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    Applicability of Miniature Compact Tension Specimens for Fracture Toughness Evaluation of Highly Neutron Irradiated Reactor Pressure Vessel Steels

    Source: Journal of Pressure Vessel Technology:;2018:;volume( 140 ):;issue: 005::page 51402
    Author:
    Ha, Yoosung
    ,
    Tobita, Tohru
    ,
    Ohtsu, Takuyo
    ,
    Takamizawa, Hisashi
    ,
    Nishiyama, Yutaka
    DOI: 10.1115/1.4040642
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The applicability of miniature compact tension (Mini-C(T)) specimens to fracture toughness evaluation of neutron-irradiated reactor pressure vessel (RPV) steels was investigated. Three types of RPV steels neutron-irradiated to a high-fluence region were prepared and manufactured as Mini-C(T) specimens according to Japan Electric Association Code (JEAC) 4216-2015. Through careful selection of the test temperature by considering previously obtained mechanical properties data, valid fracture toughness, and reference temperature (To) was obtained with a relatively small number of specimens. Comparing the fracture toughness and To values determined using other larger specimens with those determined using the Mini-C(T) specimens, To values of both unirradiated and irradiated Mini-C(T) specimens were found to be the acceptable margin of error. The scatter of 1T-equivalent fracture toughness values of both unirradiated and irradiated materials obtained using Mini-C(T) specimens did not differ significantly from the values obtained using larger specimens. The correlation between the Charpy 41 J transition temperature (T41J) and the To values agreed very well with that of the data in the literature, regardless of specimen size and fracture toughness of the materials before irradiation. Based on these findings, it was concluded that Mini-C(T) specimens can be applied to fracture toughness evaluation of neutron-irradiated materials without significant specimen size dependence.
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      Applicability of Miniature Compact Tension Specimens for Fracture Toughness Evaluation of Highly Neutron Irradiated Reactor Pressure Vessel Steels

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    contributor authorHa, Yoosung
    contributor authorTobita, Tohru
    contributor authorOhtsu, Takuyo
    contributor authorTakamizawa, Hisashi
    contributor authorNishiyama, Yutaka
    date accessioned2019-02-28T11:06:42Z
    date available2019-02-28T11:06:42Z
    date copyright8/2/2018 12:00:00 AM
    date issued2018
    identifier issn0094-9930
    identifier otherpvt_140_05_051402.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252790
    description abstractThe applicability of miniature compact tension (Mini-C(T)) specimens to fracture toughness evaluation of neutron-irradiated reactor pressure vessel (RPV) steels was investigated. Three types of RPV steels neutron-irradiated to a high-fluence region were prepared and manufactured as Mini-C(T) specimens according to Japan Electric Association Code (JEAC) 4216-2015. Through careful selection of the test temperature by considering previously obtained mechanical properties data, valid fracture toughness, and reference temperature (To) was obtained with a relatively small number of specimens. Comparing the fracture toughness and To values determined using other larger specimens with those determined using the Mini-C(T) specimens, To values of both unirradiated and irradiated Mini-C(T) specimens were found to be the acceptable margin of error. The scatter of 1T-equivalent fracture toughness values of both unirradiated and irradiated materials obtained using Mini-C(T) specimens did not differ significantly from the values obtained using larger specimens. The correlation between the Charpy 41 J transition temperature (T41J) and the To values agreed very well with that of the data in the literature, regardless of specimen size and fracture toughness of the materials before irradiation. Based on these findings, it was concluded that Mini-C(T) specimens can be applied to fracture toughness evaluation of neutron-irradiated materials without significant specimen size dependence.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleApplicability of Miniature Compact Tension Specimens for Fracture Toughness Evaluation of Highly Neutron Irradiated Reactor Pressure Vessel Steels
    typeJournal Paper
    journal volume140
    journal issue5
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.4040642
    journal fristpage51402
    journal lastpage051402-6
    treeJournal of Pressure Vessel Technology:;2018:;volume( 140 ):;issue: 005
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
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