General overview of the TOPFLOW-PTS experimental program
General overview of the TOPFLOW-PTS experimental program
Péturaud, P.; Hampel, U.; Barbier, A.; Dreier, J.; Dubois, F.; Hervieu, E.; Martin, A.; Prasser, H.-M.
During a hypothetical loss-of-coolant accident, cold emergency core cooling water may be injected in a partially uncovered cold leg, and related two-phase CFD simulations are required to demonstrate the reactor pressure vessel integrity further to the resulting pressurized thermal shock. To complement the physical validation of the two-phase CFD codes in this configuration, a dedicated integral-type experimental program – TOPFLOW-PTS – has been setup; this paper (i) supports the validation data needs, (ii) presents the related experimental setup, and (iii) provides the general guidelines of the test matrix definition and test procedure.
Keywords: pressurized thermal shock; TOPFLOW
Involved research facilities
- TOPFLOW Facility
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Contribution to proceedings
The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-14, 25.-30.09.2011, Toronto, Canada
Proceedings -
Lecture (Conference)
The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-14, 25.-30.09.2011, Toronto, Canada
Permalink: https://www.hzdr.de/publications/Publ-17598