Performance of jaeri electron beam irradiation stand

Akiba, Masato; Araki, M.; Suzuki, Satoshi; Tanaka, Shigeru; Dairaku, M.; Yokoyama, Kenji; Seki, Masanori

doi:10.1080/10519999108225538

Cited by 41 publications

(7 citation statements)

References 2 publications

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“…A number of electron beam facilities have been constructed, JUDITH 63) in Forschungszentrum Juelich (Germany), JEBIS, 64) OHBIS 62) in JAERI, ACT 65) in NIFS, EBHT 66) in Kyushu University (Japan), FE200 67) in CEA (France), TSEFFY 15) in Efremov Institute (Russia), EBTS, EB1200 21) in Sandia (USA), and an electron beam facility in SWIP (China). 68) In this paper, recent results of ITER relevant high heat flux testing performed by three of those electron beam facilities, JUDITH, JEBIS and OHBIS are mainly summarized.…”

Section: Static Heat Load Testing By Electron Beammentioning

confidence: 99%

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

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The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma facing materials. Since these materials are exposed to high heat fluxes during the operation, it is essential to perform high heat flux tests for R&D of ITER components. Static heat loads corresponding to cycling loads during normal operation, are estimated to be up to 20 MW/m 2 in the divertor targets and around 0.5 MW/m 2 at the first wall in ITER. For the static high heat flux testing, tests in electron beam facilities, particle beam facilities, IR heater and in-pile tests have been performed. Another type, more critical heat loads, which have high power densities and short durations, corresponding to transient events, i.e. plasma disruption, vertical displacement events (VDEs) and edge localized modes (ELMs) deliver considerable heat flux onto the plasma facing materials. For this purpose, tests in electron beam (short pulses), plasma gun and high power laser facilities have been carried out. The present work summarizes the features of these facilities and recent experimental results as well as the current selection of ITER plasma facing components.

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Section: Static Heat Load Testing By Electron Beammentioning

confidence: 99%

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

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“…High heat flux (HHF) experiments in the electron beam test facility, JEBIS, 10) were performed to clarify the thermal performance of the hot-pressed joint. A thermal response experiment was performed by using multiple armor blocks in the same mock-up.…”

Section: Thermal Response Experimentsmentioning

confidence: 99%

Proposal of Hot-pressed, Rod-shaped Tungsten Armor Concept for ITER Divertor and its High-heat-flux Performances

Sato¹,

Ezato²,

Takeuchi³

et al. 2005

Journal of Nuclear Science and Technology

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This paper describes the R&D of plasma facing components, especially the joining technology of the tungsten/copper joint for the ITER divertor application. The major concern for this joint is detachment due to the large differences in the thermal expansion coefficient and the modulus of elasticity of each metal. One solution is to separate the joint area into small pieces to reduce interfacial stress at the joint. From this viewpoint, JAERI proposes the hot-press method using small tungsten rods pressed into cylindrical bores in the copper substrate at high temperature. A divertor mock-up was fabricated to investigate the durability of this joint. No failures of the mock-up occurred in a thermal cycle experiment involving 3,000 cycles of 5 MW/m 2 heat flux. Using numerical analyses, the contact heat transfer coefficient between the tungsten and copper was determined to be 2,400 W/m 2 /K for this mock-up. Though this value is slightly inadequate to maintain the surface temperature below the recrystallization temperature of tungsten, it is significant that no embrittlement failures of the rod-shaped armor were observed. Further R&D is suggested to improve the hot-press method, including surface treatment of the rod faces or the use of insert material.

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“…The thermal fatigue experiments have been carried out at the repetitive incident heat fluxes of 20 and 30 MW/m 2 by using an electron beam irradiation facility in JAERI, JEBIS [3]. These heat flux conditions are set above the ITER divertor design values to simulate the transient plasma conditions [4].…”

Section: Experimental Studymentioning

confidence: 99%