Published June 1993
| Version v1
Journal article
Simulating experiment and study of transient CHF and time to crisis CHF during small break LOCA in PWR
Description
Critical Heat Flux (CHF) is an important physical phenomenon in PWR. Time to crisis CHF (tCHF) determines the time to start reactor safety system when LOCA occurs in PWR. The transients CHF and tCHF by using simulating blowdown of small break LOCA in PWR are studied and the quantitative results are given. The experiment parameters as follows: P = 0.7 ∼ 2.2 MPa; ΔTsub = 50 ∼ 120 degree C; G = 1750 ∼ 2800 kg/m2s; q = 0.3 ∼ 1 x 106 W/m2
Additional details
Publishing Information
- Journal Title
- Chinese Journal of Nuclear Science and Engineering
- Journal Volume
- 13
- Journal Issue
- 2
- Journal Page Range
- p. 126-134.
- ISSN
- 0258-0918
- CODEN
- HYGODG
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 25040442
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BENCH-SCALE EXPERIMENTS; CRITICAL HEAT FLUX; DATA PROCESSING; DEPARTURE NUCLEATE BOILING; EXPERIMENTAL DATA; LOSS OF COOLANT; MATHEMATICAL MODELS; PWR TYPE REACTORS; SIMULATION; TIME DEPENDENCE; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BOILING; DATA; ENRICHED URANIUM REACTORS; HEAT FLUX; INFORMATION; NUCLEATE BOILING; NUMERICAL DATA; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS