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Source: The Open Library

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1GSI-191

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“GSI-191” Metadata:

  • Title: GSI-191
  • Author:
  • Language: English
  • Number of Pages: Median: 285
  • Publisher: ➤  Supt. of Docs., U.S. G.P.O. [distributor] - Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - United States Government Printing Office
  • Publish Date:
  • Publish Location: Washington, DC

“GSI-191” Subjects and Themes:

Edition Identifiers:

Access and General Info:

  • First Year Published: 2002
  • Is Full Text Available: No
  • Is The Book Public: No
  • Access Status: No_ebook

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Downloads Are Not Available:

The book is not public therefore the download links will not allow the download of the entire book, however, borrowing the book online is available.

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    2USI A-43 regulatory analysis

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    “USI A-43 regulatory analysis” Metadata:

    • Title: USI A-43 regulatory analysis
    • Author:
    • Language: English
    • Publisher: ➤  Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
    • Publish Date:
    • Publish Location: Washington, D.C

    “USI A-43 regulatory analysis” Subjects and Themes:

    Edition Identifiers:

    Access and General Info:

    • First Year Published: 1985
    • Is Full Text Available: No
    • Is The Book Public: No
    • Access Status: No_ebook

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    3Draft regulatory guide DG-1107

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    “Draft regulatory guide DG-1107” Metadata:

    • Title: Draft regulatory guide DG-1107
    • Author: ➤  
    • Language: English
    • Number of Pages: Median: 30
    • Publisher: ➤  U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
    • Publish Date:
    • Publish Location: [Washington, D.C.]

    “Draft regulatory guide DG-1107” Subjects and Themes:

    Edition Identifiers:

    Access and General Info:

    • First Year Published: 2003
    • Is Full Text Available: No
    • Is The Book Public: No
    • Access Status: No_ebook

    Online Access

    Downloads Are Not Available:

    The book is not public therefore the download links will not allow the download of the entire book, however, borrowing the book online is available.

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      4Consequences of the loss of the residual heat removal systems in pressurized water reactors

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      “Consequences of the loss of the residual heat removal systems in pressurized water reactors” Metadata:

      • Title: ➤  Consequences of the loss of the residual heat removal systems in pressurized water reactors
      • Author:
      • Language: English
      • Number of Pages: Median: 153
      • Publisher: ➤  Supt. of Docs., U.S. G.P.O. [distributor] - Division of Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
      • Publish Date:
      • Publish Location: Washington, DC

      “Consequences of the loss of the residual heat removal systems in pressurized water reactors” Subjects and Themes:

      Edition Identifiers:

      Access and General Info:

      • First Year Published: 1992
      • Is Full Text Available: No
      • Is The Book Public: No
      • Access Status: No_ebook

      Online Access

      Downloads Are Not Available:

      The book is not public therefore the download links will not allow the download of the entire book, however, borrowing the book online is available.

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        5USI A-43 resolution positions

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        “USI A-43 resolution positions” Metadata:

        • Title: USI A-43 resolution positions
        • Author: ➤  
        • Language: English
        • Publisher: ➤  Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
        • Publish Date:
        • Publish Location: Washington, D.C

        “USI A-43 resolution positions” Subjects and Themes:

        Edition Identifiers:

        Access and General Info:

        • First Year Published: 1983
        • Is Full Text Available: No
        • Is The Book Public: No
        • Access Status: No_ebook

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        6USI A-43 regulatory analysis

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        “USI A-43 regulatory analysis” Metadata:

        • Title: USI A-43 regulatory analysis
        • Author:
        • Language: English
        • Publisher: ➤  Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
        • Publish Date:
        • Publish Location: Washington, D.C

        “USI A-43 regulatory analysis” Subjects and Themes:

        Edition Identifiers:

        Access and General Info:

        • First Year Published: 1985
        • Is Full Text Available: No
        • Is The Book Public: No
        • Access Status: No_ebook

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        7SUNYAB/ERPI Combined Injection ECCS Program

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        “SUNYAB/ERPI Combined Injection ECCS Program” Metadata:

        • Title: ➤  SUNYAB/ERPI Combined Injection ECCS Program
        • Author: ➤  
        • Language: English
        • Number of Pages: Median: 62
        • Publisher: EPRI
        • Publish Date:
        • Publish Location: Palo Alto, Calif

        “SUNYAB/ERPI Combined Injection ECCS Program” Subjects and Themes:

        Edition Identifiers:

        Access and General Info:

        • First Year Published: 1977
        • Is Full Text Available: No
        • Is The Book Public: No
        • Access Status: No_ebook

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        8An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2

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        “An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2” Metadata:

        • Title: ➤  An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2
        • Author:
        • Language: English
        • Number of Pages: Median: 39
        • Publisher: ➤  National Technical Information Service, [distributor - U.S. Nuclear Regulatory Commission
        • Publish Date:
        • Publish Location: ➤  Springfield, Va - Washington, DC

        “An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2” Subjects and Themes:

        Edition Identifiers:

        Access and General Info:

        • First Year Published: 1992
        • Is Full Text Available: No
        • Is The Book Public: No
        • Access Status: No_ebook

        Online Access

        Downloads Are Not Available:

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          9Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE

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          “Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE” Metadata:

          • Title: ➤  Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE
          • Author:
          • Language: English
          • Number of Pages: Median: 29
          • Publisher: ➤  U.S. Nuclear Regulatory Commission
          • Publish Date:
          • Publish Location: Washington, DC

          “Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE” Subjects and Themes:

          Edition Identifiers:

          Access and General Info:

          • First Year Published: 2013
          • Is Full Text Available: No
          • Is The Book Public: No
          • Access Status: No_ebook

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          10Safety aspects of the Yankee Rowe Nuclear Powerplant

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          Book's cover

          “Safety aspects of the Yankee Rowe Nuclear Powerplant” Metadata:

          • Title: ➤  Safety aspects of the Yankee Rowe Nuclear Powerplant
          • Author: ➤  
          • Language: English
          • Number of Pages: Median: 194
          • Publisher: ➤  U.S. G.P.O. - For sale by the U.S. G.P.O., Supt. of Docs., Congressional Sales Office
          • Publish Date:
          • Publish Location: Washington

          “Safety aspects of the Yankee Rowe Nuclear Powerplant” Subjects and Themes:

          Edition Identifiers:

          Access and General Info:

          • First Year Published: 1992
          • Is Full Text Available: No
          • Is The Book Public: No
          • Access Status: No_ebook

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          11Regulatory guide 1.82, (Task MS 203-4)

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          “Regulatory guide 1.82, (Task MS 203-4)” Metadata:

          • Title: ➤  Regulatory guide 1.82, (Task MS 203-4)
          • Author: ➤  
          • Language: English
          • Publisher: ➤  U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
          • Publish Date:
          • Publish Location: [Washington, D.C.]

          “Regulatory guide 1.82, (Task MS 203-4)” Subjects and Themes:

          Edition Identifiers:

          Access and General Info:

          • First Year Published: 1985
          • Is Full Text Available: No
          • Is The Book Public: No
          • Access Status: No_ebook

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          12Knowledge base report on emergency core cooling sump performance in operating light water reactors

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          “Knowledge base report on emergency core cooling sump performance in operating light water reactors” Metadata:

          • Title: ➤  Knowledge base report on emergency core cooling sump performance in operating light water reactors
          • Author:
          • Language: English
          • Number of Pages: Median: 427
          • Publisher: ➤  United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
          • Publish Date:
          • Publish Location: Washington, D.C

          “Knowledge base report on emergency core cooling sump performance in operating light water reactors” Subjects and Themes:

          Edition Identifiers:

          Access and General Info:

          • First Year Published: 2014
          • Is Full Text Available: No
          • Is The Book Public: No
          • Access Status: No_ebook

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          13Reliability study

          “Reliability study” Metadata:

          • Title: Reliability study
          • Language: English
          • Publisher: The Commission
          • Publish Date:
          • Publish Location: Washington, DC

          “Reliability study” Subjects and Themes:

          Edition Identifiers:

          Access and General Info:

          • First Year Published: 1998
          • Is Full Text Available: No
          • Is The Book Public: No
          • Access Status: No_ebook

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          14Compendium of ECCS research for realistic LOCA analysis

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          “Compendium of ECCS research for realistic LOCA analysis” Metadata:

          • Title: ➤  Compendium of ECCS research for realistic LOCA analysis
          • Author: ➤  
          • Language: English
          • Number of Pages: Median: 1358
          • Publisher: ➤  Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
          • Publish Date:
          • Publish Location: Washington, DC

          “Compendium of ECCS research for realistic LOCA analysis” Subjects and Themes:

          Edition Identifiers:

          Access and General Info:

          • First Year Published: 1988
          • Is Full Text Available: No
          • Is The Book Public: No
          • Access Status: No_ebook

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          15Assessment of RELAP5/MOD3/V5m5 against the UPTF test no. 11 (countercurrent flow in PWR hot leg)

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          “Assessment of RELAP5/MOD3/V5m5 against the UPTF test no. 11 (countercurrent flow in PWR hot leg)” Metadata:

          • Title: ➤  Assessment of RELAP5/MOD3/V5m5 against the UPTF test no. 11 (countercurrent flow in PWR hot leg)
          • Author:
          • Language: English
          • Number of Pages: Median: 53
          • Publisher: ➤  National Technical Information Service [distributor - Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Available from Supt. of Docs., U.S. G.P.O.
          • Publish Date:
          • Publish Location: ➤  Springfield, VA - Washington, DC

          “Assessment of RELAP5/MOD3/V5m5 against the UPTF test no. 11 (countercurrent flow in PWR hot leg)” Subjects and Themes:

          Edition Identifiers:

          Access and General Info:

          • First Year Published: 1993
          • Is Full Text Available: No
          • Is The Book Public: No
          • Access Status: No_ebook

          Online Access

          Downloads Are Not Available:

          The book is not public therefore the download links will not allow the download of the entire book, however, borrowing the book online is available.

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            16Analysis of semiscale test S-LH-1 using RELAP5/MOD2

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            “Analysis of semiscale test S-LH-1 using RELAP5/MOD2” Metadata:

            • Title: ➤  Analysis of semiscale test S-LH-1 using RELAP5/MOD2
            • Author:
            • Language: English
            • Number of Pages: Median: 32
            • Publisher: ➤  U.S. Nuclear Regulatory Commission - National Technical Information Service, [distributor - Supt. of Docs., U.S. G.P.O. [distributor]
            • Publish Date:
            • Publish Location: ➤  Washington, DC - Springfield, Va

            “Analysis of semiscale test S-LH-1 using RELAP5/MOD2” Subjects and Themes:

            Edition Identifiers:

            Access and General Info:

            • First Year Published: 1992
            • Is Full Text Available: No
            • Is The Book Public: No
            • Access Status: No_ebook

            Online Access

            Downloads Are Not Available:

            The book is not public therefore the download links will not allow the download of the entire book, however, borrowing the book online is available.

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              17Analysis of ECC bypass data

              By

              “Analysis of ECC bypass data” Metadata:

              • Title: Analysis of ECC bypass data
              • Author:
              • Language: English
              • Publisher: ➤  Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Available from National Technical Information Service
              • Publish Date:
              • Publish Location: ➤  Springfield, Va - Washington, D.C

              “Analysis of ECC bypass data” Subjects and Themes:

              Edition Identifiers:

              Access and General Info:

              • First Year Published: 1979
              • Is Full Text Available: No
              • Is The Book Public: No
              • Access Status: No_ebook

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              18RELAP/MOD3 analysis of BETHSY test 6.9c

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              “RELAP/MOD3 analysis of BETHSY test 6.9c” Metadata:

              • Title: ➤  RELAP/MOD3 analysis of BETHSY test 6.9c
              • Author:
              • Language: English
              • Number of Pages: Median: 49
              • Publisher: ➤  Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
              • Publish Date:
              • Publish Location: Washington, DC

              “RELAP/MOD3 analysis of BETHSY test 6.9c” Subjects and Themes:

              Edition Identifiers:

              Access and General Info:

              • First Year Published: 2000
              • Is Full Text Available: No
              • Is The Book Public: No
              • Access Status: No_ebook

              Online Access

              Downloads Are Not Available:

              The book is not public therefore the download links will not allow the download of the entire book, however, borrowing the book online is available.

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                19Behavior of PWR reactor coolant system components, other than steam generator tubes, under severe accident conditions

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                “Behavior of PWR reactor coolant system components, other than steam generator tubes, under severe accident conditions” Metadata:

                • Title: ➤  Behavior of PWR reactor coolant system components, other than steam generator tubes, under severe accident conditions
                • Author:
                • Language: English
                • Publisher: ➤  Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
                • Publish Date:
                • Publish Location: Washington, DC

                “Behavior of PWR reactor coolant system components, other than steam generator tubes, under severe accident conditions” Subjects and Themes:

                Edition Identifiers:

                Access and General Info:

                • First Year Published: 2003
                • Is Full Text Available: No
                • Is The Book Public: No
                • Access Status: No_ebook

                Online Access

                Downloads Are Not Available:

                The book is not public therefore the download links will not allow the download of the entire book, however, borrowing the book online is available.

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                  20Shutdown decay heat removal analysis of a combustion engineering 2-loop pressurized water reactor

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                  “Shutdown decay heat removal analysis of a combustion engineering 2-loop pressurized water reactor” Metadata:

                  • Title: ➤  Shutdown decay heat removal analysis of a combustion engineering 2-loop pressurized water reactor
                  • Author:
                  • Language: English
                  • Publisher: ➤  Division of Reactor and Plant Systems, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
                  • Publish Date:
                  • Publish Location: Washington, DC

                  “Shutdown decay heat removal analysis of a combustion engineering 2-loop pressurized water reactor” Subjects and Themes:

                  Edition Identifiers:

                  Access and General Info:

                  • First Year Published: 1987
                  • Is Full Text Available: No
                  • Is The Book Public: No
                  • Access Status: No_ebook

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                  21Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Westinghouse-designed operating plants

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                  “Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Westinghouse-designed operating plants” Metadata:

                  • Title: ➤  Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Westinghouse-designed operating plants
                  • Author: ➤  
                  • Language: English
                  • Number of Pages: Median: 671
                  • Publisher: ➤  Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission - National Technical Information Serivce - The Office
                  • Publish Date:
                  • Publish Location: ➤  Springfield, Va - Washington, D.C

                  “Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Westinghouse-designed operating plants” Subjects and Themes:

                  Edition Identifiers:

                  Access and General Info:

                  • First Year Published: 1980
                  • Is Full Text Available: No
                  • Is The Book Public: No
                  • Access Status: No_ebook

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                  22Generic assessment of delayed reactor coolant pump trip during small break loss-of-coolant accidents in pressurized water reactors

                  By

                  “Generic assessment of delayed reactor coolant pump trip during small break loss-of-coolant accidents in pressurized water reactors” Metadata:

                  • Title: ➤  Generic assessment of delayed reactor coolant pump trip during small break loss-of-coolant accidents in pressurized water reactors
                  • Author:
                  • Language: English
                  • Number of Pages: Median: 75
                  • Publisher: ➤  National Technical Information Service - Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission - Bulletins and Orders Task Force, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
                  • Publish Date:
                  • Publish Location: ➤  Springfield, Va - Washington, D.C

                  “Generic assessment of delayed reactor coolant pump trip during small break loss-of-coolant accidents in pressurized water reactors” Subjects and Themes:

                  Edition Identifiers:

                  Access and General Info:

                  • First Year Published: 1979
                  • Is Full Text Available: No
                  • Is The Book Public: No
                  • Access Status: No_ebook

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                  23Generic evaluation of feedwater transients and small break loss-of-coolant accidents in GE-designed operating plants and near-team operating license applications

                  By

                  “Generic evaluation of feedwater transients and small break loss-of-coolant accidents in GE-designed operating plants and near-team operating license applications” Metadata:

                  • Title: ➤  Generic evaluation of feedwater transients and small break loss-of-coolant accidents in GE-designed operating plants and near-team operating license applications
                  • Author: ➤  
                  • Language: English
                  • Number of Pages: Median: 222
                  • Publisher: ➤  National Technical Information Service - Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission - The Office
                  • Publish Date:
                  • Publish Location: ➤  Springfield, Va - Washington, D.C

                  “Generic evaluation of feedwater transients and small break loss-of-coolant accidents in GE-designed operating plants and near-team operating license applications” Subjects and Themes:

                  Edition Identifiers:

                  Access and General Info:

                  • First Year Published: 1980
                  • Is Full Text Available: No
                  • Is The Book Public: No
                  • Access Status: No_ebook

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                  24Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Combustion Engineering designed operating plants

                  By

                  “Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Combustion Engineering designed operating plants” Metadata:

                  • Title: ➤  Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Combustion Engineering designed operating plants
                  • Author: ➤  
                  • Language: English
                  • Number of Pages: Median: 343
                  • Publisher: ➤  National Technical Information Service - Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission - The 0ffice
                  • Publish Date:
                  • Publish Location: ➤  Springfield, Va - Washington, D.C

                  “Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Combustion Engineering designed operating plants” Subjects and Themes:

                  Edition Identifiers:

                  Access and General Info:

                  • First Year Published: 1980
                  • Is Full Text Available: No
                  • Is The Book Public: No
                  • Access Status: No_ebook

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                  25Transient response of Babcock & Wilcox-designed reactors

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                  “Transient response of Babcock & Wilcox-designed reactors” Metadata:

                  • Title: ➤  Transient response of Babcock & Wilcox-designed reactors
                  • Author: ➤  
                  • Language: English
                  • Number of Pages: Median: 272
                  • Publisher: ➤  Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission - The Task Force - National Technical Information Service
                  • Publish Date:
                  • Publish Location: ➤  Springfield, Va - Washington, D. C

                  “Transient response of Babcock & Wilcox-designed reactors” Subjects and Themes:

                  Edition Identifiers:

                  Access and General Info:

                  • First Year Published: 1980
                  • Is Full Text Available: No
                  • Is The Book Public: No
                  • Access Status: No_ebook

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                  26Containment emergency sump performance

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                  “Containment emergency sump performance” Metadata:

                  • Title: ➤  Containment emergency sump performance
                  • Author:
                  • Language: English
                  • Publisher: ➤  Division of Safety Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
                  • Publish Date:
                  • Publish Location: Washington, D.C

                  “Containment emergency sump performance” Subjects and Themes:

                  Edition Identifiers:

                  Access and General Info:

                  • First Year Published: 1985
                  • Is Full Text Available: No
                  • Is The Book Public: No
                  • Access Status: No_ebook

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                  27A criterion for the onset of quench for low flow reflood

                  By

                  “A criterion for the onset of quench for low flow reflood” Metadata:

                  • Title: ➤  A criterion for the onset of quench for low flow reflood
                  • Author:
                  • Language: English
                  • Number of Pages: Median: 28
                  • Publisher: ➤  Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
                  • Publish Date:
                  • Publish Location: Washington, D.C

                  “A criterion for the onset of quench for low flow reflood” Subjects and Themes:

                  Edition Identifiers:

                  Access and General Info:

                  • First Year Published: 1982
                  • Is Full Text Available: No
                  • Is The Book Public: No
                  • Access Status: No_ebook

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                  28Browns Ferry Nuclear Plant variation in test intervals for high-pressure coolant injection (HPCI) system

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                  “Browns Ferry Nuclear Plant variation in test intervals for high-pressure coolant injection (HPCI) system” Metadata:

                  • Title: ➤  Browns Ferry Nuclear Plant variation in test intervals for high-pressure coolant injection (HPCI) system
                  • Author:
                  • Language: English
                  • Number of Pages: Median: 14
                  • Publisher: Tennessee Valley Authority
                  • Publish Date:
                  • Publish Location: [Washington, D.C.?

                  “Browns Ferry Nuclear Plant variation in test intervals for high-pressure coolant injection (HPCI) system” Subjects and Themes:

                  Edition Identifiers:

                  Access and General Info:

                  • First Year Published: 1985
                  • Is Full Text Available: No
                  • Is The Book Public: No
                  • Access Status: No_ebook

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                  29Pressurizer surge line Counter Current Flow Limitation during AP600 Mode 5 Cold Shutdown

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                  “Pressurizer surge line Counter Current Flow Limitation during AP600 Mode 5 Cold Shutdown” Metadata:

                  • Title: ➤  Pressurizer surge line Counter Current Flow Limitation during AP600 Mode 5 Cold Shutdown
                  • Author:
                  • Language: English
                  • Number of Pages: Median: 37
                  • Publish Date:

                  “Pressurizer surge line Counter Current Flow Limitation during AP600 Mode 5 Cold Shutdown” Subjects and Themes:

                  Edition Identifiers:

                  Access and General Info:

                  • First Year Published: 1999
                  • Is Full Text Available: No
                  • Is The Book Public: No
                  • Access Status: No_ebook

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                  30Reliability study

                  “Reliability study” Metadata:

                  • Title: Reliability study
                  • Language: English
                  • Publisher: ➤  Safety Programs Division, Office for Analysis and Evaluation of Operational Data, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor
                  • Publish Date:
                  • Publish Location: Washington, DC

                  “Reliability study” Subjects and Themes:

                  Edition Identifiers:

                  Access and General Info:

                  • First Year Published: 1998
                  • Is Full Text Available: No
                  • Is The Book Public: No
                  • Access Status: No_ebook

                  Online Access

                  Downloads Are Not Available:

                  The book is not public therefore the download links will not allow the download of the entire book, however, borrowing the book online is available.

                  Online Borrowing:

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                    31Notkühlsimulation der Reaktordruckbehälter von Druckwasserreaktoren =

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                    “Notkühlsimulation der Reaktordruckbehälter von Druckwasserreaktoren =” Metadata:

                    • Title: ➤  Notkühlsimulation der Reaktordruckbehälter von Druckwasserreaktoren =
                    • Author:
                    • Language: ger
                    • Number of Pages: Median: 123
                    • Publisher: ➤  Politechnika Krakowska im. Tadeusza Kościuszki
                    • Publish Date:
                    • Publish Location: Kraków

                    “Notkühlsimulation der Reaktordruckbehälter von Druckwasserreaktoren =” Subjects and Themes:

                    Edition Identifiers:

                    Access and General Info:

                    • First Year Published: 1993
                    • Is Full Text Available: No
                    • Is The Book Public: No
                    • Access Status: No_ebook

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