High Precision Analysis of Stress Concentration in Girder Structure of Casting Crane
Qin Yixiao,
Jiang Ji,
Yang Haiming
Issue:
Volume 2, Issue 2, September 2016
Pages:
14-18
Received:
12 July 2016
Accepted:
25 July 2016
Published:
26 August 2016
Abstract: The stress concentration is easily occurred in the key local position of the main girder structure of casting crane with heavy load. The sub model method has the advantages of high efficiency and high precision in solving the complicated stress and strain problems of the local structure. Based on the result of finite element model analysis of whole bridge girder, the sub model technology is used to cut the local model of the main beam and partition more refined finite element meshes. The cutting boundary displacement of the whole bridge girder model is regarded as the forced displacement load that is applied on the boundary of the local model. The results that are closer to the engineering practical calculation can be obtained by analyzing and solving. The engineering analysis method in this paper can provide reference for product design.
Abstract: The stress concentration is easily occurred in the key local position of the main girder structure of casting crane with heavy load. The sub model method has the advantages of high efficiency and high precision in solving the complicated stress and strain problems of the local structure. Based on the result of finite element model analysis of whole...
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Assessment of Off-Site Consequences Due to Severe Nuclear Accident According to Release Pathway Reduction Mechanisms Using Computer Code
Elsayeda Farid Salem,
Asmaa. Khalill Abdeen,
Mohamed Abdelrahman Salama
Issue:
Volume 2, Issue 2, September 2016
Pages:
19-23
Received:
3 September 2016
Accepted:
20 October 2016
Published:
8 November 2016
Abstract: In order to protect public health and safety from the inadvertent release of radioactive materials, during a reactor accident the defense-in-depth strategy must include; multiple layers of protection, such as prevention of accidents, mitigation features and emergency preparedness program that include measures such as sheltering and evacuation. In the present work RASCAL computer code is going to be used to estimate the offsite consequences of a nuclear sever accident using release pathway reduction mechanisms in order to obtain an appropriate release at a Pressurized Water Reactor (PWR) operating at its full power. The existing plant (systems, equipment) assuming that will be used for accident mitigation. Calculation of the total effective dose associated with this reduction is proposed. The data obtained showed that the spray system is the most effective mechanism to mitigate dose release during the accident.
Abstract: In order to protect public health and safety from the inadvertent release of radioactive materials, during a reactor accident the defense-in-depth strategy must include; multiple layers of protection, such as prevention of accidents, mitigation features and emergency preparedness program that include measures such as sheltering and evacuation. In t...
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