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Kitagaki, Toru; Ikeuchi, Hirotomo; Yano, Kimihiko; Brissonneau, L.*; Tormos, B.*; Domenger, R.*; Roger, J.*; Washiya, Tadahiro
Journal of Nuclear Science and Technology, 56(9-10), p.902 - 914, 2019/09
Times Cited Count：7 Percentile：61.94(Nuclear Science & Technology)
Kitagaki, Toru; Hoshino, Takanori; Yano, Kimihiko; Okamura, Nobuo; Ohara, Hiroshi*; Fukasawa, Tetsuo*; Koizumi, Kenji
Journal of Nuclear Engineering and Radiation Science, 4(3), p.031011_1 - 031011_7, 2018/07
Negyesi, M.; Amaya, Masaki
Proceedings of Annual Topical Meeting on LWR Fuels with Enhanced Safety and Performance (TopFuel 2016) (USB Flash Drive), p.1065 - 1074, 2016/09
Shinozaki, Takashi; Mihara, Takeshi; Udagawa, Yutaka; Sugiyama, Tomoyuki; Amaya, Masaki
JAEA-Research 2014-025, 34 Pages, 2014/12
JAEA-Research-2014-025.pdf:6.05MB
EDC test is a test method on the mechanical property of fuel cladding tube, and it focuses on the stress condition generated by PCMI under a RIA. We conducted EDC tests which simulate the mechanical conditions during a RIA by using the unirradiated cladding tubes which simulate hydride rim. Circumferential residual strains observed in post-test specimens tended to decrease with increasing the hydrogen concentration in the test cladding tubes and the thickness of the hydride rim. We also prepared RAG tube and performed EDC tests on it. It was observed that circumferential total strains at failure tended to decrease with increasing pre-crack depth on the outer surface of RAG tube specimen. We conducted biaxial stress tests by applying longitudinal tensile load onto RAG tube specimens. It was observed that circumferential total strains at failure under biaxial stress conditions tended to decrease compared to the results under uniaxial tensile condition.
Yamada, Hirokazu*; Kawamura, Hiroshi; Nagao, Yoshiharu; Takada, Fumiki; Kono, Wataru*
Journal of Nuclear Materials, 355(1-3), p.119 - 123, 2006/09
Times Cited Count：5 Percentile：36.38(Materials Science, Multidisciplinary)In this study, the bending properties of welding joint of irradiated material and un-irradiated material (irradiated/un-irradiated joints) were investigated using SS316LN-IG, which is the candidate material for the cooling pipe of ITER. The results of this study showed that the bending position of joints using un-irradiated material was un-irradiated part and that the bending position of irradiated/irradiated joints was fusion area or HAZ (heat affected zone). Although the bending position of joints was different bor the combination pattern between irradiated and un-irradiated materials, the bending strength of joint was almost same. Additionally, it is confirmed that bending strength did not depend on the combination pattern between the irradiated and un-irradiated materials, nor on the relationship between the heat input direction and the bending load direction.
Nakamoto, Tatsushi*; Idesaki, Akira; Morishita, Norio; Ito, Hisayoshi; Kamiya, Tomihiro; Kimura, Nobuhiro*; Makida, Yasuhiro*; Ogitsu, Toru*; Ohata, Hirokatsu*; Yamamoto, Akira*
AIP Conference Proceedings 824, p.225 - 232, 2006/03
Radiation resistance with respect to mechanical properties of organic materials used in the superconducting magnets for the 50 GeV - 750 kW proton beam line for the J-PARC neutrino experiment was studied. Specimens cooled at liquid nitrogen temperature of 77 K were irradiated by gamma rays beyond 10 MGy. The flexural strength of glass-fiber reinforced plastics (GFRPs), the tear strength of polyimide films and the tensile lap-shear strength of adhesive films were evaluated. It was verified that the organic materials used in the superconducting magnet have a sufficient radiation resistance, and the degradation of their mechanical properties after 10 years operation was estimated to be negligible.
Amaya, Masaki; Fuketa, Toyoshi
Journal of Nuclear Science and Technology, 41(11), p.1091 - 1099, 2004/11
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)Effect of absorbed hydrogen on the stress corrosion cracking (SCC) susceptibility of unirradiated Zircaloy cladding was examined. The data obtained from literatures show that the ratios of SCC threshold stress (
) to 0.2% yield stress (
) in unirradiated Zircaloy claddings increase with increasing hydrogen contents below 60 ppm, irrespective of the kind of Zircaloy-2 and -4. Thermodynamic calculations were carried out for the reaction between iodine gas and zirconium containing hydrogen. The results suggested that the reactions hardly occurred at increased hydrogen content and zirconium reacted with iodine gas only below 90 ppm of hydrogen. Since these tendencies correspond to those of the ratios of to on the hydrogen content, it is considered that hydrogen affects the reactions between iodine gas and zirconium and reduces the SCC susceptibility of Zircaloy claddings.
Motohashi, Yoshinobu*; Shibata, Taiju; Harjo, S.*; Sakuma, Takaaki*; Ishihara, Masahiro; Baba, Shinichi; Sawa, Kazuhiro
Proceedings of 14th International Federation for Heat Treatment and Surface Engineering Congress Transactions of Materials and Heat Treatment Vol.25 No.5, p.1032 - 1036, 2004/10
no abstracts in English
Enoeda, Mikio
JAERI-Conf 2004-012, 237 Pages, 2004/07
JAERI-Conf-2004-012.pdf:44.1MB
This report is the Proceedings of "the Eleventh International Workshop on Ceramic Breeder Blanket Interactions" which was held as a workshop on ceramic breeders Under the IEA Implementing Agreement on the Nuclear Technology of Fusion Reactors, and the Japan-US Fusion Collaboration Framework. In the workshop, information exchange was performed for designs of solid breeder blankets and test blankets in EU, Russia and Japan, recent results of irradiation tests, HICU, EXOTIC-8 and the irradiation tests by IVV-2M, modeling study on tritium release behavior of LiTiO
and other breeders, fabrication technology developments and characterization of the LiTiO and Li
SiO pebbles, research on measurements and modeling of thermo-mechanical behaviors of LiTiO and LiSiO pebbles, and interfacing issues, such as, fabrication technology for blanket box structure, neutronics experiments of blanket mockups by fusion neutron source and tritium recovery system.
Sn heat treatmentNakajima, Hideo; Hamada, Kazuya; Takano, Katsutoshi*; Okuno, Kiyoshi; Fujitsuna, Nobuyuki*
IEEE Transactions on Applied Superconductivity, 14(2), p.1145 - 1148, 2004/06
Times Cited Count：33 Percentile：77.62(Engineering, Electrical & Electronic)In ITER, the conductor for the Central Solenoid (CS) uses Incoloy 908, which requires special environment control to prevent cracks caused by Stress Accelerated Grain Boundary Oxidation (SAGBO) during Nb3Sn heat treatment. Use of a stainless steel jacket can simplify the design and fabrication because the special caution is not required for SAGBO. JAERI has already developed high manganese, JK2, whose thermal contraction from 300K to 4 K is almost the same as that of Incoloy: thus no change in the mechanical design of the CS is necessary. However, during the heat treatment, phosphorus enhances embrittlement of JK2. Carbon reduction and boron addition was considered to be a possible solution to mitigate the phosphorus effect. Jackets of low carbon and boron added JK2(JK2LB) were produced and tensile properties, fracture toughness, and crack propagation rate were measured at 4K. Elongation and fracture toughness at 4K after the heat treatment are 33% and 91 MPam
for the final jacket, which satisfy the ITER targets. JK2LB can be applied to the ITER CS.
Motohashi, Yoshinobu*; Kobayashi, Tomokazu*; Harjo, S.*; Sakuma, Takaaki*; Shibata, Taiju; Ishihara, Masahiro; Baba, Shinichi; Hoshiya, Taiji
Nuclear Instruments and Methods in Physics Research B, 206, p.144 - 147, 2003/05
Times Cited Count：4 Percentile：33.69(Instruments & Instrumentation)The 3mol% yttria containing tetragonal zirconia polycrystals(3Y-TZP) were irradiated using 130MeV Zr
ions in the TANDEM accelerator facility at Tokai Research Establishment, JAERI. Irradiation was performed with the fluence of 3.5
10
and 2.110
ions/m
. Residual stress and changes in mechanical properties caused by the ion irradiation and the effects of the subsequent annealing are studied. The occurrence of compressive residual stresses and increases in hardness and fracture toughness were found at the surface regions of as-irradiated specimens. It was found from the subsequent annealing that these quantities decreased gradually with raising the annealing temperature and returned to that of un-irradiated state at around 1173K. A most probable cause of the increases in the hardness and fracture toughness after the irradiation may, therefore, be the residual compressive stresses left in the irradiated surface region.
Ishii, Toshimitsu; Ooka, Norikazu; Hoshiya, Taiji; Kobayashi, Hideo*; Saito, Junichi; Niimi, Motoji; Tsuji, Hirokazu
Journal of Nuclear Materials, 307-311(Part.1), p.240 - 244, 2002/12
Times Cited Count：3 Percentile：23.41(Materials Science, Multidisciplinary)no abstracts in English
Nakajima, Hideo
Chitan, 50(2), p.98 - 101, 2002/04
no abstracts in English
Tsuji, Hirokazu; Fujii, Hidetoshi*
Proceedings of 10th German-Japanese Workshop on Chemical Information, p.127 - 130, 2002/00
A neural network model within a Bayesian framework was adopted based on the material database constructed by JAERI for prediction of creep rupture properties of irradiated type 304 stainless steel. Stress level was modeled as a function of 18 variables, including rupture life, creep test temperature, chemical compositions; 10 elements, heat treatment temperature, heat treatment duration, neutron irradiation temperature, fast neutron fluence, thermal neutron fluence, irradiation time, based on JAERI material database in which 347 creep rupture data sets of type 304 stainless steels were stored. The Bayesian method puts error bars on the predicted values of the rupture strength and allows the significance of each individual factor to be estimated.
Kaji, Yoshiyuki; Sakino, Takao*; Tsuji, Hirokazu
Proceedings of 10th German-Japanese Workshop on Chemical Information, p.67 - 70, 2002/00
The JAERI Material Performance Database (JMPD) was developed with a view to utilizing material performance data efficiently. Data from more than 11,500 test pieces are prepared for data evaluation in the JMPD. Some kinds of data analyses have been performed by utilizing the JMPD. As for improvement of user interfaces, graphic function and modification function of the data were added in the JMPD. The following important points will be emphasized in the future direction of the JMPD; (1) enrichment of the stored data in both of the core and the surrounding portions of the JMPD, (2) improvement of user-friendliness, (3) construction and enrichment of data networking system, and (4) construction of knowledge base.
Oshima, Akihiro; Udagawa, Akira; Morita, Yosuke
Radiation Physics and Chemistry, 60(1-2), p.95 - 100, 2001/01
Times Cited Count：8 Percentile：52.36(Chemistry, Physical)no abstracts in English
Johnson, W. R.*; Trester, P. W.*; Sengoku, Seio; Ishiyama, Shintaro; Fukaya, Kiyoshi; Eto, Motokuni; Oda, Tomomasa*; Hirohata, Yuko*; Hino, Tomoaki*; Tsai, H.*
Journal of Nuclear Materials, 283-287(Part1), p.622 - 627, 2000/12
Times Cited Count：2 Percentile：19.44(Materials Science, Multidisciplinary)no abstracts in English
Nakano, Junichi; Fujii, Kimio; Yamada, Reiji
Journal of the American Ceramic Society, 80(11), p.2897 - 2902, 1997/00
Times Cited Count：7 Percentile：47.73(Materials Science, Ceramics)no abstracts in English
Kato, Teruo
Teion Kogaku, 30(11), p.510 - 518, 1995/00
no abstracts in English
Nakajima, Hideo; Tsuji, Hiroshi
Purazuma, Kaku Yugo Gakkai-Shi, 70(7), p.733 - 739, 1994/07
no abstracts in English
