The calculating analysis of fluid transients caused by LOCA event in primary loop
Description
The coolant must run off wherever ruptures occur in PWR. It is called LOCA event which is the one of the most serious accidents. This paper deals with the rupture of pipe in primary loop in PWR. The ruptures involve the double-end of break, which results in that coolant jets simultaneously from the double end of break pipes, and the break opening of pipe which is a hole on the wall of pipe. The main loop links up with many large diameter pipes, while auxiliary systems linking up with main loop have thin piping system. A pipe of auxiliary system has rupture, there is still time to do something with emergency. When a main pipe breaks core may be uncovered because of a great deal of loss of coolant, the temperature of core rises so that the core may fuse. How about the flow of coolant ? Analysis is shown in this paper from a viewpoint of fluid mechanics. The research of fluid transients in LOCA event help us to know the flow condition of coolant and acquaint with the fluid force acting on pressure vessel, steam generator, support of pipes etc. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Transactions of the 11th international conference on structural mechanics in reactor technology
- Imprint Pagination
- 6297 p.
- Journal Page Range
- v. SD1-SD2 p. 457-462.
Conference
- Title
- 11. international conference on structural mechanics in reactor technology.
- Dates
- 18-23 Aug 1991.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 23075971
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ECCS; LAX THEOREM; LOSS OF COOLANT; PIPES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; RUPTURES; STEAM GENERATORS; TRANSIENTS; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; BOILERS; COOLING SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; FLUID FLOW; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Distributed by Maruzen Co. Ltd. P.O. Box 5050, Tokyo Int'l, 100-31 Japan ISBN 4-89047-060-3 for 17 vols. bound in 15 (A through SD2).