The results obtained in a more-than-a-decade application of thermal-hydraulic system codes to the analysis of experiments performed in Integral Test Facilities (ITF) and Separate Effect test Facilities (SETF) including the participation to several International Standard Problems (ISP) and Standard Problem Exercises (SPE), organized by OECD/NEA/CSNI (Organization for Economic Cooperation and Development / Nuclear Energy Agency / Committee on the Safety of Nuclear Installations) and by IAEA (international Atomic Energy Agency), respectively, suggested the need for new methods and procedures for code application. The words nodalization-qualification, qualitative-accuracy-evaluation, quantitative-accuracy-evaluation, and acceptability-thresholds were introduced. This report is a follow-up of the report which F deals with nodalization qualification at the transient level for the LOBI/mod2 available at the EURATOM JRC of Ispra (Italy), the SPES, available at the SIET research center in Piacenza, Italy, the LSTF available at the Tokai-Mura Research Center of JAERI in Japan and the BETHSY available at the CEA-CENG research center in Grenoble, France. The activity was based upon the analysis of one experiment performed in each ITF, respectively: criteria for accepting the results of the comparison with calculated data are fixed from the application of the FFTBM (Fast Fourier Transform Based Method). In the present report the qualification process is extended to Nuclear Power Plant (NPP), namely the Krsko NPP, available in Slovenia, in relation to which accident measurement were not available; in this case operational transient data were available.

On Transient qualification of Lobi/mod2, Spes, Lstf, Bethsy and Krsko Plant nodalizations for Relap5/Mod2 code

D'Auria F.
Secondo
Supervision
;
1991-01-01

Abstract

The results obtained in a more-than-a-decade application of thermal-hydraulic system codes to the analysis of experiments performed in Integral Test Facilities (ITF) and Separate Effect test Facilities (SETF) including the participation to several International Standard Problems (ISP) and Standard Problem Exercises (SPE), organized by OECD/NEA/CSNI (Organization for Economic Cooperation and Development / Nuclear Energy Agency / Committee on the Safety of Nuclear Installations) and by IAEA (international Atomic Energy Agency), respectively, suggested the need for new methods and procedures for code application. The words nodalization-qualification, qualitative-accuracy-evaluation, quantitative-accuracy-evaluation, and acceptability-thresholds were introduced. This report is a follow-up of the report which F deals with nodalization qualification at the transient level for the LOBI/mod2 available at the EURATOM JRC of Ispra (Italy), the SPES, available at the SIET research center in Piacenza, Italy, the LSTF available at the Tokai-Mura Research Center of JAERI in Japan and the BETHSY available at the CEA-CENG research center in Grenoble, France. The activity was based upon the analysis of one experiment performed in each ITF, respectively: criteria for accepting the results of the comparison with calculated data are fixed from the application of the FFTBM (Fast Fourier Transform Based Method). In the present report the qualification process is extended to Nuclear Power Plant (NPP), namely the Krsko NPP, available in Slovenia, in relation to which accident measurement were not available; in this case operational transient data were available.
1991
DCMN NT
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11568/897472
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