An experimental study on feasibility of ex-vessel cooling through the external guide vessel
- 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Description
This paper presents the results of a series of experiments for assessing the efficacy of ex-vessel cooling through the external guide vessel during a severe accident. Four tests were performed in the LAVA test facility at KAERI, varying the boundary conditions at the outer surface of the vessel. The first test was a dry condition test conducted without cooling the outside of the vessel. On the other hand, in the second test, the cooling of the vessel surface was produced by gravity-driven forced injection of water along the annular gap of 25 mm between the vessel and the external guide vessel. Water flow rate was about 0.85 kg/s and total mass of available water was 300 kg. For the evaluation of the water flow rate effect, the third test was performed with a pool type cooling in the annulus without any circulation of water. These two external cooling tests were performed under elevated pressure of about 1.6 MPa. Finally, the fourth test was conducted under atmospheric pressure to evaluate the effect of system pressure on boiling heat transfer characteristics. In the dry test and the pool type ex-vessel cooling test performed under atmospheric pressure, the vessel was failed by a melt penetration at about 40 degree upper position from the vessel bottom, which is coincident with the boundary of the Al2O3/Fe melt separated layers. On the other hand, in both of the ex-vessel cooling tests conducted under elevated pressure of about 1.6 MPa, the vessel didn't fail. Compared with the pool boiling test, the vessel experienced effective cooling due to the inlet flow in the forced flow test. Synthesized the results of the tests, it was shown that the heat removal with ex-vessel cooling through the guide vessel is feasible, but the additional evaluations should be performed to guarantee enough thermal margin. (author)
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the workshop on severe accident research, Japan (SARJ-99)
- Imprint Pagination
- 377 p.
- Journal Page Range
- p. 167-173
- Report number
- JAERI-Conf--2000-015
Conference
- Title
- workshop on severe accident research, Japan
- Acronym
- SARJ-99
- Dates
- 8-10 Nov 1999
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 32026133
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM OXIDES; COOLING; CORIUM; FAILURES; FORCED CONVECTION; MELTDOWN; NUCLEAR POWER PLANTS; POOL BOILING; PRESSURE VESSELS; TEST FACILITIES
- Descriptors DEC
- ACCIDENTS; ALUMINIUM COMPOUNDS; BOILING; CHALCOGENIDES; CONTAINERS; CONVECTION; ENERGY TRANSFER; HEAT TRANSFER; MASS TRANSFER; NUCLEAR FACILITIES; OXIDES; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; POWER PLANTS; REACTOR ACCIDENTS; THERMAL POWER PLANTS
Optional Information
- Notes
- 7 refs., 7 figs.