROTECTION AND DOSIMETRY
ACCIDENTS
COMPUTERIZED SIMULATION
DOSE RATES
ELECTROMAGNETIC RADIATION
FUEL POOLS
GAMMA RADIATION
GAMMA TRANSPORT THEORY
IONIZING RADIATIONS
MATHEMATICAL MODELS
MONTE CARLO METHOD
RADIATION ACCIDENTS
RADIATIONS
SIMULATION
SPENT FUEL STORAGE
STORAGE
THREE-DIMENSIONAL CALCULATIONS
TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS