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Research Papers: Materials and Fabrication

Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Miniature Compact Tension Specimens

[+] Author and Article Information
Tohru Tobita

Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata-shirane 2-4, Tokai-mura,
Naka-gun, Ibaraki-ken 319-1195, Japan
e-mail: tobita.tohru@jaea.go.jp

Yutaka Nishiyama

Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata-shirane 2-4, Tokai-mura,
Naka-gun, Ibaraki-ken 319-1195, Japan
e-mail: nishiyama.yutaka93@jaea.go.jp

Takuyo Ohtsu

Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata-shirane 2-4, Tokai-mura,
Naka-gun, Ibaraki-ken 319-1195, Japan
e-mail: ohtsu.takuyo@jaea.go.jp

Makoto Udagawa

Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata-shirane 2-4, Tokai-mura,
Naka-gun, Ibaraki-ken 319-1195, Japan
e-mail: udagawa.makoto@jaea.go.jp

Jinya Katsuyama

Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata-shirane 2-4, Tokai-mura,
Naka-gun, Ibaraki-ken 319-1195, Japan
e-mail: katsuyama.jinya@jaea.go.jp

Kunio Onizawa

Nuclear Safety Research Center,
Japan Atomic Energy Agency,
Shirakata-shirane 2-4, Tokai-mura,
Naka-gun, Ibaraki-ken 319-1195, Japan
e-mail: onizawa.kunio@jaea.go.jp

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received October 6, 2014; final manuscript received December 14, 2014; published online February 27, 2015. Assoc. Editor: David L. Rudland.

J. Pressure Vessel Technol 137(5), 051405 (Oct 01, 2015) (8 pages) Paper No: PVT-14-1156; doi: 10.1115/1.4029428 History: Received October 06, 2014; Revised December 14, 2014; Online February 27, 2015

We conducted fracture toughness testing on five types of commercially manufactured steel with different ductile-to-brittle transition temperatures. This was performed using specimens of different sizes and shapes, including the precracked Charpy-type (PCCv), 0.4T-CT, 1T-CT, and miniature compact tension specimens (0.16T-CT). Our objective was to investigate the applicability of 0.16T-CT specimens to fracture toughness evaluation by the master curve method for reactor pressure vessel (RPV) steels. The reference temperature (To) values determined from the 0.16T-CT specimens were overall in good agreement with those determined from the 1T-CT specimens. The scatter of the 1T-equivalent fracture toughness values obtained from the 0.16T-CT specimens was equivalent to that obtained from the other larger specimens. Furthermore, we examined the loading rate effect on To for the 0.16T-CT specimens within the quasi-static loading range prescribed by ASTM E1921. The higher loading rate gave rise to a slightly higher To, and this dependency was almost the same for the larger specimens. We suggested an optimum test temperature on the basis of the Charpy transition temperature for determining To using the 0.16T-CT specimens.

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References

Figures

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Fig. 1

Temperature dependence of the yield stress of the materials

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Fig. 2

Plane strain fracture toughness of the materials

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Fig. 5

Relations between 1T-equivalent fracture toughness KJc(1Teq) and temperature with the master curve

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Fig. 11

Fracture toughness data obtained from the 0.16T-CT specimens for all materials

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Fig. 12

Relationship between Charpy 41 J transition temperature and reference temperature To determined from the 0.16T-CT specimens

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Fig. 4

Setup of the 0.16T-CT specimen

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Fig. 3

Fracture toughness specimens

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Fig. 8

Weibull plots of all specimens for each material

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Fig. 7

Comparison of reference temperature To determined from all 1T-CT and smaller specimens

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Fig. 6

Reference temperatures of all specimens for each material

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Fig. 9

Relationship between Weibull slope and number of specimens (Kmin = 20 MPa√m)

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Fig. 10

Loading rate dependency of reference temperature To

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