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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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