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    Welding Residual Stress in a Large Diameter Nuclear Reactor Pressure Vessel Nozzle

    Source: Journal of Pressure Vessel Technology:;2013:;volume( 135 ):;issue: 002::page 21208
    Author:
    Zhang, Tao
    ,
    Brust, Frederick W.
    ,
    Wilkowski, Gery
    ,
    Xu, Heqin
    ,
    Betervide, Alfredo A.
    ,
    Mazzantini, Oscar
    DOI: 10.1115/1.4007961
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The Atucha II nuclear power plant is a pressurized heavy water reactor (PHWR) being constructed in Argentina. The original plant was designed by Kraftwerk Union (KWU) in the 1970’s using the German methodology of break preclusion. The plant construction was halted for several decades, but a recent need for power was the driver for restarting the construction. Welding residual stresses in nuclear power plant piping can lead to cracking concerns later in the life of the plant, especially for stresscorrosion cracking. Hence, understanding the residual stress distribution from welding is important to evaluate the reliability of pipe and nozzle joints with welds. In this paper, a largediameter reactor pressure vessel (RPV) hotleg nozzle was analyzed. This is a nozzle from Atucha II nuclear power plant in Argentina. The main piping material is 20MnMoNi55 with Tenacito 65R weld metal, and inner diameter (ID) welded cladding at the girth weld locations is made of 309L. The special materials and weld geometry will lead interesting welding residual stress fields. In addition, postweld heat treatment (PWHT) of the girth welds and its boundary conditions could also play an important role in determining welding residual stress fields at the plant’s normal operating conditions. Sensitivity analyses were conducted and the technical observations and comments are provided.
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      Welding Residual Stress in a Large Diameter Nuclear Reactor Pressure Vessel Nozzle

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    contributor authorZhang, Tao
    contributor authorBrust, Frederick W.
    contributor authorWilkowski, Gery
    contributor authorXu, Heqin
    contributor authorBetervide, Alfredo A.
    contributor authorMazzantini, Oscar
    date accessioned2017-05-09T01:02:10Z
    date available2017-05-09T01:02:10Z
    date issued2013
    identifier issn0094-9930
    identifier otherpvt_135_2_021208.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/152991
    description abstractThe Atucha II nuclear power plant is a pressurized heavy water reactor (PHWR) being constructed in Argentina. The original plant was designed by Kraftwerk Union (KWU) in the 1970’s using the German methodology of break preclusion. The plant construction was halted for several decades, but a recent need for power was the driver for restarting the construction. Welding residual stresses in nuclear power plant piping can lead to cracking concerns later in the life of the plant, especially for stresscorrosion cracking. Hence, understanding the residual stress distribution from welding is important to evaluate the reliability of pipe and nozzle joints with welds. In this paper, a largediameter reactor pressure vessel (RPV) hotleg nozzle was analyzed. This is a nozzle from Atucha II nuclear power plant in Argentina. The main piping material is 20MnMoNi55 with Tenacito 65R weld metal, and inner diameter (ID) welded cladding at the girth weld locations is made of 309L. The special materials and weld geometry will lead interesting welding residual stress fields. In addition, postweld heat treatment (PWHT) of the girth welds and its boundary conditions could also play an important role in determining welding residual stress fields at the plant’s normal operating conditions. Sensitivity analyses were conducted and the technical observations and comments are provided.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleWelding Residual Stress in a Large Diameter Nuclear Reactor Pressure Vessel Nozzle
    typeJournal Paper
    journal volume135
    journal issue2
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.4007961
    journal fristpage21208
    journal lastpage21208
    identifier eissn1528-8978
    treeJournal of Pressure Vessel Technology:;2013:;volume( 135 ):;issue: 002
    contenttypeFulltext
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