Thermofluid experiments on ingress of coolant event
- 1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan)
Description
One of the serious thermofluid safety issues in a fusion experimental reactor is an ingress of coolant event (ICE), when the water in a coolant pipe is ejected into the vacuum vessel (VV) if an accident occurs, such as a runaway electron impact on the coolant pipes. If the VV cannot withstand the high pressurization caused by water evaporation in the VV, and on the high-temperature plasma-facing components, the steam containing activated dusts could be transferred from the VV to the environment. Therefore, it is important to understand the entire thermofluid characteristics during ICE conditions. This paper describes the first set of ICE experimental results, such as pressure transients in VV and transient temperature distributions on a water-jet impingement wall. It was found that pressurization under vacuum conditions, as an initial pressure condition in VV, is very different from that under atmospheric pressure conditions when the VV is filled with air at 0.1 MPa. The reasons for this discrepancy and some heat transfer characteristics on the target wall are discussed. (orig.)
Additional details
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 42
- Series
- Part C
- Journal Page Range
- p. 67-72
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 4. international symposium on fusion nuclear technology (ISFNT-4)
- Dates
- 6-11 Apr 1997
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Switzerland
- INIS RN
- 30001079
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; REACTOR SAFETY; TOKAMAK DEVICES
- Descriptors DEC
- CLOSED PLASMA DEVICES; SAFETY; THERMONUCLEAR DEVICES
Optional Information
- Notes
- 9 refs.