Fragmentation and quench behavior of corium melt streams in water
- Argonne National Lab., IL (United States)
- Illinois Univ., Urbana, IL (United States). Dept. of Nuclear Engineering
The interaction of molten core materials with water has been investigated for the pour stream mixing mode. This interaction plays a crucial role during the later stages of in-vessel core melt progression inside a light water reactor such as during the TMI-2 accident. The key issues which arise during the molten core relocation include: (i) the thermal attack and possible damage to the RPV lower head from the impinging molten fuel stream and/or the debris bed, (ii) the molten fuel relocation pathways including the effects of redistribution due to core support structure and the reactor lower internals, (iii) the quench rate of the molten fuel through the water in the lower plenum, (iv) the steam generation and hydrogen generation during the interaction, (v) the transient pressurization of the primary system, and (vi) the possibility of a steam explosion. In order to understand these issues, a series of six experiments (designated CCM-1 through {minus}6) was performed in which molten corium passed through a deep pool of water in a long, slender pour stream mode. Results discussed include the transient temperatures and pressures, the rate and magnitude of steam/hydrogen generation, and the posttest debris characteristics.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10136350
- Report Number(s):
- NUREG/CR-6133; ANL-93/32; ON: TI94009042; TRN: 94:006633
- Resource Relation:
- Other Information: PBD: Feb 1994
- Country of Publication:
- United States
- Language:
- English
Similar Records
Experimental observations of the breakup of multiple metal jets in a volatile liquid
Results of scoping tests in corium-water thermal interactions in ex-vessel geometry