Abstract
Electronic devices that are being designed for continuous monitoring of spent nuclear fuel (SNF) canister internal integrity may be subjected to very high radiation levels depending on their placement. Components of electronic devices (e.g., silicon semiconductors, optical glasses, insulators) have a limited tolerance to ionizing radiation. For selected locations on the inner and outer surfaces of a representative dry storage pressurized water reactor (PWR) SNF canister and a representative dry storage boiling water reactor (BWR) SNF canister, this paper provides (1) the dose rate in silicon as a function of decay time and (2) the time-integrated dose in silicon. The analyzed decay time interval is from 5 to 70 years after fuel discharge. Each representative canister contained identical SNF assemblies with bounding radiation sources. Surface dose rates varied significantly as a function of location and SNF assembly decay time. At a 5-year decay time, the estimated maximum dose rate values were 480 Gy/h (PWR canister) and ~366 Gy/h (BWR canister), and the estimated minimum dose rate was ~0.2 Gy/h for both canisters. Over a 65-year period, the dose rate decreased by a factor between 13 and 580, depending on location. The total dose over a time interval could be very large (e.g., estimated maximum value over a 5-year interval is 1.5E+07 Gy) depending on location and the time interval over which dose is accumulated.
Original language | English |
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Pages | 346-352 |
Number of pages | 7 |
State | Published - 2019 |
Event | 17th International High-Level Radioactive Waste Management Conference, IHLRWM 2019 - Knoxville, United States Duration: Apr 14 2019 → Apr 18 2019 |
Conference
Conference | 17th International High-Level Radioactive Waste Management Conference, IHLRWM 2019 |
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Country/Territory | United States |
City | Knoxville |
Period | 04/14/19 → 04/18/19 |
Funding
Notice: This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan). The sponsor of the work presented in this paper is the US Department of Energy, Office of Nuclear Energy.