Reactor vessel

Results: 229



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81Tenth International Symposium on  REACTOR DOSIMETRY September 12-17, 1999  Osaka, JAPAN

Tenth International Symposium on REACTOR DOSIMETRY September 12-17, 1999 Osaka, JAPAN

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Source URL: isrd16.reactordosimetry.org

Language: English - Date: 2015-02-17 00:11:43
82<Reference>  “Development of a technology to investigate inside  the Reactor Primary Containment Vessel (PCV)” ‐‐ Site test “Investigation B1” on grating around  the pedestal inside Unit

“Development of a technology to investigate inside  the Reactor Primary Containment Vessel (PCV)” ‐‐ Site test “Investigation B1” on grating around  the pedestal inside Unit

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Source URL: www4.tepco.co.jp

Language: English - Date: 2015-04-13 08:10:38
    83<Reference>  “Development of a technology to investigate  inside the Reactor Primary Containment Vessel (PCV)” ‐Site test “Investigation B1” report on grating around the pedestal inside Un

    “Development of a technology to investigate  inside the Reactor Primary Containment Vessel (PCV)” ‐Site test “Investigation B1” report on grating around the pedestal inside Un

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    Source URL: www4.tepco.co.jp

    Language: English - Date: 2015-04-13 06:32:14
      84Reference−3  Content of our announcement / notification at the initial stage of accident and the content of announcement of official residence / government <time series> ○We apologize once again that there is a matte

      Reference−3 Content of our announcement / notification at the initial stage of accident and the content of announcement of official residence / government

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      Source URL: www.tepco.co.jp

      Language: English - Date: 2012-12-14 05:27:52
      85<Reference>  “Development of a technology to investigate  inside the Reactor Primary Containment Vessel (PCV)” ‐Site test “Investigation B1” report on grating around the pedestal inside Un

      “Development of a technology to investigate  inside the Reactor Primary Containment Vessel (PCV)” ‐Site test “Investigation B1” report on grating around the pedestal inside Un

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      Source URL: www.tepco.co.jp

      Language: English - Date: 2015-04-13 06:32:14
        86Project Subjects Irradiation Embrittlement and Structural Integrity of Reactor Pressure Vessel Background and Objective The reactor pressure vessels (RPVs) of light water reactors (LWRs) are subjected to neutron irradiat

        Project Subjects Irradiation Embrittlement and Structural Integrity of Reactor Pressure Vessel Background and Objective The reactor pressure vessels (RPVs) of light water reactors (LWRs) are subjected to neutron irradiat

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        Source URL: criepi.denken.or.jp

        Language: English - Date: 2010-12-28 01:54:35
        87Principal Research Results  Evaluation of Fracture Toughness for Japanese Reactor Pressure Vessel Steel using Master Curve Method Background The Master Curve method has been proposed and recognized worldwide as an altern

        Principal Research Results Evaluation of Fracture Toughness for Japanese Reactor Pressure Vessel Steel using Master Curve Method Background The Master Curve method has been proposed and recognized worldwide as an altern

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        Source URL: criepi.denken.or.jp

        Language: English - Date: 2008-09-29 03:24:07
        88Project Subjects Irradiation Embrittlement and Structural Integrity of Reactor Pressure Vessel Background and Objective Mechanical properties of metallic materials used in nuclear reactors change due to circumstances suc

        Project Subjects Irradiation Embrittlement and Structural Integrity of Reactor Pressure Vessel Background and Objective Mechanical properties of metallic materials used in nuclear reactors change due to circumstances suc

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        Source URL: criepi.denken.or.jp

        Language: English - Date: 2011-11-04 00:31:32
        89Principal Research Results  Development of Flaw Evaluation Method for Class 2 and 3 Light Water Reactor Piping Background The development of “flaw evaluation method” to determine whether detected flaws are acceptable

        Principal Research Results Development of Flaw Evaluation Method for Class 2 and 3 Light Water Reactor Piping Background The development of “flaw evaluation method” to determine whether detected flaws are acceptable

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        Source URL: criepi.denken.or.jp

        Language: English - Date: 2008-09-29 03:15:15
        90NRC AUGMENTED INSPECTION TEAM EXIT MEETING DAVIS-BESSE REACTOR VESSEL HEAD CORROSION APRIL 5, 2002

        NRC AUGMENTED INSPECTION TEAM EXIT MEETING DAVIS-BESSE REACTOR VESSEL HEAD CORROSION APRIL 5, 2002

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        Source URL: www.nuceng.ca

        Language: English - Date: 2015-01-11 13:19:00