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 spent-fuel 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.

Issue Section:
Research Papers
Keywords:
silicon carbide, detectors, semiconductor, spent fuel, neutrons, gamma rays, burnup

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, work in progress under research supported by the Office of Science (BER),
United States Department of Energy
, Grant No. DE-FG02-04ER63734.
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