Results of scoping tests in corium-water thermal interactions in ex-vessel geometry
Journal Article
·
· AIChE Symp. Ser.; (United States)
OSTI ID:5420608
Results of scoping tests are reported which were performed in the ANL/EPRI Corium Ex-vessel interactions (COREXIT) Facility located at ANL. These tests are examining issues related to containment loading (i.e., steam generation, H/sub 2/ production, and debris dispersal) for hypothetical LWR accidents that are postulated to progress to the point of molten corium breaching the vessel bottom head and entering the reactor cavity. The geometry selected for these tests is a 1 : 30 linear scale of the Zion PWR containment design in which the cavity is connected to the containment volume by an open tunnel through which pass the in-core detector guide tubes. The effects of the corium-water mixing modes were investigated in the first two tests in the series. In test CWTI-1 the molten corium was ejected into water which filled the cavity mockup volume to one-half the passageway height. In CWTI-2, the molten corium was dropped atop the refractory base in the cavity mockup without the presence of water, and water was injected atop the corium melt immediately afterward as per accumulator discharge. These tests have shown significant differences in fuel fragmentation, steam generation rate, hydrogen production, and fuel dispersal. Particularly noteworthy was the significant amount of dispersal of both water and corium debris from the cavity mockup due to the initially rapid steam generation rate in CWTI-1.
- Research Organization:
- Argonne National Laboratory, Argonne, IL
- OSTI ID:
- 5420608
- Journal Information:
- AIChE Symp. Ser.; (United States), Journal Name: AIChE Symp. Ser.; (United States) Vol. 79:225; ISSN ACSSC
- Country of Publication:
- United States
- Language:
- English
Similar Records
Debris dispersal in reactor material experiments on corium-water thermal interactions in ex-vessel geometry
Results and analysis of reactor-material experiments on ex-vessel corium quench and dispersal
Corium droplet size in direct containment heating
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6474107
Results and analysis of reactor-material experiments on ex-vessel corium quench and dispersal
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6504026
Corium droplet size in direct containment heating
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6818784
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CORIUM
ENERGY TRANSFER
FISSION PRODUCTS
HEAT TRANSFER
HYDROGEN COMPOUNDS
HYDROGEN PRODUCTION
ISOTOPES
MATERIALS
MELTDOWN
MIXING
MOLTEN METAL-WATER REACTIONS
OXYGEN COMPOUNDS
PRODUCTION
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTORS
STEAM
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CORIUM
ENERGY TRANSFER
FISSION PRODUCTS
HEAT TRANSFER
HYDROGEN COMPOUNDS
HYDROGEN PRODUCTION
ISOTOPES
MATERIALS
MELTDOWN
MIXING
MOLTEN METAL-WATER REACTIONS
OXYGEN COMPOUNDS
PRODUCTION
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTORS
STEAM
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS