VALCO: Validation of transient analysis codes for VVER by using measurement data
VALCO: Validation of transient analysis codes for VVER by using measurement data
Kozmenkov, Y.; Mittag, S.; Rohde, U.; Grundmann, U.; Weiss, F.-P.; Vanttola, T.; Langenbuch, S.; Ionov, V. S.; Petkov, P.
VALCO is an EU FP5 project on transient analysis code validation for VVER type reactors that continues the work of the former EU Phare project SRR1/95. Twelve organisations from nine East and West European countries are participating. For the validation of coupled neutronic / thermal-hydraulic codes that are used in VVER safety analyses, five measured transients from different VVER-440 and VVER-1000 plants have been documented. Two of them have been chosen for validation calculations. First results of an ATHLET / DYN3D calculations for a MCP trip measured in the Kozloduy-6 VVER-1000 are presented. Uncertainty analysis applying the SUSA methodology developed at GRS to coupled-code calculations for VVER will be performed. To validate the stand-alone three-dimensional neutronic codes together with the applied two-group diffusion parameters independently from thermohydraulic feedback, the analysis of measurements in the V-1000 zero-power facility (KI Moscow), which is a full-scale VVER-1000 mock-up, is going to be performed. Preliminary results of DYN3D steady-state calculations using a HELIOS two-group data library and albedo coefficients calculated by the transport code MARIKO are compared to measurement data.
Keywords: neutron kinetics; thermohydraulics; coupled codes; transient analysis; code validation; measurement data; nuclear power plants; zero power critical facility; uncertainty analysis
-
Contribution to proceedings
Proceedings of the 12th Symposium of Atomic Energy Research, Sunny Beach (Bulgaria), September 23-27, 2002, Proc. pp. 361-381
Permalink: https://www.hzdr.de/publications/Publ-4965