THERMOSS: a thermohydraulic model of flow stagnation in a horizontal fuel channel
Description
Following a postulated inlet-side small break in the CANDU reactor, emergency coolant is injected to refull the horizontal fuel channels and remove the decay heat. As part of the accident analysis, the effects of loss of forced circulation during the accident are predicted. A break size exists for which, at the end of pump rundown, the break force balances the natural circulation force and the channel flow is reduced to near zero. The subcooled, stagnant channel condition is referred to as the standing-start condition. Subsequently, the channel coolant boils and stratifies. Eventually the steam flow from the channel heats up the endfitting to the saturation temperature and reaches the vertical feeder. The resulting buoyancy-induced flow then refills the channel. One dimensional, two-fluid conservation equations are solved in closed form to predict the duration of stagnation. In this calculation the channel water level is an important intermediate variable because it determines the amount of steam production
Availability note (English)
MF available from INIS under the Report Number.Files
16078228.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 32 p.
- Report number
- AECL--8330
Conference
- Title
- 10. Annual symposium on simulation of reactor dynamics and plant control.
- Dates
- 9-10 Apr 1984.
- Place
- St. John, New Brunswick (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 16078228
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; CANDU TYPE REACTORS; FLOW MODELS; FUEL CHANNELS; LOSS OF FLOW; PRIMARY COOLANT CIRCUITS; STAGNATION; T CODES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; HEAVY WATER MODERATED REACTORS; MATHEMATICAL MODELS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS