Critical heat flux for downward-facing pool boiling on CANDU calandria tube surface
Creators
Description
Highlights: • Pressure tube-calandria tube contact may challenge fuel channel integrity in CANDU. • Critical heat flux variation is predicted on the outer surface of CANDU calandria tube. • A two-phase boundary layer flow driven by buoyancy is modeled on the surface. • Different slip ratios and flow regimes are considered inside the boundary layer. • Subcooling effects are added to the model using wall heat flux partitioning. - Abstract: One accident scenario in CANDU reactors that can challenge the integrity of the primary pressure boundary is a loss of coolant accident, referred to as critical break LOCA, in which the pressure tube (PT) can undergo thermal creep strain deformation and contact its calandria tube (CT). In such case, rapid redistribution of stored heat from PT to CT, leads to a large spike in heat flux to the moderator which can cause bubble accumulation and dryout on the CT surface. A challenge to fuel channel integrity is posed if critical heat flux occurs on the surface of the CT and results in sustained film boiling. If the post-dryout temperature becomes sufficiently high then continued creep strain of the PT and CT may lead to fuel channel failure. In this study, a mechanistic model is developed to predict the critical heat flux variations along the downward facing outer surface of CT. The hydrodynamic model considers a liquid macrolayer beneath an elongated vapor slug on the surface. Local dryout is postulated to occur whenever the fresh liquid supply to the macrolayer is not sufficient to compensate for the liquid depletion. A boundary layer analysis is performed, treating the two phase motion as an external buoyancy driven flow. The model shows good agreement with the available experimental data and has been modified to take into account the effect of subcooling.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2017.02.017Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2017.02.017;
- PII
- S0029-5493(17)30075-4;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 315
- Journal Page Range
- p. 104-116
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48062623
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BOUNDARY LAYERS; BUBBLES; CALANDRIAS; CANDU TYPE REACTORS; CREEP; CRITICAL HEAT FLUX; DRYOUT; EXPERIMENTAL DATA; FILM BOILING; FUEL CHANNELS; HYDRODYNAMIC MODEL; LOSS OF COOLANT; MODERATORS; POOL BOILING; PRESSURE TUBES; SLIP RATIO; STRAINS; SUBCOOLING
- Descriptors DEC
- ACCIDENTS; BOILING; CONTAINERS; COOLING; DATA; DIMENSIONLESS NUMBERS; HEAT FLUX; HEAVY WATER MODERATED REACTORS; INFORMATION; LAYERS; MATHEMATICAL MODELS; MECHANICAL PROPERTIES; NUMERICAL DATA; PARTICLE MODELS; PHASE TRANSFORMATIONS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; STATISTICAL MODELS; THERMAL REACTORS; THERMODYNAMIC MODEL; TUBES
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.