Development of CHF models for inner and outer RPV gaps in a meltdown severe accident
Description
Highlights: • A CHF model was developed to predict the CHF in hemispherical narrow gap. • The computed result was validated by the test data of Park and Köhler. • An analytical CHF model was developed to predict the CHF on the outer surface of the lower head. • The predicted CHF was compared with the experimental data of ULPU-V. • Two CHF models developed for the inner and outer CHF predict the CHF well. - Abstract: During a severe accident, the core melt relocates in the lower head and a hemispherical narrow gap may appear between the crust and the lower head because of the different material expansion ratio. The existence of this gap is very important to the integrity of the lower head. Based on the counter current flow limitation (CCFL) between the vapor phase and the liquid phase, a CHF model was developed to predict the CHF in hemispherical narrow gap. The CHF model developed was validated by the test data of Park and Köhler. The effect of key parameters, including the system pressure, radius of melt, and gap size, on the CHF were investigated. And the TMI-2 accident was also calculated by using the CHF formula. Moreover, based on the interface separation model, an analytical CHF model was developed to predict the CHF on the outer surface of the lower head. The predicted CHF was compared with the experimental data of ULPU-V. It indicated that the CHF models developed for the inner and outer CHF could predict the CHF well
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2013.07.035Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2013.07.035;
- PII
- S0029-5493(13)00510-4;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 265
- Journal Page Range
- p. 1045-1056
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46008787
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COUNTER CURRENT; CRITICAL HEAT FLUX; EXPERIMENTAL DATA; LIQUIDS; MELTDOWN; PRESSURE VESSELS; TEST FACILITIES; VAPORS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; DATA; EVALUATION; FLUIDS; GASES; HEAT FLUX; INFORMATION; NUMERICAL DATA; REACTOR ACCIDENTS
Optional Information
- Copyright
- Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.