Published 1978
| Version v1
Journal article
Characteristics of average void fraction in vertical two-phase flow channels
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
The effective water head in the downcomer during the reflood phase in the postulated loss of coolant accident of PWRs, is dominated by the average void fraction in vertical two-phase flow channels. This report made clear the effects of physical properties of fluids, channel diameter and superficial velocities of two phases on the average void fraction in vertical flow system. As the results, the presentation of average void fraction by dimensionless groups can be obtained within errors of +- 15% in cases of steam-water and air-water flow systems under the stagnant liquid conditions including the case of very low liquid velocity (<30 cm/s). (author)
Additional details
Publishing Information
- Journal Title
- Nippon Dennetsu Shinpojiumu Koen Ronbunshu
- Journal Issue
- no.15
- Series
- Nippon Dennetsu Shinpojiumu Koen Ronbunshu.
Conference
- Title
- 15. annual symposium Heat Transfer Society of Japan.
- Dates
- 30 May - 1 Jun 1978.
- Place
- Sapporo, Japan.
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 10480651
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AIR; CORE FLOODING SYSTEMS; ERRORS; FLOW MODELS; FLOW RATE; LOSS OF COOLANT; PWR TYPE REACTORS; STEAM; TWO-PHASE FLOW; VOID FRACTION; WATER
- Descriptors DEC
- ACCIDENTS; ECCS; FLUID FLOW; FLUIDS; GASES; HYDROGEN COMPOUNDS; MATHEMATICAL MODELS; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS