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Fast Neutron Dosimetry and Spectrometry Using Silicon Carbide Semiconductor Detectors
Ruddy Frank, Seidel John, Dulloo Abdul


Pages: 8    Published: Jan 2007


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Source: STP1490-EB


Abstract
Silicon carbide semiconductor neutron detectors have been irradiated with Cf fission neutrons, thermal-neutron induced fission neutrons from U, and 14-MeV neutrons from a deuterium-tritium neutron generator. In the latter case, reaction peaks corresponding to C(n,)Be and Si(n,)Mg reactions have been observed. Multiple reaction branches to the Mg ground state and several excited states are observed for the Si(n, )Mg reaction, and the detector energy calibration for these reactions can be derived from the peak positions. Although only the ground state branch is observed for the C(n,)Be reaction, the shift of the reaction energy with angle relative to the 14-MeV source can be used to derive an energy scale based on this reaction. These energy response measurements will form the basis for neutron spectrum unfolding methods for inferring incident neutron energy spectra from the resulting recoil-ion energy spectra in silicon carbide detectors.


Keywords:
silicon carbide, semiconductor, neutrons, detector, spectrometry, dosimetry

Paper ID: STP45469S
Committee/Subcommittee: E10.08
DOI: 10.1520/STP45469S
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