Dynamic Analysis of AP1000 Shield Building Considering Fluid and Structure Interaction Effects

Xu, Qiang; Chen, Jianyun; Zhang, Chaobi; Li, Jingyuan; Zhao, Chunfeng

doi:10.1016/j.net.2015.08.013

Cited by 29 publications

(12 citation statements)

References 27 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…As the third generation of nuclear power technology booming in the United States and China, 1,2 such as AP1000 3,4 and CAP1400, 5 reliabilities and motion performances of related electromechanical equipment should be improved. 6,7 At present, CAP1400 is one of the maximum nuclear power technologies under the research and development, 8,9 and only the construction cost of a CAP1400 nuclear power plant can be more than billions of dollars.…”

Section: Introductionmentioning

confidence: 99%

Co-simulation design and experimental study on the hydraulic–pneumatic-powered driving system of main steam and feed water isolation valves for CAP1400

Pan

Gu²,

Guo³

et al. 2017

Advances in Mechanical Engineering

View full text Add to dashboard Cite

CAP1400 is an advanced large passive nuclear power technology under research and development, and related electromechanical equipment should be improved to guarantee the safety. The driving systems of main steam and feed water isolation valves are electromechanical equipment in nuclear power plants with nonlinear systems, which are not easy to be identified with traditional mathematical models. This article presents the design process of a novel driving system of the main steam isolation valve under the emergency quick-closing situation, which do not need the mathematical models. The novel driving system, which has a symmetrical and concise structure, is designed to include only two independent hydraulic output circuits, two independent hydraulic input circuits, and a nitrogen circuit for auxiliary driving. A cosimulation method, which takes advantage of AMESim, Adams, UG, and MATLAB, was proposed to establish the models of the main steam and feed water isolation valve and the driving system. Finally, co-simulations and experimental verifications of the emergency quick-closing situations, which include two hydraulic output circuits working together for quick closing and only one hydraulic output circuit for quick closing, were provided to confirm the performances and effectiveness of the proposed driving system and co-simulation method.

show abstract

Section: Introductionmentioning

confidence: 99%

Co-simulation design and experimental study on the hydraulic–pneumatic-powered driving system of main steam and feed water isolation valves for CAP1400

Pan

Gu²,

Guo³

et al. 2017

Advances in Mechanical Engineering

View full text Add to dashboard Cite

show abstract

“…Sener et al [12] developed a 3D nonlinear inelastic finite element model and then incorporated it into the finite element software ABAQUS for studying the seismic behavior of a pressurized water reactor containment internal structure. Based on the finite element method, Xu et al [13] investigated the effects of water level in a water tank on the dynamic response of the AP1000 shield building subjected to three-dimensional ground motion.…”

Section: Introductionmentioning

confidence: 99%

Dynamic Behavior of AP1000 Nuclear Island Building in Japanese Kobe 1995 Earthquake

Nguyen¹,

Vu²,

Gan³

2017

IOSR JMCE

View full text Add to dashboard Cite

“…Some studies (e.g., Satoh Onitsuka, Goto, Iijima and Ojima, Mechanical Engineering Journal, Vol.4, No.3 (2017) [DOI: 10.1299/mej. et al, 2010; Xu et al, 2016) used 3D FEM for structural modeling with precise fluid modeling methods (e.g., finite volume method and particle method), which can capture complicated fluid phenomena such as splashing and turbulence. However, as mentioned in the study of Rydell et al (2013), these fluid modeling methods require much computational time even in present-day commercial computers.…”

Section: Introductionmentioning

confidence: 99%

Practical modeling of fluid in ABWR suppression pool for seismic analysis using 3D FEM model

Onitsuka

Iijima

Ojima

2017

Mechanical Engineering Journal

View full text Add to dashboard Cite

This paper presents a practical modeling of the fluid in a suppression pool (SP) for seismic analysis by using three-dimensional finite element method (3D FEM) models of the reactor building of an advanced boiling water reactor (ABWR). We performed a seismic analysis considering the fluid-structure interaction by using the virtual mass method in MSC Nastran, which was verified on the basis of vibration tests in this study, and the effects of the fluid on the structures around the SP were evaluated. For the analysis, we developed the following 3D FEM models: a full model, impulsive model, and no-fluid model. The full model considered both the convective and impulsive effects of the fluid, and the impulsive model lacked the convective effects of the full model (modeling the fluid as masses). The no-fluid model removed the impulsive effects from the impulsive model (removing the fluid from the full model). From the analysis, we obtained the maximum acceleration, von Mises stresses, and pressure fluctuations at the structures around the SP. The obtained results were compared with each other. They indicate that the fluid hardly affects the seismic responses of the structures, though some effects of the fluid were found. On the basis of the effects we found, we propose a practical modeling of the fluid and a modeling flowchart to use it. The modeling flowchart enables us to practically model the fluid in the SP for seismic analysis using ABWR 3D FEM models.

show abstract

Dynamic Analysis of AP1000 Shield Building Considering Fluid and Structure Interaction Effects

Cited by 29 publications

References 27 publications

Co-simulation design and experimental study on the hydraulic–pneumatic-powered driving system of main steam and feed water isolation valves for CAP1400

Co-simulation design and experimental study on the hydraulic–pneumatic-powered driving system of main steam and feed water isolation valves for CAP1400

Dynamic Behavior of AP1000 Nuclear Island Building in Japanese Kobe 1995 Earthquake

Practical modeling of fluid in ABWR suppression pool for seismic analysis using 3D FEM model

Contact Info

Product

Resources

About