Investigation of temperature dependence of fracture toughness in high-dose HT9 steel using small-specimen reuse technique

Jong Hyuk Baek, Thak Sang Byun, Start A. Maloy, Mychailo B. Toloczko

Research output: Contribution to journalArticlepeer-review

12 Scopus citations

Abstract

The temperature dependence of fracture toughness in HT9 steel irradiated to 3-145 dpa at 380-503 C was investigated using miniature three-point bend (TPB) fracture specimens. A miniature-specimen reuse technique has been established: the tested halves of subsize Charpy impact specimens with dimensions of 27 mm × 3 mm × 4 mm were reused for this fracture test campaign by cutting a notch with a diamond-saw in the middle of each half, and by fatigue-precracking to generate a sharp crack tip. It was confirmed that the fracture toughness of HT9 steel in the dose range depends more strongly on the irradiation temperature than the irradiation dose. At an irradiation temperature <430 C, the fracture toughness of irradiated HT9 increased with the test temperature, reached an upper shelf of 180-200MPam at 350-450 C, and then decreased with the test temperature. At an irradiation temperature ≥430 C, the fracture toughness was nearly unchanged up to about 450 C and decreased slowly with test temperatures in a higher temperature range. Such a rather monotonic test temperature dependence after high-temperature irradiation is similar to that observed for an archive material generally showing a higher degree of toughness. A brittle fracture without stable crack growth occurred in only a few specimens with relatively lower irradiation and test temperatures. In this discussion, these TPB fracture toughness data are compared with previously published data from 12.7 mm diameter disc compact tension (DCT) specimens.

Original languageEnglish
Pages (from-to)206-213
Number of pages8
JournalJournal of Nuclear Materials
Volume444
Issue number1-3
DOIs
StatePublished - 2014

Funding

This research was supported by National Research Foundation (NRF) and Ministry of Education, Science and Technology (MEST), Korean government, through its National Nuclear Technology Program. This research was also sponsored by US Department of Energy, Office of Nuclear Energy under Contract DE-AC05-00OR22725 with UT-Battelle, LLC. The authors would like to express special thanks to S.-H. Kim of KAERI for his technical review and thoughtful comments.

FundersFunder number
National Nuclear Technology Program
U.S. Department of Energy
Office of Nuclear EnergyDE-AC05-00OR22725
National Research Foundation of Korea
Ministry of Education, Science and Technology

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