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Spent Fuel Monitoring with Silicon Carbide Semiconductor Neutron/Gamma Detectors
J. G. Seidel
T. Natsume
H. Doi
A. R. Dulloo
F. H. Ruddy
出版
ASTM International
, 2006
URL
http://books.google.com.hk/books?id=R815zgEACAAJ&hl=&source=gbs_api
註釋
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.
