THERMAL FATIGUE TESTS ON CVD-W CU DIVERTOR MOCK-UPS/

BOSCARY J SUZUKI S NAKAMURA K SUZUKI T AKIBA M

J. Boscary et al., THERMAL FATIGUE TESTS ON CVD-W CU DIVERTOR MOCK-UPS/, Fusion engineering and design, 39-4, 1998, pp. 537-542

8

INGLESE

Article

Nuclear Sciences & Tecnology

Fusion engineering and design → ACNP

0920-3796

39-4

1998

537 - 542

ISI

0920-3796(1998)39-4:<537:TFTOCC>2.0.ZU;2-0

Tungsten is a promising candidate for plasma-facing materials to cover the surface of the divertor plate in the design of the International Thermonuclear Experimental Reactor (ITER). The Japan Atomic Energy Res earch Institute (JAERI) has developed divertor mock-ups coated with tu ngsten using the chemical vapor deposition (CVD) technique. Thermal fa tigue and screening tests of ITER-relevant divertor mock-ups carried o ut in an electron beam gun facility are presented. The two mock-ups co nsist of a 2 mm thick CVD tungsten layer on heat sinks made of OFHC-Cu and 30 wt.% Cu-infiltrated tungsten, respectively. The cooling channe l is equipped with a twisted tape as heat transfer enhancement. Both m ock-ups successfully withstood a steady-state deposited heat flux of 5 MW m(-2) for 1000 cycles. These experiments show that CVD W-coated di vertor mock-ups meet ITER requirements for plasma-facing components. T hese tests also demonstrate the capability of these mock-ups to withst and a transient deposited heat flux of 22 MW m(-2) for 10 s without fa ilure. (C) 1998 Published by Elsevier Science S.A. All rights reserved .