Rewetting of composite slab
Description
The process of re-establishment of wetting of hot surface is of practical importance in chemical, metallurgical and nuclear industries. Rewetting is considered in emergency core cooling in nuclear reactors in the event of postulated loss of coolant accident (LOCA). This paper deals with numerical solution of the two-dimensional quasi-static conduction controlled rewetting of an infinite parallel sided composite slab assuming perfect contact is maintained at the interface. On the wetted side upstream of the quench front, a constant heat transfer coefficient is assumed. The downstream of quench front and unwetted side of slab are supposed to be adiabatic. The solution gives the quench front temperature as a function of various model parameters such as Peclet number, wet side Blot number, dimensionless thickness of slab and cladding to fuel ratio of thermal conductivities. The results show that for large values of rewetting velocities, the dimensionless rewetting temperature is unaffected by fuel properties for all values of Blot numbers. (author). 7 refs., 2 tabs., 1 fig
Additional details
Publishing Information
- Publisher
- Tata McGraw-Hill Publishing Company Limited.
- Imprint Place
- New Delhi (India)
- ISBN
- 0-07-462307-9
- Imprint Title
- Heat and mass transfer 95
- Imprint Pagination
- 975 p.
- Journal Page Range
- p. 185-189.
Conference
- Title
- 2. ISHMT-ASME heat and mass transfer conference; 13. national heat and mass transfer conference.
- Dates
- 28-30 Dec 1995.
- Place
- Surathkal (India).
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 27075570
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOUNDARY CONDITIONS; BWR TYPE REACTORS; COMPOSITE MATERIALS; FUEL-CLADDING INTERACTIONS; LOSS OF COOLANT; MATHEMATICAL MODELS; PWR TYPE REACTORS; QUENCHING; REWETTING; SLABS; TEMPERATURE CONTROL; THERMAL CONDUCTION
- Descriptors DEC
- ACCIDENTS; CONTROL; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; HEAT TREATMENTS; MATERIALS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS