Published November 1982 | Version v1
Report Open

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)

MF available from INIS under the Report Number.

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Publishing Information

Imprint Pagination
43 p.
Report number
JAERI-M--82-166