Calculation of radiation damage in insulators for fusion reactors

The MORSE neutron transport code has been used to characterize the neutron and gamma ray fluxes in a typical irradiation cave from a Li(d,n) neutron source. Recoil-atom damage and gas generation have been evaluated for Al2O3 and Si3N4 using the damage program DON.

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Bibliographic Details
Published inJournal of nuclear materials Vol. 85-86; pp. 373 - 377
Main Authors Dell, G.F., Berry, H.C., Goland, A.N., Lazareth, O.W.
Format Journal Article
LanguageEnglish
Published Elsevier B.V 02.12.1979
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Summary:The MORSE neutron transport code has been used to characterize the neutron and gamma ray fluxes in a typical irradiation cave from a Li(d,n) neutron source. Recoil-atom damage and gas generation have been evaluated for Al2O3 and Si3N4 using the damage program DON.
ISSN:0022-3115
1873-4820
DOI:10.1016/0022-3115(79)90518-X