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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.
; 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
; ; Shiraishi, K.
Trans.Jpn.Inst.Met., 20(12), p.697 - 705, 1979/00
no abstracts in English
Tanno, Takashi; Yano, Yasuhide; Sekio, Yoshihiro; Oka, Hiroshi; Otsuka, Satoshi; Kaito, Takeji; Tachi, Yoshiaki
no journal, ,
Ferritic/martensitic (F/M) steels are candidate for core material of fast reactors (FR) because of its superior swelling resistance. A 11Cr F/M steel (PNC-FMS) have been developed for wrapper tube and cladding tube of demonstration FR in Japan Atomic Energy Agency. For demonstration of in-reactor performance and preparation of material strength standard, it is important to extend database on irradiation and thermal aging effects. In this work, ring tensile tests and hardness tests of PNC-FMS irradiated in Joyo up to 32.5 dpa at 455-835 
C were carried out, and the results were compared with those of aging tests in order to clarify the irradiation effects exclusive of thermal aging effects. The UTS at RT of PNC-FMS irradiated at over 600 C tended to be lower than those of as-received and/or thermal aged ones. The hardness showed the same trend. But, the UTS and hardness test results showed that PNC-FMS irradiated at 835 C could be harder than that of aged one.
Tanno, Takashi; Yano, Yasuhide; Oka, Hiroshi; Sekio, Yoshihiro; Otsuka, Satoshi; Kaito, Takeji; Tachi, Yoshiaki
no journal, ,
Ferritic/martensitic (F/M) steels are candidate for core material of fast reactors (FR) because of its superior swelling resistance. A 11Cr F/M steel (PNC-FMS) have been developed for wrapper tube and cladding tube for FR in JAEA. For demonstration of in-reactor performance and preparation of material strength standard, it is important to extend database on irradiation and thermal aging effects. In this work, ring tensile tests and hardness tests of PNC-FMS irradiated in Joyo up to 32.5 dpa at 455-835 C were carried out, and the results were compared with those of aging tests to clarify the irradiation effects exclusive of thermal aging effects. The UTS and hardness at RT of PNC-FMS irradiated at over 600 C tended to be lower than those of as-received and/or thermal aged ones. The facts indicate evident irradiation softening. On the other hand, PNC-FMS irradiated at 835 C was harder than that of aged one. Transformation during irradiation would be the cause.
Takayanagi, Tomohiro; Shibanuma, Yoshihiro*; Hofuku, Yuji*
no journal, ,
There is an area where a high radiation environment of 1 MGy per year at J-PARC. The device is required to have radiation resistance and the main parts are made of metal material, but the gasket etc. are made of rubber. However, the surface of EPDM rubber, which is known as radiation-resistant rubber, softens when irradiated with several MGy. Various sub-materials were selected from EPDM as raw materials, and samples in which the blending of the plasticizer was changed were prepared. The sample prepared with barium sulfate did not undergo surface softening such as hydrolysis or bleeding even after irradiation with 5 MGy. We report 11 kinds of rubber materials and evaluation results after gamma ray irradiation.
