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AEA TECHNOLOGY CALCULATIONAL SUPPORT FOR THE CORA EARLY PHASE MELT PROGRESSION EXPERIMENTS

DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.390

T. J. Haste
AEA Technology, Winfrith Technology Centre, United Kingdom

R. P. Hiles
AEA Technology, Winfrith Technology Centre, United Kingdom

S. Hagen
Forschungszentrum Karlsruhe, Karlsruhe, Germany

P. Hofmann
Forschungszentrum Karlsruhe, Karlsruhe, Germany

Resumo

The CORA electrically heated melt progression bundle experiments performed at FZK (formerly KfK) Karlsruhe aimed to identify and quantify the mechanisms and sequence of events causing severe fuel damage to light water reactor (LWR) fuel rods during heat-up and reflooding. They were supported by separate-effect tests to measure the kinetics of chemical reactions identified as important in the integral experiments.
During the test series, which ran from August 1987 to April 1993, AEA Technology provided calculational support at the request of FZK for five of the PWR-related experiments, namely tests 15, 7, 29, 30 and 10. For CORA-15, recommendations were provided regarding the rod fill pressure to be used in this experiment to study the effect of ballooning on melt progression. For the CORA-7 large bundle test, the SCDAP code was used to advise on the scaling of the power and coolant conditions required in going from the standard 25-rod configuration to the 57-rod bundle employed. For CORA-29, which examined the effect of a limited degree of cladding pre-oxidation, SCDAP/RELAP5 calculations were made of the likely effect of the pre-oxidation used. For the CORA-30 low heat-up rate test, and for the CORA-10 test which simulated melt progression in a partially flooded bundle, SCDAP/RELAP5 was used to provide recommendations regarding the power and coolant conditions required to achieve the test objectives. In all cases, the tests were conducted successfully. In general, SCDAP/RELAP5 performed well and reliably in modelling the CORA facility, being well suited to the application.

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