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    Brittle Failure Assessment of a PWR-RPV for Operating Conditions and Loss of Coolant Accident

    Source: Journal of Pressure Vessel Technology:;2008:;volume( 130 ):;issue: 003::page 31403
    Author:
    Dieter Siegele
    ,
    Gerhard Nagel
    ,
    Igor Varfolomeyev
    DOI: 10.1115/1.2937759
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The brittle failure assessment for the reactor pressure vessel (RPV) of a 1300MW pressurized water reactor was revised according to the state of the art. The RPV steel is 22 NiMoCr 37 (A 508 Cl. 2). The expected neutron fluence at the end of license (EOL) after 32years of full operation is Φ<2.3×1018neutrons∕cm2. The assessment followed a multibarrier concept to independently prove the exclusion of crack initiation, crack arrest, and exclusion of the load necessary to advance the arrested cracks through the RPV wall. Thermal and structural analyses of the RPV were performed both for the reactor shutdown with postulated upset conditions, as the most severe load case at operation, and for loss of coolant accident (LOCA) conditions. For LOCA transients, a leak size screening of different combinations of cold∕hot leg injection of emergency core cooling was performed, and the leading leak size was determined. A fracture mechanics based assessment was carried out for extended circumferential flaws in the weld joint between the RPV shell and the flange, as well as for axial flaws in the nozzle corner. These flaw geometries postulated at locations of the highest principal stresses and lowest temperatures under the respective transient conditions are representative for the brittle failure assessment of the whole vessel. For a normal operation, the maximum crack driving force takes place at high temperatures preceding the upset conditions. The transient follows a load path decreasing with temperature, producing a warm prestressing effect, which is considered in the assessment. Thus, a large safety margin against crack initiation can be demonstrated. At LOCA, the most severe conditions are determined for postulated cracks in the nozzle corner. Here, applying the constraint modified master curve, which takes account of the low stress triaxiality in the component, the exclusion of crack initiation is proven. Furthermore, two additional safety barriers are proven, the crack arrest after postulated crack initiation well within the allowable depth, as well as the preclusion of the load necessary to advance the arrested crack through the RPV wall.
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      Brittle Failure Assessment of a PWR-RPV for Operating Conditions and Loss of Coolant Accident

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    http://yetl.yabesh.ir/yetl1/handle/yetl/139194
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    contributor authorDieter Siegele
    contributor authorGerhard Nagel
    contributor authorIgor Varfolomeyev
    date accessioned2017-05-09T00:30:16Z
    date available2017-05-09T00:30:16Z
    date copyrightAugust, 2008
    date issued2008
    identifier issn0094-9930
    identifier otherJPVTAS-28496#031403_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/139194
    description abstractThe brittle failure assessment for the reactor pressure vessel (RPV) of a 1300MW pressurized water reactor was revised according to the state of the art. The RPV steel is 22 NiMoCr 37 (A 508 Cl. 2). The expected neutron fluence at the end of license (EOL) after 32years of full operation is Φ<2.3×1018neutrons∕cm2. The assessment followed a multibarrier concept to independently prove the exclusion of crack initiation, crack arrest, and exclusion of the load necessary to advance the arrested cracks through the RPV wall. Thermal and structural analyses of the RPV were performed both for the reactor shutdown with postulated upset conditions, as the most severe load case at operation, and for loss of coolant accident (LOCA) conditions. For LOCA transients, a leak size screening of different combinations of cold∕hot leg injection of emergency core cooling was performed, and the leading leak size was determined. A fracture mechanics based assessment was carried out for extended circumferential flaws in the weld joint between the RPV shell and the flange, as well as for axial flaws in the nozzle corner. These flaw geometries postulated at locations of the highest principal stresses and lowest temperatures under the respective transient conditions are representative for the brittle failure assessment of the whole vessel. For a normal operation, the maximum crack driving force takes place at high temperatures preceding the upset conditions. The transient follows a load path decreasing with temperature, producing a warm prestressing effect, which is considered in the assessment. Thus, a large safety margin against crack initiation can be demonstrated. At LOCA, the most severe conditions are determined for postulated cracks in the nozzle corner. Here, applying the constraint modified master curve, which takes account of the low stress triaxiality in the component, the exclusion of crack initiation is proven. Furthermore, two additional safety barriers are proven, the crack arrest after postulated crack initiation well within the allowable depth, as well as the preclusion of the load necessary to advance the arrested crack through the RPV wall.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleBrittle Failure Assessment of a PWR-RPV for Operating Conditions and Loss of Coolant Accident
    typeJournal Paper
    journal volume130
    journal issue3
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.2937759
    journal fristpage31403
    identifier eissn1528-8978
    treeJournal of Pressure Vessel Technology:;2008:;volume( 130 ):;issue: 003
    contenttypeFulltext
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