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  1. 1
    Case study of the propagation of a small flaw under PWR loading conditions and comparison with the ASME code design life. Comparison of ASME Code Sections III and XI

    Case study of the propagation of a small flaw under PWR loading conditions and comparison with the ASME code design life. Comparison of ASME Code Sections...

    Published 1986
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  2. 2
    Wall thinning in nuclear piping Status and ASME Section XI activities.

    Wall thinning in nuclear piping Status and ASME Section XI activities.

    Published 1989
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  3. 3
    Appropriate nominal stresses for use with ASME Code pressure-loading stress indices for nozzles

    Appropriate nominal stresses for use with ASME Code pressure-loading stress indices for nozzles

    Published 1976
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  4. 4
    Comparison of ASME Code NB-3200 and NB-3600 results for fatigue analysis of B31.1 branch nozzles

    Comparison of ASME Code NB-3200 and NB-3600 results for fatigue analysis of B31.1 branch nozzles

    Published 1996
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  5. 5
    Analysis of inservice inspection relief requests

    Analysis of inservice inspection relief requests

    Published 1989
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  6. 6
    End effects on elbows subjected to moment loadings. [PWR; BWR]

    End effects on elbows subjected to moment loadings. [PWR; BWR]

    Published 1982
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  7. 7
    Fatigue crack growth testing of sub-clad defects

    Fatigue crack growth testing of sub-clad defects

    Published 1998
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  8. 8
    LOFT blowdown loop piping thermal analysis Class I review

    LOFT blowdown loop piping thermal analysis Class I review

    Published 1978
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  9. 9
    ADDITIONAL STRESS AND FRACTURE MECHANICS ANALYSES OF PRESSURIZED WATER REACTOR PRESSURE VESSEL NOZZLES

    ADDITIONAL STRESS AND FRACTURE MECHANICS ANALYSES OF PRESSURIZED WATER REACTOR PRESSURE VESSEL NOZZLES

    Published 2012
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  10. 10
    Technical basis for the initiation and cessation of environmentally-assisted cracking of low-alloy steels in elevated temperature PWR environments

    Technical basis for the initiation and cessation of environmentally-assisted cracking of low-alloy steels in elevated temperature PWR environments

    Published 1997
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  11. 11
    Analysis of LOFT containment nozzles 11A, 11B, 11D, 12A, 13B, 13C, and 13D by Bijlaard method

    Analysis of LOFT containment nozzles 11A, 11B, 11D, 12A, 13B, 13C, and 13D by Bijlaard method

    Published 1978
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  12. 12
    Generic analyses for evaluation of low Charpy upper-shelf energy effects on safety margins against fracture of reactor pressure vessel materials

    Generic analyses for evaluation of low Charpy upper-shelf energy effects on safety margins against fracture of reactor pressure vessel materials

    Published 1993
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  13. 13
    Technical considerations for flexible piping design in nuclear power plants

    Technical considerations for flexible piping design in nuclear power plants

    Published 1985
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  14. 14
    Corrosion fatigue of alloys 600 and 690 in simulated LWR environments

    Corrosion fatigue of alloys 600 and 690 in simulated LWR environments

    Published 1996
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  15. 15
    Erosion/Corrosion-Induced Pipe Wall Thinning in U.S. Nuclear Power Plants

    Erosion/Corrosion-Induced Pipe Wall Thinning in U.S. Nuclear Power Plants

    Published 1989
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  16. 16
    Effects of LWR coolant environments on fatigue design curves of carbon and low-alloy steels

    Effects of LWR coolant environments on fatigue design curves of carbon and low-alloy steels

    Published 1998
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  17. 17
    Assessment of Field Experience Related to Pressurized Water Reactor Primary System Leaks

    Assessment of Field Experience Related to Pressurized Water Reactor Primary System Leaks

    Published 1999
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  18. 18
    Assessment of Field Experience Related to Pressurized Water Reactor Primary System Leaks

    Assessment of Field Experience Related to Pressurized Water Reactor Primary System Leaks

    Published 1999
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  19. 19
    Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Volume 15, Semiannual report October 1991--March 1992.

    Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Volume 15, Semiannual report October 1991--March 1992.

    Published 1993
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  20. 20
    Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Semiannual report, April 1992--September 1992 Volume 16.

    Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Semiannual report, April 1992--September 1992 Volume 16.

    Published 1993
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