Stability of natural-circulation flow in a CANDU-type fuel channel
Creators
- 1. Atomic Energy of Canada Ltd., Pinawa, Manitoba. Whiteshell Nuclear Research Establishment
- 2. Atomic Energy of Canada Ltd., Mississauga, Ontario. CANDU Operations
Description
This paper describes the results of natural-circulation flow experiments in a full-scale representation of a single CANDU reactor fuel channel and its associated feeders. The objective was to investigate the stability of natural-circulation flow for various channel powers, system pressures and inlet flow subcooling levels. The results show that the flow becomes unstable for two-phase flow conditions at the channel outlet. Two types of periodic behaviour are observed: (1) an intermittent flow instability that occurs at low channel exit qualities, caused by periodic formation and expulsion of two-phase region from the channel, and (2) an oscillatory flow instability that occurs at high channel exit qualities, characterized by large-amplitude sinusoidal-type oscillations in the channel flow. The paper describes the parametric trends with power, pressure and degree of subcooling. The dynamic instability is analyzed using a linear stability model. (orig.)
Additional details
Publishing Information
- Journal Title
- Nucl. Eng. Des.
- Journal Volume
- 99
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 403-412
- ISSN
- 0029-5493
- CODEN
- NEDEA
Conference
- Title
- 3. international topical meeting on reactor thermal hydraulics.
- Dates
- 15-18 Oct 1985.
- Place
- Newport, RI (USA).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 18057680
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; COMPARATIVE EVALUATIONS; FLOW MODELS; FLOW RATE; MEASURING METHODS; NATURAL CONVECTION; OSCILLATIONS; REACTOR CHANNELS; SUBCOOLING; TWO-PHASE FLOW
- Descriptors DEC
- CONVECTION; COOLING; ENERGY TRANSFER; EVALUATION; FLUID FLOW; HEAT TRANSFER; HEAVY WATER MODERATED REACTORS; MATHEMATICAL MODELS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS