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  1. 1
    Assessment study of RELAP5/MOD2 cycle 36.04 based on pressurizer safety and relief valve tests /

    Assessment study of RELAP5/MOD2 cycle 36.04 based on pressurizer safety and relief valve tests / by Stubbe, E. J. (Elie J.), Vanhoenacker, L.

    Published 1990
    “…Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  2. 2
    HECTR analyses of the Nevada Test Site (NTS) premixed combustion experiments /

    HECTR analyses of the Nevada Test Site (NTS) premixed combustion experiments / by Wong, Chung-Nin Channy

    Published 1988
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  3. 3
    Compendium of ECCS research for realistic LOCA analysis : final report.

    Compendium of ECCS research for realistic LOCA analysis : final report.

    Published 1988
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  4. 4
    Damaged fuel experiment DF-1 : results and analyses /

    Damaged fuel experiment DF-1 : results and analyses /

    Published 1990
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
    Government Document Book
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  5. 5
    Quality assurance and verification of the MACCS code, version 1.5 /

    Quality assurance and verification of the MACCS code, version 1.5 /

    Published 1990
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  6. 6
    Iodine chemical forms in LWR severe accidents final report /

    Iodine chemical forms in LWR severe accidents final report /

    Published 1992
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
    Government Document Microfilm Book
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  7. 7
    Aerosol Sampling and Transport Efficiency Calculation (ASTEC) and application to surtsey/DCH aerosol sampling system : code version 1.0 : code description and user's manual /

    Aerosol Sampling and Transport Efficiency Calculation (ASTEC) and application to surtsey/DCH aerosol sampling system : code version 1.0 : code description and user's manual / by Yamano, N.

    Published 1989
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  8. 8
    CHARM, a model for aerosol behavior in time varying thermal-hydraulic conditions /

    CHARM, a model for aerosol behavior in time varying thermal-hydraulic conditions / by Wheatley, C. J.

    Published 1988
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  9. 9
    Analysis of natural circulation during a Surry Station blackout using SCDAP/RELAP5 /

    Analysis of natural circulation during a Surry Station blackout using SCDAP/RELAP5 / by Bayless, Paul D.

    Published 1988
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
    Government Document Book
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  10. 10
    The influence of selected containment structures on debris dispersal and transport following high pressure melt ejection from the reactor vessel /

    The influence of selected containment structures on debris dispersal and transport following high pressure melt ejection from the reactor vessel / by Pilch, M.

    Published 1988
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  11. 11
    Submission for the CSNI/GREST benchmark exercise on chemical thermodynamic modeling in core-concrete interaction releases of radionuclides /

    Submission for the CSNI/GREST benchmark exercise on chemical thermodynamic modeling in core-concrete interaction releases of radionuclides / by Powers, D. A. (Dale A.)

    Published 1988
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  12. 12
    Development of programmatic performance indicators /

    Development of programmatic performance indicators /

    Published 1988
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  13. 13
    A Computational model for critical flow through intergranular stress corrosion cracks /

    A Computational model for critical flow through intergranular stress corrosion cracks /

    Published 1988
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  14. 14
    INEL personal computer version of MACCS 1.5 /

    INEL personal computer version of MACCS 1.5 / by Jones, K. R.

    Published 1991
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  15. 15
    A Risk-based review of instrument air systems at nuclear power plants /

    A Risk-based review of instrument air systems at nuclear power plants /

    Published 1990
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  16. 16
    Organization and safety in nuclear power plants /

    Organization and safety in nuclear power plants /

    Published 1990
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  17. 17
    PARTITION, a program for defining the source term/consequence analysis interface in the NUREG-1150 probabilistic risk assessments : user's guide /

    PARTITION, a program for defining the source term/consequence analysis interface in the NUREG-1150 probabilistic risk assessments : user's guide / by Iman, Ronald L.

    Published 1990
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  18. 18
    Integrated reliability and risk analysis system (IRRAS) version 2.0 user's guide

    Integrated reliability and risk analysis system (IRRAS) version 2.0 user's guide by Russell, K. D., 1941-

    Published 1990
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
    Government Document Microfilm Book
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  19. 19
    FLAME facility the effect of obstacles and transverse venting on flame acceleration and transition to detonation for hydrogen-air mixtures at large scale /

    FLAME facility the effect of obstacles and transverse venting on flame acceleration and transition to detonation for hydrogen-air mixtures at large scale / by Sherman, Martin P. (Martin Philip), 1937-

    Published 1989
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
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  20. 20
    An Investigation of core liquid level depression in small break loss-of-coolant accidents

    An Investigation of core liquid level depression in small break loss-of-coolant accidents

    Published 1991
    “…Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory …”
    Government Document Microfilm Book
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