Đang hiển thị 1 - 20 kết quả của 84 cho tìm kiếm '', thời gian truy vấn: 0.10s Tinh chỉnh kết quả
  1. 1
    Study on the Irradiation Embrittlement of a Microalloyed Ferritic Steel /
    Bằng Balakrishnan, KS, Ganguly, C., Viswanathan, UK
    Được phát hành 1994

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  2. 2
    Evaluation of Thermal-Aged Plates, Forgings, and Submerged-Arc Weld Metals /
    Bằng DeVan, MJ, Lowe, Al, Wade, CS
    Được phát hành 1994

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  3. 3
    Effects of Fission and Fusion Neutron Irradiations on Mechanical Properties and Defect Recovery Behavior in ?-Iron /
    Bằng Aono, Y., Kayano, H., Kuramoto, E., Kurishita, H., Yoshida, N.
    Được phát hành 1994

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  4. 4
    Microstructural Studies in Fast Reactor Irradiated FV448 Ferritic-Martensitic Alloy Plate and Weldment /
    Bằng Faulkner, RG, Little, EA, Morgan, TS
    Được phát hành 1994

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  5. 5
    The Effect of Irradiation on the Mechanical Properties of 6061-T651 Aluminum /
    Bằng Alexander, DJ
    Được phát hành 1994

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  6. 6
    The Role of Nickel and Zinc in Defect Behavior and Microstructural Evolution of Copper Under Electron Irradiation /
    Bằng Ishimaru, E., Muroga, T., Yoshida, N.
    Được phát hành 1994

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  7. 7
    Predictions of Interfacial Phosphorus Segregation in Irradiated Ferritic Steels /
    Bằng Faulkner, RG, Little, EA
    Được phát hành 1994

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  8. 8
    Mechanical Properties of Vanadium Alloys Doped with Helium Using Various Techniques /
    Bằng Abe, K., Hasegawa, A., Matsui, H., Tanaka, M., Yamamoto, M.
    Được phát hành 1994

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  9. 9
    Usnrc Research on Reactor Pressure Vessel Steel Embrittlement /
    Bằng Mayfield, M., Taboada, A.
    Được phát hành 1994

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  10. 10
    Meeting Future Power Needs in Licensing Space /
    Bằng Rossin, AD
    Được phát hành 1994

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  11. 11
    Helium-Induced Weld Degradation of HT-9 Steel /
    Bằng Chin, BA, Grossbeck, ML, Lin, HT, Wang, C-A
    Được phát hành 1994

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  12. 12
    The Role of Phase-Boundary Fission-Gas Bubbles in the Cavitational Swelling of Irradiated U-Pu-Zr Fuel /
    Bằng Rest, J.
    Được phát hành 1994

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  13. 13
    The Effect of Neutron Irradiation on the Structure and Properties of Carbon-Carbon Composite Materials /
    Bằng Burchell, TD, Eatherly, WP, Strizak, JP
    Được phát hành 1994

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  14. 14
    The Relationship of Grain Boundary Composition in Irradiated Type 304SS to Neutron Fluence and IASCC /
    Bằng Jacobs, AJ
    Được phát hành 1994

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  15. 15
    The Observation and Interpretation of Microstructural Evolution and Swelling in Austenitic Steels Under Irradiation /
    Bằng Hamada, K., Ishino, S., Sekimura, N.
    Được phát hành 1994

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  16. 16
    Mechanical Properties of 1950's Vintage Type 304 Stainless Steel Weldment Components After Low Temperature Neutron Irradiation /

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  17. 17
    Tensile Properties of Neutron Irradiated 316Ti and 15-15Ti Steels /
    Bằng Fissolo, A., Lévy, V., Maillard, A., Rabouille, O., Royer, J., Séran, JL
    Được phát hành 1994

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  18. 18
    Development and Application of an LWR Reactor Pressure Vessel-Specific Flaw Distribution /
    Bằng Foulds, JR, Kennedy, EL, Rosinski, ST
    Được phát hành 1994

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  19. 19
    Void Formation and Induced-Segregation During Electron-Irradiation in Ti and Nb Modified Austenitic Steels /

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  20. 20
    Microstructural and Microchemical Evolution During Fast Neutron Irradiation in Nickel and Nickel-Silicon Alloys Doped with Isotopically Controlled Boron /
    Bằng Muroga, T.
    Được phát hành 1994

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