A fusion reactor design with a liquid first wall and divertor

Fusion Engineering and Design - Tập 72 - Trang 181-221 - 2004
R.E. Nygren1, T.D. Rognlien2, M.E. Rensink2, S.S. Smolentsev3, M.Z. Youssef3, M.E. Sawan4, B.J. Merrill5, C. Eberle6, P.J. Fogarty6, B.E. Nelson6, D.K. Sze7, R. Majeski8
1Sandia National Laboratories, P.O. Box 5800, MS 1129, Albuquerque, NM 87185-1129, USA
2Lawrence Livermore National Laboratory, USA
3University of California, Los Angeles, CA USA
4University of Wisconsin, USA
5Idaho National Energy and Environmental Laboratory, USA
6Oak Ridge National Laboratory, USA
7University of California, San Diego, CA, USA
8Princeton Plasma Physics Laboratory, USA

Tài liệu tham khảo

Abdou, 1999, Exploring novel high power concepts for attractive fusion systems, Fus. Eng. Des., 45, 145, 10.1016/S0920-3796(99)00018-6 Mattas, 2000, ALPS – advanced limiter-divertor plasma facing systems, Fus. Eng. Des., 49–50, 127, 10.1016/S0920-3796(00)00385-9 B. Badger, UWMAK-I, A Wisconsin Toroidal Fusion Reactor Design, University of Wisconsin, UWFDM-68, 1973. Golubchikov, 1976, Development of a liquid-metal fusion-reactor divertor with a capillary-pore system, JNM, 237, 667, 10.1016/S0022-3115(96)00010-4 Pitts, 1980, A consistent HYLIFE wall design that withstands transient loading conditions Muraviev, 1980, Contact devices for divertor and limiter systems of Tokamak reactors. I. Devices with LM working surface, Voprosy Atomnoi Nauki I Tekhniki Ser. Termoyaderniy Sintez, 2, 57 Wells, 1981, A system for handling divertor ion and energy flux based on a lithium droplet cloud, Nucl. Technol./Fus., 1, 120 Baranov, 1983, Liquid metal film flow for fusion application Bond, 1984, A liquid metal protected divertor for a demo reactor, 1225 Karasev, 1988, LM contact divertor for INTOR Tokamak reactor, 225 Vodyanyuk, 1988, Liquid metal Tokamak limiter – problem definition and first results, Plasma Phys., 14, 628 I. Kirillov, Alternate concepts of the divertor targets working materials to the ITER, October 1990, ITER-IL-PC-8-0-18. Liao, 1992, A feasibility assessment of liquid-metal divertors, Fus. Technol., 21, 1845, 10.13182/FST92-A29987 Mirnov, 1992, Liquid-metal Tokamak divertors, JNM, 196, 45, 10.1016/S0022-3115(06)80010-3 Chuyanov, 1994, Advanced divertor plates system development proposal, ITER EDA Memo Muraviev, 1995, Liquid-metal-cooled divertor for ARIES, Fus. Eng. Des., 29, 98, 10.1016/0920-3796(95)80011-L Muraviev, 1995, Open surface MHD flow of liquid metal coolant in a rotating divertor target of a Tokamak fusion reactor, Magnetohydrodynamics, 31, 306 Pistunovich, 1996, Research of the capillary structure heat removal efficiency under divertor conditions, JNM, 237, 650, 10.1016/S0022-3115(96)00050-5 Lazarev, 1999, Compatibility of the lithium capillary limiter with plasma in T-11M, ECA, 23J, 845 Evtikhin, 2000, Energy removal and MHD performance of lithium capillary-pore systems for divertor target application, FED, 49, 195, 10.1016/S0920-3796(00)00423-3 Mahdavi, 1998, Heat removal with a liquid pellet curtain (paper) Sheffield, 1998, World population and energy demand growth: the potential role of nuclear energy in an efficient world, Fus. Technol., 34, 281, 10.13182/FST98-A11963630 Sheffield, 1999, World population and energy demand growth: the potential role of fusion energy in an efficient world, Phil. Trans. R. Soc. London Ser. A: Math. Phys. Eng. Sci., 357, 377, 10.1098/rsta.1999.0333 Sheffield, 2001, An assessment of the economics of future electric power generation options and the implications for fusion, Fus. Technol., 39, 228 Tillack, 1998, Engineering Design of the ARIES-RS Power Plant, Fus. Eng. Des., 41, 491, 10.1016/S0920-3796(97)00161-0 Wong, 1997, ARIES divertor system – selection and analysis, FED, 38, 115, 10.1016/S0920-3796(97)00117-8 Rognlien, 2001, Edge-plasma properties in liquid-wall environments Merrill, 2002, Safety implications of CliFF liquid metal first walls, FED, 63–64, 285 Rognlien, 2001, Interactions between liquid-wall vapor and edge plasmas, JNM, 290–293, 312, 10.1016/S0022-3115(00)00575-4 Bastasz, 2001, Plasma–Surface Interactions on Liquids, JNM, 290–293, 19, 10.1016/S0022-3115(00)00557-2 Brooks, 2001, Erosion/redeposition of lithium-based liquid surface divertors, JNM, 290-293, 185, 10.1016/S0022-3115(00)00608-5 S. Smolentsev, B. Freeze, N. Morley, M. Abdou, Experimental study of turbulent supercritical open channel water flow as applied to the CLiFF concept, Fus. Eng. Des., in press. B. Freeze, S. Smolentsev, N. Morley, M. Abdou, Characterization of surface waves and their effect on heat transfer in high Fr, high We open channel turbulent water flow, Int. J. Heat Mass Transfer, in press. Smolentsev, 2002, Application of the K–epsilon model to open channel flows in a magnetic field, Int. J. Eng. Sci., 40, 693, 10.1016/S0020-7225(01)00088-X Brooks, 2000, Sheath superheat transmission due to redeposition of thermally emitted material, Phys. Plasmas, 7, 2565, 10.1063/1.874097 Naujoks, 2001, Combined sheath and thermal analysis of overheated surfaces in fusion devices, JNM, 290–293, 1123, 10.1016/S0022-3115(00)00549-3 Brooks, 2002, Modeling of sputtering erosion/redeposition – status and implications for fusion design, FED, 60, 515, 10.1016/S0920-3796(02)00007-8 Ueda, 1977, Eddy diffusivity near the free surface of open channel flow, Int. J. Heat Mass Transfer, 20, 1127, 10.1016/0017-9310(77)90121-1 J.H. Schaffer, Preparation and handling of salt mixtures for the molten salt reactor experiments, Oak Ridge National Laboratory, Oak Ridge, TN, 1971, ORNL-4616. S. Cantor, Density and viscosity of several molten flouride mixtures, Oak Ridge National Laboratory, Oak Ridge, TN, 1973. ORNL/TM-4308 Cantor, 1969, Viscosity and density in LiF–BeF2 solutions, J. Chem. Phys., 50, 2874, 10.1063/1.1671478 S. Cantor, S.D.S. Hsu, W.T. Ward, Vapor pressures of flouride melts, Reactor Chem. Div. Annual Progress Report, Oak Ridge National Laboratory, Oak Ridge, TN, 1965, ORNL-391324-26. W.R. Grimes, et al., Fused-salt Systems, Sec. 6 in Reactor Handbook, vol. 2, Engineering, USAEC Report AECD-3646, 1955. R.E. Moore, C.J. Barton, W.R. Grimes, R.E. Meadows, L.M. Bratcher, G.D. White, T.N. McVay, L.A. Harris, in: R.B. Thoma (Ed.), Phase Diagrams of Nuclear Reactor Materials, Oak Ridge National Laboratory, ORNL-2548, 1959, p. 43 Levin, 1979, 436 Toropov, 1957, Modelnye Sistemy – Na2BeF4–Li2BeF4 I Ca2SiO4–Mg2SiO4, Zhurnal Neorganische Khimi 2, 8, 1855 Levin, 1979, 436 R.W. Moir, M.G. Adamson, R.O. Bangerter, R.L. Bieri, R.H. Condit, et al., HYLIFE Progress Report, Lawrence Livermore National Laboratory, Livermore, CA, 1991. UCID-21816 Moir, 1994, HYLIFE-II: a molten-salt inertial fusion energy power plant design – final report, Fus. Technol., 25, 5, 10.13182/FST94-A30234 D.L. Smith, et al., Blanket comparison and selection study (final report), vols. 1–3, Argonne National Laboratory, Argonne, IL, September 1984. ANL-Report, ANL:FPP-84-1 Smith, 1985, Overview of the blanket comparison and selection study, Fus. Technol., 8, 10, 10.13182/FST85-4 Sze, 2001, Flibe assessments, Fus. Technol., 2, 746, 10.13182/FST01-A11963328 Muroga, 2002, Overview of materials research for fusion reactors, FED, 61–62, 13, 10.1016/S0920-3796(02)00219-3 Zinkle, 2000, Operating temperature windows for fusion reactor structural materials, Fus. Eng. Des., 51–52, 55, 10.1016/S0920-3796(00)00320-3 R.L. Klueh, et al. Microstructure and mechanical properties of oxide dispersion-strengthened steels, DOE/ER-0313/28, June 2000 Klueh, 2002, Tensile and creep properties of an oxide dispersion-strengthened ferritic steel, J. Nucl. Mater., 307–311, 773, 10.1016/S0022-3115(02)01046-2 Ukai, 2002, Perspective of ODS alloys application in nuclear environments, J. Nucl. Mater., 307–311, 749, 10.1016/S0022-3115(02)01043-7 Smith, 2002, Progress in coating development for fusion systems, FED, 61–62, 629, 10.1016/S0920-3796(02)00291-0 Youssef, 2001, Nuclear performance of the thin-liquid FW concept of the CLiFF design, Fus. Technol., 39, 839, 10.13182/FST01-A11963344 Youssef, 2002, The breeding potential of Flinabe and comparison to Flibe in CLiFF high power density concept, Fus. Eng. Des., 61–62, 497, 10.1016/S0920-3796(02)00245-4 Youssef, 2002, Component lifetime comparison and waste volume in CLiFF Sn/Flibe and Sn/LiPb blankets, this issue, Fus. Eng. Des., 63–64, 277, 10.1016/S0920-3796(02)00252-1 Youssef, 2000, Heat deposition, damage, and tritium breeding characteristics in thick liquid wall blanket concepts, Fus. Eng. Des., 49–50, 719, 10.1016/S0920-3796(00)00179-4 Youssef, 2002, Radwaste volume in lithium and Flibe LW and comparison to conventional SW concepts, Fus. Eng. Des., 63–64, 263, 10.1016/S0920-3796(02)00251-X W.W. Engle, ANISN: a one dimensional discrete ordinates transport code with anisotropic scattering, Report K-1693, Union Carbide Corporation, 1967. A.B. Pashchenko, Completion of FENDL-1 and start of FENDL-2, INDC(NDS)-352, IAEA Nuclear Data Section, International Atomic Energy Agency, March 1996. Najmabadi, 1997, Overview of the ARIES-RS reversed-shear Tokamak power plant study, Fus. Eng. Des., 38, 3, 10.1016/S0920-3796(97)00110-5 Youssef, 1998, X-ray surface and volumetric heat deposition and tritium breeding issues in liquid-protected FW in high power density devices, Fus. Technol., 34, 697, 10.13182/FST98-A11963696 A.P. Malinauskas, D.M. Richardson, MSR Program Semiannual Progress Report, Oak Ridge National Laboratory, Oak Ridge, TN, February 1972, ORNL-4782. R. Aymar, et al., Technical Basis for the ITER Final Design Report, Cost Review and Safety Analysis (FDR), ITER EDA Documentation Series No. 16, International Atomic Energy Agency, Vienna, 1998, Chapter IV, pp. 36–50. DOE STD 6002-96, The Safety of Magnetic Fusion Facilities: Requirements, May 1996. L. Cadwallader, D. Petti, Safety in the design of three burning plasma experiments, in: Presented at the 15th Topical Meeting on the Technology of Fusion Energy, Washington, DC, 17–21 November 2002, Fus. Sci. Technol., in press. R.E. Alcouffe, et al., DANTSYS 3.0, One-, two-, and three-dimensional multigroup discrete ordinates transport code system, RSICC Computer Code Collection CCC-547, Contributed by Los Alamos National Lab, August 1995. M.J. Sisolak, Q. Wang, H. Khater, D. Henderson, DKR-PULSAR2.0: a radioactivity calculation code that includes pulsed/intermittent operation, in press. A. Pashchenko, et al., FENDL/A-2.0: neutron activation cross-section data library for fusion applications, Report INDC(NDS)-173, IAEA Nuclear Data Section, March 1997. B.J. Merrill, J.L. Jones, D.F. Holland, TMAP/MOD1: Tritium migration analysis program code description and user's manual, Idaho National Engineering Laboratory Report, EGG-EP-7407, April 1988. R.O. Gauntt, et al., MELCOR Computer Code Reference Manuals: Version 1.8.4, NUREG/CR-6619, vol. 2, Rev. 1, July 1997, HS-RM 37-41. Merrill, 2000, Modifications to the MELCOR code for application in fusion accident analysis, Fus. Eng. Des., 51–52, 555, 10.1016/S0920-3796(00)00220-9 Wong, 2001, Evaluation of the tungsten alloy vaporizing lithium first wall and blanket concept, Fus. Technol., 39, 815, 10.13182/FST01-A11963340 Steiner, 1997, ARIES-RS safety design and analysis, Fus. Eng. Des., 38, 189, 10.1016/S0920-3796(97)00116-6 M. Abbott, Revised results – MACCS2 doses for fusion isotopes released to the atmosphere using P-G dispersion parameters, An INEEL letter to D.A. Petti, MLA-11-99, 14 April 1999. Merrill, 2002, Safety implications of CLiFF liquid metal first walls, FED, 63–64, 285, 10.1016/S0920-3796(02)00254-5 Ying, 2000, MHD and heat transfer issues and characteristics for Li free surface flows under NSTX conditions Kaita, 2002, Spherical torus plasma interactions with large-area liquid lithium surfaces in CDX-U, Fus. Eng. Des., 61–62, 217, 10.1016/S0920-3796(02)00117-5 Majeski, 2003, CDX-U operation with a large area liquid lithium limiter, J. Nucl. Mater., 313, 625, 10.1016/S0022-3115(02)01365-X See conference website: http://www.aps.org/meet/DPP00/baps/abs/S1350.html. R.E. Nygren, Part 4, Section 7, Notes on the thermal Properties of Sn, ALPS Report, August 2001, p. 162. http://fusion.anl.gov/ALPS_Info_Center/alps.pdf.