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Graphite first wall thermal performance in ICF reactor
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Graphite first wall thermal performance in ICF reactor

H. Attaya, E. Lovell, R. Engelstad, R. Peterson, S. Abdel-Khalik, G. MosesG. Kulcinski
Journal of Nuclear Materials, 卷.141-143(PART 1), 頁碼.142-147
1986

摘要

Nuclear and High Energy Physics Materials Science (all) Nuclear Energy and Engineering
Graphite has been considered as a candidate material for the first wall in ICF reactors. This paper shows the thermal performance of the graphite first wall (GFW) in the 0.25 μm laser driven materials test reactor SIRIUS-M. The first wall temperature response due to the X-rays, reflected laser light, and ions that emanate from the 13.4 MJ yield target was calculated for dry GFWs which were either unprotected or gas protected. Evaporation rates and thermal stresses were calculated and minimum radii were chosen for both cases. It was found that the reflected laser light from the target produces the highest temperature rise in the gas protected GFW. If 10% of the laser light is reflected from the target and the reflectivity of graphite is 50%, the maximum thermal stress in the GFW is about 90% of the compressive strength for a 2 m radius cavity. Therefore, the viability of the first wall design depends critically on the laser light reflected from the target. the graphite reflectivity and the strength of the graphite. © 1986.

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