Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Verification and validation analyses of LMFBR core mock-up seismic experiments by finds code

Abstract

The FINDS code which has capabilities of analyzing PWR, APWR and LMFBR cores deflection and colliding behaviors under seismic conditions has been applied to the LMFBR core mock-up test data analyses to confirm the code capabilities to simulate LMFBR core seismic behaviors, performing the PEC, the RAPSODIE and the MONJU core mockup seismic analyses. At first the PEC core seismic tests data were analyzed by using the FINDS code to check the code capabilities to simulate LMFBR core seismic behaviors. Then it was confirmed that PEC experimental data are simulated fairly well by the FINDS code models. The RAP087 AX01 wave test case in the air condition was selected for the calculation of the RXPSODIE mockup tests where 19 assemblies of one array were modeled. In addition the RAPZIMME32 wave test in the water condition was selected where whole assemblies composing the RAPSODIE three dimensional mockup with 271 core assemblies of fuel assemblies and neutronic shield elements are modeled in the FINDS calculations. Then it was assured again that the RAPSODIE displacements data can be reproduced by the FINDS code models for both one row and three dimensional cases, and three dimensional movements are recognized by the graphical presentations in which some reduced response in three dimensional analysis appears because of shock forces dispersion effects in vertical direction compared with two dimensional behaviors, although slight discrepancy exists in neutronic shield elements displacements. The Japanese prototype reactor MONJU mockup test data were analyzed for single assembly natural frequency and pad collision test data by the FINDS code, and the one array 29 assemblies test data were analyzed by the general purpose code ANSYS. The consistencies were obtained in the ANSYS analyses both in displacements and colliding forces between wapper pads. Comparison with other codes calculations are summarized considering the test accuracies because the tests results cannot be traced now by the lack of data. Finally future tasks remained are discussed not only to get more precise codes and but also to get design methodology for seismic events.

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Reference:

Final research co-ordination meeting on intercomparison of liquid metal fast reactor seismic analysis codes. Bologna (Italy). 30 May - 2 Jun 1995

International Atomic Energy Agency, Vienna (Austria)

IAEA-TECDOC--882, pp:59-109