Published December 1984 | Version v1
Report

Results and analysis of reactor-material experiments on ex-vessel corium quench and dispersal

  • 1. Argonne National Lab., IL (USA)
  • 2. Electric Power Research Inst., Palo Alto, CA (USA)

Description

The results of reactor material experiments and related analysis are described in which molten corium is injected into a mock-up of the reactor cavity region of a PWR. The experiments address exvessel interactions such as steam generation (for those cases in which water is present), water and corium dispersal from the cavity, hydrogen generation, direct atmosphere heating by dispersed corium, and debrids characterization. Test results indicate efficiencies of steam generation by corium quench ranging up to 65%. Corium sweepout of up to 62% of the injected material was found for those conditions in which steam generation flowrate was augmented by vessel blowdown. The dispersed corium caused very little direct heating of the atmosphere for the configuration employing a trap at the exit of the cavity-to-containment pathway. Corium sweepout phenomena were modeled for high-pressure blowdown conditions, and the results applied to the full-size reactor system predict essentially complete sweepout of corium from the reactor cavity. (orig.)

Additional details

Publishing Information

Imprint Title
5th international meeting on thermal nuclear reactor safety. Proceedings. Vol. 2
Imprint Pagination
664 p.
Journal Page Range
p. 1079-1089.
Report number
KFK--3880/2

Conference

Title
5. international meeting on thermal nuclear reactor safety.
Dates
9-13 Sep 1984.
Place
Karlsruhe (Germany, F.R.).