Published 1988
| Version v1
Journal article
Evaluation of heat transfer coefficient at direct contact condensation of cold water and steam
Description
The estimation of heat transfer coefficient at the direct contact condensation of cold water and steam is very hard, since the phenomena is unsteady and the interface moves complicately. Present research shows the heat transfer coefficient evaluated in the simulation analyses and experiments on the phenomena related to the Loss-of-Coolant Accident of light water reactors. At chugging the heat transfer coefficient was up to 106W/m2K. At condensation oscillation it was between 105-106 W/m2K. At jet region of cold water injected into steam flow it was around 105 W/m2K, and the surface of stratified flow it was between 104-5 x 104 W/m2K. (author)
Additional details
Publishing Information
- Journal Title
- Nippon Dennetsu Shinpojiumu Koen Ronbunshu
- Journal Volume
- 25
- Journal Issue
- 1
- Series
- Nippon Dennetsu Shinpojiumu Koen Ronbunshu.
- Journal Page Range
- 100-102
- CODEN
- NDSRD
Conference
- Title
- 25. national heat transfer symposium of Japan.
- Dates
- 1-3 Jun 1988.
- Place
- Kanazawa (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 20003682
- 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; ECCS; HEAT TRANSFER; LAMINAR FLOW; LOSS OF COOLANT; OSCILLATIONS; PWR TYPE REACTORS; REACTOR SAFETY; STEAM; VAPOR CONDENSATION; WATER
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SOLVENTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS