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