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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 ... [1]
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Jaros M [1]
Mora DF [1]
Niceno B [1]
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钱桂安 [1]
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2019 [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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Submit date：2019/11/26
Pressurized thermal shock
Large Break LOCA
Stress intensity factor
Reactor pressure vessel
Fracture mechanics
XFEM
