Published 1991
| Version v1
Book
Transient critical heat flux during loss of flow at high pressure
Creators
- 1. Institute of Nuclear Energy Research, Lung-Tan, Taiwan (China)
Description
An experimental study of flow transient critical heat flux (CHF) under the Light Water Reactor (LWR) conditions has been performed using the high pressure boiling loop at the Institute of Nuclear Energy Research (INER). The influence of flow decay rates on CHF is explored in the present study for the better understanding of CHF mechanisms. Based on local-condition hypothesis, the predictions of existing steady-state CHF correlations against the experimental data are presented under the simulation of the LWR flow transients. (author)
Additional details
Publishing Information
- Publisher
- Japan Society of Multiphase Flow.
- Imprint Place
- Ashiya, Hyogo (Japan)
- Imprint Title
- Proceedings of the international conference on multiphase flows '91-Tsukuba
- Imprint Pagination
- 1319 p.
- Journal Page Range
- v. 1 p. 47-50.
Conference
- Title
- international conference on multiphase flows.
- Acronym
- ICMF '91
- Dates
- 24-27 Sep 1991.
- Place
- Tsukuba, Ibaraki (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 24054678
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CORRELATIONS; CRITICAL HEAT FLUX; HIGH PRESSURE; LOSS OF COOLANT; MEDIUM PRESSURE; PWR TYPE REACTORS; STEADY-STATE CONDITIONS; SUBCOOLING; TRANSIENTS; VELOCITY
- Descriptors DEC
- ACCIDENTS; COOLING; ENRICHED URANIUM REACTORS; HEAT FLUX; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Composed of three volumes.