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C in Mod.9Cr-1Mo steel to 1
10
cyclesToyota, Kodai; Imagawa, Yuya; Onizawa, Takashi; Kato, Shoichi; Furuya, Yoshiyuki*
Nihon Kikai Gakkai Rombunshu (Internet), 89(928), p.23-00206_1 - 23-00206_15, 2023/12
In order to design fast reactors, it is necessary to consider high cycle fatigue of structural materials up to 110
cycles; to evaluate high cycle fatigue at 110 cycles, it is necessary to develop a best-fit fatigue curve applicable up to 110 cycles. In this study, high cycle fatigue tests were conducted under strain-controlled conditions and ultrasonic fatigue tests were also conducted to develop a high cycle fatigue evaluation method for Mod.9Cr-1Mo steel, which is a candidate material for fast reactor structural materials. Based on the test results, the best-fit fatigue curves were extended and the applicability of the JSME best-fit fatigue curves up to 110 cycles was verified.
Xiong, Z.; Naoe, Takashi; Wan, T.; Futakawa, Masatoshi; Maekawa, Katsuhiro*
Procedia Engineering, 101, p.552 - 560, 2015/03
Times Cited Count：2 Percentile：62.07(Engineering, Multidisciplinary)Very high-cycle fatigue behaviour of SUS316L, which is used as the structural material of the spallation neutron sources, was investigated through the ultrasonic fatigue test with the strain rate of 10
s
. Cross-sectional hardness distributions of the fatigue-failed specimens for solution annealed (SA) and cold worked (CW) 316L were measured to understand the cyclic hardening or softening. In addition, the tensile tests of the fatigue-failed specimens were performed at room temperature. Furthermore, the nonlinear ultrasonic system was used for evaluating the dislocation density variation. The results showed the cyclic hardening in the region of very high-cycle fatigue in the case of SA. In contrast, in the case of 10%CW, cyclic softening occurred when the number of cycles below 10
and followed by cyclic hardening. In the case of 20%CW, cyclic softening was observed when the number of cycles below 10
, while cyclic hardening occurred subsequently.
Ishii, Toshimitsu; Yonekawa, Minoru; Omi, Masao; Takada, Fumiki; Saito, Junichi; Ioka, Ikuo; Miwa, Yukio
KAERI/GP-192/2002, p.157 - 166, 2002/00
no abstracts in English
; Aoto, Kazumi; ;
JNC TN9400 2000-022, 46 Pages, 2000/03
ln this report, a study on the behaviors of the magnetization induced by mechanical damages is carried out. By introducing mechanical damages to a test-piece with a tension or/and a zero, tension fatigue testing and measuring the corresponding leakage flux signal, natural magnetization change is proved and found increasing with the mechanical damages (viz. plastic deformation or fatigue damages) though a saturation occurs when damage gets too large. From the experimental results of fatigue testing utilizing test-pieces with a central slit, it was verified that observing the natural leakage flux density (leakage flux without applying external magnetic field) is a reasonable way to identify fatigue cracks. A feature parameter (area of the 
B hysteresis curve) of the in-situ magnetic field signal measured during the fatigue testing is proposed for predicting the fatigue damages, which is found depending on the cyclic number of the applied loading. At last, residual magnetic fields of a magnetized test-piece are also measured and found depending on the applied plastic deformation in case that the plastic strain is not too small. From these experimental results, it is found that the approach detecting natural magnetization is applicable for monitoring the damage status though it may be not efficient for a scanning inspection concerning its small signal magnitude. On the other hand, the method employing permanent magnet is robust against the environment noise but possibly not valid for the ISl of a structural component with a relative low damage level. For practical application, efforts to evaluate the feasibility of the proposed method are necessary for more testing conditions especially its suitability in a practical environment.
; *
JNC TN9450 2000-002, 335 Pages, 1999/10
JNC-TN9450-2000-002.pdf:21.65MB
This report summarizes the material test dala of SUS304 welded joints. Numbers of the data are as follows: [Tensile tests 71 (Post-irradiation: 39, others: 32) [Creep tests 77 (Post-irradiation: 20, others: 57) [Fatigue tests 50 (Post-irradiation: 0) [Creep-fatigue tests 14 (Post-irradiation: 0) This report consists of the printouts from "the structural material data processing system".
; *
JNC TN9450 2000-001, 1370 Pages, 1999/10
JNC-TN9450-2000-001.pdf:117.18MB
This report summarizes the material test data of SUS304. Numbers of the data are as follows. (1)Tensile tests 738 (Post-irradiation: 250, others: 488) (2)Creep tests 434 (Post-irradiation: 89, others: 345) (3)Fatigue tests 612 (Post-irradiation: 60, others: 552) (4)Creep-fatigue tests 200 (Post-irradiation: 40, others: 160) This report consists of the printouts from "the structural material data processing system".
Miwa, Yukio; Jitsukawa, Shiro; Hishinuma, Akimichi
Journal of Nuclear Materials, 258-263(PT.A), p.457 - 461, 1998/00
Times Cited Count：15 Percentile：74.74(Materials Science, Multidisciplinary)no abstracts in English
; Fukaya, Kiyoshi; Nishiyama, Yutaka; Suzuki, Masahide; Eto, Motokuni; Omi, Masao; Mimura, Hideaki; Ooka, Norikazu
JAERI-Research 96-028, 33 Pages, 1996/06
JAERI-Research-96-028.pdf:1.85MB
no abstracts in English
Omi, Masao; Mimura, Hideaki; ; Fukaya, Kiyoshi; Yonekawa, Minoru; Goto, Ichiro; ; Saito, Junichi; Eto, Motokuni;
JAERI-Tech 96-005, 39 Pages, 1996/02
no abstracts in English
Kaji, Yoshiyuki; Kikuchi, Kenji;
Nihon Kikai Gakkai Rombunshu, A, 61(586), p.1145 - 1152, 1995/06
no abstracts in English
Motooka, Takafumi; Kiuchi, Kiyoshi
JAERI-Research 95-032, 21 Pages, 1995/03
JAERI-Research-95-032.pdf:1.52MB
no abstracts in English
; Omi, Masao; Eto, Motokuni; Watanabe, Katsutoshi
KAERI-NEMAC/TR-32/95, 0, p.282 - 295, 1995/00
no abstracts in English
Tsuji, Hirokazu; Miya, Kenzo*
Nucl. Eng. Des., 155, p.547 - 557, 1995/00
Times Cited Count：2 Percentile：28.65(Nuclear Science & Technology)no abstracts in English
JAERI-M 93-076, 438 Pages, 1993/05
no abstracts in English
Tsuji, Hirokazu; Miya, Kenzo*
Preprints of the Post SMiRT Seminar No. ll on Construction Codes and Engineering, p.3.4-20 - 3.4-39, 1991/08
no abstracts in English
Kimura, Hidetaka; *; *; Kawasaki, Hirotsugu; Aoto, Kazumi;
PNC TN9450 91-003, 28 Pages, 1991/03
None
; ;
Nihon Genshiryoku Gakkai-Shi, 29(10), p.929 - 938, 1987/10
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
;
JAERI-M 86-145, 28 Pages, 1986/10
no abstracts in English
Horie, Tomoyoshi; Seki, Masahiro; Minato, Akio; Tone, Tatsuzo
Fusion Technology, 10, p.753 - 758, 1986/00
Analysis and experiments on lifetime predictions of the first wall and plate of fusion reactors have been performed.
; *; ; ;
Nihon Genshiryoku Gakkai-Shi, 28(3), p.258 - 265, 1986/00
Times Cited Count：13 Percentile：79.15(Nuclear Science & Technology)no abstracts in English
