Published November 1982
| Version v1
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Assessment of TRAC-PD2 reflood core thermo-hydraulic model by CCTF Test C1-16
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
The TRAC-PD2 reflood core thermo-hydraulic model was assessed by CCTF Test C1-16. The measured data were utilized as core boundary conditions in the TRAC calculations. The results indicate that the core inlet liquid temperature and the core heater rod temperatures are in reasonable agreement with data, but the pressure distribution in the core and water pool formation in the upper plenum are not in good agreement. The parametric effects of the droplet critical Weber number, the material properties of the heater rod, the noding of the upper plenum, and the minimum stable film boiling temperature are also discussed. (author)
Availability note (English)
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14799108.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 43 p.
- Report number
- JAERI-M--82-166
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 14799108
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- BENCHMARKS; HEAT TRANSFER; HYDRODYNAMICS; LOSS OF COOLANT; PRESSURE MEASUREMENT; PWR TYPE REACTORS; T CODES; TEMPERATURE MEASUREMENT; THERMAL ANALYSIS; THERMODYNAMIC MODEL; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; MATHEMATICAL MODELS; MECHANICS; PARTICLE MODELS; REACTOR ACCIDENTS; REACTORS; STATISTICAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS