MCNP5 modeling of the Oregon State TRIGA Reactor for skyshine dose estimation after a loss of coolant accident Public Deposited

http://ir.library.oregonstate.edu/concern/graduate_thesis_or_dissertations/sq87bz54v

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  • This thesis evaluates dose rates from the TRIGA® reactor by comparing ion chamber measured exposure rates to exposure rates calculated from MCNP5 model data. The first step evaluates the energy distribution required to match ion chamber exposure rates from measurements taken at 1 foot increments above the reactor core. Next, the back calculated source activity is used to determine the exposure rates, at those same 1 ft increments above the core, in the event of a loss of coolant accident (LOCA). Then the energies deposited in simulated ion chambers, above the core are used to determine the dose rate to a person standing on top of the reactor bioshield after a LOCA. The dose rates that are calculated using the MCNP5 data were compared to calculations from the Oregon State TRIGA® Reactor (OSTR) Safety Analysis Report (SAR). The final step is to determine the maximum dose rate at the OSTR facility perimeter after a LOCA, due to skyshine. The MCNP5 results showed that OSTR SAR overestimates dose rates at the top of the reactor bioshield. The discrepancy stems from the OSTR SAR using worst case scenario data, while this report uses less conservative, yet accurate, assumptions. The instantaneous dose rates on the reactor building exterior from photon skyshine peak at approximately 30 mrem per hour. The integrated activity resulted in a dose rate of approximately .005 mrem within the first hour after the reactor has shut down.
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