Conceptual design of the China fusion power plant FDS-II

Fusion Engineering and Design - Tập 83 Số 10-12 - Trang 1683-1689 - 2008
Yifei Wu1
1Institute of Plasma Physics, Chinese Academy of Sciences, P.O. Box 1126, Hefei, Anhui 230031, China

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Tài liệu tham khảo

Wu, 2006, Conceptual design activities of FDS series fusion power plants in China, Fusion Eng. Des., 81, 2713, 10.1016/j.fusengdes.2006.07.068

Wu, 2007, Design status and development strategy of China liquid lithium-lead blankets and related material technology, J. Nucl. Mater., 367–370, 1410, 10.1016/j.jnucmat.2007.04.031

Wu, 2006, Conceptual design of the fusion-driven subcritical system FDS-I, Fusion Eng. Des., 81, 1305, 10.1016/j.fusengdes.2005.10.015

Wu, 2005, Conceptual design study on the fusion power reactor FDS-II, Chin. J. Nucl. Sci. Eng., 25, 76

Wu, 2002, Progress in fusion-driven hybrid system studies in China, Fusion Eng. Des., 63–64, 73, 10.1016/S0920-3796(02)00239-9

H. Chen, Y. Wu, S.Konishi, Jim Hayward. A High Temperature Blanket Concept for Hydrogen Production, in: Presented at the 8th International Sympo-siumon Fusion Nuclear Technology (ISFNT-8), Heidelberg,Germany. September 30-October 5, 2007, 2007 (accepted by Fusion Engineering and Design).

ITER: “Study of Options for the Reduced Technical Objectives/Reduced Cost (RTO/RC). ITER”, report presented at the ITER Council Meeting No. 15, March 10–11, 1999. Also see “ITER-FEAT Outline Design Report”, ITER Meeting, Tokyo, January 2000.

Maisonnier, 2006, PPCS Team, DEMO and fusion power plant conceptual studies in Europe, Fusion Eng. Des., 81, 1123, 10.1016/j.fusengdes.2005.08.055

Najmabadi, 2006, The ARIES-AT advanced tokamak, advanced technology fusion power plant, Fusion Eng. Des., 80, 3, 10.1016/j.fusengdes.2005.11.003

Raffray, 2006, Advanced power core system for the ARIES-AT power plant, Fusion Eng. Des., 80, 79, 10.1016/j.fusengdes.2005.06.356

Yasushi, 2000, Overview of the Japanese fusion reactor studies programme, Fusion Eng. Des., 48, 247, 10.1016/S0920-3796(00)00148-4

Kikuchi, 2000, The advanced SSTR, Fusion Eng. Des., 48, 265, 10.1016/S0920-3796(00)00168-X

S. Zhang, Development and application of fusion economic analysis software SYSCODE, Ph.D. thesis, Chinese Academy of Sciences, China, 2007.

Sardain, 2006, The European power plant conceptual study: helium-cooled lithium–lead reactor concept, Fusion Eng. Des., 81, 2673, 10.1016/j.fusengdes.2006.07.056

Boccaccini, 2004, Materials and design of the European DEMO blankets, J. Nucl. Mater., 329–333, 148, 10.1016/j.jnucmat.2004.04.125

Norajitra, 2002, The EU advanced dual coolant blanket concept, Fusion Eng. Des., 61–62, 449, 10.1016/S0920-3796(02)00107-2

Norjitra, 2003, Conceptual design of dual-coolant blanket in the frame of the EU power plant conceptual study, Fusion Eng. Des., 69, 669, 10.1016/S0920-3796(03)00207-2

Norajitra, 2003, The EU advanced lead lithium blanket concept using SiCf/SiC flow channel inserts as electrical and thermal insulators, Fusion Eng. Des., 58–59, 629

Sze, 2000, Blanket system selection for ARIES ST, Fusion Eng. Des., 48, 371, 10.1016/S0920-3796(00)00146-0

Poitevin, 2002, Status of the design and performances of the WCLL test blanket module for ITER-FEAT, Fusion Eng. Des., 61–62, 431, 10.1016/S0920-3796(02)00108-4

Wong, 2006, An overview of dual coolant Pb-17Li breeder first wall and blanket concept development for the US ITER-TBM design, Fusion Eng. Des., 81, 461, 10.1016/j.fusengdes.2005.05.012

Rampal, 2005, HCLL TBM for ITER-design studies, Fusion Eng. Des., 75–79, 917, 10.1016/j.fusengdes.2005.06.322

Huang, 2007, Progress in development of china low activation martensitic steel for fusion application, J. Nucl. Mater., 367–370, 142, 10.1016/j.jnucmat.2007.03.153

Huang, 2007, R&D status of China low activation martensitic steel, Chin. J. Nucl. Sci. Eng., 27, 41

Liu, 2005, Structural design and analysis of dual-cooled lithium-lead blanket module for the fusion power reactor FDS-II, Chin. J. Nucl. Sci. Eng., 25, 91

J.F. Briesmeister (Ed.), MCNP4C General Monte Carlo Nparticle Transport Code, Los Alamos National Laboratory, LA-13709-M, 2000.

D. Lopez Aldama, A. Trkov, FENDL-2.1, Update of an Evaluated Nuclear Data Library for Fusion Applications, report INDC(NDS)-467, International Atomic Energy Agency (December 2004).

Li, 2007, Comparison analysis of 1D/2D/3D neutronics modeling for a fusion reactor

Wang, 2005, Thermal-hydraulics design and analysis on the dual-cooled lithium-lead breeder blanket for the fusion power reactor FDS-II, Chin. J. Nucl. Sci. Eng., 25, 163

Raffray, 2001, Design and material issues for high performance SiCf/SiC-based fusion power cores, Fusion Eng. Des., 55, 55, 10.1016/S0920-3796(01)00181-8

Chen, 2005, Temperature and stress calculation and analysis on dual-cooled lithium-lead breeder blanket structure for the fusion power reactor FDS-II, Chin. J. Nucl. Sci. Eng., 25, 174

Wang, 2002, Preliminary study on thermal features for high temperature gas-cooled reactor gas turbine cycle, Chin. High Tech. Lett., 9, 91

Malang, 1998, Combination of a self-cooled liquid metal breeder blanket with a gas turbine power conversion system, Fusion Eng. Des., 41, 561, 10.1016/S0920-3796(98)00220-8

Wu, 2007, Integrated multi-functional neutronics calculation and analysis code system: VisualBUS, Chin. J. Nucl. Sci. Eng., 27, 365

Gao, 2004, Integral data test of HENDL1.0/MG and VisualBUS with neutronics shielding experiments (I), Plasma Phys. Technol., 6, 2507, 10.1088/1009-0630/6/5/016

Gao, 2004, Integral data test of HENDL1.0/MG with neutronics shielding experiments (II), Plasma Phys. Tech., 6, 2598

Chen, 2005, Activation analysis and waste management for dual-cooled lithium-lead breeder (DLL) blanket of the fusion power reactor FDS-II, Chin. J. Nucl. Sci. Eng., 25, 178

Clearance levels for radionuclides in solid materials: application of the exemption principles, Interim Report for Comment, IAEA TECDOC-855, Vienna, January 1996.

Sheffield, 1986, Cost assessment of a feneric magnetic fusion reactor, Fusion Technol., 9, 199, 10.13182/FST9-2-199

Huang, 2004, Economic analysis of the fusion driven subcritical system, Chin. J. Nucl. Sci. Eng., 24, 184