Analysis of refill behaviour in CANDU-type feeders
Creators
- 1. Atomic Energy of Canada Ltd., Pinawa, Manitoba. Whiteshell Nuclear Research Establishment
Description
By analyzing the feeder-surface temperature and channel differential-pressure measurements in these experiments, a detailed picture of the quench and refill processes in a feeder has been obtained. The extended time delay associated with feeder refill can be split into two components: a feeder-quenching time delay and a feeder complete-refill time delay. It is concluded that the rate of feeder quenching is limited by countercurrent flow flooding in the feeders, whereas the rate of feeder complete refill is controlled by the hydrostatic pressure imbalance between the inlet and outlet feeders. The progress of the quench front through the feeder pipework is observed to be nonuniform. It takes more time to quench some feeder sections (referred to as critical feeder sections) than others. A possible explanation is presented to account for this observation. The influence of parallel channels on feeder refill is also described. (orig./DG)
Additional details
Publishing Information
- Publisher
- Braun.
- Imprint Place
- Karlsruhe (Germany, F.R.)
- ISBN
- 3-7650-1116-9
- Imprint Title
- Fourth international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4). Proceedings. Vol. 2
- Imprint Pagination
- 696 p.
- Journal Page Range
- p. 1183-1188.
Conference
- Title
- 4. international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4).
- Dates
- 10-13 Oct 1989.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 22038423
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; CORE FLOODING SYSTEMS; LOSS OF COOLANT; REACTOR SAFETY EXPERIMENTS
- Descriptors DEC
- ACCIDENTS; ECCS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS