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Enhancement of engineering models for simulation of soft, and hard projectile impact on reinforced concrete structures. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111187] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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Chung CH, Choi K, Choi HS, Lee J. Local impact resistance analysis of prestressed concrete structures considering curvature and post-tensioning effects. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107415] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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3
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Dynamic assessment of the seismic isolation influence for various aircraft impact loads on the CPR1000 containment. NUCLEAR ENGINEERING AND TECHNOLOGY 2018. [DOI: 10.1016/j.net.2018.08.003] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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4
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Takazawa H, Hirosaka K, Miyazaki K, Tohyama N, Matsumoto N. Analysis Method for Impact and Dispersion Behavior of Water-Filled Tank. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2018. [DOI: 10.1115/1.4040432] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
A new Japanese nuclear regulation involves estimating the possible damage to plant structures due to intentional aircraft impact. The effect of aircraft impact needs to be considered in the existing nuclear power plants. The structural damage and fuel dispersion behavior after aircraft impact into plant structures can be evaluated using finite element analysis (FEA). FEA needs validated experimental data to determine the reliability of the results. In this study, an analysis method was validated using a simple model such as a cylindrical tank. Numerical simulations were conducted to evaluate the impact and dispersion behavior of a water-filled cylindrical tank. The simulated results were compared with the test results of the VTT Technical Research Centre of Finland (VTT). The simulations were carried out using a multipurpose FEA code LS-DYNA®. The cylindrical tank was modeled using a shell element, and the tank water was modeled using smoothed particle hydrodynamics (SPH) elements. First, two analysis models were used to evaluate the effect of the number of SPH elements. One had about 300,000 SPH elements and the other had 37,000 SPH elements. The cylindrical tank ruptured in the longitudinal direction after crashing into a rigid wall, and the filled water dispersed. There were few differences in the simulated results when using different numbers of SPH elements. The VTT impact test was simulated with an arbitrary Lagrangian-Eulerian (ALE) element to consider the air drag. The analytical dispersion pattern and history of dispersion velocity ratio agreed well with the impact test results.
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Affiliation(s)
- Hidekazu Takazawa
- Research and Development Group, Hitachi, Ltd., 7-1-1, Omika, Hitachi 319-1292, Ibaraki, Japan e-mail:
| | - Kazuma Hirosaka
- Research and Development Group, Hitachi, Ltd., 7-1-1, Omika, Hitachi, Ibaraki, 319-1292, Japan e-mail:
| | - Katsumasa Miyazaki
- Research and Development Group, Hitachi, Ltd., 7-1-1, Omika, Hitachi 319-1292, Ibaraki, Japan e-mail:
| | - Norihide Tohyama
- Hitachi Works, Hitachi-GE Nuclear Energy, Ltd., 3-1-1, Saiwai, Hitachi 317-0073, Ibaraki, Japan e-mail:
| | - Naomi Matsumoto
- Hitachi Works, Hitachi-GE Nuclear Energy, Ltd., 3-1-1, Saiwai, Hitachi 317-0073, Ibaraki, Japan e-mail:
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Soft impact testing of a wall-floor-wall reinforced concrete structure. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2016.10.052] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Schaffrath A, Sonnenkalb M, Sievers J, Luther W, Velkov K. Scientific codes developed and used at GRS – Nuclear simulation chain. KERNTECHNIK 2016. [DOI: 10.3139/124.110695] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
Over 60 technical experts of the reactor safety research division of the Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH are developing and validating reliable methods and computer codes – summarized under the term nuclear simulation chain – for the safety-related assessment for all types of nuclear power plants (NPP) and other nuclear facilities considering the current state of science and technology. This nuclear simulation chain has to be able to simulate and assess all relevant physical processes and phenomena for all operating states and (severe) accidents. In the present contribution, the nuclear simulation chain developed and applied by GRS as well as selected examples of its application are presented. The latter demonstrate impressively the width of its scope and its performance. The GRS codes can be passed on request to other (national as well as international) organizations. This contributes to a worldwide increase of the nuclear safety standards. The code transfer is especially important for developing and emerging countries lacking the financial means and/or the necessary know-how for this purpose. At the end of this contribution, the respective course of action is described.
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Affiliation(s)
- A. Schaffrath
- Gesellschaft für Anlagen und Reaktorsicherheit (GRS) gGmbH , Forschungszentrum, Boltzmannstr. 14, 85748 Garching/München , Germany
| | - M. Sonnenkalb
- Gesellschaft für Anlagen und Reaktorsicherheit (GRS) gGmbH , Forschungszentrum, Boltzmannstr. 14, 85748 Garching/München , Germany
| | - J. Sievers
- Gesellschaft für Anlagen und Reaktorsicherheit (GRS) gGmbH , Forschungszentrum, Boltzmannstr. 14, 85748 Garching/München , Germany
| | - W. Luther
- Gesellschaft für Anlagen und Reaktorsicherheit (GRS) gGmbH , Forschungszentrum, Boltzmannstr. 14, 85748 Garching/München , Germany
| | - K. Velkov
- Gesellschaft für Anlagen und Reaktorsicherheit (GRS) gGmbH , Forschungszentrum, Boltzmannstr. 14, 85748 Garching/München , Germany
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