Verification and validation of dynamic response simulation codes for BWR fuel assemblies under seismic loading
| Autor: | Shinobu Yoshimura, Yuuichi Koide, Shohei Onitsuka, Tadashi Iijima, Tomonori Yamada |
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| Rok vydání: | 2018 |
| Předmět: |
Computer simulation
Computer science Mechanical Engineering Nuclear engineering Control rod Seismic loading 01 natural sciences Finite element method 010305 fluids & plasmas Coolant 010101 applied mathematics Mechanics of Materials 0103 physical sciences Boiling water reactor General Materials Science 0101 mathematics Added mass Verification and validation |
| Zdroj: | International Journal of Pressure Vessels and Piping. 167:25-31 |
| ISSN: | 0308-0161 |
| DOI: | 10.1016/j.ijpvp.2018.10.005 |
| Popis: | The purpose of this study is to verify and validate two independently developed simulation codes for investigating dynamic response behaviors of fuel assemblies in a boiling water reactor (BWR) under seismic loading. The core of BWR consists of several hundreds of fuel assemblies. They are supported with both top guide and fuel support and are surrounded by coolant water. It is important to grasp their dynamic response behaviors under seismic loading for securing the structural integrity of the fuel assembly itself as well as for assessing control rod scrammability. For this evaluation of dynamic response behaviors, reliable simulation codes are required. In this study, we employ two different numerical simulation methods of acoustic fluid-structure interaction (AFSI) developed by the present authors independently. The one is a three-dimensional parallel finite element method for AFSI problems with solid elements based on a partitioned coupling approach, while the other is a finite element method of beam elements for fuel assemblies combining added mass matrix, which represents coupled inertia effects caused by coolant water. Both methods are implemented and applied to a problem of 368 fuel assemblies for verification and validation. The problem was set up based on the demonstration test performed by Nuclear Power Engineering Corporation in 1986. Both simulation results agreed well with each other, and the simulated results also agreed well with the experimental ones. In addition, we have discussed seismic response behaviors of fuel assemblies, which were not shown in the demonstration test. Finally, we conclude that the both developed simulation codes based on the proposed methods are powerful tools to grasp the behavior of huge number of fuel assemblies of BWR under seismic loading and to improve the seismic safety design of BWR core. |
| Databáze: | OpenAIRE |
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