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Literaturverzeichnis
Abschnitt 1.1
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Abschnitt 1.2
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Abschnitt 1.3
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Abschnitt 1.4
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Abschnitt 2.1
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Abschnitt 2.2
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Varian Ass., Palo Alto, Calif., USA, Typ Nr. VGA-8000 und VGA-8050A
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Abschnitt 2.3
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Abschnitt 2.4
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Swinhoe M.T., C.A. Uttley: “Measurements of MeV neutron cross-sections by activation”, in: United Kingdom Nuclear Data Progress Report 1978 (1979) 54
DeVan J.H.: “Compatibility of structural materials with fusion reactor coolant and breeder fluids”, Proc. of the First Topical Meeting on Fusion Reactor Materials, Miami Beach, Florida, 1979
DeVan J.H.: “Compatibility of structural materials with fusion reactor coolant and breeder fluids”, J. of Nucl. Mat. 85&86 (1979) 249
Dänner W.: “First Wall and blanket structure performance”, Transactions of the 5th International Conference on Structural Mechanics in Reactor Technology, Berlin, 1979, Bd. N, Beitrag N2.4/1
Badger B. et al.: “UWMAK-I, a Wisconsin toroidal fusion reactor design”, University of Wisconsin, Report UWFDM-68 (Bd. I 1974, Bd. II 1975)
Badger B. et al.: “UWMAK-III, a high performance noncircular tokamak power reactor design”, University of Wisconsin, Report UWFDM-150 (1976)
Stanbridge J.R., H.M. Carruthers, B.A. Keen, H.A. Shotter: “Design of stainless steel blanket cells for a fusion reactor”, Culham Laboratory, Report CLM-R 127 (1974)
Wells W.M.: “ORNL fusion power demonstration study: Lithium as a blanket coolant”, Oak Ridge National Laboratory, Report ORNL-TM-6214 (1978)
Kearney D.U. et al.: “Mechanical and thermal design of a gas-cooled fusion blanket module”, General Atomic Co., Report GA-A14671 (1977)
Farfaletti-Casali F. et al.: “Design of a modular blanket with gas cooled liquid lithium”, Proc. of the 3rd Topical Meeting on the Technology of Controlled Nuclear Fusion, Santa Fe, New Mexico, 1978, Bd. 1, S. 249
Smidt D.: “Reaktortechnik”, Bd. 1, Karlsruhe (1971) 37
Radiation Shielding Information Center: “360 ANISN, a one dimensional discrete ordinates transport code”, Oak Ridge National Laboratory, Report CCC-82 (1973)
Lathrop K.D.: “DTF-IV, a FORTRAN-IV program for solving the multigroup transport equation with anisotropic scattering”, Los Alamos Scientific Laboratory, Report LA-3373 (1965)
Hill T.R.: “ONETRAN: a discrete ordinates finite element code for the solution of the one-dimensional multigroup transport equation”, Los Alamos Scientific Laboratory, Report LA-5990-MS (1975)
Radiation Shielding Information Center: “DOT 3.5, two dimensional discrete ordinates radiation transport code”, Oak Ridge National Laboratory, Report CCC-276 (1978)
Radiation Shielding Information Center: “TWOTRAN, two-dimensional discrete ordinates code system programs”, Oak Ridge National Laboratory, Report CCC-195
Radiation Shielding Information Center: “MORSE-CG, General purpose Monte Carlo multigroup neutron and gamma-ray transport code system”, Oak Ridge National Laboratory, Report CCC-203
Plaster D.M., R.T. Santoro, W.E. Ford III: “Coupled 100-group neutron and 21-group gamma-ray cross-sections for EPR calculations”, Oak Ridge National Laboratory, Report ORNL-TM-4872 (1975)
Radiation Shielding Information Center: “VITAMIN-C, 171 neutron, 36 gamma-ray group cross-sections in AMPX and CCCC interface formats for fusion and LMFBR neutronics”, Oak Ridge National Laboratory, Report DLC-41 (1978)
Garber D., C. Dunford, S. Pearlstein: “ENDF-102, Data formats and procedures for the evaluated nuclear data file, ENDF”, Brookhaven National Laboratory, Report BNL-NCS-50496 (1975)
Krakowski R.A., F.L. Ribe, T.A. Coultas, A.J. Hatch (Hrsg.): “An engineering design study of a reference theta-pinch reactor (RTPR)”, Los Alamos Scientific Laboratory, Argonne National Laboratory, Report LA-5536, ANL-8019 (1974)
Darvas J.: “A blanket with low lithium and tritium inventories”, Proc. of the IAEA Workshop on Fusion Reactor Design Problems, Culham 1974, Nucl. Fus., Special Supplement (1974) 377
Abdou M.A., Y. Gohar, R.Q. Wright: “MACK-IV, a new version of MACK: a program to calculate nuclear response functions from data in ENDF/B format”, Argonne National Laboratory, Report ANL/FPP-77–5 (1978)
Gohar Y., M.A. Abdou: “MACKLIB-IV, a library of nuclear response functions generated with the MACK-IV computer program from ENDF/B-IV”, Argonne National Laboratory, Report ANL/FPP/TM-106 (1978)
Radiation Shielding Information Center: “SMUG, multigroup photon cross-section generator”, Oak Ridge National Laboratory, Report PSR-51 (1974)
Adbou M.A., C.W. Maynard: “Calculation methods for nuclear heating”, University of Wisconsin, Report FDM-66 (1973)
Hunt J.C.R., R. Hancox: “The use of liquid lithium as coolant in a toroidal fusion reactor; Part I: Calculation of pumping power”, Culham Laboratory, Report CLM-R 115 (1971)
Hoffman M.A., G.A. Carlson: “Calculation techniques for estimating the pressure Tosses for conducting fluid flows in magnetic fields”, Lawrence Radiation Laboratory, University of California, Livermore, Report UCRL-51010 (1971)
Dänner W., M. Korzen: “MHD-Druckverluste in Rohrleitungssystemen für toroidale Fusionsreaktoren”, Max-Planck-Institut für Plasmaphysik, Bericht IPP 4/180 (1979)
Ehrlich K.: “First wall materials for fusion reactors”, Kerntechnik 19 (1977) 263
Ehrlich K., B.L. Eyre, D. Kaletta, R. Klingelhöfer, G.L. Kulcinski: “Werkstoffe für Fusionsreaktoren”, Kernforschungszentrum Karlsruhe, Bericht KfK 2590 (1978)
Dänner W., J. Raeder: “The mechanical performance of the fusion reactor first wall; Part III: Inelastic materials response”, Max-Planck-Institut für Plasmaphysik, Bericht IPP 4/190 (1980)
Bloom E.E., F.W. Wiffen, P.J. Maziasz, J.O. Stiegler: “Temperature and fluence limits for a type 316 stainless steel controlled thermonuclear reactor first wall”, Nucl. Technol. 31 (1976) 115
Pottmeyer E.W. Jr.: “The fusion materials irradiation test facility at Hanford”, Proc. of the First Topical Meeting on Fusion Reactor Materials, Miami Beach, Florida, 1979
Pottmeyer E.W. Jr.: “The fusion materials irradiation test facility at Hanford”, J. of Nucl.Mat. 85&86 (1979) 463
Abschnitt 2.5
Spitzer L. Jr.: “The stellarator concept”, Phys. Fluids 1 (1958) 253
Verschiedene Beitrage in den Proceedings of the 6th Symposium on Engineering Problems of Fusion Research, San Diego, California, 1975
Allgeyer R. et al.: “The design of the ASDEX tokamak”, Proc. of the 6th Symposium on Engineering Problems of Fusion Research, San Diego, California, 1975, S. 378
Nagami M.: “Divertor experiment for impurity control in DIVA”, Japanese Atomic Energy Research Institute, Report JAERI-M 8215 (1979)
Mills R.G. (Hrsg.): “A fusion power plant”, Princeton Plasma Physics Laboratory, Report MATT-1050 (1974)
Badger B. et al.: “UWMAK-I, a Wisconsin toroidal fusion reactor design”, University of Wisconsin, Report UWFDM-68 (Bd. I, 1974, Bd. II, 1975)
Badger B. et al.: “UWMAK-II, a conceptual tokamak power reactor design”, University of Wisconsin, Report UWFDM-112 (1975)
Badger B. et al.: “UWMAK-III, a high performance noncircular tokamak power reactor design”, University of Wisconsin, Report UWFDM-150 (1976)
Plummer K.M. et al.: “The engineering of the “Divertor Injection Tokamak Experiment” (DITE)”, Proc. of the 6th Symposium on Engineering Problems of Fusion Research, San Diego, California, 1975, S. 361
Crawley H.J.: “The practical feasibility of a bundle divertor for a tokamak power reactor”, Proc. of the 9th Symposium on Fusion Technology, Garmisch-Partenkirchen, 1976, EUR 5602, S. 381
Engelmann F., W.J. Goedheer, A. Nocentini, F.C. Schüller: “Plasmas with cold blankets”, Proc. of the Internat.Symposium on Plasma Wall Interaction, Jülich, 1976, EUR 5782 e, S. 627
Anderson J.L. et al.: “Tritium systems test assembly, design for major device fabrication review”, Los Alamos Scientific Laboratory, Report LA-6855-P (1977)
Genty C., R. Schott: “Quantitative analysis for the isotopes of hydrogen — H2. HD, HT, D2, DT, and T2 — by gaschromatography”, Analytic Chemistry 42 (1970) 7
Perchermeier J., H. Weichselgartner: “Evaluation of large-scale gaschromatography for the recovery and separation of tritium from the exhaust of tritium-burning tokamak fusion experiments”, Proc. of the 11th Symposium on Fusion Technology, Oxford, 1980
Fraas A.P.: “A diffusion process for removing tritium from the blanket of a thermonuclear reactor”, Oak Ridge National Laboratory, Report ORNL-TM-2358 (1968)
Messer CE.: “A survey report on lithium hydride”, United States Atomic Energy Commission, Report NYO-9470 (1960)
Dänner W.: “Tritium economy and tritium safety of fusion power plants”, Max-Planck-Institut für Plasmaphysik, Garching, Bericht IPP 4/112 (1974)
Krakowski R.A., R.L. Ribe, T.A. Coultas, A.J. Hatch (Hrsg.): “An engineering design study of a reference theta-pinch reactor (RTPR)”, Los Alamos Scientific Laboratory, Argonne National Laboratory, Report LA-5536, ANL-8019 (1974)
Powell J.R.: “Tritium recovery from fusion blankets using solid lithium compounds — I: Design and minimization of tritium inventory”, Proc. of the Conference on Radiation Effects and Tritium Technology for Fusion Reactors, Gatlinburg, Tennessee, 1975, Bd. III, S. 197
Abschnitt 2.6
Söll M.: “Superconducting magnet systems for fusion reactors”, Kerntechnik 19 (1977) 272
Hagler M.O., M. Christianson: “An introduction to controlled thermonuclear fusion”, 1. Auflage, Toronto (1977)
Badger B. et al.: “NUWMAK, a tokamak reactor design study”, University of Wisconsin, Report UWFDM-330 (1979)
Ullmaier H.: “Irreversible properties of type II superconductors”, 1. Auflage, Berlin, Heidelberg, New York (1975)
Weber H.W., O. Hittmair: “Supraleitung”, 1. Auflage, München (1979)
Brechna H.: “Superconducting magnet systems”, Technische Physik in Einzeldarstellungen, Bd.18, 1.Auflage, Berlin, Heidelberg, New York (1973)
Applied Superconductivity Conference 1978, IEEE Trans.on Magnetics 15 (1979)
Wittgenstein F., Rev. Industries Atomique, 5/6 (1970) 23
Haubenreich P.N., J.N. Luton, P.B. Thompson: “The role of the large coil programme in the development of superconducting magnets for fusion reactors”, IEEE Trans. on Magnetics, 15 (1979) 520
Knobloch A.F.: “Superconducting magnet systems in EPR designs”, Proc. of the Course on Tokamak Reactors for Breakeven, International School of Fusion Reactor Technology, Erice, 1976, 1. Auflage, Oxford, New York, Toronto, Sydney, Paris (1978)
Badger B. et al.: “UWMAK-III, a noncircular tokamak power reactor design”, University of Wisconsin, Report UWFDM-150 (1976)
File J., R.G. Mills, G.V. Sheffield: “Large superconducting magnet designs for fusion reactors”, Princeton University, Report MATT-848 (1971)
Knobloch A.F., “Contribution to an optimum conceptual tokamak scaling”, Proc. 7th Symposium on Engineering Problems of Fusion Research, Knoxville, 1977, S. 250
Soll M.: “Maximum attainable toroidal magnetic fields for tokamaks”, IEEE Trans. on Magnetics 15 (1979) 752
Raeder J.: “Some analytical results for toroidal magnetic field coils with elongated minor cross-sections”, Max-Planck-Institut für Plasmaphysik, Garching, Bericht 4/141 (1976)
McCracken G.M., S. Blow: “The shielding of superconducting magnets in a fusion reactor”, Culham Laboratory, Report CLM-R120 (1972)
Dustmann C.H. et al.: “Supraleitungstechnologie für Fusionsmagnete”, Gesellschaft für Kernforschung Karlsruhe, Bericht KFK 2359 (1976)
“Radiation damage on superconductivity”, J. Nucl. Mater. 72 (1978)
Maddock B.J., G.B. James: “Protection and stabilization of large superconducting coils”, Proc. IEE 115 (1968) 543
Longmire C.L.: “Elementary Plasma Physics”, 1. Auflage, New York, London (1963)
Komarek P., H. Krauth: “Der Large Coil Task, ein internationaler Beitrag zur Entwicklung supraleitender Magnete für die Fusion”, Kerntechnik 20 (1978) 274
Abschnitt 2.7
Söll M.: “Influence of radiation damage on the maximum attainable magnetic field for toroidal fusion magnet systems”, J. of Nucl. Mat. 72 (1978) 168
Kriese J.T., D. Steiner: “Magnet shield design for fusion reactors”, Oak Ridge National Laboratory, Report ORNL-TM-4256 (1973)
Casini G., R. Cuniberti: “Nuclear blanket and shielding problems in demonstration fusion reactors”, Proc. of the First Topical Meeting on the Technology of Controlled Nuclear Fusion, San Diego, California, 1974, Bd. II, S. 238
Abdou M.A.: “Important aspects of radiation shielding for fusion reactor tokamaks”, Atomkernenergie 30 (1977) 308
Badger B. et al.: “UWMAK-III, a high performance noncircular tokamak power reactor design”, University of Wisconsin, Report UWFDM-150 (1976)
Schmatz H., M. Nöthlichs (Hrsg.): “Sicherheitstechnik, Band VII, Strahlenschutz”, Berlin
Mills R.G. (Hrsg.): “A fusion power plant”, Princeton Plasma Physics Laboratory, Report MATT-1050 (1974)
VDEW: “Begriffsbestimmungen in der Energiewirtschaft, Band 3: Verfügbarkeit von Wärmekraftwerken”, Vereinigung Deutscher Elektrizitätswerke, Frankfurt/Main
Badger B. et al.: “UWMAK-I, a Wisconsin toroidal fusion reactor design”, University of Wisconsin, Report UWFDM-68 (Bd.1, 1974; Bd.II, 1975)
Fraas A.P., A.S. Thompson: “ORNL Fusion power demonstration study: fluid flow, heat transfer, and stress analysis considerations in the design of blankets for full-scale fusion reactors”, Oak Ridge National Laboratory, Report ORNL-TM 5960 (1978)
Guthrie J.A.S., J.T.D. Mitchell: “Remote operated shield door and transporter for the Culham conceptual tokamak reactor Mark II”, Culham Laboratory, Report CCCM-P 593 (1979)
Steiner D. et al.: “ORNL Fusion power demonstration study: interim report”, Oak Ridge National Laboratory, Report 0RNL-TM-5813 (1977)
Dänner D.: “A new approach to the problem of blanket replacement in tokamak fusion reactors”, Proc. of the 9th Symposium on Fusion Technology, Garmisch-Partenkirchen, 1976, S. 441
“GAC-ANL TNS Scoping studies, Vol. VII: Remote maintenance system”, General Atomic Company, Report GA-A 14614 (1977)
“Fusion reactor remote maintenance study — Final report”, Electric Power Research Institute, Report EPRI ER-1046 (1979)
Cohn D.R. et al.: “High field compact tokamak reactor (HFCTR) conceptual design”, MIT Plasma Fusion Center, Report RR-79–2 (1979)
Powell J., D. Hsieh, J. Lehner: “DEALS: A demountable externally anchored low stress superconducting magnet system for fusion reactors”, Brookhaven National Laboratory, Report BNL 50616 (1977)
Badger B. et al.: “NUWMAK, a tokamak reactor design study”, University of Wisconsin, Report UWFDM-330 (1979)
Hsieh S.Y., J. Allinger, G. Danby, J. Keane, J. Powell, A. Prodell: “A survey of failure experience in existing superconducting magnet systems and its relevance to fusion power reactors”, IEEE Trans. on Magn. 13 (1977) 90
Powell J.R. et al.: “DEALS: A demountable superconducting magnet system for fusion reactors”, Cryogenics (1980) 59
Badger B. et al.: “UWMAK-II, a conceptual tokamak power reactor design”, University of Wisconsin, Report UWFDM-112 (1975)
Abschnitt 3.1
Lawson J.D.: “Some criteria for a power producing thermonuclear reactor”, Proc. Phys. Soc. 70 (1957) 6
Miley G.H.: “Fusion energy conversion”, (1976) S. 77 ff und S. 153 ff
Nozawa M., D. Steiner: “An assessment of the power balance in fusion reactors”, Oak Ridge National Laboratory, Report ORNL-TM-4421 (1974)
Bünde R.: “Cost structure of electric energy from fusion power plants — Review and evaluation of data from the literature”, Projekt Systemstudien im Bereich Technologie, Max-Planck-Institut für Plasmaphysik, Garching, Interner Bericht Nr. 8 (1976)
Badger B. et al.: “UWMAK-I, A Wisconsin toroidal fusion reactor design”, Report UWFDM-68 (Bd. I, 1974; Bd. II, 1975)
Mills R.G. (Hrsg.): “A fusion power plant”, Princeton Plasma Physics Laboratory, Report MATT-1050 (1974)
Powell J. et al.: “An evaluation of the technical, economic and environmental features of a synthetic fuels economy based on fusion reactors”, Brookhaven National Laboratory, Report BNL 18430 (1973)
NUS-531, Guide for Economic Evaluation of Nuclear Reactor Plant Designs. NUS-Corporation, January 1969
1000 MWE Central Station Power Plants, Investment Cost Study, WASH-1230, June 1972. Bd. I: Pressurized water reactor plant; Bd. II: Coal-fired fossil plant
Schulte S.C., T.L. Willke, J.R. Young: “Fusion reactor design studies — standard accounts for cost estimates”, Battel le Pacific Northwest Laboratory, Report PNL-2648 (1978)
Schulte S.C., W.E. Bickford, C.E. Willingham, S.K. Ghose, G.M. Walker: “Fusion reactor design studies — standard unit costs and cost scaling rules”, Battel le Pacific Northwest Laboratory, Report PNL-2987 (1979)
Bünde R.: “Calculation of the power production costs for fusion power plants — method and reference data”, Projekt Systemstudien im Bereich Technologie, Max-Planck-Institut für Plasmaphysik, Garching, Interner Bericht Nr. 5 (1975)
VDEW: Begriffsbestimmungen in der Energiewirtschaft, Bd. 3: Verfügbarkeit von Wärmekraftwerken. VDEW-Verlag
Watson J.S. et al.: “Current CTR related tritium handling studies at ORNL”, Proc. The Technology of Controlled Nuclear Fusion, Richland, Washington, 1976
McDonald C.F., D.L. Vrable: “Component design considerations for gas turbine HTGR waste heat power plant”, 11th Intersociety Energy Conversion Engineering Conference (IECEC), State Line, Nevada, 1976
Borraß K., R. Bünde, W. Dänner: “SISYFUS — A simulation model for systematic analyses of fusion power plants”, Proc. 10th Symposium on Fusion Technology (SOFT), Padua, 1978, S. 161
Bünde R.: “Die Empfindlichkeit der Kosten möglicher Fusionskraftwerke”, Projekt Systemstudien im Bereich Technology, Max-Planck-Institut für Plasmaphysik, Garching, Interner Bericht Nr. 11 (1977); in engl. Sprache: “Cost sensitivity analysis of possible fusion power plants”, Atomkernenergie 30 (1977) 183
Kasai M., S. An, S. Kondo: “Parametric study and optimization of CTR engineering design”, 5th Symposium on Engineering Problems of Fusion Research, Princeton, 1973
Abdou M.A., D. Ehst, V. Maroni, W.M. Stacey: “Impact of major design parameters on the economics of tokamak power plants”, Proc. of an IAEA Technical Committee Meeting and Workshop on Fusion Reactor Design Concepts, Madison, 1977, Beitrag IAEA-TC 145/44, S. 673
Kulcinski, G.L., J.R. Young: “The influence of first wall lifetime on the cost of electricity in UWMAK type fusion reactors”, International Conference on Radiation Effects and Tritium Technology for Fusion Reactors, Oak Ridge, Tennessee, 1975
DeFreece D.A., G.M. Fuller, L.M. Waganer: “The impact of neutron wall loading on the cost of a tokamak fusion power system”, Proc. The Technology of Controlled Nuclear Fusion, Richland, Washington, 1976
Abschnitt 4
Häfele W. (Internationales Institut für Angewandte Systemanalyse, Laxenburg bei Wien): Das aktuelle Interview “Kernenergie — haben wir eine andere Wahl?”, UMSCHAU 77 (1977) 259
Häfele W., J.P. Holdren, G. Kessler, G.L. Kulcinski: “Fusion and fast breeder reactors”, Internationales Institut für Angewandte Systemanalyse, Laxenburg bei Wien, Report RR-77–8 (1977)
Schmatz H., M. Nöthlichs (Hrsg.): “Sicherheitstechnik, Band VII, Strahlenschutz”, Berlin
Lorscheider R.: “Herkunft, Handhabung und Verbleib von Tritium”, NUKEM GmbH Hanau, Bericht NUKEM-500 (1980)
Strand J.A., R.C. Thompson: “Biological effects of tritium releases from fusion power plants”, Battelle Pacific Northwest Laboratories, Report BNWL-2022 (1976)
“Recommendations of the International Commission on Radiological Protection”, Annals of the ICRP Publication 26, Oxford, New York, Frankfurt (1977)
Schmatz H., M. Nöthlichs (Hrsg.): “Sicherheitstechnik, Band VII, Strahlenschutz”, Berlin
Mills R.G. (Hrsg.): “A fusion power plant”, Princeton Plasma Physics Laboratory, Report MATT-1050 (1974)
Badger B. et al.: “UWMAK-I, a Wisconsin toroidal fusion reactor design”, University of Wisconsin, Report UWFDM-68 (Bd.I, 1974, Bd.II, 1975)
Badger B. et al.: “UWMAK-II, a conceptual tokamak power reactor design”, University of Wisconsin, Report UWFDM-112 (1975)
Badger B. et al.: “UWMAK-III, a high performance noncircular tokamak power reactor design”, University of Wisconsin, Report UWFDM-150 (1976)
Bell B.J., R.K. Adams: “MATEXP, a general purpose digital computer program for solving ordinary differential equations by the matrix exponential method”, Oak Ridge National Laboratory, Report ORNL-TM-1933 (1967)
Odenthal H.-J., W. Dänner, H. Gorenflo: “AKTIV, a computer program for evaluating the activity, afterheat, and biological hazard potential of stainless steel structures in fusion reactor blankets”, Max-Planck-Institut für Plasmaphysik, Garching, Bericht IPP 4/154 (1977)
Jarvis O.N.: “Transmutation and activation of fusion reactor wall and structural materials”, Harwell, Report AERE-R 9298 (1979)
Fischerhof H. (Hrsg.): “Atomgesetz mit Verordnungen”, Baden-Baden, 4. Auflage (1971)
Mills R.G. (Hrsg.): “A fusion power plant”, Princeton Plasma Physics Laboratory, Report MATT-1050 (1974)
Abdou M.A.: “Important aspects of radiation shielding for fusion reactor tokamaks”, ATOMKERNENERGIE 30 (1977) 308
Santoro R.T., R.A. Lillie, R.G. Alsmiller, jr., J.M. Barnes: “Two- and three-dimensional neutronics calculations for the TFTR neutral beam injectors”, Oak Ridge National Laboratory, Report ORNL-TM-6354 (1978)
Fraas A.P.: “A diffusion process for removing tritium from the blanket of a thermonuclear reactor”, Oak Ridge National Laboratory, Report ORNL-TM-2358 (1968)
Fraas A.P.: “Conceptual design of the blanket and shield region and related systems for a full scale toroidal fusion reactor”, Oak Ridge National Laboratory, Report ORNL-TM-3096 (1973)
Bell J.T., J.D. Redman:”Tritium permeation through metals under steam conditions”, Proc. of the 9th Symposium on Fusion Technology, Garmisch-Partenkirchen, 1976, EUR 5602, S. 345
Bonka H.: “Die ortsabhängige mittlere natürliche Strahlenbelastung der Bevölkerung in der Bundesrepublik Deutschland”, ATOMKERNENERGIE 23 (1974) 137
Farfaletti-Casali F., P. Rocco: “Vacuum outer containment of a fusion power plant: implications for overall safety and tritium control”, Proc. of the 7th Symposium on Engineering Problems of Fusion Research, Knoxville, Tennessee, 1977
Keilhacker M. et al.: “Impurity control experiments in the ASDEX divertor tokamak”, Proc. of the 8th International Conference on Plasma Physics and Controlled Nuclear Fusion Research, Brüssel, 1980
Jarvis O.N.: “Transmutation and activation of fusion reactor wall and structural materials”, Harwell, Report AERE-R 9298 (1979)
Bünde R., W. Dänner, H. Herold, J. Raeder, M. Soll: Programmstudie “Nukleare Primärenergieträger, Teil II: Energie durch Kernfusion”, Arbeitsgemeinschaft der Großforschungseinrichtungen, Köln, Bericht ASA-ZE/09/78 (1978)
Casey L.A., A.Z. Ullman: “Comparative safety aspects of candidate breeding materials for fusion reactors”, Proc. of the 2nd Topical Meeting on the Technology of Controlled Nuclear Fusion, Richland, Washington, 1976, Bd. II, S. 1039
Badger B. et al.: “UWMAK-I, a Wisconsin toroidal fusion reactor design”, University of Wisconsin, Report UWFDM-68 (Bd. I, 1974; Bd. II, 1975)
Powell J. (Hrsg.): “Aspects of safety and reliability for fusion magnet systems”, Brookhaven National Laboratory, Report BNL 50542 (1976)
Lorscheider R.: “Herkunft, Handhabung und Verbleib von Tritium”, NUKEM GmbH Hanau, Bericht NUKEM-500 (1980)
The JET team: “The JET project, design proposal for the Joint European Torus”, Commission of the European Communities, Nuclear Science and Technology (Fusion), EUR 5516e (1976)
“Tokamak fusion test reactor. Final design report”, Princeton Plasma Physics Laboratory, Ebasco Services Inc., Grumman Aerospace Corp., PPPL-1445 (1978)
“Detailed design of JT-60”, Japanese Atomic Energy Research Institute, Report JAERI-M-7177 (1977)
“Experimental thermonuclear installation Tokamak-20; preliminary study”, National Committee for the Utilization of Atomic Energy Soviet Ministry, USSR (1975), Translated by I.N. Sviatoslavsky, University of Wisconsin, Report UWFDM-129
Andelfinger C. et al.: “Investigation for the ZEPHYR ignition and burn experiment”, Max-Planck-Institut für Plasmaphysik, Garching, Bericht IPP 1/181 (1980)
Komarek P., H. Krauth:”Der Large Coil Task, ein internationaler Beitrag zur Entwicklung supraleitender Magnete für die Fusion”, Kerntechnik 20 (1978) 274
Anderson J.L. et al.: “Tritium systems test assembly; design for major device fabrication review”, Los Alamos Scientific Laboratory, Report LA-6855-P (1977)
Abschnitt 5
Badger B. et al.: “UWMAK-I, a Wisconsin toroidal fusion reactor design”, University of Wisconsin, Report UWFDM-68 (Bd. I, 1974; Bd. II, 1975)
Mills R.G. (Hrsg.): “A fusion power plant”, Princeton Plasma Physics Laboratory, Reprint MATT-1050, Juni 1974
Powell J.R. et al.: “Minimum activity blankets for commercial and experimental power reactors”, IAEA Workshop on Fusion Reactor Design Problems, Culham, 1974
Badger B. et al.: “UWMAK-II, a conceptual tokamak power reactor design”, University of Wisconsin, Report UWFDM-112 (1975)
Lee J.D.: “Tritium breeding and energy generation in liquid lithium blankets”, Proc. BNES Nuclear Fusion Reactors Conference, Culham, 1969
Bauer L. et al.: “Classification schemes and their importance for the assessment of energy supplies”, Proc. 10th World Energy Conference, Istanbul, 1977, Beitrag 1.1–2
Schanz J.J.: “Problems and opportunities in adapting US Geological Survey terminology of energy resources”, Proc. First IIASA Conference on Energy Resources, Laxenburg, 1975
McKelvey V.E.: “Mineral resource estimates and public policy”, American Scientist 60 (1972) 32
World Energy Resources 1985–2000. Executive summaries of reports on resources conservation and demand to the Conservation Commission of the World Energy Conference, 1978
Vine J.D. (Hrsg.): “Lithium resources and requirements by the year 2000, papers presented at a Symposium held in Golden/Col.”, US Geological Survey Prof. Paper 1005 (1976)
Schmidt H.: “Lithiumlagerstätten in der Welt”, Kurzbericht der Bundesanstalt für Bodenforschung, Hannover (1973)
Norton J.J.: “Lithium, cesium, and rubidium — the rare earth alkali metals”, in US Mineral Resources, US Geological Surves Prof. Paper 830 (1973)
Hubbert M.K.: “Energy resources for power production”, Beitrag IAEA-SM-146/1, 1970/71. (Angaben liber Lithium-Reserven nach T.L. Kessler, 1960 und 1961)
Cairns E.J., F.A. Cafasso, V.A. Maroni: “A review of the chemical, physical, and thermal properties of lithium that are related to its use in fusion reactors”, Proc. of a Symposium “The Chemistry of Fusion Technology”, 1972, Boston, Mass.
Lidsky L.M.: “The quest for fusion power”, Technology Review (1972)
Vine J.D.: “The lithium-resource enigma”, Beitrag zu /5.2–5/, S. 35, (1976)
/5.2–12/ Bauer H., MetallgeselIschaft AG, Frankfurt/M.: Private Mitteilung
United States Atomic Energy Commission (USAEC), Division of Controlled Nuclear Fusion: “Fusion power, an assessment of ultimate potential”, WASH-1239 (1973)
Holdren J.P.: “Adequacy of lithium supplies as a fusion energy source”, Lawrence Livermore Laboratory, University of California: prepared for US Atomic Energy Commission under contract No. W-7405-Eng. 8. Dez. 1971
Schulte S.C., W.E. Bickford, C.E. Willingham, S.K. Ghose, M.G. Walker: “Fusion reactor design studies — standard unit costs and cost scaling rules”, Battelle Pacific Northwest Laboratory, Report PNL-2987 (1979)
Vine J.D.: “Nonpegmatite lithium resource potential”, Beitrag zu /5.2–5/, S. 54, (1976)
White D.E. et al.: “Lithium contents of thermal and mineral waters”, Beitrag zu /5.2–5/, S. 58. (1976)
Berthold C.E., D.H. Baker: “Lithium recovery from geothermal fluids”, Beitrag zu /5.2–5/, S. 61, (1976)
Collins A.G.: “Lithium abundances in oilfield waters”, Beitrag zu /5.2–5/, S. 116, (1976)
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/5.5–2/ wie /5.2–20/
/5.5–3/ wie /5.2–27/
/5.5.4/ wie /5.2–33/
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Raeder, J. et al. (1981). Literaturverzeichnis. In: Kontrollierte Kernfusion. Teubner Studienbücher. Vieweg+Teubner Verlag, Wiesbaden. https://doi.org/10.1007/978-3-322-92737-8_7
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