ISSN: 1546-962X
Page Count: 8

Spent Fuel Monitoring with Silicon Carbide Semiconductor Neutron/Gamma Detectors
Natsume, T
Mitsubishi Heavy Industries, LTD,

Doi, H
Nuclear Development Corporation,

Ruddy, FH
Westinghouse Electric Company, PA

Seidel, JG

Dulloo, AR

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.

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

Paper ID: JAI13430
DOI: 10.1520/JAI13430
ASTM International is a member of CrossRef.