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中国科学院力学研究所机构知识库
Knowledge Management System of Institue of Mechanics, CAS
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State Key ... [2]
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Mora DF [2]
Niceno B [2]
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钱桂安 [2]
Garrido OC [1]
Jaros M [1]
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Modelling of reactor pressure vessel subjected to pressurized thermal shock using 3D-XFEM
期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2019, 卷号: 353, 页码: 13./通讯作者:Mora, Diego F.
Authors:
Mora DF
;
Niffenegger M
;
Qian GA(钱桂安)
;
Jaros M
;
Niceno B
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View/Download:390/115
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Submit date:2019/11/26
Pressurized thermal shock
Large Break LOCA
Stress intensity factor
Reactor pressure vessel
Fracture mechanics
XFEM
Uncertainties in pressurized thermal shock analyses
会议论文
ASME 2019 Pressure Vessels and Piping Conference, PVP 2019, San Antonio, TX, United states, July 14, 2019 - July 19, 2019
Authors:
Niffenegger M
;
Garrido OC
;
Mora DF
;
Qian GA(钱桂安)
;
Mukin R
;
Sharabi M
;
Lafferty N
;
Niceno B
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View/Download:146/0
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Submit date:2020/11/20
Computational fluid dynamics
Finite element method
Pressurized thermal shock
Probabilistic fracture mechanics
Warm pre-stressing