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THERMO-HYDRAULIC MODEL TEST OF THE FIRST NUCLEAR SHIP REACTOR IN JAPAN

Thermohydraulic model tests were carried out to confirm that the first nuclear ship reactor in Japan was properly designed. Test models were a half-size core structural model, a full-size fuel assembly model and a half-size steam generator plenum model. Measured results were compared with the design calculation of the reactor and were found to be in good agreement with experiment. However, the pressure drop in the reactor vessel was overestimated, and correction was made on the system design. Also flow velocity distribution was found to be more distorted than expected in the fuel assembly, and design modification was made in the lower end plate. Flow coastdown in the primary loop and coolant mixing in the fuel assembly are also discussed.

  • Corporate Authors:

    North Holland Publishing Company

    68-70 N.Z. Voorburgwal, Box 103
    Amsterdam C,   Netherlands 
  • Authors:
    • Takada, Y
    • Yokomura, T
    • KUROSAWA, A
  • Publication Date: 1969-6

Media Info

Subject/Index Terms

Filing Info

  • Accession Number: 00005482
  • Record Type: Publication
  • Source Agency: Engineering Index
  • Files: TRIS
  • Created Date: Oct 30 1973 12:00AM