Feng Lu
7 Papers
13 Citations
Feng Lu is an academic researcher. The author has contributed to research in topics: Reactor pressure vessel & Fracture mechanics. The author has an hindex of 5, co-authored 7 publications.
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Papers
The deterministic structural integrity assessment of reactor pressure vessels under pressurized thermal shock loading
TL;DR: In this article, a 3-D finite element model is used to perform fracture mechanics analyses considering both crack initiation assessment and arrest assessment, and it is shown that the critical part along the crack front is always the clad-base metal interface point (IP) rather than the deepest point (DP) for either crack initiation or crack arrest assessment under the thermal load.
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Application of the French Codes to the Pressurized Thermal Shocks Assessment
Mingya Chen,Guian Qian,Jinhua Shi,Rongshan Wang,Weiwei Yu,Feng Lu,Guodong Zhang,Xue Fei,Zhilin Chen +8 more
TL;DR: In this article, an integrity assessment of an RPV subjected to a thermal shock transient based on the French RCC-M and RSE-M codes has been presented and compared with ASME and FAVOR codes.
9
Patent
Welding fixture for recombining metal samples
Rongshan Wang,Fei Xue,Qiang-mao Wan,Likui Weng,Feng Lu,Huang Ping +5 more
- 24 Nov 2010
TL;DR: In this article, the utility model relates to a welding fixture for recombining metal samples, which comprises a lower plate and an upper plate disposed on the lower plate, and the middle of the upper plate is provided with a crossed through hole.
3
Prediction of Irradiation Embrittlement for Chinese Domestic A508-3 Steel
Feng Lu,Rongshan Wang,Ping Huang,Haiyang Qian +3 more
- 01 Jan 2010
TL;DR: In this article, the prediction of irradiation embrittlement for a certain Chinese domestic manufactured A508-3 steel is performed, and the calculation results given by the US safety standards, the French RCC-M standards and other international safety standards are compared with each other and compared to the data from commercial operation NPP surveillance program.
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Structural integrity assessment of the reactor pressure vessel under the pressurized thermal shock loading
TL;DR: In this article, the influence of different parameters, such as crack size, cladding effect and neutron fluence, were reviewed based on 3-D finite element analyses, and the sensitivity study of elastic-plastic approach, crack type and cladding thickness were reviewed.