Assessment of the capability of the existing heat transfer data base and of designated data sources to privide data over the calculated heat transfer variable ranges during a LOCA blowdown
Description
Data for transition boiling, film boiling and critical heat flux are compared to code calculated heat transfer variable ranges to determine whether the data are sufficient to support the calculations during the blowdown phase of a postulated loss of coolant accident. The data were selected from the Heat Transfer Data Bank. RELAP4/MOD5, RELAP4/MOD6 and TRAC-P1 calculated heat transfer variables of mass flux, pressure, quality, heat flux, and surface temperature are used in the study for the core and steam generator components of PWR and Semiscale systems. The various heat transfer regimes used by the codes for the core and steam generator are determined and a comparison of the usage is presented. Test facilities designated to provide heat transfer data during blowdown are evaluated with respect to their capability to provide data for heat transfer correlation development and testing. Conclusions and recomendations concerning the calculated heat transfer variable ranges and the data are presented
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A05/MF A01.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 88 p.
- Report number
- CAAP-TR--048
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11499828
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BLOWDOWN; COMPUTER CALCULATIONS; CRITICAL HEAT FLUX; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; HEAT FLUX; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS