The document deals with the description of results obtained by the Relap5 code in the simulation of the Small Break Loss of Coolant Accident (SBLOCA) experiment in the Pressurized Water Reactor (PWR) Nuclear Power Plant (NPP) Krsko in Slovenia. The Relap5 is the well-known computer code developed at Idaho National Laboratory in US: the code is in use at UNIPI since more than a decade. The Krsko NPP is a two loop Westinghouse reactor, around 650 Mwe power jointly owned by electrical companies of Croatia and Slovenia. The concerned test was selected because of the availability of experimental data in Integral Test Facilities (ITF). The idea, leading to the so called Kv-scaled calculation, was to calculate for the NPP the same scenario (basically assuming scaled Boundary and initial conditions) measured in one ITF. Differences, expected between the calculated NPP scenario and the measured ITF scenario must be fully understood (this is achieved by performing a variety of sensitivity analyses): the final product of the activity is to the best possible “qualified” NPP nodalization.

Analysis of the RELAP5/MOD2 code calculations of KRSKO "LSTF Kv-scaled" and "Nominal" conditions small break LOCA in cold leg

D'Auria F.
Co-primo
Methodology
;
1993-01-01

Abstract

The document deals with the description of results obtained by the Relap5 code in the simulation of the Small Break Loss of Coolant Accident (SBLOCA) experiment in the Pressurized Water Reactor (PWR) Nuclear Power Plant (NPP) Krsko in Slovenia. The Relap5 is the well-known computer code developed at Idaho National Laboratory in US: the code is in use at UNIPI since more than a decade. The Krsko NPP is a two loop Westinghouse reactor, around 650 Mwe power jointly owned by electrical companies of Croatia and Slovenia. The concerned test was selected because of the availability of experimental data in Integral Test Facilities (ITF). The idea, leading to the so called Kv-scaled calculation, was to calculate for the NPP the same scenario (basically assuming scaled Boundary and initial conditions) measured in one ITF. Differences, expected between the calculated NPP scenario and the measured ITF scenario must be fully understood (this is achieved by performing a variety of sensitivity analyses): the final product of the activity is to the best possible “qualified” NPP nodalization.
1993
DCMN NT
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11568/898897
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