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This paper describes a seismic analysis which includes fluid-structure interactions for a large LMFBR reactor with many internal components and structures. Two mathematical models were employed. An axisymmetrical model was used for the vertical excitation analysis whereas a three-dimensional model was used for the horizontal excitation analysis. In both analyses, the sodium coolant was treated by continuum fluid elements. Thus, important seismic effects such as fluid-structure interaction, free-surface sloshing, fluid coupling, etc. are included in the analysis. This study is useful to the design of future LMFBR reactors. The results of this study can be used to improve the margin of safety of LMFBR plants under seismic conditions.
The seismic analysis of a large LMFBR with many internal components and structures is presented. Both vertical and horizontal seismic excitations are considered. The important hydrodynamic phenomena such as fluid-structure interaction, sloshing, fluid coupling and fluid inertia effects are included in the analysis. The results of this study are discussed in detail. Information which is useful to the design of future reactions under seismic conditions is also given. 4 refs., 12 figs.
Fluid modeling is of great importance in the seismic analysis of the LMFBR primary system. If the fluid model used in the analysis is too simplified, the results could be very uncertain. On the other hand, if the model is too detailed, considerable difficulty might be encountered in the analysis. The objectives of this study are to examine the validity of the two commonly used fluid modeling techniques. i.e. simplified added mass method and lumped mass method and to provide some useful information on the treatment of fluid in seismic analysis. The validity of these two methods of analysis is examined by comparing the calculated seismic responses of a fluid-structure system based on these two methods with that calculated from a coupled fluid-structure interaction analysis in which the fluid is treated by continuum fluid elements.
This paper describes the seismic analysis of a 400-MWe advanced fast reactor under 0.3 g SSE ground excitation. Two types of analyses are performed - the sloshing analysis and the fluid-structure interaction analysis. In the sloshing analysis, the sloshing frequency and wave patterns are calculated. The maximum wave height and the sloshing forces exerted on the submerged components and the primary tank are evaluated. In the fluid-structure interaction analysis, the maximum horizontal acceleration for the reactor core and the relative displacement between the reactor core and UIS are examined. The fluid-coupling phenomena between various components are investigated. Seismic stresses at critical areas are examined. The results obtained from this study are very useful to the design of the advanced reactors. Meanwhile, the computer code FLUSTR-ANL has proved to be a useful analytical tool for assessing the complicated seismic fluid-structure interactions and sloshing in the fast reactor systems. 10 refs., 25 figs.
Large breeder reactor vessels are often designed under the top-suspended condition. Since the vessel contains a large volume of liquid sodium as reactor coolant, the structural integrity of the vessel bottom head and its effect on the vessel dynamic response are of great importance to the safety and reliability of the reactor systems. This paper presents a dynamic analysis of the large suspended reactor vessel subjected to the horizontal earthquake excitation with the emphasis on the effect of bottom head vibration on fluid pressure and sloshing response. Unlike the conventional lumped mass method, the present analysis treats the liquid sodium as a continuum medium. As a result, the important effects ignored in the lumped mass method such as fluid coupling, fluid-structure interaction, interaction between sloshing and vessel vibration, etc. can be accounted into the analysis.
This paper describes the seismic analysis of a 450-MWe pool-type liquid metal reactor (LMR) under 0.3 g SSE ground excitations. It also assess the ultimate inelastic structural capabilities for other beyond-design-basis seismic events. Calculation is focused on a new design configuration where the vessel thickness is reduced considerably compared to the previous design (Ma and Gvildys, 1987). In the analysis, the stress and displacement fields at important locations of the reactor vessel, guard vessel, and support skirt are investigated. Emphasis is placed on the horizontal excitation in which large stress is generated. The possibility of impact between the reactor and guard vessels is examined. In the reactor vessel analysis, the effect of fluid-structure interaction is included. Attention is further given to the maximum horizontal acceleration of the reactor core as well as the relative displacement between the reactor core and the upper internal structure. The Argonne National Laboratory augmented three-dimensional Fluid-Structure Interaction program, FLUSTR-ANL is utilized for performing the base calculation where ground excitation is assumed to be 0.3 g SSE. The Newmark-Hall Ductility modification method was used for the beyond-design-basis seismic events. In both calculations, stress fields generated from the horizontal and vertical excitations are evaluated separately. The resultant stresses due to combined actions of these events are computed by the SRSS method. 4 refs., 5 figs., 2 tabs.