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Spent Fuel Monitoring with Silicon Carbide Semiconductor Neutron/Gamma Detectors
Natsume T., Doi H., Ruddy F., Seidel J., Dulloo A.


Pages: 8    Published: Jan 2007


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Source: STP1490-EB


Abstract
Silicon carbide semiconductor radiation detectors have been demonstrated for neutron and gamma-ray monitoring of spent nuclear fuel. Neutrons and gamma rays were monitored simultaneously over a 2050-h period, resulting in a gamma dose of over 6000 Gy to the SiC detector. No changes in the neutron and gamma-ray sensitivity were observed as a result of the gamma-ray exposure. After the spentfuel measurements, the absolute neutron sensitivity was determined in a standard neutron field, and the degree of gamma-ray and neutron spectrum overlap were determined through exposures in intense gamma ray fields. No overlap was observed for gamma-ray dose rates up to 100 G/h.


Keywords:
silicon carbide, detectors, semiconductor, spent fuel, neutrons, gamma rays, burnup

Paper ID: STP45471S
Committee/Subcommittee: E10.07
DOI: 10.1520/STP45471S
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