Published 1979 | Version v1
Book

Field vibration test results and design for reactor coolant piping systems of ATR 'Fugen'

  • 1. Mitsubishi Atomic Power Industries, Inc., Omiya, Saitama (Japan). Nuclear Development Center
  • 2. Mitsubishi Heavy Industries Ltd., Takasago, Hyogo (Japan). Takasago Technical Inst.

Description

In most Japanese Nuclear Power Plants, the field vibration test on the important piping systems has been performed to verify the appropirateness of the seismic design and the integrity of the pipe work. For a prototype Heavy-Water Reactor 'FUGEN' (165-MWe heavy-water-moderated, boiling light-water-cooled pressure tube reactor, developed along one of the Japan's national projects, and reached criticality on March, 1978), the reactor coolant piping systems are connected with the pressure tube, the steam drums and the recirculation pumps. The steam drums are set in the top level and the recirculation pumps in the bottom level. This layout is complicated in comparing with other type of Reactors. The seismic analysis of the main piping systems in the FUGEN was performed by means of the model analysis method using the floor response spectrum. (orig.)

Additional details

Publishing Information

Publisher
North-Holland Publsihing Co.
Imprint Place
Amsterdam, Netherlands
ISBN
0444 85366 9
Imprint Title
Structural mechanics in reactor technology. Transactions. Vol. K(b)
Journal Page Range
p. K13/7 (1-9).

Conference

Title
5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2).
Dates
9 - 21 Aug 1979.
Place
Berlin, Germany, F.R.

Optional Information

Secondary number(s)
INKA-Conf--79-321-470.