Transient condensation heat transfer coefficient expressions during and after blowdown
Creators
- 1. Lawrence Livermore National Lab., CA (USA)
- 2. Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Koeln (Germany, F.R.)
Description
Analytical expressions are presented for calculating condensation heat transfer coefficients during and after blowdown at specific locations in a containment structure. A forced convention model is used during and immediately after blowdown when much turbulence exists, and a free convection model is used after blowdown end when the turbulence subsides. The forced convection expression depends primarily on a turbulent velocity relationship which is dependent on the distance from the break. The free convection expression depends on the wall-mixture temperature difference and the ratio of air partial pressure to total air-steam pressure. Experimental results were used to refine both of these expressions. Recommendations are given on how they are to be used. Calculations are compared with experimental values. (orig.)
Additional details
Publishing Information
- Imprint Title
- 5th international meeting on thermal nuclear reactor safety. Proceedings. Vol. 3
- Imprint Pagination
- 736 p.
- Journal Page Range
- p. 1850-1858.
- Report number
- KFK--3880/3
Conference
- Title
- 5. international meeting on thermal nuclear reactor safety.
- Dates
- 9-13 Sep 1984.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 16068364
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANALYTICAL SOLUTION; BLOWDOWN; BWR TYPE REACTORS; CONTAINMENT; FILM CONDENSATION; HEAT TRANSFER; LOSS OF COOLANT; PWR TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; VAPOR CONDENSATION; WATER COOLED REACTORS; WATER MODERATED REACTORS