Published December 1981
| Version v1
Journal article
Free-convection cooling of blocked fuel subassemblies in pool-type liquid metal fast reactors
Description
A theoretical analysis of the thermal hydraulics of fast reactor subassemblies with a complete inlet blockage of the coolant flow reveals that substantial rates of heat removal can be sustained through natural convection. A thermal-syphon mechanism is responsible, and shown to be capable of removing fission-product decay heat from any core subassembly in the prototype fast reactor such that the peak coolant temperatures will not exceed the boiling point. For low-rated radial breeder subassemblies the mechanism should remove fission heat at full power without the initiation of coolant boiling. (author)
Additional details
Publishing Information
- Journal Title
- Nucl. Energy
- Journal Volume
- 20
- Journal Issue
- 6
- Series
- Nucl. Energy.
- Journal Page Range
- 481-493
- ISSN
- 0140-4067
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 13700320
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT REMOVAL; FUEL ASSEMBLIES; LMFBR TYPE REACTORS; LOSS OF FLOW; NATURAL CONVECTION; PFR REACTOR; PRIMARY COOLANT CIRCUITS; SODIUM; STAGNATION
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; BREEDER REACTORS; CONVECTION; COOLING SYSTEMS; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT TRANSFER; LIQUID METAL COOLED REACTORS; METALS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SODIUM COOLED REACTORS