scholarly journals Mechanical analysis of sealing performance for compression packer rubber tube

2018 ◽  
Vol 19 (3) ◽  
pp. 309 ◽  
Author(s):  
Fuying Zhang ◽  
Xiangmin Jiang ◽  
Honghao Wang ◽  
Nana Song ◽  
Jianlei Chen ◽  
...  

The compression packer rubber is one of the core components of the packer. According to the sealing mechanism of the compression packers rubber, the deformation of rubber between the central tube and casing tube is analyzed in the initial and working stages. The compression rubber is also strained radially against the support ring by means of a controlled tubular expansion process. In this paper, the theoretical model for the deformation analysis is established by the structure and working characteristics of rubber tube. In addition, the nonlinear relationship between the material, geometry and stress in the constrained and stable deformation stages is analyzed by application of pressure methods. The analytical results show the contact pressure and shear stress distribution on the sealing surface of the rubber and the effect of rubber geometry and its material properties on sealing performance in terms of maximum sealing pressure. Then, the criterion of sealing performance evaluation of the rubber is established by the numerical results. This analytical model will provide a theoretical basis and guidance for the structural design of the compression packer rubber and it will be of great significance to improve the sealing performance and reliability of packer rubber.

Author(s):  
Weiping Qiu ◽  
Jianbo Wang ◽  
Wangyu Liu ◽  
Zhenhong Xie ◽  
Pengfei Tian ◽  
...  

2020 ◽  
Vol 316 ◽  
pp. 02001
Author(s):  
Jing Sheng ◽  
Aamir Sohail ◽  
Mengguang Wang ◽  
Zhimin Wang

In order to realize the need for lightweight automobiles through replacing steel with plastics, the research and development of the plastic clutch pump body based on the friction welding was carried out. For the clutch pump body connected by friction welding process between the upper pump body and the lower pump body, the technical requirements of pressure 14 MPa and durability (high temperature 7.0 × 104 times, room temperature 7.0 × 105) are required. The structure type of the upper and lower pump bodies of the end face welding type was proposed. Through the static analysis of the pump body and weld and the mechanical analysis under the working condition, the structure of the clutch pump body (upper and lower pump body) was determined. According to the established welding process, the pressure of the clutch pump body is more than 15 MPa, and the number of high-temperature durable circulation and the number of room temperature durable circulation also reached 7.2×104 and 7.3×105 times respectively. The results show that the structural design of a clutch pump body meets the design requirements.


Author(s):  
T. Zhou ◽  
Y. Song

International Thermonuclear Experimental Reactor (ITER) TF feeder systems convey the cryogenic supply and electrical power to the TF coils. The Cryostat Feed-through (CFT) includes the straight feeder part from the cryostat wall to the S-Bend Box (SBB). It is the bottleneck of the feeders. The huge Lorentz-force is a challenge for the CFT design. So the reasonable distribution and structural design of the internal and external supports are important. The CFT include the cold (cryogenic) to warm (room temperature) transitions. It is highly integrated with the cryo-pipes, the busbars, the superconductor joints, the thermal radiation shield and the instrumentation pipes and so on. The cryogenic and electrical requirements, the vacuum and mechanical requirements, and so on are considered when the CFT is designed. This paper presents the functional requirements on the TF CFT, gives its structure. The supports are designed and arrayed according to their mechanical or thermal function separately to stand the huge mechanical loads and isolate the conducting heat load from room temperature respectively. The assembly scheme is also described. Mid-joint and cryostat joint are designed to give the facility for the assembly on location. The mechanical analysis result shows the stress in the stainless steel and G10 material both are within the materials stress safety margin. The heat load to the cryogenic pipes and busbars are also less than the requirement 15W. Transient thermal analysis of global feeder model indicates that 32 days are needed for the feeder components to cool down to the required condition.


Author(s):  
Yuya Omiya ◽  
Masahiro Fujii

Abstract Pipe flange connection with metal gasket is used under high temperature and pressure in place required high sealing performance. It has been known that gasket compressive force, which is closely related the leakage decreases by internal pressure action. Since the pressure is very high in metal gaskets, the sealing performance evaluation in internal pressure action is important. However, there is little research that evaluates a little leakage, metal gasket is empirically used up to the present time. Therefore, evaluated sealing performance of metal gasket, it is necessary to clarify the sealing mechanism. In this study, evaluated effect that decreasing of gasket compressive force affects leakage in both octagonal type and oval type in ring joint gasket by simplified leak test using grooved platen and finite element method stress analysis, evaluation method of leakage in metal gasket is proposed. Based on this evaluation method, decision method of initial tightening force that guaranteed one amount of leakage to design internal pressure is shown in pipe flange connection with metal gasket.


2012 ◽  
Vol 502 ◽  
pp. 392-396
Author(s):  
Hong Li ◽  
Kun Ju Bai

this paper, focusing on the actuality and the features of the cold ring rolling, studies the forming principle of the rolling of multi-mandrel roller. Through the kinematics analysis of the rolling of ring multi-mandrel roller, the deformation simulation and the mechanical analysis of the infinitesimal gridding strain, this paper builds the infinitesimal deformation model of ring blank’s cold rolling, analyzes the deformation rules of the ring blank’s thickness direction rolled by the multi-mandrel roller and the relation between the tangential strain and the radial strain which should be satisfied by the mandrel roller’s movement values, and deduces out the mathematical expressions of the needed technological parameters like the minimum instantaneous rolling reduction. The research result can be used as the theoretical foundations for designing the multi-mandrel rolling miss and working out the rolling technology of the ring multi-mandrel roller.


1981 ◽  
Vol 103 (4) ◽  
pp. 380-387
Author(s):  
V. K. Sazawal

This paper presents the results of a comprehensive trial application of the draft structural design criteria for highly irradiated core components to a typical blanket assembly duct. The development of the criteria (proposed RDT F 9-7) is sponsored by the U.S. Department of Energy. The activity focuses on the evaluation of the criteria using a typical breeder reactor blanket assembly as a test case and is not intended for judging the adequacy of the component design. Pertinent design rules from the draft criteria are applied to the component to determine: (a) difficulties, if any, that may arise in interpretation and application of the criteria, and (b) adequacy of the criteria rules and analysis methods to address various potential failure mechanisms expected in the reactor core during service. Based on the trial application, various recommendations are made to promote further development of the criteria.


2016 ◽  
Vol 697 ◽  
pp. 797-806
Author(s):  
Junya Sumita ◽  
Taiju Shibata ◽  
Tatsuo Iyoku ◽  
Masahiro Ishihara ◽  
Tetsuo Nishihara

Nuclear energy is one of the most promising energy sources to satisfy energy security, environmental protection, and efficient supply. The High Temperature Gas-cooled Reactor (HTGR) has attractive inherent safety features and it can be used as many kinds of heat applications such as hydrogen production, electricity generation, process heat supply, district heating and desalination. Many countries, especially developing countries, show their interests in HTGR. Graphite materials are used for the core components of the HTGR. IG-110 graphite, fine-grained isotropic graphite, with high strength and high oxidation resistance is used in the High temperature Engineering Test Reactor (HTTR) of Japan Atomic Energy Agency (JAEA) and High Temperature Reactor-Pebble-bed Modules (HTR-PM) in China. IG-110 graphite is a major candidate for the core graphite components of the Very High Temperature Reactor (VHTR) which is one of HTGRs and one of the most promising candidates as the Generation-IV nuclear reactor systems. This paper describes design of core components of HTTR and R&D on nuclear graphite for HTGR. JAEA established the graphite structural design code and inspection standard of graphite to construct the HTTR. JAEA developed an in-service inspection method and a draft graphite structural design code for future HTGR on the basis of the HTTR technologies. Moreover, JAEA are now developing the design data base of IG-110 graphite and IG-430 graphite including irradiation data for HTGR.


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