scholarly journals Thick SS316 materials TIG welding development activities towards advanced fusion reactor vacuum vessel applications

2012 ◽  
Vol 390 ◽  
pp. 012063 ◽  
Author(s):  
B Ramesh Kumar ◽  
R Gangradey
2021 ◽  
Vol ahead-of-print (ahead-of-print) ◽  
Author(s):  
Changyang Li ◽  
Huapeng Wu ◽  
Harri Eskelinen ◽  
Haibiao Ji

Purpose This paper aims to present a detailed mechanical design of a seven-degrees-of-freedom mobile parallel robot for the tungsten inert gas (TIG) welding and machining processes in fusion reactor. Detailed mechanical design of the robot is presented and both the kinematic and dynamic behaviors are studied. Design/methodology/approach First, the model of the mobile parallel robot was created in computer-aided design (CAD) software, then the simulation and optimization of the robot were completed to meet the design requirements. Then the robot was manufactured and assembled. Finally, the machining and tungsten inert gas (TIG) welding tests were performed for validation. Findings Currently, the implementation of the robot system has been successfully carried out in the laboratory. The excellent performance has indicated that the robot’s mechanical and software designs are suitable for the given tasks. The quality and accuracy of welding and machining has reached the requirements. Originality/value This mobile parallel industrial robot is particularly used in fusion reactor. Furthermore, the structure of the mobile parallel robot can be optimized for different applications.


2020 ◽  
Vol 152 ◽  
pp. 111453 ◽  
Author(s):  
Jianguo Ma ◽  
Jiefeng Wu ◽  
Zhihong Liu ◽  
Haibiao Ji ◽  
Xiaosong Fan

2008 ◽  
Vol 580-582 ◽  
pp. 431-434 ◽  
Author(s):  
Ha Geun Kim ◽  
Sang Beom Shin ◽  
Dae Soon Kim

The purpose of this study is to establish the proper control method of angular distortion of multi-pass STS 316LN weldment in the vacuum and cryostat vessel of the fusion reactor. To achieve it, the predictive equation of angular distortion in the multi-pass STS 316LN weldment with reference to welding heat input and effective bending rigidity of weldment was established using FEA and experiment. The bending restraint degree of each weldment in the the vacuum vessels of the fusion reactor was evaluated using FEA. Based on the prediction equation of distortion, both proper welding deposit sequence of double sided butt weldment of STS 316LN for cryostat vessel and proper welding sequence for the vacuum vessel were established and verified by the measured distortion of actual welded structure.


2000 ◽  
Vol 2000 (0) ◽  
pp. 613-614
Author(s):  
Takashi SHIMAKAWA ◽  
Sabrou USAMI ◽  
Koichi KOIZUMI ◽  
Kenzo MIYA ◽  
Hideo KOBAYASHI

Author(s):  
R. Lo Frano ◽  
A. Pesetti ◽  
D. Aquaro ◽  
M. Olcese

Abstract The Direct Contact Condensation (DCC) is the main phenomenon characterizing the steam condensation. It plays an important role for the operation of Vacuum Vessel Pressure Suppression System (VVPSS) tanks, particularly for managing the Ingress of Coolant Event (determining fusion reactor overpressurization). It is safety relevant (key) system of the fusion reactor because by condensing the steam generated during such accident event allows to damp the overpressure. This paper deals with experimental and theoretical analyses of the DCC at sub-atmospheric pressure. The similitude analysis was elaborated to scale up the experimental results obtained in the reduced scale facility: similitude laws are used for the design of large experimental rig. Correlations are defined starting from the water temperature and pressure variation already obtained in the small-scale rig. Furthermore, the experimental rig and its main components accordingly designed (and under construction at the University of Pisa) allow to study at large scale the steam condensation. The testing conditions are presented and discussed.


2006 ◽  
Vol 81 (19) ◽  
pp. 2213-2220 ◽  
Author(s):  
J. Jordanova ◽  
U. Fischer ◽  
P. Pereslavtsev ◽  
Y. Poitevin ◽  
A. Li Puma ◽  
...  
Keyword(s):  

Author(s):  
Takayuki SUZUKI ◽  
Saburo USAMI ◽  
Takae KIMURA ◽  
Kouichi KOIZUMI ◽  
Masataka NAKAHIRA ◽  
...  

Author(s):  
H. J. Ahn ◽  
B. C. Kim ◽  
J. W. Sa ◽  
Y. J. Lee ◽  
K. H. Hong ◽  
...  

The ITER vacuum vessel (VV) is a double walled torus structure and one of the most critical components in the fusion reactor. The design and fabrication of the VV as nuclear equipment shall be consisted with the RCC-MR code based on French fast breeder reactor. The VV is a heavy welded structure with 60 mm thick shells, 40 mm ribs and flexible housing of 275 mm diameter. The welding distortion should be controlled since the total welding length is over 1500 m. To satisfy the design requirement, the electron beam welding (EBW) and narrow gap gas tungsten arc welding (GTAW) techniques are to be applied and developed through the fabrication of mock-ups. The fabrication design has been developed to manufacture the main vessel and port structures in accordance with the RCC-MR code. All fabrication sequences including welding methods are also established to meet the demanding tolerance and inspection requirement by HHI as a supplier.


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