Published 1992
| Version v1
Book
Heat transfer and voidage measurements in steady state post-dryout at low quality and high pressure
Description
Steady state post-dryout heat transfer and voidage data have been obtained at pressures up to 70 bar and flows up to 1000 kg/m2s inside a vertical tube. The data were obtained with steam/water using a directly heated hot notch test section. Heat flux and voidage data are presented. The data are used to investigate aspects of the TRAC-PF1/MOD2 version 5.3 reflood model and are compared against heat transfer models used in it. (8 figures) (Author)
Additional details
Publishing Information
- Publisher
- Institution of Chemical Engineers.
- Imprint Place
- Rugby (United Kingdom)
- ISBN
- 0 85295 282 1
- Imprint Title
- Heat transfer. V. 1
- Imprint Pagination
- 724 p. (v.1-2).
- Journal Issue
- no. 129
- Series
- Institution of Chemical Engineers Symposium Series.
- Journal Page Range
- p. 607-615.
Conference
- Title
- 3. UK national conference incorporating 1. European conference on thermal sciences.
- Dates
- 16-18 Sep 1992.
- Place
- Birmingham (United Kingdom).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 25031722
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DRYOUT; FLOW RATE; HEAT FLUX; HEAT TRANSFER; LOSS OF COOLANT; MATHEMATICAL MODELS; PWR TYPE REACTORS; STEAM; T CODES; TUBES; VOID FRACTION; WATER
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS