Water tests for determining post voiding behavior in the LMFBR
Description
The most serious of the postulated accidents considered in the design of the Liquid Metal Cooled Fast Breeder Reactor (LMFBR) is the Loss of Pipe Integrity (LOPI) accident. Analysis models used to calculate the consequences of this accident assume that once boiling is initiated film dryout occurs in the hot assembly as a result of rapid vapor bubble growth and consequent flow stoppage or reversal. However, this assumption has not been put to any real test. Once boiling is initiated in the hot assembly during an LMFBR LOPI accident, a substantial gravity pressure difference would exist between this assembly and other colder assemblies in the core. This condition would give rise to natural circulation flow boiling accompanied by pressure and flow oscillations. It is possible that such oscillations could prevent or delay dryout and provide substantial post-voiding heat removal. The tests described were conceived with the objective of obtaining basic information and data relating to this possibility
Availability note (English)
MF available from INIS under the Report Number.Files
8290222.pdf
Files
(4.5 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 129 p.
- Report number
- ORNL-SUB--4450-1
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8290222
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BOILING; DRYOUT; FUEL ASSEMBLIES; LMFBR TYPE REACTORS; LOSS OF FLOW; MOCKUP; SIMULATION; VOIDS; WATER
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HYDROGEN COMPOUNDS; LIQUID METAL COOLED REACTORS; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTORS; STRUCTURAL MODELS
Optional Information
- Notes
- Available from NTIS. $6.00.
- Secondary number(s)
- MIT-EL--76-005.