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Journal Articles

Effect of heat treatments on mechanical properties and microstructures of 8Cr-2W(F82H) steel doped with boron or boron and nitrogen

Wakai, Eiichi; Sato, Michitaka*; Okubo, Nariaki; Sawai, Tomotsugu; Shiba, Kiyoyuki; Jitsukawa, Shiro

Nippon Kinzoku Gakkai-Shi, 69(6), p.460 - 464, 2005/06

 Times Cited Count:1 Percentile:82.49(Metallurgy & Metallurgical Engineering)

no abstracts in English

JAEA Reports

Recent accomplishment for the development of reduced activation ferritic/martensitic steels; Interim report for HFIR phase 4 with results of relating activities

Department of Materials Science; Department of Fusion Engineering Research (Tokai Site)

JAERI-Review 2004-018, 97 Pages, 2004/08

JAERI-Review-2004-018.pdf:18.92MB

Extensive efforts for evaluating the irradiation performances of a reduced activation ferritic/martensitic steel (RAF/M) of F82H* and other several RAF/Ms have been made in recent several years. They are, examinations of the effects of neutron irradiation on (1) Ductile to brittle transition temperature (DBTT) up to a damage level of 20 dpa to explore lower temperature limit, (2) Enhanced He effect on DBTT shift for Ni/B doped heats (isotopic tailoring method was used for B doping), (3) Susceptibility to environmentally assisted cracking by the slow strain rate tensile tests (SSRT) in a high temperature pressurized water and (4) Flow stress-plastic strain relation obtained by measuring the profile of the specimen during tensile testing, together with the activities of (5) the development of the test methods after neutron irradiation and (6) other supporting researches. Results are summarized in the present report. They clearly indicate the good applicability of RAF/Ms to fusion machines.

Journal Articles

Microstructure property analysis of HFIR-irradiated reduced-activation ferritic/martensitic steels

Tanigawa, Hiroyasu; Hashimoto, Naoyuki*; Sakasegawa, Hideo*; Klueh, R. L.*; Sokolov, M. A.*; Shiba, Kiyoyuki; Jitsukawa, Shiro; Koyama, Akira*

Journal of Nuclear Materials, 329-333(1), p.283 - 288, 2004/08

 Times Cited Count:18 Percentile:22.54(Materials Science, Multidisciplinary)

Reduced-activation ferritic/martensitic steels (RAFs) were developed as candidate structural materials for fusion power plants. In a previous study, it was reported that ORNL9Cr-2WVTa and JLF-1 (Fe-9Cr-2W-V-Ta-N) steels showed smaller ductile-brittle transition temperature (DBTT) shifts compared to IEA modified F82H (Fe-8Cr-2W-V-Ta) after neutron irradiation up to 5 dpa at 573K. This difference in DBTT shift could not be interpreted as an effect of irradiation hardening, and it is also hard to be convinced that this difference was simply due to a Cr concentration difference. To clarify the mechanisms of the difference in Charpy impact property between these steels, various microstructure analyses were performed.

Journal Articles

Microstructural analysis of mechanically tested reduced activation ferritc/martensitic steels

Tanigawa, Hiroyasu; Hirose, Takanori; Ando, Masami; Jitsukawa, Shiro; Kato, Yudai*; Koyama, Akira*

Journal of Nuclear Materials, 307-311(Part1), p.293 - 298, 2002/12

 Times Cited Count:9 Percentile:44.38

It has been a key issue to get the mechanical understanding of fracture process on microstructure basis, especially on neutron-irradiated materials, but not yet to be understood well enough as for the difficulty of making transmission electron microscope (TEM) thin film sample from mechanical-tested specimen. To solve this technical problem, the focused ion beam (FIB) micro-sampling system was installed to the Research Hot Laboratory of Japan Atomic Research Institute (JAERI), Japan. This system makes it possible to fabricate the TEM specimens from the critical points of mechanical-tested radioactive specimens, such as the crack initiation points of fatigue fracture on neutron irradiated specimen. In this paper, the microstructure of mechanical-tested specimen of Reduced Activation Ferritic/martensitic steels, RAFs are investigated focusing on the helium effects to fatigue fracture.

Journal Articles

Microstructural study of irradiated isotopically tailored F82H steel

Wakai, Eiichi; Miwa, Yukio; Hashimoto, Naoyuki*; Robertson, J. P.*; Klueh, R. L.*; Shiba, Kiyoyuki; Abiko, Kenji*; Furuno, Shigemi*; Jitsukawa, Shiro

Journal of Nuclear Materials, 307-311(Part.1), p.203 - 211, 2002/12

 Times Cited Count:20 Percentile:20.56

no abstracts in English

Journal Articles

Evaluation of high temperature tensile and greep properties of light water reactor coolant piping materials for severe accident analyses

Harada, Yuhei; Maruyama, Yu; Maeda, Akio*; Chino, Eiichi; Shibazaki, Hiroaki*; Kudo, Tamotsu; Hidaka, Akihide; Hashimoto, Kazuichiro; Sugimoto, Jun

Journal of Nuclear Science and Technology, 37(6), p.518 - 529, 2000/06

no abstracts in English

JAEA Reports

Post-lrradiation examination on Fe-15Cr-20Ni series model alloy irradiated by CMIR-2(1); Effect of defect sink and size of solute atom on radiation induced segregation(1)

; Yamagata, Ichiro; ; Akasaka, Naoaki

JNC-TN9400 2000-046, 24 Pages, 2000/02

JNC-TN9400-2000-046.pdf:1.1MB

lt is well known that solute atoms are segregated on surface, grain boundary, etc. and composition changed partially in irradiated austenitic stainless steel. For understanding radiation induced segregation (RIS), we adopt a Fe-15Cr-20Ni-x (x: Si, Mo) which is basically alloy system in PNC1520, and size of Si, Mo are different from matrix atoms to investigate RIS behaviors. The specimens were irradiated by "Joyo" fast reactor that irradiation condition is 3.5 $$times$$ 10$$^{26}$$ n/m$$^{2}$$ (E>0.1Mev) at 476$$^{circ}$$C. After irradiation, the specimen were observed and analyzed with EDS (Energy Dispersive X-ray Spectroscope) of 400kV TEM (Transmission Electron Microscope). The behavior of RIS depends on size of solute atoms of alloy. For example, oversized atoms are decreased and undersized atoms are increased in sink. RIS of voids are as same as or more than grain boundaries and smaller than precipitates. The void denuded zone was existed nearby G.B. in case of combinations between the grains from G.B.0ne of the reasons in this, the voids swepted by moving G.B. in radiation induced G.B. migration.

Journal Articles

Microstructural evolution of cold-worked austenitic stainless steels irradiated to 17 DPA in spectrally tailored experiments of the ORR and HFIR at 400$$^{circ}$$C

Wakai, Eiichi; Hashimoto, N.*; J.P.Robertson*; Sawai, Tomotsugu; Hishinuma, Akimichi

Fusion Materials, 313(25), p.197 - 201, 1999/04

no abstracts in English

Journal Articles

Swelling of HFIR-irradiated F82H, F82H+$$^{10}$$B and F82H+$$^{58}$$Ni steels

Wakai, Eiichi; Hashimoto, N.*; Shiba, Kiyoyuki; Miwa, Yukio; J.P.Robertson*; R.L.Klueh*

Fusion Materials, 313(25), p.161 - 169, 1999/04

no abstracts in English

Journal Articles

In situ observation of microstructural development during electron irradiation in Al$$_{2}$$O$$_{3}$$ containing Cr$$_{2}$$O$$_{3}$$ or TiO$$_{2}$$

*; Katano, Yoshio; Noda, Kenji

Journal of Nuclear Materials, 258-263, p.1831 - 1835, 1998/00

 Times Cited Count:1 Percentile:83.51

no abstracts in English

Journal Articles

Damage structure evolution in Al$$_{2}$$O$$_{3}$$ irradiated with multiple ion beams of H,He and O and after annealing

Katano, Yoshio; ; Yamaki, Daiju; Aruga, Takeo; Noda, Kenji

Journal of Nuclear Materials, 258-263, p.1842 - 1847, 1998/00

 Times Cited Count:4 Percentile:58.55

no abstracts in English

Journal Articles

Development of a triple beam irradiation facility

Hamada, Shozo; Miwa, Yukio; Yamaki, Daiju; Katano, Yoshio; ; Noda, Kenji

Journal of Nuclear Materials, 258-263, p.383 - 387, 1998/00

 Times Cited Count:11 Percentile:33.3

no abstracts in English

Journal Articles

Cross-sectional observation of damage structures in Al$$_{2}$$O$$_{3}$$ irradiated with multiple beams of H,He and O ions and after annealing at 1273K

Katano, Yoshio; ; Yamaki, Daiju; Aruga, Takeo; Noda, Kenji; Yamamoto, Shunya

Nuclear Instruments and Methods in Physics Research A, 140(1-2), p.152 - 158, 1998/00

no abstracts in English

Journal Articles

Cavity formation in single crystal Al$$_{2}$$O$$_{3}$$ irradiated with triple beams of O,H and He ions

Katano, Yoshio; Hojo, Kiichi; ; Yamaki, Daiju; Aruga, Takeo; Noda, Kenji

Nuclear Instruments and Methods in Physics Research B, 141(1-4), p.411 - 418, 1998/00

 Times Cited Count:6 Percentile:47.71

no abstracts in English

JAEA Reports

Study of irradiation damage structures in austenitic stainless steels

Hamada, Shozo

JAERI-Tech 97-041, 180 Pages, 1997/08

JAERI-Tech-97-041.pdf:13.34MB

no abstracts in English

Journal Articles

Development of failure prediction method for structural ceramics based on micro-fracture mechanics and probabilistic theory

Nippon Genshiryoku Gakkai-Shi, 39(5), p.10 - 13, 1997/00

no abstracts in English

Journal Articles

Effect of triple beam irradiation on microstructural evolution in austenitic stainless steel

Hamada, Shozo; Y.C.Zhang*; Miwa, Yukio; Yamaki, Daiju

Radiation Physics and Chemistry, 50(6), p.555 - 559, 1997/00

 Times Cited Count:6 Percentile:49.66

no abstracts in English

Journal Articles

Modelling irradiation induced porosity evolution in gas cooled reactor graphites at temperatures between 300-1500$$^{circ}$$C

B.J.Marsden*; ; R.Charles*

Proc. of meeting: Open Discussion on Current Issues in Nuclear Graphite and Carbon Topics, 0, 1 Pages, 1996/00

no abstracts in English

Journal Articles

The Microstructural evolution and swelling behavior of type 316 stainless steel irradiated in HFIR

Hamada, Shozo; Suzuki, Masahide; P.J.Maziasz*; Hishinuma, Akimichi;

Effects of Radiation on Materials,Vol. 1, p.172 - 184, 1990/00

no abstracts in English

29 (Records 1-20 displayed on this page)