Materials for Advanced Energy Systems and Fission & Fusion Engineering: Proceedings of the Seventh China-Japan Symposium

Thermal Fatigue Study of W/Cu Joint

FU ZHANG, JIHONG WU, ZENGYU XU, YING XU
Southwestern Institute of Physics P. O. Box 432 Chengdu 610041 China
Email:
zhangf@swip.ac.cn

HHFC mock-ups with a structure of W/Cu/SS were developed by hot isostatic pressing (HIP). The performance of the W/Cu joint under high heat loads was tested using an electron beam. The size of specimens for heat load tests was 25 25 mm and the size of beam spot on the specimen surface was 22 mm in diameter. During heat load test, the specimens were water-cooled. Thermal fatigue test were conducted at power density of 8.7 MW/m 2 with pulse duration of 20 seconds and interval of 20 seconds. After 1000 cycles of tests, no cracks and failure were found in the W/Cu joint. The thermal performance was also investigated in the range of 1 ~ 9 MW/m 2.

1 INTRODUCTION

With the improvement of plasma confinement, tungsten is envisaged as the candidate armor material of high heat flux components (HHFC) in fusion reactors. CuCrZr alloy is largely studied as heat sink materials and stainless steel (SS) as back plate of the HHFC in recent works. [1 ,2 ] In the basic performance phase (BPP) of ITER, the divertor target plate will suffer high heat loads with power density of 5~10MW/m 2 of normal operations and ~20MW/m 2 of transient power excursions[3]. The joint of tungsten armor and Cu alloy heat sink is largely concerned of the performance under high heat loads. Electron beam...

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