SYMPOSIA PAPER Published: 01 January 1994

Effect of Neutron Irradiation on Thermal Conductivity of Carbon/Carbon Fiber Materials at 400 and 600°C in the Fluence Range 1 × 10 to 1 × 10 m


Because of their low atomic number and excellent thermal conductivity, carbon/ carbon fiber materials are seen as potential candidates for plasma-facing components, such as divertors, in Tokamak fusion devices. In the technology phase of Next European Torus (NET) or International Thermonuclear Experimental Reactor (ITER), the surface of a divertor will operate between 400 and 1000°C, and the materials will accumulate a lifetime neutron fluence equivalent to a dpa damage of 0.1. Low doses of neutron irradiation cause a significant decrease in the thermal conductivity of graphitic materials at low temperatures. To quantify the effect, candidate materials such as fine- and superfine-grained graphites (as reference materials), carbon/carbon fiber composites, and an oriented pyrolytic carbon (PyC) were irradiated at 400 and 600°C up to 0.1 dpa. At this fluence and at 400°C, the thermal conductivity (/) is reduced by 40 to 60%, whereas irradiation at 600°C caused a reduction of the l-values at irradiation temperature by about 20 to 40%. This spread seems to be caused by material differences but could be due to the uncertainties in the measurement and neutron fluence.

Author Information

Thiele, BA
Institute for Reactor Materials, Forschungszentrum Jülich, Jülich, Germany
Binkele, L
Institute for Reactor Materials, Forschungszentrum Jülich, Jülich, Germany
Koizlik, K
Institute for Reactor Materials, Forschungszentrum Jülich, Jülich, Germany
Nickel, H
Forschungszentrum Jülich, Jülich, Germany
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Developed by Committee: E10
Pages: 1304–1314
DOI: 10.1520/STP24006S
ISBN-EB: 978-0-8031-5262-5
ISBN-13: 978-0-8031-1488-3