DocumentCode
807510
Title
Preparation of a Standard Technique for Determination of Neutron Equivalence for Bulk Damage in Silicon
Author
Green, M.L. ; Thatcher, R.K.
Author_Institution
Battelle Columbus Laboratories Columbus, Ohio 43201
Volume
19
Issue
6
fYear
1972
Firstpage
200
Lastpage
208
Abstract
This report defines how a neutron energy (1 MeV) equivalence should be calculated and the limitations of its utility. The differences in the l-MeV equivalence obtained by using Messenger´s expression for the damage curve is examined. An experiment was performed to verify the adequacy and utility of using l-MeV equivalence units to compare different neutron spectra. It is shown that for fission spectra close to a bare reactor that l-MeV equivalence provides a slight improvement in the correlation of data taken from devices irradiated at different reactors. However, this improvement in correlation did not extend to devices irradiated with 14 MeV neutrons. The devices irradiated in this experiment showed a fission/fusion fluence ratio for equal damage of about 1.7 rather than the expected value of 2.5.
Keywords
Accuracy; Design engineering; Dosimetry; Inductors; Laboratories; Mathematical model; Neutrons; Performance evaluation; Silicon; System testing;
fLanguage
English
Journal_Title
Nuclear Science, IEEE Transactions on
Publisher
ieee
ISSN
0018-9499
Type
jour
DOI
10.1109/TNS.1972.4326833
Filename
4326833
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