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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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  • "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."@en

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  • "Calculation of radiation damage in insulators for fusion reactors"@en