SIMMER-II analysis of the R-7 TREAT test
Description
The SIMMER-II code was used in a simulation of the R-7 loss-of-flow TREAT test. Comparison with the test scenario encompassed thermocouple data, flowmeter tracers, hodoscope data, and the posttest configuration. Reasonably successful results were obtained on the overall heat balance. The calculated boiling time was within 0.2 s of the experimental result, and respectable agreement with the integrated lower flowmeter trace was achieved over the first 2 s of boiling. Although the details of cladding relocation and blockage formation could not be well simulated, the calculated fuel motion appears to be plausible given the available experimental information. It was further concluded that this type of study is quite useful for revealing areas for model improvement
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.
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Additional details
Publishing Information
- Imprint Pagination
- 30 p.
- Report number
- NUREG/CR--0760
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10487421
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CALCULATIONS; FFTF REACTOR; LOSS OF FLOW; SIMULATION; TREAT REACTOR
- Descriptors DEC
- ACCIDENTS; AIR COOLED REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; SOLID HOMOGENEOUS REACTORS; TEST REACTORS; THERMAL REACTORS
Optional Information
- Secondary number(s)
- LA--7763-MS.