This report is being issued within the COLOSS Project of 5th Framework EC Programme Key Action on Nuclear Fission.Pre-test ana1ysis of QUENCH-09 test has been performed by ENEA using ICARE/CATHARE VI Mod1 code to verify the adequacy of boundary conditions to achieve the test objectives and help FZK in test conduct. Some sensitivity calculations bave been performed to evaluate the influence of some important parameters on the test conduct such as the residual steam flow rate and the power ramp during the transient phase.Post-test analysis of QUENCH-09 has been carried out with an improved version of ICARE/CATHARE code to validate the revised material oxidation and degradation models developed within the COLOSS project and implemented in the code.

Analysis of QUENCH-O9 Test with ICARE/CATHARE Code(SAM-COLOSS-PO71 - Part B)

Bandini, G.
2003-05-27

Abstract

This report is being issued within the COLOSS Project of 5th Framework EC Programme Key Action on Nuclear Fission.Pre-test ana1ysis of QUENCH-09 test has been performed by ENEA using ICARE/CATHARE VI Mod1 code to verify the adequacy of boundary conditions to achieve the test objectives and help FZK in test conduct. Some sensitivity calculations bave been performed to evaluate the influence of some important parameters on the test conduct such as the residual steam flow rate and the power ramp during the transient phase.Post-test analysis of QUENCH-09 has been carried out with an improved version of ICARE/CATHARE code to validate the revised material oxidation and degradation models developed within the COLOSS project and implemented in the code.
Rapporto tecnico;QUENCH experiments;B4C control rod degradation;ICARE/CATHARE code
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/6966
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