High pressure melt ejection relevant to CANDU reactors
Description
The modelling of fuel-coolant interaction following a severe flow blockage in a single channel of a CANDU reactor is assessed. The available data that support these models is also reviewed. It is concluded that it is appropriate to employ the forced fuel-coolant interaction methodology in analyzing CANDU single channel flow blockage event with a severe power-cooling mismatch. The hydrodynamic transients are conservatively determined for various amounts of molten fuel available for discharge. The magnitude of the pressure transient and impulse loads decrease as the distance from the rupture site increases. The higher discharged mass produces more energy deposited in the bubble over the transient which results in a faster and greater pressurization of the moderator and results in higher impulsive loads on adjacent structures. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- Imprint Title
- Proceedings of the Canadian Nuclear Society 19th annual conference
- Imprint Pagination
- 2 v.
- Journal Page Range
- v. 2 [15 p.]
Conference
- Title
- 19. annual conference of the Canadian Nuclear Society
- Dates
- 18-21 Oct 1998
- Place
- Toronto, Ontario (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 31042470
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BLOWDOWN; CANDU TYPE REACTORS; FLOW BLOCKAGE; FUEL CHANNELS; FUEL-COOLANT INTERACTIONS; HYDRODYNAMICS; POWER-COOLING-MISMATCH ACCIDENTS; REACTOR COOLING SYSTEMS
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; FLUID MECHANICS; HEAVY WATER MODERATED REACTORS; MECHANICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 10 refs., 1 tab., 12 figs.