Irradiation damage analysis on the flat plate type target plate of the divertor for fusion experimental reactors

Ishiyama, Shintaro; Akiba, Masato; Eto, Minoru

doi:10.1016/0022-3115(96)00004-9

Cited by 3 publications

(3 citation statements)

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“…In the present analysis, C / C armor is bonded to the OFHC substrate in such a way that the fiber alignment direction is perpendicular to the bonded interface< 7 ).…”

Section: Modeling and Calculation Proceduresmentioning

confidence: 99%

“…The Plasma Facing Components (PFCs) of fusion experimental reactors, such as the divertor component, will be subjected to high energy neutron and high power heat loading of the order of 15 MW /m 2 < 1 )- ( 7 ). Therefore irradiation and heat loading damages on PFCs are very serious problems for the divertor designs.…”

Section: Introductionmentioning

confidence: 99%

“…Therefore irradiation and heat loading damages on PFCs are very serious problems for the divertor designs. The problems of the PFCs structure under high heat loading in fusion reactors were discussed< 1 )-C 5 ) and the authors already reported< 6 ) irradiation damage on the target plate structure under high heat loading with irradiation and discussed to prolong the "life-time" of the structure< 7 ).…”

Section: Introductionmentioning

confidence: 99%

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Thermal and Irradiation Induced Stress Analysis on Relevant Target Plate Structure of the Divertor for Fusion Experimental Reactors

Ishiyama

Akiba

Eto

2000

Journal of Nuclear Science and Technology

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This paper presents finite element analytical results of the thermal and irradiation induced stresses occurred in the target plate of the divertor structures which are exposed to neutron irradiation at 0-1 dpa with high heat flux up to 15 MW /m 2 . Three types of target plate models are studied in the present work, e.g., flat plate, saddle and mono-block type models which have bonded structures of one-dimensional high thermal conductivity Carbon-Carbon (C/C) composite material and Oxygen-Free-High Conductivity Copper (OFHC). With these results, it is concluded that flat model exhibits the longer life-time up to 1 dpa under 15 MW /m 2 , whereas serious troubles, such as fracture in bonded interface or drop-off of armor tile from bonded substrate, are expected in saddle and mono-block type models before 1 dpa. Design change with reduction of the volume of armor region in the model is also effective to prolong the life-time by the reduction of sublimation of armor material.

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“…In the present analysis, C / C armor is bonded to the OFHC substrate in such a way that the fiber alignment direction is perpendicular to the bonded interface< 7 ).…”

Section: Modeling and Calculation Proceduresmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%