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Research Papers: Materials and Fabrication

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

[+] Author and Article Information
Yoosung Ha

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

Tohru Tobita

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

Takuyo Ohtsu

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

Hisashi Takamizawa

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

Yutaka Nishiyama

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

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received February 8, 2018; final manuscript received June 14, 2018; published online August 2, 2018. Assoc. Editor: Yun-Jae Kim.

J. Pressure Vessel Technol 140(5), 051402 (Aug 02, 2018) (6 pages) Paper No: PVT-18-1039; doi: 10.1115/1.4040642 History: Received February 08, 2018; Revised June 14, 2018

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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References

Wallin, K. , 1984, “ The Scatter in KIc Results,” Eng. Fract. Mech., 19(6), pp. 1085–1093. [CrossRef]
Yamamoto, M. , Kimura, K. , Onizawa, K. , Yoshimoto, K. , Ogawa, T. , Chiba, A. , Hirano, T. , Sugihara, T. , Sugiyama, M. , Miura, N. , and Soneda, N. , 2012, “ A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: First Round Robin Test on Uniform Specimens of Reactor Pressure Vessel Material,” ASME Paper No. PVP2012-78661.
Yamamoto, M. , Kimura, A. , Onizawa, K. , Yoshimoto, K. , Ogawa, T. , Mabuchi, Y. , Viehrig, H. W. , Miura, N. , and Soneda, N. , 2014, “ A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens-3rd Report: Comparison of To Under Various Selections of Temperature Conditions,” ASME Paper No. PVP2014-28898.
JEA, 2015, “ Test Method for Determination of Reference Temperature, to, of Ferritic Steels,” Japanese Electric Association, Japan, Paper No. JEAC 4216-2015 (in Japanese).
Tobita, T. , Nishiyama, Y. , Ohtsu, T. , Udagawa, M. , Katsuyama, J. , and Onizawa, K. , 2015, “ Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Miniature Compact Tension Specimens,” ASME J. Pressure Vessel Technol., 137(5), p. 051405. [CrossRef]
Chaouadi, R. , Walle, E. V. , Scibetta, M. , and Gérard, R. , 2016, “ On the Use of Miniaturized CT Specimens for Fracture Toughness Characterization of RPV Materials,” ASME Paper No. PVP2016-63607.
Ishino, S. , Kawakami, T. , Hidaka, T. , and Satoh, M. , 1990, “ The Effect of Chemical Composition on Irradiation Embrittlement,” Nucl. Eng. Des., 119(2–3), pp. 139–148. [CrossRef]
Soneda, N. , Dohi, K. , Nishida, K. , Nomoto, A. , Tomimatsu, M. , and Matsuzawa, H. , 2009, “ Microstructural Characterization of RPV Materials Irradiated to High Fluences at High Flux,” J. ASTM Int., 6(7), pp. 1–16. [CrossRef]
Onizawa, K. , Tobita, T. , and Suzuki, M. , 2000, “ Effect of Irradiation on Fracture Toughness in the Transition Range of RPV Steels,” ASTM International, West Conshohocken, PA, Standard No. STP1366.
JEA, 2007, “ Method of Surveillance Tests for Structural Materials of Nuclear Reactors,” Japanese Electric Association, Japan, Paper No. JEAC 4201-2007 (in Japanese).
ASTM, 2013, “ Standard Test Method for Determination of Reference Temperature, To, for Ferritic Steels in the Transition Range,” American Society for Testing and Materials, West Conshohocken, PA, Standard No. ASTM E 1921-13.
Miura, N. , and Soneda, N. , 2010, “ Evaluation of Fracture Toughness by Master Curve Approach Using Miniature C(T) Specimens,” ASME Paper No. PVP2010-25862.
Sokolov, M. A. , and Nanstad, R. K. , 2000, “ Comparison of Irradiation-Induced Shifts of KJc and Charpy Impact Toughness for Reactor Pressure Vessel Steels,” United States Nuclear Regulatory Commission, Washington, DC, Technical Report No. NUREG/CR-6609.
Takamizawa, H. , Tobita, T. , Ohtsu, T. , Katsuyama, J. , Nishiyama, Y. , and Onizawa, K. , 2015, “ Finite Element Analysis on the Application of Mini-C(T) Specimens for Fracture Toughness Evaluation,” ASME Paper No. PVP2015-45412.
IAEA, 2005, “ Application of Surveillance Programme Results to Reactor Pressure Vessel Integrity Assessment,” International Atomic Energy Agency, Vienna, Austria, Technical Document No. IAEA-TECDOC-1435.

Figures

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Fig. 1

Geometries of Mini-C(T) specimens and method of cutting them from Charpy-type specimens

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Fig. 6

Correlation between Weibull exponent and number of specimens

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Fig. 7

Correlation between To obtained using Mini-C(T) specimen and Charpy T41J compared with data taken from Sokolov and Nanstad

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Fig. 2

Master curves of unirradiated and irradiated materials: (a) Steel B, (b) 3B, and (c) 5B

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Fig. 3

Reference temperature obtained using PCCv, 1T-C(T), and Mini-C(T) specimens of Steel B, 3B, and 5B

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Fig. 4

Comparison of To obtained using Mini-C(T) and larger specimens

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Fig. 5

Weibull plots of all types of specimens: (a) Steel B, (b) 3B, and (c) 5B

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