Materials Technology for Fusion: Current Status and Future Requirements
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F. W. Clinard | E. E. Bloom | D. L. Smith | F. Clinard | W. G. Wolfer | D. Smith | R. D. Stevenson | R. E. Gold | R. Gold | W. Wolfer | R. Stevenson
[1] E. Cairns,et al. Review of chemical, physical, and thermal properties of lithium related to its use in fusion reactors , 1972 .
[2] C. Liu,et al. Development of ductile long-range ordered alloys for fusion reactor systems , 1979 .
[3] G. Imel,et al. The effects of radiation on tftr coil materials , 1979 .
[4] C. Liu,et al. Control of ordered structure and ductility of (Fe, Co, Ni)3V alloys , 1979 .
[5] C. Echer,et al. High-energy neutron irradiation effects on the tensile properties and microstructure of 316 stainless steel , 1980 .
[6] J. Narayan,et al. The characteristics of 15 MeV and fission neutron damage in niobium , 1976 .
[7] K. Kelton,et al. The effect of electric current on the conductivity of MgO single crystals at temperatures above 1300 K , 1978 .
[8] K. Merkle. TEM investigation of 14-MeV neutron damage , 1973 .
[9] R. Hancox,et al. International Tokamak Reactor (Executive Summary of the IAEA Workshop, 1979) , 1980 .
[10] R. G. Clemmer,et al. Fusion reactor blanket/shield design study , 1979 .
[11] H. Brager,et al. Defect development in neutron irradiated type 316 stainless steel , 1973 .
[12] J. Mitchell,et al. Comparison of 16-MeV proton, 14-MeV neutron, and fission-neutron damage in copper , 1973 .
[13] E. E. Bloom,et al. Austenitic stainless steels with improved resistance to radiation-induced swelling☆ , 1976 .
[14] R. J. Price,et al. Effects of fast-neutron irradiation on pyrolytic silicon carbide , 1969 .
[15] B. H. Rose,et al. Radiation-induced conductivity of AlO: Experiment and theory , 1980 .
[16] G. Kulcinski. First wall protection schemes for inertial confinement fusion reactors , 1979 .
[17] E. E. Bloom. Mechanical properties of materials in fusion reactor first-wall and blanket systems , 1979 .
[18] Donald L. Smith,et al. Physical sputtering model for fusion reactor first-wall materials , 1978 .
[19] Robert A. Krakowski,et al. Trends and developments in magnetic confinement fusion reactor concepts , 1981 .
[20] J. Macchesney,et al. Room‐Temperature Dielectric Properties of Fast‐Neutron‐Irradiated Fused Silica and α Alumina , 1964 .
[21] R. Brook,et al. The influence of temper embrittlement on fracture toughness , 1976 .
[22] R. J. Price,et al. Neutron irradiation-induced voids in β-silicon carbide , 1973 .
[23] N. H. Packan,et al. Multispecimen dual-beam irradiation damage chamber , 1980 .
[24] D. Stow,et al. Void-swelling in irons and ferritic steels: II. An experimental survey of materials irradiated in a fast reactor , 1979 .
[25] P. L. Hendrick,et al. Transient irradiation-induced creep of nickel during deuteron bombardment , 1978 .
[26] G. Cunningham. Materials development for advanced reactors , 1976 .
[27] R. E. Gold,et al. Refractory metal alloys for fusion reactor applications , 1979 .
[28] G. Hopkins,et al. Ceramic materials for fusion , 1975 .
[29] P. Patriarca,et al. U.S. Advanced Materials Development Program for steam generators , 1976 .
[30] A. Pineau,et al. Temper embrittlement in 12%Cr martensitic steel , 1979 .
[31] W. Martin,et al. Solutions to the Problems of High-Temperature Irradiation Embrittlement , 1967 .
[32] P. Maziasz,et al. Tensile properties of type 316 stainless steel irradiated in a simulated fusion reactor environment , 1979 .
[33] J. Mitchell,et al. Some electron microscopy observations of 14 MeV neutron damage in niobium , 1975 .
[35] R. A. Patterson,et al. Stainless-Steel Weight Loss in Nitrogen-Contaminated Liquid Lithium , 1976 .
[36] F. Clinard. Ceramics for applications in fusion systems , 1979 .
[37] W. F. Calaway,et al. Electrochemical Extraction of Hydrogen from Molten LiF-LiCI-LiBr and Its Application to Liquid-Lithium Fusion Reactor Blanket Processing , 1978 .
[38] P. R. Malmberg,et al. Swelling Behavior of Commercial Ferritic Alloys, EM-12 and HT-9, as Assessed by Heavy Ion Bombardment , 1976 .
[39] B. Chin,et al. Comparison of the in-reactor creep of selected ferritic, solid solution strengthend, and precipitation hardened commercial alloys , 1979 .
[40] N. H. Packan,et al. Simulation of first wall damage: Effects of the method of gas implantation , 1979 .
[41] R. S. Wilks,et al. The irradiation-induced macroscopic growth of α-Al2O3 single crystals , 1967 .
[42] F. W. Wiffen,et al. Microstructures developed in ‘simulated’ fusion irradiations , 1979 .
[43] R. J. Price,et al. Thermal conductivity of neutron-irradiated pyrolytic β-silicon carbide , 1973 .
[44] A. Brailsford,et al. Swelling with inhomogeneous point defect production — a cascade diffusion theory , 1979 .
[45] K. Natesan,et al. Effectiveness of tritium removal from a CTR lithium blanket by cold trapping secondary liquid metals Na, K, and NaK , 1974 .
[46] R. S. Wilks. Neutron-induced damage in BeO, Al2O3 and MgO — a review , 1968 .
[47] L J Pionke,et al. Technical assessment of niobium alloys data base for fusion reactor applications , 1979 .
[48] J. L. Brimhall,et al. 14 MeV Neutron damage in molybdenum , 1976 .
[49] W. Wolfer. Correlation of radiation creep theory with experimental evidence , 1980 .
[50] P. Dunn. Single-phase and two-phase magnetohydrodynamic pipe flow , 1980 .
[51] D. Gelles,et al. An experimental method to determine the role of helium in neutron-induced microstructural evolution , 1979 .
[52] R. Wiswall,et al. Removal of tritium from fusion reactor blankets. Annual report, FY 1977 , 1977 .
[53] C. E. Pugh,et al. Some trends in constitutive equation model development for high-temperature behavior of fast-reactor structural alloys , 1978 .
[54] L. A. Glenn,et al. Dynamic Loading of the Structural Wall in a Lithium Fall Fusion Reactor , 1979 .