Published September 1998 | Version v1
Journal article

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.