Estimation of average void fraction in vertical two-phase flow channel under low liquid velocity
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
During the reflood phase in a postulated loss-of-coolant accident of a pressurized water reactor, the driving force to feed the emergency core coolant into the core is the effective water head of a two-phase flow in the downcomer surrounding the core in the reactor vessel. The effective water head in the downcomer is dominated by the characteristics of the average void fraction in a vertical two-phase flow channel. This paper makes clear the effects of the physical properties of fluids, the channel diameter and superficial velocities of two phases on the void fraction in a vertical flow system by both carrying out the experiment of an air-water system under 1 atm and investigating the previous experimental results of steam-water and air-water systems. As the results, the presentation of the average void fraction could be obtained within errors of +- 15% by dimensional analyses in cases of both steam-water and air-water systems in the range of low superficial water velocities ( lt 30 cm/s) including the stagnant water condition. (author)
Additional details
Publishing Information
- Journal Title
- J. Nucl. Sci. Technol. (Tokyo)
- Journal Volume
- 17
- Journal Issue
- 1
- Series
- J. Nucl. Sci. Technol. (Tokyo).
- Journal Page Range
- 1-15
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 11571413
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- CORE FLOODING SYSTEMS; EXPERIMENTAL DATA; FLOW MODELS; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; TWO-PHASE FLOW; VELOCITY; VOID COEFFICIENT; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; DATA; ECCS; FLUID FLOW; INFORMATION; MATHEMATICAL MODELS; NUMERICAL DATA; REACTIVITY COEFFICIENTS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS