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Yano, Yasuhide; Tanno, Takashi; Oka, Hiroshi; Otsuka, Satoshi; Kaito, Takeji
Journal of Nuclear Materials, 555, p.153105_1 - 153105_8, 2021/11
Times Cited Count:1 Percentile:16.35(Materials Science, Multidisciplinary)The aim of this study was to evaluate the tensile properties and microstructures of dissimilar welds between 11Cr-ferritic/martensitic steel and 316 stainless steel after thermal aging at temperatures between 400 and 600C up to 30,000 h. Characterization of microstructure was carried out by scanning electron microscopy and transmission electron microscopy. Microstructural analysis showed that the microstructure in the weld metals consisted of lath martensite containing a small amount of residual austenite. Thermal aging hardening of WMs occurred at 400 and 450C due to the effects of both a-a' phase separation and G-phase precipitation. However, there was no significant change in the total elongation, and fracture surfaces indicated that very fine dimpled rupture was predominant rather than the cleavage rupture. It was suggested that lath martensite phases enhanced the tensile strength due to phase separation, while residual austenite played a role in keeping elongation as a soft phase.
Yano, Yasuhide; Tanno, Takashi; Otsuka, Satoshi; Kaito, Takeji; Ukai, Shigeharu*
Materials Transactions, 62(8), p.1239 - 1246, 2021/08
Times Cited Count:5 Percentile:41.35(Materials Science, Multidisciplinary)The FeCrAl-ODS alloy claddings were manufactured and Vickers hardness, ring tensile tests and TEM observations of these claddings were performed to investigate the effects of thermal aging at 450 C for 5,000 and 15,000 h. The age-hardening of all FeCrAl-ODS alloy cladding was found. In addition, the significant increase in tensile strength was accompanied by much larger loss of ductility. It was suggested that this age-hardening behavior was attributed to the (Ti, Al)-enriched phase (' phase) and the ' phase precipitates (content of Al is 7 wt%). In comparison with FeCrAl-ODS alloys with almost same chemical compositions, there was significant age-hardening in both alloys. However, the extrusion bar with no-recrystallized structures was keeping good ductility. It was suggested that this different behavior of reduction ductility was attributed to the effects of grain boundaries, dislocation densities and specimen preparation direction.
Ishijima, Yasuhiro; Ueno, Fumiyoshi
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 4 Pages, 2015/05
In this study, to evaluate the effect of thermal aging on creep properties of Alloy 625, we carried out creep tests on aged and solution-treated Alloy 625 at 1073 K. According to the creep test results, time-to-rupture decreased by thermal aging when test stress was more than 100 MPa, but did not change when test stress was less than 100 MPa for any specimens. In the solution-treated alloy, creep deformation behaviors changed over 100 MPa. These results show that time-to-rupture was constant because intermetallic compounds precipitated when the test stress was less than 100 MPa in solution-treated alloy. The observed relationship between creep strain rate and test time showed that the precipitation started after 100 hr for solution treated alloys. These results suggest that intermetallic compounds precipitate immediately after furnace operation. And it is appropriate to use creep data of thermal-aged Alloy 625 for the reducing roasting furnace lifetime prediction.
Nishiyama, Yutaka; Onizawa, Kunio; Idei, Yoshio; Suzuki, Masahide
JAERI-Research 2000-047, 32 Pages, 2000/10
no abstracts in English
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JNC TN9400 2000-035, 164 Pages, 2000/03
High Strength Ferritic/Martensitic Steel (PNC-FMS : 0.12C-11Cr-0,5Mo-2W-0.2V-0.05Nb), developed by JNC, is one of the candidate materials for the long-life core of large-scale fast breeder reactor. Ductile brittle transition temperature (DBTT) was tentatively determined in 1992 in material design base standard of PNC-FMS. Howevcr, specimen size effect on impact property and upper shelf energy (USE) have not been evaluated. ln this study, effects of specimen size, thermal aging and neutron irradiation on the charpy impact property of PNC-FMS were evaluated, using together with recently obtained data. The design value of USE and DBTT as fabricated and each correlation of aging and irradiation effects were determined. The results are summarized as follows. (1)lt was found that USE is related to (Bb) as USE=m(Bb), where B is specimen width, b is ligament size and both m and n are constant. For PNC-FMS, n value is equal to 1.4. It's possible to determine n value from USE (J) for full size specimen using the correlation: n=1.3810 USE + 1.20. (2)lt was clarified that DBTT is correlated with (BKt) as DBTT=p(logBKt)+q, where Kt is elastic stress concentration factor and both p and q are constant. For PNC-FMS, the correlation is as follows: DBTT=119(logBKt)-160. (3)DBTT estimated at the irradiation temperature from 350 to 650 C for sub size specimen (width and height are 3 and 10 mm, respectively), was below 180 C, based on the design value of DBTT as fabricated and each correlation of aging and irradiation effects.
Kawanishi, Hiroshi*; Suzuki, Masahide
Effects of Radiation on Materials (ASTM STP 1366), p.492 - 515, 2000/03
Times Cited Count:1 Percentile:65.28(Materials Science, Multidisciplinary)no abstracts in English
Hada, Kazuhiko
Nihon Kikai Gakkai Rombunshu, A, 65(636), p.108 - 115, 1999/08
no abstracts in English
Kaji, Yoshiyuki; Aoki, So; Kondo, Keietsu; Yamamoto, Masahiro
no journal, ,
The influence of long term thermal aging on SCC susceptibility in L-grade austenitic stainless steels (SSs) has been investigated using Creviced Bent Beam (CBB) tests. Test materials were type 304L and 316L SSs, and aging heat treatments were conducted at 288C in air for up to 14000 hours followed by solution-annealing (SA) or 20% cold-working (CW). The evaluation of the SCC initiation susceptibility was conducted by CBB tests in BWR simulated high-temperature water at 288C for 1000 hours. It was revealed by CBB tests that long term aged 304L-SA, 304L-CW, and 316L-SA showed low susceptibility of cracking, whereas long term aged 316L-CW showed high SCC susceptibility. And so far, it is considered that the low temperature sensitization was not the main cause of SCC in long term aged 316L-CW, because the previous TEM/EDX analysis on the long term aged 316L specimen showed no chromium depletion in the vicinity of grain boundaries. Further investigations are in progress from the viewpoint of mechanical properties, cold-rolling texture, microstructure and michrochemistry after the long term thermal aging in order to discuss the factors increasing SCC susceptibility.
Matsukawa, Yoshitaka*; Takeuchi, Tomoaki; Nagai, Yasuyoshi*
no journal, ,
no abstracts in English
Iwata, Keiko; Takamizawa, Hisashi; Ha, Yoosung; Okamoto, Yoshihiro; Shimoyama, Iwao; Kojima, Hiroshi*; Mayumi, Ren*; Iwase, Akihiro*; Nagai, Yasuyoshi*; Nishiyama, Yutaka
no journal, ,
Microstructure analysis for thermally aged stainless overlay cladding was conducted by using X-ray absorption. X-ray absorption fine structure analysis was adapted, which was possible to obtain the average information of a material and to identify the bond length and chemical state by the selected atoms. In this study, changes of coordination number and bond length around the Mn atom were recognized.
Suzudo, Tomoaki; Nagai, Yasuyoshi*; Alfredo, C.*
no journal, ,
It is widely known that Fe-Cr binary alloys undergo spinodal decomposition when they are thermally aged, and that this microstructural evolution causes hardening and loss of ductility of the material. The present study is about the first attempt to tackle this problem by exploiting atomistic modeling techniques. We apply Monte Carlo simulation to creating spinodally-decomposed microstructure and molecular dynamics to simulating edge dislocations moving through this microstructure by imposing shearing deformation. We then measure the critical stress as a measure of hardness for many cases over the progress in spinodal decomposition, and succeed in reproducing an experimentally-discovered proportionality between the phase separation parameter and the hardening.
Kaji, Yoshiyuki; Aoki, So; Kondo, Keietsu; Yamamoto, Masahiro
no journal, ,
The influence of long term thermal aging (LTA) on SCC initiation susceptibility in L-grade austenitic stainless steels (SSs) has been investigated using Creviced Bent Beam (CBB) tests. Test materials were type 304L and 316L SSs, and aging heat treatments were conducted at 288C in air for up to 14000 hours followed by solution-annealing (SA) or 20% cold-working (CW). The evaluation of the SCC initiation susceptibility was conducted by CBB tests in BWR simulated high-temperature water at 288C for 1000 hours. It was revealed by CBB tests that 304L-SA, 304L-CW, 304L-SA+LTA, 304L-CW+LTA, 316L-SA 316L-CW and 316L-SA+LTA showed no SCC initiation susceptibility, whereas 316L-CW+LTA showed high SCC susceptibility. To clarify the cause of SCC initiation in 316L-CW+LTA, several investigations are in progress from the viewpoint of mechanical properties, cold-rolling texture, microstructure and michrochemistry after LTA. It is considered that the low temperature sensitization was not the main cause of SCC in 316L-CW+LTA, because the TEM/EDX analysis on the 316L+LTA and 316L-CW+LTA specimens showed no chromium depletion in the vicinity of grain boundaries. In this presentation, we will explain the further investigation results for effect of LTA on SCC initiation susceptibility in L-grade austenitic SSs.
Kaji, Yoshiyuki; Kondo, Keietsu; Aoki, So; Hirade, Tetsuya; Yamamoto, Masahiro
no journal, ,
To clarify the causal relationship between the LTA treatment and the SCC initiation susceptibility, microstructural analyses on 316L CW specimens before and after the LTA treatment have been conducted. One of viewpoints in our research is the deformation microstructure. Results of the surface examination by SEM on CBB tested specimens suggested the difference in the deformation microstructure of 316L CW and CW+LTA. Coarse and planar slip steps were frequently observed on the surface of 316L CW+LTA specimens, indicating the localization of dislocation motion to limited slip planes. On the other hand, surface morphology observed in 316L CW was mainly fine and wavy slip step, indicating the occurrence of the homogeneous plastic deformation. The detail mechanism of the change in the deformation microstructure by the LTA treatment is unknown yet. Researches on its effect on the deformation microstructure and, furthermore, the SCC susceptibility is now in progress.
Kaji, Yoshiyuki; Aoki, So; Fujimura, Yuki; Kondo, Keietsu
no journal, ,
In this study, the influence of the long term thermal aging (LTA) on SCC initiation susceptibility of L-grade SSs was examined. Results of CBB testing on Type 316L CW and CW + LTA under the BWR simulated water condition showed the increase of SCC susceptibility to initiation after the LTA treatment. The material examinations on those materials were conducted to identify the SCC accelerating factors. The initial microstructure in Type 316L CW and CW + LTA was characterized to dislocation tangles and dislocation cell structures, respectively, indicating that the LTA treatment induced the rearrangement of dislocations toward the energetically favorable state. Whereas, no sensitization of the grain boundaries of Type 316L CW + LTA was confirmed by means of TEM/EDX analysis. The examination of surface deformation microstructure by bending deformation was conducted by the consecutive SEM observation before and after CBB testing. The more heterogeneous deformation was enhanced by the LTA treatment, that is, the reduction in dislocation motion and increase of deformation twinning. It was considered from those obtained results that the concentration of local stress around grain boundaries caused by the more heterogeneous deformation might be one of the promoting factors for increasing the SCC susceptibility in non-sensitized Type 316L CW + LTA.
Nakabachi, Kaito*; Yokoyama, Kenichi*; Ishijima, Yasuhiro; Ueno, Fumiyoshi; Abe, Hitoshi
no journal, ,
The effects of thermal aging on hydrogen embrittlement behavior were investigated for Zr/Ta/SUS explosive joints used in spent nuclear fuel reprocessing plants, especially at the Zr/Ta interface, which is considered to be susceptible to hydrogen embrittlement. The results showed that brittle fracture occurred at the Zr/Ta interface when the hydrogen concentration of Ta was over 20 ppm, and the ductility of the specimens with such hydrogen concentration was recovered when the hydrogen concentration of Ta decreased below 10 ppm by thermal aging at 300C for 1000 hr, while the hydrogen concentration was reduced to The ductility of the Ta/Zr interface was not recovered without significant decrease in hydrogen concentration. These results suggest that the hydrogen concentration in Ta at the Ta/Zr interface affects the hydrogen embrittlement behavior of the explosion joint and that the hydrogen state changes with thermal aging.
Nakabachi, Kaito*; Yokoyama, Kenichi*; Ishijima, Yasuhiro; Ueno, Fumiyoshi; Abe, Hitoshi
no journal, ,
To investigate the effects of strain and thermal aging on hydrogen embrittlement of Ta, tensile tests and internal friction measurements were carried out on cold rolled Ta after hydrogen charging and thermal aging. As a result, the internal friction increased with cold rolling. The internal friction was further increased by hydrogen charging. However, the internal friction of these specimens decreased after thermal aging. These results suggest that aging causes the annihilation or re-arrangement of defects or a change in the hydrogen trapping. In addition, the ductility of the hydrogen-charged and cold-rolled specimens decreased after thermal aging, suggesting that the change in hydrogen and defect state due to thermal aging affects the mechanical properties.
Kondo, Keietsu; Aoki, So; Fujimura, Yuki; Kaji, Yoshiyuki
no journal, ,
The effect of the long-term thermal aging (LTA) on the SCC susceptibility to initiation in cold worked L-grade austenitic stainless steels has been investigated. The thermal aging treatments at 288C for more than 14,000h were conducted on Type 316L SS samples after cold rolling with 20% thickness reduction, and CBB testing was performed to both aged and unaged samples. The results showed that an obvious increase of IGSCC susceptibility was induced after the LTA treatment. In order to reveal the enhancement factor of the SCC susceptibility in LTA treated specimens microstructural examination was conducted by means of SEM/EBSD and TEM. Those results suggested that movement and rearrangement of dislocations toward the dislocation cell structure occurred during LTA treatment. It is presumed that the dislocation cell structure formed during the LTA process might cause the homogeneous plastic deformation and the localization of stress/strain, and consequently, enhance the SCC susceptibility to initiation.
Fujita, Koji; Shizukawa, Yuta; Tanno, Takashi; Yano, Yasuhide
no journal, ,
Japan Atomic Energy Agency has been developed 11 Cr martensitic steel PNC-FMS as the candidate material for wrapper tubes of fast reactors. Developing database of property changes by thermally aging is necessary to clarify the irradiation effects from post irradiation experimental data. Tensile tests and hardness measurement of PNC-FMS aged up to 45,000 hours were carried out. Tensile test and hardness test after the thermal aging showed that the strength of specimens aged at 600C or higher decreased with aging time. It was shown that the decrease trend was described by linear correlation with Larson-Miller parameter. This means that the strength decrease should have been made by microstructural degradation due to the diffusion-controlled process.
Tanno, Takashi; Shizukawa, Yuta; Fujita, Koji
no journal, ,
The evaluation of the fracture toughness of thermal-aged PNC-FMS was conducted using the miniature three-point bending fracture toughness evaluation technique under development. The results implied that although the Charpy impact properties of PNC-FMS after thermal aging for 6000 hours at 600C degraded, the fracture toughness at room temperature did not degraded. Furthermore, as a result of comparing the cases where fatigue pre-crack was introduced to the test specimen before and after thermal aging, it was found that there was no significant difference under the present thermal aging conditions.
Toyota, Kodai; Imagawa, Yuya; Onizawa, Takashi
no journal, ,
no abstracts in English