High heat flux experiments of plasma facing components for next fusion devices

K. Nakamura, M. Akiba, S. Suzuki, K. Satoh, K. Yokoyama, M. Dairaku, M. Araki, Y. Ohara, T. Inoue, Y. Okumura, Ivica Smid

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Scopus citations

Abstract

To develop plasma facing components(PFC) for the next fusion devices, JAERI has been carrying out high heat flux and high particle flux experiments on the divertor modules and candidate materials in JAERI Electron Beam Irradiation System(JEBIS). 1) To investigate the feasibility and the advantage of a saddle type divertor modules, which has unidirectional(1-D) carbon fiber reinforced carbon composites(CFCs) armour tile brazed on OFHC-copper heat sink, high heat flux experiments have been carried out under a cyclic heat load of 24.5 MW/m2 at a duration of 30 s. After 1,000 cycles, no degradation of thermal response and no defect in the module was found. 2) To reduce the residual stress around the brazed interface, we have developed small specimens with the new materials combination of W-30Cu composites heat sink and 1-D CFC armour tile and carried out the high heat flux experiments under a cyclic heat load of 15 MW/m2 at a duration of 20 s. After 1,000 cycles, no cracks have been observed at the interface. 3) To evaluate the erosion of armour tiles by high heat flux, we have measured the erosion of CFCs and isotropic graphite up to 1,100 °C under a heat flux of 1,800 MW/m2 for the duration of 1.5approx.2 ms. It is clear that the erosion of carbon based materials increases with the bulk temperature and decreases with the thermal conductivity. 4) To evaluate the erosion by high particle flux, we have developed a new irradiation device, which have a high hydrogen particle flux of 1021/m2/s at 50approx.100 eV.

Original languageEnglish (US)
Title of host publicationProceedings - Symposium on Fusion Engineering
PublisherPubl by IEEE
Pages830-833
Number of pages4
ISBN (Print)0780314131
StatePublished - Dec 1 1993
EventProceedings of the 15th IEEE/NPSS Symposium on Fusion Engineering. Part 2 (of 2) - Hyannis, MA, USA
Duration: Oct 12 1993Oct 12 1993

Publication series

NameProceedings - Symposium on Fusion Engineering
Volume2

Other

OtherProceedings of the 15th IEEE/NPSS Symposium on Fusion Engineering. Part 2 (of 2)
CityHyannis, MA, USA
Period10/12/9310/12/93

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

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    Nakamura, K., Akiba, M., Suzuki, S., Satoh, K., Yokoyama, K., Dairaku, M., Araki, M., Ohara, Y., Inoue, T., Okumura, Y., & Smid, I. (1993). High heat flux experiments of plasma facing components for next fusion devices. In Proceedings - Symposium on Fusion Engineering (pp. 830-833). (Proceedings - Symposium on Fusion Engineering; Vol. 2). Publ by IEEE.