HIGH HEAT-FLUX TESTING OF HIP BONDED DS-CU 316SS FIRST WALL PANEL FORFUSION EXPERIMENTAL REACTORS/

HATANO T SATO K DAIRAKU M KURODA T ARAKI M TAKATSU H SATO S FUKAYA K KURASAWA T TOKAMI I AKIBA M

T. Hatano et al., HIGH HEAT-FLUX TESTING OF HIP BONDED DS-CU 316SS FIRST WALL PANEL FORFUSION EXPERIMENTAL REACTORS/, Fusion technology, 30(3), 1996, pp. 752-756

2

INGLESE

Article

Nuclear Sciences & Tecnology

Fusion technology → ACNP

0748-1896

30

3

1996

2A

752 - 756

ISI

0748-1896(1996)30:3<752:HHTOHB>2.0.ZU;2-W

A shielding blanket design in a fusion reactor such as ITER (Internati onal Thermonuclear Experimental Reactor) has been proposed to be a mod ular structure integrated with the first wall. In terms of the fabrica tion, HIP (Hot Isostatic Pressing) method has been proposed for the jo ining of dispersion strengthened copper (DS-Cu) and type 316L stainles s steel (SS316L) at FW. High heat flux tests of HIP bonded DS-Cu/SS316 L first wall panel were performed at Particle Beam Engineering Facilit y in JAERI to investigate its thermo-mechanical performance. They cons isted of foul test campaigns. The former two campaigns simulated ITER normal operation conditions in terms of the temperature and strain at the HIP bonded interfaces between DS-Cu and SS316L, respectively. The latter two simulated disruption conditions. Under normal heat flux con ditions, temperature responses of the first wall panel measured by the thermocouples agreed very well with those predicted by FEM analyses. On the other hand, ejection of a number of small particles from DS-Cu surface was observed during the last campaign with the high heat flux simulating disruptions; After four campaigns of high heat flux testing , the FW panel was cut to observe the HIP bonded interface and heated surface of DS-Cu. Though melting of DS-Cu surface was observed, there were no cracks at the HIP bonded interface.