Published October 1980
| Version v1
Report
Problems in modeling of small break LOCA. Technial report
Description
The report deals with: (1) two-phase flow regime transitions, (2) liquid entrainment in break flow, (3) vapor pull-through, and (4) CCFL in horizontal ducts. The first three processes influence the mass flow through the break, whereas the fourth one imposes a limit on liquid flow from the steam generator through the hot leg break into the core. Correlations available in the literature which deal with these processes are presented and applied to a hot leg of a PWR, LOFT and Semiscale for quantitative estimates, as well as for determining the scale distortion in the latter two facilities
Availability note (English)
Available from NTIS., PC A05/MF A01.Additional details
Publishing Information
- Imprint Pagination
- 91 p.
- Report number
- NUREG--0724
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12632482
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- DUCTS; LOSS OF COOLANT; MATHEMATICAL MODELS; PIPES; PWR TYPE REACTORS; REACTOR CORES; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; FLUID FLOW; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS