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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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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Abstract 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.
AbstractList 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.
Author Berry, H.C.
Lazareth, O.W.
Goland, A.N.
Dell, G.F.
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CitedBy_id crossref_primary_10_1016_0022_3115_81_90491_8
crossref_primary_10_1016_j_fusengdes_2013_01_063
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Cites_doi 10.1063/1.1702438
10.1063/1.1735307
10.1016/0029-554X(77)90559-6
10.1103/PhysRevLett.27.1288
10.1039/DF9613100130
10.1080/00337577608233025
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Kelly (BIB10) 1966
Persiani, Becker, Donahue (BIB3) July 1977
Coltman, Klabunde, McDonald, Redman (BIB9) 1962; 33
Parkin, Goland (BIB5) 1976; 28
Oen, Holmes (BIB11) 1959; 30
Parkin, Coulter (BIB6) Jan.–March 1978
Compton, Arnold (BIB8) 1961; 31
Pells, Phillips (BIB7) August 1978
Alsmiller, Barish (BIB4) August 1978
Saltmarsh, Ludemann, Fulmer, Styles (BIB2) 1977; 145
Coltman (10.1016/0022-3115(79)90518-X_BIB9) 1962; 33
Alsmiller (10.1016/0022-3115(79)90518-X_BIB4) 1978
Parkin (10.1016/0022-3115(79)90518-X_BIB6) 1978
Compton (10.1016/0022-3115(79)90518-X_BIB8) 1961; 31
(10.1016/0022-3115(79)90518-X_BIB1) 1976
Persiani (10.1016/0022-3115(79)90518-X_BIB3) 1977
Pells (10.1016/0022-3115(79)90518-X_BIB7) 1978
Oen (10.1016/0022-3115(79)90518-X_BIB11) 1959; 30
Kelly (10.1016/0022-3115(79)90518-X_BIB10) 1966
Smoluchowski (10.1016/0022-3115(79)90518-X_BIB12) 1971; 27
Saltmarsh (10.1016/0022-3115(79)90518-X_BIB2) 1977; 145
Parkin (10.1016/0022-3115(79)90518-X_BIB5) 1976; 28
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  doi: 10.1080/00337577608233025
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Snippet 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....
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Title Calculation of radiation damage in insulators for fusion reactors
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