Abstract
The applicability of pitch-type carbon for thermal shielding in fusion devices was studied by estimating the degradation of its a-axis thermal conductivity on neutron irradiation at cryogenic temperatures. This was done by the use of, in part, the experimental data on unirradiated pitch carbon FRP specimens from which the pre-irradiation phonon relaxation time parameters were determined. The post-irradiation parameters were estimated by considering Frenkel pair formation due to irradiation with neutrons of an energy spectrum equivalent to that in the moderator of a fission reactor. The effective relaxation time was then determined by using all the parameters and the new thermal conductivity with its temperature dependency was calculated. From this analysis it is estimated that a pitch carbon based thermal shield would maintain a thermal conductivity superior to that of stainless steel for neutron irradiations up to 3×1018n/cm2.
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Rugaiganisa, B.M.S., Nishijima, S., Okada, T. (1996). Applicability of a Pitch Carbon FRP Thermal Shield Under Neutron Irradiation — a Theoretical Estimate. In: Summers, L.T. (eds) Advances in Cryogenic Engineering Materials . Advances in Cryogenic Engineering Materials , vol 42. Springer, Boston, MA. https://doi.org/10.1007/978-1-4757-9059-7_16
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DOI: https://doi.org/10.1007/978-1-4757-9059-7_16
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