Abstract
In this opening chapter, we present the structure of world energy and the importance of fusion energy to solve world energy issues. In the view of tokamak as a main plant that produces and utilizes effectively the fusion energy, its basic operating principle and its main components are prescribed. During its being constructed tokamak subjects to engineering problems. The solution of its engineering problems commonly involve different mechanics that include solid mechanics, fluid mechanics, heat transfer theory, magnetic solid mechanics, MHD, and so on. Therefore, it is necessary to develop a special mechanics for meeting the requirements of design and manufacturing on tokamak. It is thus named as “tokamak engineering mechanics,” which contains statics, thermal stress, fatigue, fracture, and seismic response analysis and interactions in soil–structure and fluid–structure referring to components of the tokamak. The chapter ends with an overview of how our study on engineering mechanics on the tokamak is organized in the chapters to follow.
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References
BP Company (2012) BP statistical review of world energy
Weisz PB (2004) Basic choices and constraints on long-term energy supplies. Phys Today 57:47–52
Wesson J (1987) Tokamaks (Oxford Engineering Science Series). Clarendon Press, Oxford
http://www.websters-online-dictionary.org/definitions/Tokamak
Dale Meade (2010) 50 years of fusion research. Nucl Fusion 50:1–14
Yao DM, Song YT, Wu ST et al (2000) Design and structure analyses of HT-7U vacuum vessel, 21st SOFT 2000
Yao DM, Song YT, Wu ST et al (2003) HT-7U vacuum vessel [J]. Fusion Eng Des 69:355–359
Kim BC et al (2008) Recent progress of ITER vacuum vessel related design activities in Korea. Fusion Eng Des 83:1571–1577
ITER DDD (Design Description Document) (2012) 15 Vacuum vessel
Ioki K et al (2010) ITER vacuum vessel design and construction. Fusion Eng Des 85:1307–1313
How J et al (2009) PD—Plant description
Bauer et al P (2009) The ITER magnet feeder systems functional specification and interface document. ITER Organization, Cadarache
Jong CTJ, Mitchell N, Sborchia C (2001) The ITER-FEAT toroidal field structures. Fusion Eng Des 58–59:165–170
Lee YW, Ahn HJ, Choi CH (2003) Structural analysis of the KSTAR toroidal field magnet system. Fusion Eng Des 66–68:1195–1199
Watanabe K, Ikib S, Takiue K (2005) Structural and fracture mechanics analysis of ITER toroidal field coil. Fusion Eng Des 75–79:429–433
Xiao Bingjia, Weng Peide (2006) Integrated analysis of the electromagnetical, thermal, fluid flow fields in a Tokamak. Fusion Eng Des 81:1549–1554
Song Y, Nishio S (2005) Optimization study on the normal conducting center post for the low aspect ratio tokamak reactor. Fusion Eng Des 72:345–362
Tamai H, Kikuchi M, Arai T (1998) Stress analysis for the crack observation in cooling channels of the toroidal field coils in JT-60U. Fusion Eng Des 38:429–439
Takahashi H, Kudo Y, Tsuchiya K (2006) Fracture mechanics analysis including the butt joint geometry for the superconducting conductor conduit of the National Centralized Tokamak. Fusion Eng Des 81:1005–1011
Yao DM, Song YT, Wu ST (2001) Design and structure analysis of the HT-7U vacuum vessel. Fusion Eng Des 58–59:839–843
Song YT, Yao DM, Wu ST (2003) Structure analysis for the HT-7U vacuum vessel during quench of toroidal field. China Mech Eng 14:1261–1264
Song YT (2004) Numerical simulation and analysis for the baking out system of the HT-7U super-conducting Tokamak device. Nucl Power Eng 25:340–345
Song YT, Wu ST (2005) Structure design and stress analysis for the vacuum vessel of HELIMAK device. J Mech Strength 27:640–646
Song YT, Yao DM, Wu ST (2006) Structural analysis and manufacture for the vacuum vessel of experimental advanced superconducting tokamak (EAST) device. Fusion Eng Des 81:1117–1122
Song YT, Peng YH (2007) Analysis of EAST vacuum vessel load due to HALO current. Nucl Fusion Plasma Phys 27:222–226
Santra P, Bedakihale V, Ranganath T (2009) Thermal structural analysis of SST-1 vacuum vessel and cryostat assembly using ANSYS. Fusion Eng Des 84:1708–1712
Liu CL, Yu J, Wu ST (2006) Virtual design of ITER vacuum vessel in-wall shielding structure. China Mech Eng 17:15–18
Liu CL, Wu ST, Yu J (2005) Design of ITER vacuum vessel neutron shielding structure. Nucl Fusion Plasma Phys 25:68–73
Liu CL, Yu J, Wu ST (2007) Thermo-static FEM analysis for neutron shielding component of ITER vacuum vessel. J Mech Strength 29:67–071
Bohn FH, Czymek G, Giesen B (2001) Elastic-plastic cyclic deformation of the TEXTOR 94 modified liner under conditions of heating and plasma disruption. Fusion Eng Des 58–59:875–879
Bykov V, Krasikov Yu, Grigoriev S (2005) The ITER thermal shields for the magnet system: design evolution and analysis. Fusion Eng Des 75–79:155–162
Kim GH, Kim WC, Yang HL (2009) KSTAR thermal shield. Fusion Eng Des 84:1043–1048
Xie H, Liao ZY (2004) Structural design and analysis of thermal load for EAST tokamak thermal shield. Cryogenics 140:50–54
Xie H, Liao ZY (2004) Analysis of thermal load for EAST tokamak cryostat thermal shield design. Cryog Supercond 32:59–62
Xie H, Liao ZY (2005) Structural design and analysis of forces for the thermal shield of the EAST tokamak. Nucl Fusion Plasma Phys 25:133–138
Xie H, Wang XM, Liao ZY (2006) The analyze of vacuum and heat load for TS of EAST tokamak. Vac Cryog 12:157–161
Liu SM, Tao YT, Wu ST, Wang ZW (2009) Coupled analysis between structure and heat conduction on the thermal shield support of CTB for ITER. Nucl Fusion Plasma Phys 29:166–170
Cardella A, Gohar Y, Gorenflo H (1995) Thermal-mechanical analyses of the ITER shielding blanket designs. Fusion Eng Des 27:467–472
Ying A, Abdou M, Calderoni P (2006) Solid breeder test blanket module design and analysis. Fusion Eng Des 81:659–664
Vitkovsky IV, Golovanov MM, Divavin VA (2000) Neutronic, thermal–hydraulic and stress analysis of RF lithium cooled test blanket module for ITER. Fusion Eng Des 49–50:703–707
Aiello G, Gabriel F, Giancarli L (2007) Thermal–hydraulic analysis of the HCLL DEMO blanket. Fusion Eng Des 82:2189–2194
Ying A, Narula M, Hunt R (2007) Integrated thermo-fluid analysis towards helium flow path design for an ITER solid breeder blanket module. Fusion Eng Des 82:2217–2225
Jordan T, Schneiderb D (1996) Effects of an electrically conducting first wall on the blanket loading during a Tokamak plasma disruption. Fusion Eng Des 31:313–321
Smolentsev S, Abdoua M, Morley NB (2006) Numerical analysis of MHD flow and heat transfer in a poloidal channel of the DCLL blanket with a SiCf/SiC flow channel insert. Fusion Eng Des 81:549–553
Starke K, Bühler L, Horanyi S (2009) Experimental MHD—flow analyses in a mock-up of a test blanket module for ITER. Fusion Eng Des 84:1794–1798
Hua TQ, Gohar Y (1995) MHD pressure drops and thermal hydraulic analysis for the ITER breeding blanket design. Fusion Eng Des 27:696–702
Smolentsev S, Morley N, Abdou M (2005) Code development for analysis of MHD pressure drop reduction in a liquid metal blanket using insulation technique based on a fully developed flow model. Fusion Eng Des 73:83–93
Kurihara R, Ueda S, Nishio S (2001) Fracture mechanics evaluation of a crack generated in SiC/SiC composite first wall. Fusion Eng Des 54:465–471
Pinna T, Boccaccini LV, Salavy JF (2008) Failure mode and effect analysis for the European test blanket modules. Fusion Eng Des 83:1733–1737
Tanchuk V, Grigoriev S, Divavin V (2001) Thermal analysis of the tile impacted by concentrated heat loads caused by the lost of an upstream tile. Fusion Eng Des 56–57:225–231
Kurihara Ryoichi (2002) Thermofluid analysis of free surface liquid divertor in tokamak fusion reactor. Fusion Eng Des 61–62:209–216
Narula M, Abdou MA (2006) A. Ying, Exploring liquid metal plasma facing component (PFC) concepts-Liquid metal film flow behavior under fusion relevant magnetic fields. Fusion Eng Des 81:1543–1548
Mirnov SV, Evtikhin VA (2006) The tests of liquid metals (Ga, Li) as plasma facing components in T-3 M and T-11 M tokamaks. Fusion Eng Des 81:113–119
Song YT, Yao DM, Wu ST (2005) Thermal and mechanical analysis of the EAST plasma facing components. Fusion Eng Des 75–79:499–503
You JH, Bolt H (2003) Thermal stress intensity factor of interfacial cracks of a plasma facing component under high heat flux loading. Fusion Eng Des 65:483–492
Caporali R, Caruso G, Di Pace L (1998) Cryostat pressurization in ITER during an ex-vessel loss of coolant accident sequence. Fusion Eng Des 38:343–351
Yu J, Wu ST, Mao XQ (2007) Cryostat engineering design and manufacturing of the EAST superconducting Tokamak. Fusion Eng Des 82:1929–1936
Wang JQ, Tao YT, Wu ST (2006) Structural design and optimization of cryostat feed-through for ITER magnet. Nucl Tech 29:271–275
Zhang YB, Tao YT, Wu ST (2006) Structural design and analysis of cryostat feed-through for international thermonuclear experimental reactor. Atomic Energy Sci Technol 40:352–355
Wang KS, Zhao H, Tao YT et al (2008) ITER Optimization design and buckling analysis of the straight-line duct for ITER feeder. Nucl Fusion Plasma Phys 28:146–149
Li CC, Tao YT, Wu ST (2010) Thermal analysis on the ITER TF In-cryostat feeder system. Cryogenics 37:21–25
Wang JQ, Tao YT, Wu ST, Zhang YB (2005) Structural design and analysis of magnet feeder support for ITER. Mach Des Res 21:67–69
Wang JQ, Liu LB, Wu ST, Shao YJ (2009) Structural design and heat transfer calculation of cryostat feed-through auxiliary supports for ITER. Atomic Energy Sci Technol 43:716–719
Ciattaglia E, Ingesson LC, Campbell D (2007) ITER diagnostic port plug engineering design analysis in the EU. Fusion Eng Des 82:1231–1237
Doceul L, Walker C, Ingesson C (2007) CEA engineering studies and integration of the ITER diagnostic port plugs. Fusion Eng Des 82:1216–1223
Dong-man YU, Da-mao YAO, Han XIE (2009) Seismic response analysis for equatorial diagnostic port plug of international thermonuclear experimental reactor. J Cent South Univ Technol 16:112–118
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Song, Y., Wu, W., Du, S., Ni, X. (2014). Introduction. In: Tokamak Engineering Mechanics. Mechanical Engineering Series. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-642-39575-8_1
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DOI: https://doi.org/10.1007/978-3-642-39575-8_1
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