Published 1978
| Version v1
Journal article
Measurements of void fraction in the pipe line during blowdown
Creators
- 1. Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works
Description
This paper describes void behavior in an outlet pipe at simulated loss of coolant accident for a pressure tube type nuclear reactor. Three needle contact probes type void meter was set at same cross section in the pipe of 3 inch diameter in order to measure the radial void distribution change with time. Experiments performed at 70 ata show that the void meter can measure the transient void behavior such as void fractuation and cholking phenomena. (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
- 10480673
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BLOWDOWN; FLOW RATE; LOSS OF COOLANT; PIPES; PRESSURE TUBE REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION; TIME DEPENDENCE; TRANSIENTS; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY