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1_VANADIUM ALLOYS
- BIAXIAL THERMAL CREEP OF V-4Cr-4Ti AT 700°C and 800iC - R. J. Kutz and M. L. Hamilton (Pacific Northwest National Laboratory), pp. 3-10.
- MICROSTRUCTURAL EXAMINATION OF V-4Cr-4Ti PRESSURIZED TUBES - D. S. Gelles, M. L. Hamilton, and R. J. Kurtz (Pacific Northwest National Laboratory), pp. 11-19.
- UNIAXIAL CREEP BEHAVIOR OF V-Cr-Ti ALLOYS - K. Natesan, W. K. Soppet, and D. L. Rink (Argonne National Laboratory), pp. 20-24.
- HIGH TEMPERATURE TENSILE PROPERTIES AND DEFORMATION BEHAVIOR OF V-4Cr-4Ti - A. F. Rowcliffe, D. T. Hoelzer, and S. J. Zinkle (Oak Ridge National Laboratory, pp. 25-32.
- EFFECT OF ORIENTATION ON EFFECTIVE TOUGHNESS-TEMPERATURE CURVES IN V-4Cr-4Ti - E. Donahue, G. R. Odette, and G. E. Lucas (University of California, Santa Barbara), pp. 33-35.
- STUDY OF IRRADIATION CREEP OF VANADIUM ALLOYS - H. Tsai, R. V. Strain, M. C. Billone, T. S. Bray, and D. L. Smith (Argonne National Laboratory), pp. 36-37.
- FRACTOGRAPHY RESULTS FOR V-ALLOY TENSILE SPECIMENS IRRADIATED IN THE BOR-60 ATR, AND FFTF REACTORS - T. S. Bray, H. Tsai, R. V. Strain, M. C. Billone, and D. L. Smith (Argonne National Laboratory), pp. 38-43
- IMPURITY STUDIES OF GAS TUNGSTEN ARC WELDING OF VANADIUM ALLOYS - M. L. Grossbeck and J. F. King (Oak Ridge National Laboratory), pp. 44-48.
- IMPROVEMENT OF LASER WELD QUALITY OF V-Cr-Ti ALLOYS - Z Xu, C. B. Reed, K. Natesan, and D. L. Sinith (Argonne National Laboratory), pp. 49-53.
- DIFFUSION BONDING OF VANADIUM ALLOYS - Z. Xu, D. L. Smith, and C. B. Reed (Argonne National Laboratory), pp. 54-56.
- DEVELOPMENT OF ELECTRICALLY INSULATING CaO COATINGS - K. Natesan, M. Uz, and S. Wieder (Argonne National Laboratory), pp. 57-62.
2_SILICON CARBIDE COMPOSITE MATERIALS
- METHODS FOR JOINING SILICON CARBIDE COMPOSITES FOR HIGH TEMPERATURE STRUCTURAL APPLICATIONS - C. A. Lewinsohn, R. H. Jones, (Pacific Northwest National Laboratory), M. Singh (NASA Lewis Research Center), T. Shibayama (Center for Advanced Research of Energy Technology, Hokkaido University), T. Hinoki, M. Ando, Y. Katoh, and A. Kohyama (Institute of Advanced Energy, Kyoto University), pp. 65-72.
3_FERRITIC/MARTENSITIC STEELS
- IMPURITY CONTENT OF REDUCED-ACTIVATION FERRITIC STEELS AND THE EFFECT ON THE REDUCED-ACTIVATION CHARACTERISTICS - F. L. Klueh (Oak Ridge National Laboratory), E. T. Cheng (TSl Research, Inc.), M. L. Grossbeck and E. E. Bloom (ORNL), pp. 75-82.
- CONSTITUTIVE AND FRACTURE TOUGHNESS PROPERTIES OF AN ADVANCED FERRITIC/MARTENSITIC STEEL - P. Spatig, G. R. Odette, G. E. Lucas, and M. Victoria (University of California, Santa Barbara); M. Victoria (Technologiesde la Fusion-Centre de Recherches en Physique des Plasmas, Ecole Polytechnique Federale de Lausanne), pp. 83-95.
- MICROSTRUCTURE OF ISOTOPICALLY-TAILORED MARTENSITIC STEEL HT9 IRRADIATED AT 400¡C - N. Hashimoto, J. P. Robertson (Oak Ridge National Laboratory), and K. Shiba (Japan Atomic Energy Research Institute), pp. 96-101.
- TENSILE PROPERTIES OF LOW ACTIVATION FERRITIC STEELS FOLLOWING IRRADIATION IN ORR - M. L. Hamilton and D. S. Genes (Pacific Northwest National Laboratory), 102-116.
- EFFECT OF HEAT TREATMENT AND IRRADIATION TEMPERATURE ON IMPACT PROPERTIES OF Cr-W-V FERRITIC STEELS - R. L. Klueh (Oak Ridge National Laboratory) and D. J. Alexander (Los Alamos National Laboratory), pp. 117-118.
4_COPPER ALLOYS AND HIGH HEAT FLUX MATERIALS
- POST-IRRADIATION ANNEALING RESPONSE OF PURE COPPER IRRADIATED AT 1OO°C - D. J. Edwards (Pacific Northwest National Laboratory), B. N. Singh, P. Toft, and M. Eldrup (Risa National Laboratory), 121-125.
- MICROSTRUCTURES OF Ti-Al INTERMETALLIC COMPOUNDS IRRADIATED AT 674 K IN HFIR - Y. Miwa, T. Sawai (Japan Atomic Energy Research Institute) D. T. Hoelzer (Oak Ridge National Laboratory), and A. Hishinuma (JAERI), pp. 126-148.
5_RADIATION EFFECTS, MECHANISTIC STUDIES, AND EXPERIMENTAL METHODS
- AN INTEGRATED THEORY, MODELING, EXPERIMENTAL AND DATABASE PROGRAM FOR THE DEVELOPMENT OF ADVANCED FUSION MATERIALS - R. E. Stoller (Oak Ridge National Laboratory), G. R. Odette (University of Califomia- Santa Barbara), and H. L. Heinisch (Pacific Northwest National Laboratory), pp. 157-178.
- A KINETIC MONTE CARLO STUDY OF MIXED 1-D/3-D DEFECT MIGRATION - H. L. Heinisch (Pacific Northwest National Laboratory), B. N. Singh (R&a National Laboratory), S. L Golubov (Institute of Physics and Power Engineering), pp. 179-184.
8_DOSIMETRY, DAMAGE PARAMETERS, AND ACTIVATION CALCULATIONS
- RADIATION DAMAGE CALCULATIONS FOR THE FUBR AND BEATRIX IRRADIATIONS OF LITHIUM COMPOUNDS IN EBR-11 AND FFTF - L. R. Greenwood (Pacific Northwest National Laboratory), pp. 187-193.
- NEUTRON DOSIMETRY AND DAMAGE CALCULATIONS FOR THE TRIST ER-I EXPERIMENT IN HFIR - L. R. Greenwood (Pacific Northwest National Laboratory) and C. A. Baldwin (Oak Ridge National Laboratory), pp. 194-198.
- NEUTRON DOSIMHRY AND DAMAGE CALCULATIONS FOR THE HFIR-CTR-62 AND 63 IRRADIATIONS - L. R. Greenwood (Pacific Northwest National Laboratory) and C. A. Baldwin (Oak Ridge National Laboratory, pp. 199-204.
9_IRRADIATION FACILITIES, TEST MATRICES, AND EXPERIMENTAL METHODS
- CONCEPTUAL DEVELOPMENT OF FUSION-2 EXPERIMENT FOR IRRADIATION TESTING OF VANADIUM ALLOYS IN A LITHIUM ENVIRONMENT AT =500-750°C N THE BOR-60 REACTOR - V. Kazakov, V. Chakin, V. Efimov, V. Petukhov, A. Tuktabiev, P. Gabiev (Research Institute of Atomic Reactors), H. Tsai, T. S. Bray, D. L. Smith (Argonne National Laboratory), and A. F. Rowcliffe (Oak Ridge National Laboratory), pp. 207-209.
- SCHEDULE AND STATUS OF IRRADIATION EXPERIMENTS - A. F. Rowcliffe (Oak Ridge National Laboratory), pp. 210-232.
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