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PRESENT STATUS OF RESEARCH AND DEVELOPMENT ON CRYOSORPTION PANELS FOR HELIUM PUMPING.

[In Japanese. / En japonais.]

Author(s) : NAKAMURA K., MURAKAMI Y.

Type of article: Article

Summary

SINCE TOKAMAK FUSION EXPERIMENTAL REACTORS TRY TO SUSTAIN 100-200 SECOND D-T BURNING, HELIUM EXHAUST FROM PLASMA CORE IS ONE OF THE MAJOR ISSUES OF THE TOKAMAK REACTORS. A VERY LARGE PUMPING SYSTEM IS REQUIRED FOR THE HELIUM AND FUEL PUMPING. THE CRYOSORPTION PUMP WITH 4.2 K PANELS IS CONSIDERED BUT THE PUMP MAY NOT BE ABLE TO ACCOMMODATE HELIUM-HYDROGEN ISOTOPE MIXTURES, BECAUSE CONDENSED DEUTERIUM AND TRITIUM WILL BLOCK THE ADSORBENT SURFACE AND PREVENT HELIUM PUMPING. IN THE CRYOPUMPS, IT IS NECESSARY TO RECOVER THE PUMPED GASES AS QUICKLY AS POSSIBLE IN ORDER TO ACHIEVE LOW INVENTORIES OF TRITIUM. THE REGENERATION CYCLE WILL BE DETERMINED BY CONSIDERING SEVERAL ITEMS WHICH INCLUDE TRITIUM INVENTORY AND SAFETY PROBLEMS.

Details

  • Original title: [In Japanese. / En japonais.]
  • Record ID : 1983-2074
  • Languages: Japanese
  • Publication date: 1983
  • Source: Source: Cryog. Eng.
    vol. 18; n. 2; 49-56; 10 fig.; 3 tabl.; 21 ref.
  • Document available for consultation in the library of the IIR headquarters only.

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