| 渡邉 英雄（わたなべ ひでお） | データ更新日：2023.09.28 |
准教授 ／
応用力学研究所
核融合力学部門
先端エネルギー理工専攻、高エネルギー物質理工学
| 1. | Luwei Xue, Hideo Watanabe, Radiation-induced hardening of ion-irradiated Zircaloy-2 at 573 K under applied stress, Nuclear Instruments and Methods in Physics Research，B, https://doi.org/10.1016/j.nimb.2023.07.009, 542, 223-229, 2023.09. |
| 2. | Ranran Li, Xiaoou Yi, Wentuo Han, Pingping Liu, Qian Zhan, Yoshitaka Matsukawa, Hideo Watanabe, Farong Wan, Micron-scale 1D migration of interstitial-type dislocation loops in aluminum, Materials Characterization, https://doi.org/10.1016/j.matchar.2023.113149, 203, 113149, 2023.09. |
| 3. | Yasuhiro Kamada, Tomoki Oyake, Takeshi Murakami, Satoru Kobayashi, Kazuyuki Shimizu and Hideo Watanabe, Ion Irradiation Effects on the Crystal Structure and Magnetic Properties of Iron-Nickel Binary Alloys, IEEE Transactions on Magnetics, DOI 10.1109/TMAG.2023.3293195, 2023.07. |
| 4. | Kazuyuki Shimizu, Hanako Tsuruta, Yasuhiro Kamada, Takeshi Murakami, Hideo Watanabe, Crystallographic analysis of Ga+ irradiation-induced phase transformation in austenitic stainless steels, Materials Characterization, 194, 2022.10. |
| 5. | T.Fujita J.Hirabayashi Y.Katayama F.Kano H.Watanabe, Contribution of dislocation loop to radiation-hardening of RPV steels studied by STEM/EDS with surveillance test pieces, Journal of Nuclear Materials, 2022.09. |
| 6. | Q. Xu, H.Q. Guan, S.S. Huang, Z.H. Zhong, H. Watanabe, M. Tokitani, Compositional stability in medium and high-entropy alloys of CoCrFeMnNi system under ion irradiation, Journal of Alloys and Compounds, 2022.08. |
| 7. | Hideo Watanabe, Tomonari Tanaka, Takuya Turu and Yasuhiro Kamada, Direct Observation of Cu Clusters and Dislocation Loops by Cs-Corrected STEM in Fe-0.6wt%Cu Alloy Irradiated in BR2, metals, 2022.04. |
| 8. | Katsuhito Takahashi , Tomio Iwasaki, Hideo Watanabe, Kenta Murakami, Effect of zirconium-ion irradiation on properties of secondary phase particles in zirconium-oxide film, Journal of Nuclear Materials, 2021.12. |
| 9. | 鶴田 華子、清水 一行、村上 武、鎌田 康寛、渡邉 英雄, Ga イオン照射したSUS304鋼の構造相変態, 日本金属学会誌 J-STAGE, https://doi.org/10.2320/jinstmet.J2021006, 85, 6, 239-246, 2021.04. |
| 10. | Hideo Watanabe ,Yoshiki Saita ,Katsuhito Takahashi ,Kazufumi Yasunaga, Desorption of Implanted Deuterium in Heavy Ion-Irradiated Zry-2, quantum beam science, https://doi.org/10.3390/qubs5020009, 5(2), 9, 2021.04, To understand the degradation behavior of light water reactor (LWR) fuel-cladding tubes under neutron irradiation, a detailed mechanism of hydrogen pickup related to the point defect formation (i.e., a-component and c-component dislocation loops) and to the dissolution of precipitates must be elucidated. In this study, 3.2 MeV Ni3+ ion irradiation was conducted on Zircaloy-2 samples at room temperature. Thermal desorption spectroscopy is used to evaluate the deuterium desorption with and without Ni3+ ion irradiation. A conventional transmission electron microscope and a spherical aberration-corrected high-resolution analytical electron microscope are used to observe the microstructure. The experimental results indicate that radiation-induced dislocation loops and hydrides form in Zircaloy-2 and act as major trapping sites at lower (400–600 °C) and higher (700–900 °C)-temperature regions, respectively. These results show that the detailed microstructural changes related to the hydrogen pickup at the defect sinks formed by irradiation are necessary for the degradation of LWR fuel-cladding tubes during operation.. |
| 11. | Peng Song, Akihiko Kimura, Kiyohiro Yabuuchi, Peng Dou, Hideo Watanabe, Jin Gao, Yen Jui Huang, Assessment of phase stability of oxide particles in different types of 15Cr-ODS ferritic steels under 6.4 MeV Fe ion irradiation at 200 °C, Journal of Nuclear Materials, 10.1016/j.jnucmat.2019.151953, 529, 2020.04, [URL], Three types of 15Cr-ODS ferritic steels were irradiated with 6.4 MeV Fe3+ at 200 °C up to a nominal displacement damage of 10 dpa to assess the phase stability of different sorts of oxide particles under ion-irradiation. Before the irradiation, dominant oxide particles in (Y, Ti) ODS, (Y, Al) ODS and (Y, Zr) ODS steels were identified as Y-Ti-O, Y-Al-O, and Y-Zr-O types, respectively, and the difference in the average diameters and number densities of oxide particles among the three ODS ferritic steels was as small as within the factor of two. After the irradiation, the number densities and volume fractions of oxide particles in all the three ODS steels decreased with increasing dpa regardless of the different dispersion morphologies, chemical compositions and crystal structures of the particles, which was interpreted in terms of the dominant mechanism of ballistic dissolution with a moderate occurrence of radiation-enhanced diffusion (RED) and re-precipitation of the nano-clusters. Almost no significant difference in the phase stability of oxide particles was recognized among the three types of ODS ferritic steels. However, normalized volume fractions of Y-Zr-O particles were slightly bigger than those of Y-Ti-O and Y-Al-O at high damage levels. Moreover, Y-Al-O particles underwent the loss of moiré fringe because of the amorphization of oxide particles, while the δ-phase Y4Zr3O12 in (Y, Zr) ODS still maintained crystalline structure even at ∼ 20 dpa/local. It is concluded that Y-Zr-O particles are more stable than Y-Al-O and possibly Y-Ti-O particles.. |
| 12. | Shiro Entani, Konstantin V. Larionov, Zakhar I. Popov, Masaru Takizawa, Masaki Mizuguchi, Hideo Watanabe, Songtian Li, Hiroshi Naramoto, Pavel B. Sorokin, Seiji Sakai, Non-chemical fluorination of hexagonal boron nitride by high-energy ion irradiation, Nanotechnology, 10.1088/1361-6528/ab5bcc, 31, 12, 2020.01, [URL], Two-dimensional materials such as hexagonal boron nitride (h-BN) and graphene have attracted wide attention in nanoelectronics and spintronics. Since their electronic characteristics are strongly affected by the local atomic structure, the heteroatom doping could allow us to tailor the electronic and physical properties of two-dimensional materials. In this study, a non-chemical method of heteroatom doping into h-BN under high-energy ion irradiation was demonstrated for the LiF/h-BN/Cu heterostructure. Spectroscopic analysis of chemical states on the relevant atoms revealed that 6% ± 2% fluorinated h-BN is obtained by the irradiation of 2.4 MeV Cu2+ ions with the fluence up to 1014 ions cm-2. It was shown that the high-energy ion irradiation leads to a single-sided fluorination of h-BN by the formation of the fluorinated sp 3-hybridized BN.. |
| 13. | Kazuhito Ohsawa, Takeshi Toyama, Yuji Hatano, Masatake Yamaguchi, Hideo Watanabe, Stable structure of hydrogen atoms trapped in tungsten divacancy, Journal of Nuclear Materials, 10.1016/j.jnucmat.2019.151825, 527, 2019.12, [URL], Stable structures of hydrogen atoms trapped in a divacancy in tungsten and their binding energies are presented on the basis of first-principle calculations. The hydrogen atoms are favorable sitting in the vicinity of octahedral interstitial sites (O-sites) next to the divacancy. Besides, hydrogen atoms preferentially occupy O-sites located in the center of the divacancy. As hydrogen atoms increases, O-sites located in the periphery of the divacancy are also occupied by the hydrogen atoms. The divacancy in tungsten is energetically unstable, compared with two isolated monovacancies. However, the divacancy is extremely stabilized by the hydrogen atom trapping. The binding energy of the divacancy depends on the sort of the hydrogen isotope.. |
| 14. | 李然然, 张一帆, 耿殿程, 张高伟, 渡边英雄, 韩文妥, 万发荣 , V-4Cr-4Ti/Ti复合材料界面的辐照损伤特性研究, 物理学报 Acta Physica Sinica, 10.7498/aps.68.20191204, 68, 216101-1-216101-8, 2019.12. |
| 15. | Jean Marc Costantini, Gérald Lelong, Maxime Guillaumet, Didier Gourier, Seiya Takaki, Norito Ishikawa, Hideo Watanabe, Kazuhiro Yasuda, Optical reflectivity of ion-irradiated cerium dioxide sinters, Journal of Applied Physics, 10.1063/1.5100582, 126, 17, 2019.11, [URL], Reflection spectra of cerium dioxide sintered samples were measured in the UV-visible range after irradiation with various heavy ions (2.4-MeV Cu, 5-MeV W, 10-MeV W, 36-MeV W, 100-MeV Kr, and 200-MeV Xe). Differential reflectance spectra of irradiated samples after subtraction of the reference sample spectrum are fit with six broad Gaussian bands centered at about 1.2, 2.2, 2.8, 4.0, 4.8, and 6.2 eV. The growth curves of most bands show a saturation behavior vs ion fluence. Reflection spectra are consistent with the UV-visible absorption spectra of electron-irradiated ceria single crystals for photon energies lower than 3.2 eV, corresponding to the optical gap. The spectra are tentatively analyzed on the basis of charge transfer bands and the 4f-5d transitions related to the Ce3+ ions in the distorted environment formed by irradiation. More insight into defect formation is given by the reflection spectra rather than the absorption ones due to the limitation in the absorption of the optical gap. These data are also discussed with reference to the radiation damage processes by electronic excitations and nuclear collisions in ceria.. |
| 16. | Moeko Nakata, Keisuke Azuma, Akihiro Togari, Qilai Zhou, Mingzhong Zhao, Takeshi Toyama, Yuji Hatano, Naoaki Yoshida, Hideo Watanabe, Masashi Shimada, Dean Buchenauer, Yasuhisa Oya, Dynamics evaluation of hydrogen isotope behavior in tungsten simulating damage distribution, Fusion Engineering and Design, 10.1016/j.fusengdes.2019.03.114, 146, 2096-2099, 2019.09, [URL], 0.8 MeV and 6 MeV iron (Fe) ions were implanted into tungsten (W) to produce the irradiation damages with the various damage distributions. Thereafter, 1.0 keV deuterium ion (D2 +) implantation was performed to evaluate the D retention behavior on damage distribution in W. The experimental results showed that the total D retentions were decreased by increasing the damage concentration introduced near the surface region by 0.8 MeV Fe ion implantation. The retention of D trapped by vacancy clusters and voids, which would be the stable trapping sites with higher trapping energies, were reduced, suggesting that the recombination of D atom into D2 on the W surface was enhanced due to D accumulation near the surface region. It can be said that the hydrogen retention behavior in PFMs will be controlled by the damage distribution near the surface.. |
| 17. | Jean Marc Costantini, Gaëlle Gutierrez, Hideo Watanabe, Kazuhiro Yasuda, Seiya Takaki, Gérald Lelong, Maxime Guillaumet, William J. Weber, Optical spectroscopy study of modifications induced in cerium dioxide by electron and ion irradiations, Philosophical Magazine, 10.1080/14786435.2019.1599145, 99, 14, 1695-1714, 2019.07, [URL], UV-visible absorption spectroscopy and Raman spectroscopy were used to study damage production in cerium dioxide epitaxial films and polycrystalline sintered samples after irradiation with electrons for three energies to span the threshold displacement energies of cerium and oxygen atoms, and 2.4-MeV Cu ions. Neither amorphization nor specific colour-centre bands were detected. Evolutions of the refractive index were derived from the interference fringes in the optical transmission spectra of epilayers after irradiation. No significant change of the refractive index occurred for the 1.0-MeV electron irradiation, whereas a maximum decrease by 28 ± 8% was deduced for the 1.4-MeV and 2.5-MeV energies. These modifications are consistent with ballistic damage on the cerium sublattice for high electron energies producing Ce3+ ions. However, no significant change of refractive index was found for the Cu ion irradiation. This likely stems from the high rate of Frenkel pair recombination in the collision cascades induced by more energetic recoils than for the electron irradiations, combined with electronic excitations and hole capture on Ce3+ ions. This study reveals modifications of the electronic structure upon irradiation that could take place in other non-amorphizable oxide systems.. |
| 18. | Yun Wang, Hideo Watanabe, Dongyue Chen, Junya Kaneda, Naoto Shigenaka, Effect of Ta addition on irradiation resistance properties of austenitic stainless steels for reactor pressure vessel internals, 27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019 Proceedings of the 27th International Conference on Nuclear Engineering, ICONE 2019 - "Nuclear Power Saves the World!", 2019.05, In order to elevate the resistance against irradiation-assisted stress corrosion cracking (IASCC) of reactor pressure vessel internals (RINs) in the environment of boiling water reactor (BWR), austenitic stainless steels (SSs) with tantalum (Ta) addition have been examined. The oversized element Ta is considered to reduce the concentration of free vacancy due to trapping effect. It is expected that radiation-induced grain boundary (GB) segregation of constituent element such as chromium (Cr) can be suppressed by Ta addition. In this study the irradiation tests were performed with Fe2+ ion in a dose range from 0.1 to 3 dpa on the specimens sampled from base materials and heat-affected zone (HAZ) of welding joint plates. Considering the Cr segregation might also occur during the heat history of welding process, we first confirmed and discussed the effect of Ta addition to SUS310S on irradiation resistance properties in the HAZ. The radiation-induced segregation (RIS) on random GBs in HAZ after the irradiation tests was evaluated by scanning transmission electron microscope (STEM) and X-ray energy dispersive spectroscopy (XEDS). The improvement of resistance against RIS by Ta addition was evaluated. Further the effect of Ta addition on radiation induced hardening was investigated on the base materials, but from the results of nanoindentation test the obvious relief of radiation-induced hardening was not confirmed. The corrosion properties after heavy ion irradiation were also discussed on the base materials in the conditions of electrochemical potentiokinetic reactivation (EPR) test. GB corrosion was observed on the ion-irradiated surface of commercial material of SUS310S. However, no GB corrosion was observed on the irradiated surface of SUS310S with 0.4 % Ta addition, indicating the effect of Ta addition on the improvement of resistance against IASCC.. |
| 19. | K. Hanada, N. Yoshida, M. Hasegawa, A. Hatayama, K. Okamoto, I. Takagi, T. Hirata, Y. Oya, M. Miyamoto, M. Oya, T. Shikama, A. Kuzmin, Z. X. Wang, H. Long, H. Idei, Y. Nagashima, K. Nakamura, O. Watanabe, T. Onchi, H. Watanabe, K. Tokunaga, A. Higashijima, S. Kawasaki, T. Nagata, S. Shimabukuro, Y. Takase, S. Murakami, X. Gao, H. Liu, J. Qian, R. Raman, M. Ono, Particle balance investigation with the combination of the hydrogen barrier model and rate equations of hydrogen state in long duration discharges on an all-metal plasma facing wall in QUEST, Nuclear Fusion, 10.1088/1741-4326/ab1858, 59, 7, 2019.05, [URL], The fuel particle balance during long duration discharges in the Q-shu University Experiment with steady state spherical tokamak (QUEST) was investigated. QUEST has all-metal plasma facing walls (PFWs) that were temperature controlled during the experiments. The presence of a transport barrier for hydrogen (H) at the interface between a plasma-induced deposition layer and metallic substrate was confirmed by nuclear reaction analysis with exposing deuterium plasma. An effective method to evaluate global hydrogen flux to PFWs is proposed, taking advantage of the nature of wall saturation. The outgoing flux of fuel particles from the PFWs just after the plasma termination was proportional to the square of wall-stored H, which indicates that enhanced recombination of solved hydrogen played an essential role in dynamic retention and was in agreement with predictions from the H-barrier model. A simple calculation based on the combination of wall modelling and rate equations of the H states denoted a significant impact of wall modelling on the time response of the plasma density. Hence, a proper wall model including the effects of the deposition layer creating the H barrier is required to be developed, even for all-metal PFW devices.. |
| 20. | 井上 利彦、関尾 佳弘、渡邉 英雄, オーステナイト系ステンレス鋼における析出物とボイドの照射挙動, まてりあ, 10.2320/materia.58.92, 58, 2, 92-92, 2019.02. |
| 21. | Kenji Matsumoto, Akira Sasaki, Naoki Yoshida, Hideo Watanabe, Surface damage under tribological conditions induced by electrical discharge, Tribology Online, 10.2474/trol.14.214, 14, 4, 214-219, 2019.01, [URL], We have seen small black spots or craters on the surface of worn machine parts. They are considered to be caused by discharges of static electricity. However, there is no clear evidence of being caused by discharges of static electricity, as nobody can see the phenomena when discharges are caused there. Using TEM (Transmission Electron Microscope) and SEM (scanning electron microscope), the authors examined the black spots which were found on the lubricated surfaces of machine components and the ones which were artificially caused by spark discharges on a surface of a test material. The results of this study showed that the grains of black spots on the lubricated surface of worn machine parts were almost identical to those which were artificially caused by discharges of static electricity. Moreover, melted wear debris that might have been formed during spark discharge, was found in an oil filter, showing that there was high temperature melting the metal.. |
| 22. | 渡邉 英雄, 中性子照射されたFe-0.6Cu合金のクラスター解析, まてりあ, 10.2320/materia.57.613, 57, 12, 613-613, 2018.12. |
| 23. | Y. Hishinuma, M. Tanaka, T. Tanaka, K. Matsuda, Hideo Watanabe, T. Muroga, Microstructure and peeling behavior of MOCVD processed oxide insulator coating before and after ion beam irradiation, Nuclear Materials and Energy, 10.1016/j.nme.2018.06.001, 16, 123-127, 2018.08, [URL], The mechanical durability and soundness of the several oxide coating materials used as the electrical insulator and tritium permeation barrier are important design parameters on an advanced liquid breeding blanket system. We tried to investigate the adhesion strength evaluation due to the peeling behavior on the MOCVD processed multilayered oxide coating (Er2O3/Y2O3) on the stainless steel (SUS) substrate before and after Cu2+ ion beam irradiation using the nano-scratch tester. The adhesion strength of the coating material was able to estimate easily from the scratch trace and scratch stress, and the nano-scratch test was suitable method to evaluate the mechanical durability and soundness. After the Cu2+ ion beam irradiation, the adhesion strength was decreased with increasing the displacement per atom (dpa). The adhesion strength degradation by the Cu2+ ion beam irradiation was caused by the embrittlement of the thicker and amorphous Fe-(Y)-O interlayer formation between Y2O3 buffer layer and SUS substrate based on the displacement damage dose effect.. |
| 24. | Hideo Watanabe, Katsuhito Takahashi, Kazufumi Yasunaga, Yun Wang, Yasuhisa Aono, Yusaku Maruno, Kenichi Hashizume, Effects of an alloying element on a c-component loop formation and precipitate resolution in Zr alloys during ion irradiation, Journal of Nuclear Science and Technology, 10.1080/00223131.2018.1486244, 1-13, 2018.07, [URL], It is important to clarify the mechanisms of the dislocation loop formation, dissolution of precipitates to understand the degradation behavior of the fuel cladding tubes in light water reactors (LWR) under neutron irradiation. In this study, 3.2 MeV Ni ion irradiation was carried out at 400°C on Zircaloy-2 and two types of model alloys with and without Fe (Zr-1.5Sn-0.3Fe and Zr-1.5Sn). To understand the effects of hydrogen, 60 and 300 ppm pre-injected Zircaloy-2 samples were also irradiated. The microstructure was observed with a conventional transmission electron microscopy. Additionally, the dissolution of precipitates and the enrichment of the alloying element due to irradiation were analyzed using a spherical aberration (Cs)-corrected high-resolution analytical electron microscope. After ion irradiation at 400°C, the dissolution of Fe-enriched precipitates and the c-component dislocation loops were observed in the region of peak ion damage. Observations by STEM-EDS showed that Fe atoms were enriched in the c-component dislocation loops. On the contrary, the c-component dislocation loops were detected in Fe-containing alloys (Zircaloy-2 and Zr-1.5Sn-0.3Fe alloy) but were not in the Zr-1.5Sn alloy. These results indicate that the dissolution of Fe-enriched precipitates and the enhanced formation of c-component dislocation loops are essential for the degradation of LWR fuel cladding under irradiation.. |
| 25. | Takuya Nagasaka, Haiying Fu, Nobuyuki Kometani, Takeshi Miyazawa, Takeo Muroga, Hideo Watanabe, Masanori Yamazaki, Takeshi Toyama, Impact property of low-activation vanadium alloy NIFS-HEAT-2 after electron beam welding and neutron irradiation, Fusion Science and Technology, 10.1080/15361055.2017.1352428, 72, 4, 645-651, 2017.11, [URL], In order to investigate the effect of post-weld heat treatment (PWHT) and post-irradiation annealing (PIA), electron-beam-weld specimens of the reference low activation vanadium alloy, NIFS-HEAT-2, were neutronirradiated to a fluence of 7.62 × 1023 neutron m-2 (E > 1 MeV) at 563 K in Belgian Reactor-2. In the present experiments, unexpected oxidation of the surface of the samples occurred during the neutron irradiation, and significantly degraded impact properties of the weld metal, while the degradation was not significant for the base metal. The removal of the oxidized layer by electro-polishing improved the impact properties of the weld metal. Although complete removal of the oxidized layer could not be confirmed, it is revealed that impact absorbed energy of the weld metal with post-weld heat treatment at 1073 K was comparable to that of the base metal after the postirradiation polishing. In other words, irradiation embrittlement of the weld metal was successfully suppressed by the PWHT. PIA at 773 K and above was effective to recover the irradiation hardening and irradiation embrittlement. Mechanisms of the irradiation hardening, irradiation embrittlement and its recovery were discussed.. |
| 26. | K. Hanada, N. Yoshida, T. Honda, Z. Wang, A. Kuzmin, I. Takagi, T. Hirata, Y. Oya, M. Miyamoto, H. Zushi, M. Hasegawa, K. Nakamura, A. Fujisawa, H. Idei, Y. Nagashima, O. Watanabe, T. Onchi, K. Kuroda, H. Long, H. Watanabe, K. Tokunaga, A. Higashijima, S. Kawasaki, T. Nagata, Y. Takase, A. Fukuyama, O. Mitarai, Investigation of hydrogen recycling in long-duration discharges and its modification with a hot wall in the spherical tokamak QUEST, Nuclear Fusion, 10.1088/1741-4326/aa8121, 57, 12, 2017.10, [URL], Fully non-inductive plasma maintenance was achieved by a microwave of 8.2 GHz and 40 kW for more than 1 h 55 min with a well-controlled plasma-facing wall (PFW) temperature of 393 K, using a hot wall in the middle-sized spherical tokamak QUEST, until the discharge was finally terminated by the uncontrollability of the density. The PFW was composed of atmospheric plasma-sprayed tungsten and stainless steel. The hot wall plays an essential role in reducing the amount of wall-stored hydrogen and facilitates hydrogen recycling. The behaviour of fuel hydrogen in the PFW was investigated by monitoring the injection and evacuation of hydrogen into and from the plasma-producing vessel. A fuel particle balance equation based on the presence of a hydrogen transport barrier between the deposited layer and the substrate was applied to the long-duration discharges. It was found that the model could readily predict the observed behaviour in which a higher wall temperature likely gives rise to faster wall saturation.. |
| 27. | Takuya Nagasaka, Haiying Fu, Nobuyuki Kometani, Takeshi Miyazawa, Takeo Muroga, Hideo Watanabe, Masanori Yamazaki, Takeshi Toyama, Impact Property of Low-Activation Vanadium Alloy NIFS-HEAT-2 After Electron Beam Welding and Neutron Irradiation, Fusion Science and technology, https://doi.org/10.1080/15361055.2017.1352428, 72, 645-651, 2017.09, In order to investigate the effect of post-weld heat treatment (PWHT) and post-irradiation annealing (PIA),electron-beam-weld specimens of the reference low activation vanadium alloy, NIFS-HEAT-2,were neutron-irradiated to a fluence of 7.62 × 1023 neutron m−2 (E > 1 MeV) at 563 K in Belgian Reactor-2. In the present experiments, unexpected oxidation of the surface of the samples occurred during the neutron irradiation, and significantly degraded impact properties of the weld metal, while the degradation was not significant for the base metal. The removal of the oxidized layer by electro-polishing improved the impact properties of the weld metal. Although complete removal of the oxidized layer could not be confirmed, it is revealed that impact absorbed energy of the weld metal with post-weld heat treatment at 1073 K was comparable to that of the base metal after the post-irradiation polishing. In other words, irradiation embrittlement of the weld metal was successfully suppressed by the PWHT. PIA at 773 K and above was effective to recover the irradiation hardening and irradiation embrittlement. Mechanisms of the irradiation hardening, irradiation embrittlement and its recovery were discussed.. |
| 28. | 相原 雄太, 鎌田 康寛, 村上 武, 小林 悟, 渡辺 英雄, クラッド付圧力容器鋼の磁気ヒステリシス統制とビッカース硬さの相関, 81, 10, 475-479, 2017.08. |
| 29. | Yuki Uemura, Shodai Sakurada, Hiroe Fujita, Keisuke Azuma, Quilai Zhou, Takumi Chikada, Yasuhisa Oya, Yuji Hatano, Naoaki Yoshida, Hideo Watanabe, Makoto Oyaizu, Kanetsugu Isobe, Masashi Shimada, Dean Buchenauer, Robert Kolasinski, Effect of helium irradiation on deuterium permeation behavior in tungsten, Journal of Nuclear Materials, 10.1016/j.jnucmat.2017.04.041, 490, 242-246, 2017.07, [URL], In this study, we measured deuterium (D) gas-driven permeation through tungsten (W) foils that had been pre-damaged by helium ions (He+). The goal of this work was to determine how ion-induced damage affects hydrogen isotope permeation. At 873 K, the D permeability for W irradiated by 3.0 keV He+ was approximately one order of magnitude lower than that for un-damaged W. This difference diminished with increasing temperature. Even after heating to 1173 K, the permeability returned to less than half of the value measured for un-damaged W. We propose that this is due to nucleation of He bubbles near the surface which potentially serve as a barrier to diffusion deeper into the bulk. Exposure at higher temperatures shows that the D permeability and diffusion coefficients return to levels observed for undamaged material. It is possible that these effects are linked to annealing of defects introduced by ion damage, and whether the defects are stabilized by the presence of trapped He.. |
| 30. | Yuki Uemura, Shodai Sakurada, Hiroe Fujita, Keisuke Azuma, Quilai Zhou, Yuji Hatano, 吉田 直亮, Hideo WATANABE, Makoto Oyaizu, Kanetsugu Isobe, Masashi Shimada, Dean Buchenauer, Robert Kolasinski, Takumi Chikada, Yasuhisa Oya, Effect of helium irradiation on deuterium permeation behavior in tungsten, Journal of Nuclear Materials, 490, 242-246, 2017.04. |
| 31. | Y. Matsukawa, S. Kitayama, K. Murakami, Y. Shinohara, K. Yoshida, H. Maeno, H. L. Yang, T. Toyama, Kazuhiro Yasuda, Hideo Watanabe, A. Kimura, H. Muta, S. Yamanaka, Y. F. Li, Y. Satoh, S. Kano, H. Abe, Reassessment of oxidation-induced amorphization and dissolution of Nb precipitates in Zr−Nb nuclear fuel cladding tubes, Acta Materialia, 10.1016/j.actamat.2017.01.032, 127, 153-164, 2017.04, [URL], The surface oxide film of a Zr−2.5Nb alloy subjected to long term corrosion at 633 K in simulated primary coolant of pressurized water reactors has been analyzed. The primary concerns were whether Nb precipitates exhibit amorphization upon oxidation, and whether they dissolve into the matrix, as suggested by previous studies. Their behavior is of particular interest, from the viewpoint of engineering, as the mechanism of improving corrosion resistance of Zr fuel cladding by Nb addition, and from the viewpoint of basic materials science, as the critical condition of solid-state amorphization. If amorphization and dissolution proceed simultaneously, it would follow that amorphization occurs at conditions where both O and Nb atoms are mobile; under such conditions diffusion-induced amorphization has never been observed. It was found that the Nb precipitates exhibited amorphization without dissolution. Some of the inconsistencies among the previous studies were found to be artifacts of materials characterization methods. The final configuration of precipitates was amorphous Nb2O5, which is distinct from the other Nb oxides in terms of its dielectric nature with a wide band gap. The matrix initially contained a large amount of Nb greater than the solubility. Although the excess Nb atoms did not precipitate by thermal aging alone, oxidation was found to enhance their precipitation at this temperature. It appears that amorphization can occur even when the motion of atoms is not frozen-in.. |
| 32. | Yuta Aihara, Yasuhiro Kamada, Takeshi Murakami, Satoru Kobayashi, Hideo Watanabe, Correlation between magnetic hysteresis properties & vickers hardness in cladded reactor pressure vessel steel, Nippon Kinzoku Gakkaishi/Journal of the Japan Institute of Metals, 10.2320/jinstmet.JAW201702, 81, 10, 475-479, 2017.01, [URL], We investigated the microstructure, magnetic hysteresis properties, and micro Vickers hardness of nuclear reactor pressure vessel(RPV) steel cladded with austenitic stainless steel. Characterization of the crystalline structure by electron backscatter diffraction revealed the existence of a delta ferrite phase in the austenitic cladding, and the formation of coarse and fine grain microstructures in the heat affected zone(HAZ)of the RPV steel. The block specimen was cut into small pieces and magnetic hysteresis loops were measured with a vibrating sample magnetometer. Although the saturation magnetization of the RPV steel was constant, the coercivity in the HAZ region decreased gradually as a function of distance from the weld fusion boundary. A linear correlation was confirmed between the coercivity and hardness. This study demonstrates the feasibility of a magnetic evaluation of hardness and microstructures in RPV steel.. |
| 33. | Takeo MUROGA, Takeshi MIYAZAWA, Takuya NAGASAKA, Hideo WATANABE, Correlation of Microstructural Evolution in V-4Cr-4Ti by Heavy Ion and Neutron Irradiations, Plasma and Fusion Research, 10.1585/pfr.11.2405007, 11, 2405007-1-2405007-5, 2016.12. |
| 34. | Y. Oya, H. Fujita, C. Hu, Y. Uemura, S. Sakurada, K. Yuyama, X. Li, Y. Hatano, N. Yoshida, Hideo Watanabe, Y. Nobuta, Y. Yamauchi, M. Tokitani, S. Masuzaki, T. Chikada, Effect of impurity deposition layer formation on D retention in LHD plasma exposed W, Nuclear Materials and Energy, 10.1016/j.nme.2016.07.005, 9, 84-88, 2016.12, [URL], Effect of carbon based mixed-material deposition layer formation on hydrogen isotope retention was studied. The tungsten (W) samples were placed at four different positions, namely PI (sputtering erosion dominated area), DP (deposition dominated area), HL (higher heat load area), and ER (erosion dominated area) during 2013 plasma experimental campaign in Large Helical Device (LHD) at National Institute for Fusion Science (NIFS), Japan and were exposed to ∼ 4000 shots of hydrogen plasma in a 2013 plasma experimental campaign. Most of the sample surface except for ER was covered by a mixed-material deposition layer formed by plasma experimental campaign, which consisted of carbon, but some metal impurities were contained. For ER sample, He bubbles were formed due to long term He discharge cleaning and He plasma experiments during the plasma experimental campaign. The additional 1�keV D2+ implantation was performed to evaluated the D retention enhancement by plasma exposure. It was found that both of H and D retentions were clearly increased. In particular, the H retention was controlled by the thickness of the carbon-dominated mixed-material deposition layer, indicating most of the H was trapped by this mixed-material deposition layer. It is concluded that the accumulation of low-Z mixed-material layer on the surface of the first wall is one of key issues for the determination of hydrogen isotope retention in first wall.. |
| 35. | Hideo Watanabe, K. Yamasaki, A. Higashijima, H. Taguma, T. Nagasaka, T. Muroga, Microstructural changes of Y-doped V-4Cr-4Ti alloys after ion and neutron irradiation, Nuclear Materials and Energy, 10.1016/j.nme.2016.06.001, 9, 447-450, 2016.12, [URL], High-purity Y-doped V-4Cr-4Ti alloys (0.1–0.2 wt. % Y), manufactured by the National Institute for Fusion Science (NIFS), were used for this study. Heavy-ion and fission-neutron irradiation was carried out at temperatures 673–873 K. During the ion irradiation at 873 K, the microstructure was controlled by the formation of Ti(C,O,N) precipitates lying on the (100) plane. Y addition effectively suppressed the growth of Ti(C,O,N) precipitates, especially at lower dose irradiation to up to 4 dpa. However, at higher dose levels (12.0 dpa), the number density was almost at the same levels irrespective of the presence of Y. After neutron irradiation at 873 K, fine titanium oxides were also observed in all V alloys. However, smaller oxide sizes were observed in the Y-doped samples under the same irradiation conditions. The detailed analysis of EDS showed that the center of the Ti(C,O,N) precipitates was mainly enriched by nitrogen. The results showed that the contribution of not only oxygen atoms picked up from the irradiation environment but also nitrogen atoms is essential to understand the microstructural evolution of V-4Cr-4Ti-Y alloys.. |
| 36. | Hideo WATANABE, Takeo MUROGA, Takuya NAGASAKA, Effects of Irradiation Environment on V-4Cr-4Ti Alloys, Plasma and Fusion Research, 10.1585/pfr.12.2405011, 12, 2405011-1-2405011-5, 2016.09. |
| 37. | Y. Matsukawa, T. Takeuchi, Y. Kakubo, T. Suzudo, H. Watanabe, H. Abe, T. Toyama, Y. Nagai, The two-step nucleation of G-phase in ferrite, Acta Materialia, 10.1016/j.actamat.2016.06.013, 116, 104-113, 2016.09, [URL], By combining atom probe tomography (APT) with transmission electron microscopy (TEM) we have attempted to identify the stage at which solute clusters transform into compounds crystallographically distinct from the matrix, in the precipitation of the G-phase (Ni16Si7Mn6) from ferrite solid solution subjected to isothermal annealing at 673 K. Based on a systematic analysis on the number density, size, composition and structure of solute clusters as a function of annealing time, the nucleation of the G-phase was found to occur via a two-step process: spontaneous growth of solute clusters first, followed by a structural change transforming into the G-phase. Moreover, the structural change was found to occur via another two-step process. There was a time lag between the end of cluster growth to become a critical size (mean diameter: ∼2.6 nm) and the start of the structural change. During the incubation period solute enrichment occurred inside the clusters without further size growth, indicating that the nucleation of the G-phase occurs at the critical size with a critical composition. Judging from the results of APT, TEM and the simulation of electron diffraction patterns, the critical composition was estimated to be Ni16Si3.5(Fe,Cr)3.5Mn6.. |
| 38. | S. Entani, M. Mizuguchi, H. Watanabe, Liybov Yu. Antipina, Effective fluorination of single-layer graphene by high-energy ion irradiation through a LiF overlayer, ROYAL SOCIETY OF CHEMISTRY, 10.1039/c6ra09631j, RSC Adv. 2016. 6, 68525-68529, 2016.06. |
| 39. | V. Kh Alimov, Y. Hatano, N. Yoshida, H. Watanabe, M. Oyaidzu, M. Tokitani, T. Hayashi, Surface modification and sputtering erosion of reduced activation ferritic martensitic steel F82H exposed to low-energy, high flux deuterium plasma, Nuclear Materials and Energy, 10.1016/j.nme.2016.01.001, 7, 25-32, 2016.05, [URL], Targets prepared from Reduced Activation Ferritic Martensitic (RAFM) steel F82H were exposed to low-energy (200eV) deuterium (D) plasma at various temperatures with highfluxes of about 1022 D/m2s to various fluences in the range from 1025 to 2.5×1026 D/m2. Under the plasma exposure, micro-structured layers are formed on the target surfaces, and the surface morphology is dependent on the exposure temperature. The erosion yield of the F82H samples increases by a factor of about two as the exposure temperature rises in the range from 403 to 773K.. |
| 40. | H. Watanabe, S. Arase, T. Yamamoto, P. Wells, T. Onishi, G. R. Odette, Hardening and microstructural evolution of A533b steels irradiated with Fe ions and electrons, Journal of Nuclear Materials, 10.1016/j.jnucmat.2015.12.045, 471, 243-250, 2016.04, [URL], Radiation hardening and embrittlement of A533B steels is heavily dependent on the Cu content. In this study, to investigate the effect of copper on the microstructural evolution of these materials, A533B steels with different Cu levels were irradiated with 2.4 MeV Fe ions and 1.0 MeV electrons. Ion irradiation was performed from room temperature (RT) to 350°C with doses up to 1 dpa. At RT and 290°C, low dose (n, with n initially approximately 0.5 and consistent with a barrier hardening mechanism, but saturating at ≈0.1 dpa. At higher dose levels, the radiation-induced hardening exhibited a strong Cu content dependence at 290°C, but not at 350°C. Electron irradiation using high-voltage electron microscopy revealed the growth of interstitial-type dislocation loops and enrichment of Ni, Mn, and Si in the vicinities of pre-existing dislocations at doses for which the radiation-induced hardness due to ion irradiation was prominent.. |
| 41. | V. Kh. Alimov, Y. Hatano, N. Yoshida, H. Watanabe, M. Oyaidzu, M. Tokitani, T. Hayashi, Surface modification and sputtering erosion of reduced activation ferritic martensitic steel F82H exposed to low-energy high flux deuterium plasma, Nuclear Materials and Energy, http://dx.doi.org/10.1016/j.nme.2016.01.001, 7, (2016), 25-32, 2016.01. |
| 42. | Takeo MUROGA, Nam-Jin HEO, Takuya NAGASAKA, Hideo WATANABE, Arata NISHIMURA, Kenji SHINOZAKI, Heterogeneous Precipitation and Mechanical Property Change by Heat Treatments for the Laser Weldments of V-4Cr-4Ti Alloy, plasma and fusion research, 10.1585/pfr.10.1405092, 10, 1405092-1-1405092-7, 2015.11. |
| 43. | H. Kurishita, M. Hatakeyama, M. Nari, S. Matsuo, T. Shikama, N. Ohno, H. Watanabe, K. Tokunaga, T. Hino, Current Activities in the Interface Joint Researcih at Tohoku University- Advanced Education of Radiation Effects on Fusion Materials, Plasma and Fusion Research, dx.doi.org/10.1016/j.jnucmat.2014.03.032, 9, 2016, 440-340, 2015.09. |
| 44. | T. Miyazawa, T. Nagasaka, R. Kasada, Y. Hishinuma, T. Muroga, H. Watanabe, T. Yamamoto, S. Nogami, M. Hatakeyama, Evoluation of Irradiation Hardening of Ion-irradiated V-4Cr-4Ti-0.15Y Alloys by Nanoidentatiion Techniques, Journal of Nuclear Materials, dx.doi.org/10.1016/j.jnucmat.2014.07.059, 455, 2014, 440-444, 2015.08. |
| 45. | Y. Oya, X. Li, K. Yuyama, L. Zhang, S. Kondo, T . Hinoki, Y. Hatano, H. Watanabe, N. Yoshida, T. Chikada, Thermal desorpiton behavior of deuterium for 6MeV Fe ion irradiated W with various damge concentrations, Journal of Nuclear Materials, dx.doi.org/10.1016/j.jnucmat.2014.03.032, 461, 2015, 336-340, 2015.03. |
| 46. | M. Miyamoto, H. Takaoka, K. Ono, S. Morito, N. Yoshida, H. Watanabe, A. Sagara, Crystal orientation dependence of surface modification in molybdenum mirror irradiated with helium ions, Journal of Nuclear Materials, dx.doi.org/10.1016/j.jnucmat.2014.06.030, 455, 2014, 297-300, 2014.07. |
| 47. | 大矢 恭久, 増崎 貴, 時谷 政行, 渡邉 英雄, 吉田 直亮, 波多野 雄治, 宮本 光貴, 山内 有二, 奥野 健二, LHDプラズマに曝されたタングステンにおける水素同位体滞留能変化, Journal of Plasma and Fusion Research, 90, 6（2014）, 319-324, 2014.06. |
| 48. | H. Watanabe, N. Futagami, S. Naitou, N. Yoshida, Microsturucture and Thermal Desorption of Deterium in Heavy Ion Irradiated Pure Tungsten, Journal of Nuclear Materials, 10.1016/j.jnucmat.2014.03.060, 455, 2014, 51-55, 2014.04. |
| 49. | H. Kurishita, S. Matsuo, H. Arakawa, T. Sakamoto, S. Kobayashi, K. Nakai, H. Okano, Hideo Watanabe, Naoaki Yoshida, Y. Torikai, Y. Hatano, T. Takida, M. Kato, A. Ikegaya, Y.Ueda, M. Hatakeyama, T. Shikama, Current status of nanostructured tungsten-based materials development, Physica Scripta, 10.1088/0031-8949/2014/T159/014032, T159(2014), 014032(7PP), 1-7, 2014.04. |
| 50. | 鎌田 康寛, 兜森 達彦, 小林 悟, 菊池 弘昭, 渡邉 英雄, Fe-Cr合金の照射損傷と磁性のコンビナトリアル型研究, 日本AEM学会誌, 22, 2(2014), 249-254, 2014.03. |
| 51. | Hiroaki Kurishita, Masahiko Hatakeyama, Minoru Narui, Satoru Matsuno, Tatsuo Shikama, Kohei Tada, Noriyasu Ohno, Takao Takeuchi, Yuji Hatano, Masaki Nishiura, Hideo Watanabe, KAZUTOSHI TOKUNAGA, Tomoaki Hino, Yoshino Ueda, Takeo Muroga, Akio Sagara, Osamu Kaneko, Current Activities in the Interactive Joint Research at Tohoku University – Advanced Evaluation of Radiation Effects on Fusion Materials - *), Plasma and Fusion Research: Regular Articles, 10.1585/pfr.9.3405136, 9, 3405136(2014), 3405136-1-3405136-4, 2014.03. |
| 52. | Y. Oya, S. Masuzaki, M. Tokitani, M. sato, H. Uchimura, Naoaki Yoshida, HIDEO WATANABE, Y. Yamaguchi, T. Hino, M. Miyamoto, Y. Hatano, K. Okuno, Comparison of Hydrogen Isotope Retention for Tungsten Probe in LHD Vacuum Vessel during the Experimental Campaigns in 2011 and 2012, Fusion Engineering and Design, 10.1016/j.fusengdes.2013.12.018, 89, (2014), 1091-1095, In Press, 2014.01, [URL]. |
| 53. | KENJI MATSUMOTO, HIDEO WATANABE, Naoaki Yoshida, A TEM Investigation of Crack Formation Mechanism on Chrome-Molybdenum Steel Tested under Real Driving Conditions, Society of Tribologists and Lubrication Engineers, 10.1080/10402004.2013.783660, Tribology Transactions, 56, Issues 6, 897-907, 2013.08. |
| 54. | Takuya Nagasaka, Yoshimitsu Hishinuma, Takeo Muroga, HIDEO WATANABE, Hideo Sakasegawa, Hiroyasu Tanigawa, Masami Ando, Analysis on precipitation behavior of reduced activationferritic/martensitic steels with extraction residue tests, Fusion Engineering and Design, 10.1016/j.fusengdes.2013.037, 88,Issues9-10, 2013, 2565-2568, 2013.06. |
| 55. | Takuya Nagasaka, Takeo Muroga, WATANABE HIDEO, Takeshi Miyazawa, Masanori Yamazaki, Kenji Shinozaki, Impact property of low-activation vanadium alloy after laser welding and heavy neutron irradiation, Journal of Nuclear Materials, 10.1016/j.jnucmat.2013.05.046, 442,Issues1-3,Supplement 1, 2013, s364-s369, 2013.05. |
| 56. | Y.Kamada, J.N.Mohapatra, H. Kikuchi, S. Kobayashi, T. Murakami, HIDEO WATANABE, Neutron Irradiation Effects on Mechanical and Magnetic Properties of Pre-deformed Iron-based Model Alloys, Journal of the Magnetics Society of Japan , Vol.37, No.3-2, 2013, 147-150, 2013.05. |
| 57. | Y. Hatano, M. Shimada, T. Otsuka, Y. Oya, V.Kh. Alimov, M. Hara, J. Shi, M. Kobayashi, T. Oda, G. Cao, K. Okuno, T. Tanaka, K. Sugiyama, J. Roth, B. Tyburska-P¨ uschel, J. Dorner, Yoshida Naoaki, N. Futagami, WATANABE HIDEO, M. Hatakeyama, Deuterium trapping at defects created with neutron and ion irradiations in tungsten, NUCLEAR FUSION , 10.1088/0029-5515/53/7/073006, 53,No.7, 2013, 073006-1-073006-7, 2013.05. |
| 58. | Tomonori Tokunaga, HIDEO WATANABE, Naoaki Yoshida, Takuya Nagasaka, Ryuta Kasada, Akihiko Kimura, Masayuki Tokitani, Masatoshi Mitsuhara, Hideharu Nakashima, Suguru Masuzaki, Takeshi Takabatake, Nobuyoshi Kuroki, Koichiro Ezato, Satoshi Suzuki, Masato Akiba, Manufacture of Vacuum Plasma Spraying Tungsten with Homogenous Texture on Reduced Activation Ferritic Steel at about 873K, Plasma and Fusion Research: Regular Articles, 10.1585/prf.8.1405111, Volume 8, 1405111(2013), 1405111-1-1405111-6, 2013.05. |
| 59. | Yasuhisa Oya, Suguru Masuzaki, Masayuki Tokitani, Naoaki Yoshida, HIDEO WATANABE, Yuji Yamauchi, Tomoaki Hino, Mitsutaka Miyamoto, Yuji Hatano, Kenji Okuno, Enhancement of hydrogen isotope retention capacity for the impurity deposited tungsten by long-term plasma exposure in LHD, Fusion Engineering and Design, 88,Issues9-10, 2013, 1699-1703, 2013.04. |
| 60. | WATANABE HIDEO, A. Hiragane, S. Shin, Yoshida Naoaki, Y. Kamada, Effect of stress on radiation-induced hardening of A533B and Fe–Mn model alloys, Journal of Nuclear Materials, 10.1016/j.jnucmat.2013.04.029, 442,Issues1-3,Supplement 1, 2013, s776-s781, 2013.04. |
| 61. | Q.Xu, K.Sato, X.Z.Cao, P.Zhang, bB.Y.Wang, T.Yoshiie, HIDEO WATANABE, Naoaki Yoshida, Interactions of deuterium with vacancies induced by ion irradiation in W, Nuclear Instruments and Methods in Physics Research B:Beam Interactions with Materials and Atoms, 315, 2013, 146-148, 2013.04. |
| 62. | Muroga Takeo, Nagasaka Takuya, P.F. Zheng, Y. F. Li, WATANABE HIDEO, Dislocation evolution during thermal creep deformation in V-4Cr-4Ti with various thermal and mechanical treatments, Journal of Nuclear Materials, 10.1016/j.jnucmat.2013.03.061, 442, 2013, s354-s359, 2013.03. |
| 63. | WATANABE HIDEO, Tokunaga Tomonori, Yoshida Naoaki, Nagasaka Takuya, Muroga Takeo, Investigation on the microstructure of W-coated low-activation alloy V-4Cr-4Ti , Journal of Nuclear Materials, 10.1016/j.jnucmat.2013.02.051, 442, 2013, s292-s296, 2013.03, Ｖ系低放射性構造材料（ＮＩＦＳ－ＨＥＡＴ２）にＷをロウ付け並びにＶＰＳ(Vacumme Plasma Spray)法にて接合し、界面の電子顕微鏡観察を実施した。界面近傍ではＶ中にチタン析出物が 熱により消失し、材料の挙動に大きな影響を与えることを明らかにした。. |
| 64. | Yasuhisa Oya, Suguru Masuzaki, Tetsuo Fujishima, Masayuki Tokitani, Yoshida Naoaki, WATANABE HIDEO, Yuji Hamauchi, Tomoaki Hino, Mitsutaka Miyamoto, Yuji Hatano, Kenji Okuno, Enhaancement of hydrogen isotope retention in tungsten exposed to LHD plasmas, Journal of Nuclear Materials, 10.1016/j.jnucmat.2013.01.231, 438, 2013, s1055-s1058, 2013.01. |
| 65. | Yasuhisa Oya, Masashi Shimada, Tomonori tokunaga, WATANABE HIDEO, Yoshida Naoaki, Yuji Hatano, Ryuta Kasada, Takuya Nagasaka, Akihiko Kimura, Kenji Okuno, Behavior of deuterium retention and surface morphology for VPS-W/F82H, Journal of Nuclear Materials, 10.1016/j.jnucmat.2013.01.321, 442, 2013, s242-s245, 2013.01. |
| 66. | T.Tokunaga, WATANABE HIDEO, Yoshida Naoaki, T.Nagasaka, R.Kasada, Y.Lee, A.Kimura, M.Tokitani, T.Hinoki, H.Nakasima, S.Masuzaki, T.Takabatake, N.Kuroki, K.Ezato, S.Suzuki, M.Akiba, Development of high-grade VPS-tungsten coating on F82H reduced activation steel , Journal of Nuclear Materials, 10.1016/j.jnucmat.2012.11.004, 442, 2013, s287-s291, 2012.12. |
| 67. | Yasuhiro Kamada, WATANABE HIDEO, Seiji Mitani, Jitendra Narayana Mohapatra, Hiroaki Kikuchi, Satoru Kobayashi, Masaki Muzuguchi, Koki Takanashi, Ion-irradiation enhancement of materials degradation in Fe–Cr single crystals detected by magnetic technique, Journal of Nuclear Materials, 10.1016/j.jnucmat.2012.11.042, 442, 2013, s861-s864, 2012.12. |
| 68. | N. Ohno, Y. Hirahata, M. Yamagiwa, S. Kajita, M. Takagi, Yoshida Naoaki, Reiko Yoshihara, Tomonori Tokunaga, M. Tokitani, Influence of crystal orientation on damages of tungsten exposed to helium plasma, Journal of Nuclear Materials, accepted for publication, 2012.12. |
| 69. | WATANABE HIDEO, A. Hiragane, S. Shin, Yoshida Naoaki, Kamada Yasuhiro, The effects of stress on radiation-induced hardening of A533B and Fe-Mn alloys , Journal of Nuclear Materials, accepted for publication, 2012.12. |
| 70. | Tomonori Tokunaga, WATANABE HIDEO, Yoshida Naoaki, T. Nagasaka, R. Kasada, A. Kimura, M. Tokitani, M. Mitsuhara, H. Nakashima, S. Masuzaki, T. Takabatake, N. Kuroki, K. Ezato, S. Suzuk, M. Akiba, Manufacture of vacuum plasma sprayed tungsten with homogenous texture on metallic substrate at low temperatures, Plasma and Fusion Research, submitted, 2012.12. |
| 71. | 車田亮、小吹隆之、伊藤吾朗、渡邉英雄、松尾明, 銅とタングステンの接合界面強度に及ぼすイオン照射後熱処理の影響, 銅と銅合金（2012）, 第51巻, 1号, 153-157, 2012.12. |
| 72. | HIDEO WATANABE, S.Masaki, S.Masubuchi, Naoaki Yoshida, K.Dohi, Effects of Mn addition on dislocation loop formation in A533B and model alloys, Jouenal of Nuclear Materials, 10.1016/j.jnucmat.2012.08.029, 439, 2013, 268-275, 2012.09. |
| 73. | WATANABE HIDEO, M.Masaki, S.Masubuchi, Yoshida Naoaki, Kamada Yasuhiro, Effects of Mn addition on Dislocation Loop Formation in A533B and Model Alloys Journal of Nuclear Materials, Journal of Nuclear Materials, 439, 268-275, 2012.08, 実用材料であるＡ５３３Ｂ並びにＦｅモデル合金を用いてＭｎ添加の影響が転位ループ（マトリクス欠陥）の数密度増加に起因するものであることを、電子線照射並びにイオン照射実験から秋化にした。. |
| 74. | 隅野裕也, 渡辺英雄, 吉田直亮, 高照射量および高サイクル温度変動環境下における純銅の損傷組織変化, 日本金属学会誌 , 第76巻, 第8号, 482-488, 2012.08. |
| 75. | Masashi Shimada, Y. Hatano, Y. Oya, T. Oda, M. Hara, G. Cao, M. Kobayashi, M. Sokolov, HIDEO WATANABE, B. Tyburska-Puschel, Y. Ueda, P. Calderoni, K. Okuno, Overview of the US–Japan collaborative investigation on hydrogen isotope retention in neutron-irradiated and ion-damaged tungsten , Fusion Engineering and Design, 10.1016/j.fusengdes.2012.02.103, 87, 2012, 1166-1170, 2012.04. |
| 76. | S.K. Sharma, hideki zushi, Naoaki Yoshida, HIDEO WATANABE, M. Osakabe, Y. Takeri, M. Hasegawa, T. Tanabe, KAZUTOSHI TOKUNAGA, kazuaki hanada, Hiroshi Idei, M. Sakamoto, Kazuo Nakamura, Akihide Fujisawa, S. Tashima, Analysis of PWI footprint traces and material damage on the first walls of the spherical tokamak QUEST, Fusion Engineering and Design, 10.1016/j.fusengdes.2011.10.001, 87, 2012, 77-86, 2011.11. |
| 77. | Kazuhito Ohsawa, Keisuke Eguchi, Hideo Watanabe, Masataka Yamaguchi and Masatoshi Yagi, Configuration and binding energy of multiple hydrogen atoms trapped in movovacancy in bcc transition metals, PHYSICAL REVIEW B, 10.1103/PhysRevB.85.094102, 85, 2012, 094102-1~8, 2011.11. |
| 78. | Takuya Nagasaka, Yoshimitsu Hishinuma, Takeo Muroga, Yanfen Li, HIDEO WATANABE, Hiroyasu Tanigawa, Hideo Sakasegawa, Masami Ando, Extraction residue analysis on F82H-BA07 heat and other reduced activation ferritic/martensitic steels , Fusion Engineering and Design, 10.1016/j.fusengdes.2010.11.006, 86, 2011, 2581-2584, 2011.10. |
| 79. | Yasuhisa Oya, Masashi Shimada, Makoto Kobayashi, Takuji Lda, Masanori Hara, Hideo Watanabe, Yuji Hatano, Pattorick Calderoni and Kenji Okuno, Comparison of deuterium retention for ion-irradiated and neutron-irradeated tungsten, PHYSICA SCRIPTA, 10.1088/0031-8949/2011/T145/014050, T145, 014050(5PP), 2011.05. |
| 80. | Yasuhiro Kamada, Hideo Watanabe, Seiji Mitani, Jun-ichi Echigoya, Hiroaki Kikuchi, Satoru Kobayashi and Koki Takanashi , Magnetic Properties of Ion Irradiated Epitaxial Fe Films, Joural of Physics : Conference Series, Vol. 266(2011) pp.012035/1-5, Vol.50, No.9 pp.2134to2138, 2011.04. |
| 81. | Nagasaka Takuya, Muroga Takeo, WATANABE HIDEO, Kasada Ryota, Kimura Akihiko, Mechanial properties of V-4Cr-4Ti alloy after first-wall coating with tungsten, Journal of Nuclear Materials, 306-309, 417 , 2011.04. |
| 82. | T.Muroga,T.Nagasaka,H.Watanabe,M.Yamazaki, The effect of final heat treatment temperature on radiation response of V-4Cr-4Ti, Journal of Nuclear Materials, 2011.04. |
| 83. | H.Watanabe,S.Masaki,S.Masubuchi,N.Yoshida,Y.kamada, Radiation induced hardening of irradiated RPV steels, Journal of Nuclear Materials, 2011.04. |
| 84. | WATANABE HIDEO, Yoshida Naoaki, Nagasaka Takuya, Muroga Takeo, The microstructure and hardness changes of neutron irradiated weld joint of vanadium alloy, Journal of Nuclear Materials, 2011.04. |
| 85. | 渡邉 英雄, 電子線照射下における原子炉圧力容器モデル合金Ｆｅ-1.4Ｍｎのその場観察, 日本金属学会誌, 75, 3, 173-178, 2011.04. |
| 86. | 車田 亮、Mohd Yusairy、伊藤 吾朗、渡邉 英雄、松尾 明, 銅とタングステンとの接合材の硬さと組織に及ぼすイオン照射効果, 銅と銅合金, 第50巻, 1号, 110-114, 2011.04. |
| 87. | Takuya Nagasaka, Yoshimitsu Hishinuma, Takeo Muroga, Yanfen Li, HIDEO WATANABE, Hiroyasu Tanigawa, Hideo Sakasegawa, Masami Ando, Extraction residue analysis on F82H-BA07 heat and other reduced activation ferritic/martensitic steels, Fusion Engineering and Design, 10.1016/j.fusengdes.2010.11.006, 86, 2011, 2581-2584, 2010.12. |
| 88. | Hideo WATANABE,Naoaki YOSHIDA, Environmntal EffectS on Titanium Oxide Formation in V-4Cr-4Ti Alloys, Reports of Research Institute for Applied Mechanics,Kyushu University, 139, 81-84, 2010.09. |
| 89. | 徳永知倫、渡辺英雄、吉田直亮、長坂琢也、笠田竜太、時谷政行、光原昌寿、中島英治、 増崎貴、高畠剛、黒木信義、江里幸一郎、鈴木哲、秋場真人 , VPS-タングステン被覆低放射フェライト・マルテンサイト鋼の耐熱不可特性改良に向けた検討, 九州大学応用力学研究所所報, 139, 153-157, 2010.09. |
| 90. | 關 人史、渡辺英雄、吉田直亮, Ｆｅ-Ｍｎ合金の応力下での欠陥形成のその場観察, 九州大学応用力学研究所所報, 139, 141-144, 2010.09. |
| 91. | 土肥謙次、西田憲二、野本明義、曽根田直樹、渡辺英雄, 中性子及び重イオン照射した原子炉圧力容器鋼モデル合金の3次元アトムプローブ観察, 日本金属学会誌 , 第74巻, 第3号, 195-198, 2010.03. |
| 92. | 渡辺英雄、真崎信吾、鱒渕俊児、吉田直亮, 超高圧電子顕微鏡による軽水炉圧力容器鋼の欠陥挙動, 九州大学応用力学研究所所報, 第137号（157-160）, 2009.09.  |
| 93. | 鎌田康寛、菊池弘昭、小林 悟、荒 克之、高橋正氣、渡辺英雄、吉田直亮、海老根典也
鈴木雅秀
, 中性子照射した純鉄および圧力容器鋼の磁気特性と照射欠陥の関係, 九州大学応用力学研究所所報, 第137号（151-155）, 2009.09. |
| 94. | 平金晶憲、渡辺英雄、吉田直亮, 応力下における圧力容器鋼の照射欠陥挙動, 九州大学応用力学研究所所報, 第137号（161-163）, 2009.09. |
| 95. | T.Muroga,T.Nagasaka,J.M.Chen,Y.F.Li,H.Watanabe, Microstructure of creep-deformed V-4C-4Ti strengthened by precipitation and cold rollng, Journal of Nuclear Materials, 606-609, 386-388 606-609, 2009.04. |
| 96. | Y.Sumino, H.Watanabe, N.Yoshida, The microstructural evolution of precipitate strengthened copper alloys by varying temperature irradiation, Journal of Nuclear Materials, 386-388 654-657, 2009.04. |
| 97. | H.Watanabe, A.Higashijima, N.Yoshida, T.Nagasaka,T.Muroga, The microstructure of laser welded Y doped V-4C-4Ti alloys after ion irradiation, Journal of Nuclear Materials, 386-388 598-601, 2009.04. |
| 98. | Yasuhiro Kamada, Hideo Watanabe, Seiji Mitani, Jun-ichi Echigoya, Hiroaki Kikuchi, Satoru Kobayashi
Naoaki Yoshida and Koki Takanashi
, Effects of Room Temperaturre Heavy-Ion Irradiation on Magnetic and Electrical Properties of a Single Crystalline Iron Thin Film , Materials Transactions, Vol.50, No.9 pp.2134to2138, 2009.04. |
| 99. | 室賀健夫、長坂琢也、鈴木晶大、福元謙一、佐藤 学、渡辺英雄, バナジウム合金・液体リチウムシステムの研究, Journal of plasma and Fusion Research, Vol.85, No5 ,260-266, 2009.02. |
| 100. | 土肥謙次、西田憲二、野本明義、曽根田直樹、渡辺英雄, 重イオン照射された原子炉圧力容器鋼モデル合金の三次元アトムプロープ観察, Materials Science Research Laboratory, Rep. NoQ08029, 2009.02. |
| 101. | 渡辺英雄、鱒渕俊児、吉田直亮, ＨＶＥＭ照射による軽水炉圧力容器鋼の欠陥挙動解析, まてりあ、日本金属学会, 第47巻、第12号、620, 2008.12. |
| 102. | 渡辺英雄、吉田直亮, イオン照射した低放射性Ｖ－４Ｃｒ－４Ｔｉ合金の表面近傍での微細チタン酸化物の形成, まてりあ、日本金属学会, 第47巻、第12号、631, 2008.12. |
| 103. | 曽根田直樹、佐藤紘一、渡辺英雄, ＹＡＧレーザー溶接されたＶ－４Ｃｒ－４Ｔｉ合金の照射組織に及ぼす溶接後熱処理の効果, Ｊｏｕｒｎａｌ of Plasma and Fusion Research , VOL.84, No.６(200８)383-394 , 2008.06. |
| 104. | 渡辺英雄、山崎和宏、東嶋 彬、吉田直亮、長坂琢也、室賀健夫、許 男鎮、篠崎賢二, ＹＡＧレーザー溶接されたＶ－４Ｃｒ－４Ｔｉ合金の照射組織に及ぼす溶接後熱処理の効果, Ｊｏｕｒｎａｌ of Plasma and Fusion Research , VOL.84, No.1(200８)46-50 , 2008.01. |
| 105. | 渡辺英雄、今村武史、鱒渕俊児、吉田直亮、鎌田康寛、高橋正氣, 軽水炉圧力容器鋼の中性子照射脆化に関する研究, 九州大学応用力学研究所所報, 第１３３号１６1－165, 2007.06. |
| 106. | 渡辺英雄、山崎和宏、東嶋 彬、吉田直亮、長坂琢也、室賀健夫, レーザー溶接されたＶ－４Ｃｒ－４Ｔｉ合金の照射組織に及ぼす溶接後熱処理の影響, 九州大学応用力学研究所所報, 第１３３号１６７－１７２, 2007.06. |
| 107. | Q. Xu, T. Yoshiie, H. Watanabe, and N. Yoshida, Ｅｆｆｅｃｔｓ oｆ ｏｖｅｒｓｉｚｅｄ ｅｌｅｍｅｎｔ Ｓｎ ｏｎ ｄｉｆｆｕｓｉｏｎ ｏｆ Iｎｔｅｒｓｉｔｉｔｉａｌ ｃｌｕｓｔｅｒ ｉｎ Ｎｉ ｉｒｒａｄｉａｔｅｄ ｂｙ ｉｏｎｓ and neutrons, Journal of Nuclear Materials, 367-370(2007)361-367, 2007.05. |
| 108. | H. Watanabe, K, Yamazaki, A. Higashizima, N. Yoshida, T. Nagasaka and T. Muroga, The microstructure of laser welded V-4Cr-4Ti alloy after neutron irradiation, Journal of Nuclear Materials, 367-370(2007)794-799, 2007.05. |
| 109. | 隅野裕也、渡辺英雄、吉田直亮, アルミナ分散強化型銅合金の内部組織変化に及ぼす温度変動効果, 九州大学総合理工学報告, 第28巻2号241-245, 2006.09. |
| 110. | T. Nagasaka,T. Muroga, K. Fukumoto, H. Watanabe, M. L. Grossbeck, J. Chen, Development of fabrication technology for low activation vanadium alloys as fusion blanket structural materials, Nulc. Fusion , Vol.5.618-625, 2006.05. |
| 111. | Y. Sumino, H. Watanabe, N. Yoshida, and T,Muroga, The Microstructure of Pure Copper After Stepwise Ｃhange of Irradiation Temperature, Material Scicence Forum, 475-479, 1479-1482, Vols. 475-479(2005)pp.1479-1482, 2005.10. |
| 112. | H. Watanabe, M. Nagamine, K. Yamasaki, N. Yoshida, Nam-JIn Heo, T. Nagasaka and T,Muroga, The Microstructure of Laser Welded V-4Cr-4Ti Alloys After Ion Irradiation, Material Scicence Forum, 475-479, 1491-1495, Vols. 475-479(2005)pp.1491-1496, 2005.10. |
| 113. | 渡辺英雄、長嶺成将、山崎和宏、吉田直亮、室賀健夫、長坂琢也、許男鎮、篠崎賢二, Yag レーザー溶接したV-4Cr-4Ti合金（NIFS-HEAT2)のイオン照射特性, プラズマ核融合学会誌, Vol.80, No.10(2004),pp.889〜894, 2004.10. |
| 114. | 渡辺英雄、室賀健夫、吉田直亮, オーステナイトステンレス鋼のミクロ組織発達に関する温度変動照射実験の最近の成果, プラズマ核融合学会誌, Vol.80. No6(2004).pp.523〜528, 2004.06. |
| 115. | M. Hatakeyama, H. Watanabe, T. Muroga and N. Yoshida, The precipitation behavior of ion irradiated V-4Vr-4Ti alloys at various oxygen and nitrogen levels, Journal of Nuclear Materials, 10.1016/j.jnucmat.2004.04.076, 329, 420-424, 329-333(2004)420-424, 2004.01. |
| 116. | Ham-Jin HEO, T. Nagasaka, T. Muroga, A. Nismura, K. Shinozaki, H. Watanabe, Mechanical Properites of Laser Weldment of V-4Cr-4Ti Alloy, Fusion Science and Technology, 44, 2, 470-474, Vol.44.470-474, 2003.09. |
| 117. | H. Watanabe, D. J. Edwards, Y. Aono, N. Yoshida, Microstructure of Neutron Irradiated SS316L/DS-Cu Joint, Journal of Nuclear Materials, 10.1016/S0022-3115(02)01205-9, 307, 335-338, Vol.307-311.335-338, 2002.12. |
| 118. | H. Watanabe, T. Muroga, N. Yoshida, Effects of Temperature Variation Change on Vadadium Alloys Irradiated in HFIR, Journal of Nuclear Materials, Vol.307-311.403-407, 2002.12. |
| 119. | H. Watanabe, M. Suda, T. Muroga, N. Yoshida, Oxide Formation of a Purified V-4Cr-4Ti Alloys During Heat Treatment and Ion Irradiation, Journal of Nuclear Materials, 10.1016/S0022-3115(02)01097-8, 307, 408-411, Vol.307-311.408-411, 2002.12. |
| 120. | H. Watanabe, N. Yoshida, ODS銅/ステンレス接合材料の中性子照射による組織変化, まてりあ、日本金属学会, 第40巻、第12号、1027, 2002.03. |
| 121. | H. Watanabe, T. Muroga, N. Yoshida, Effects of Varying Temperature Irradiation of the Microstructure of Neutron Irradiated Austenitic Stainless Steels, 日本金属学会, 2002.03. |
| 122. | 渡辺英雄、室賀健夫、吉田直亮, オーステナイト系ステンレス鋼の耐中性子照射特性の改善, 電子顕微鏡法の実践と応用写真集（日本金属学会編）, 2002.03. |
| 123. | T. Muroga, S.J.Zinkle, A. L. Qualls, H. Watanabe, Varying Temperature Irradiation Experiment in HFIR, Journal of Nuclear Materials, 10.1016/S0022-3115(01)00675-4, 299, 2, 148-156, Vol. 299 148-156, 2001.11. |
| 124. | 畠山賢彦、渡辺英雄、秋場真人、吉田直亮, 酸化物分散銅合金のイオン照射による組織発達, 九州大学総合理工学報告, 第23巻2号179-185, 2001.09. |
| 125. | K. Yasunaga, H. Watanabe, N. Yoshida, T. Murorga, N. Noda, Correlation between Defect Structure and Hardness in Tantalum Irradiated by Heaby Ions, Journal of Nuclear Materials, 10.1016/S0022-3115(00)00354-8, 283, 179-182, Vol.283-287 179-182, 2000.10. |
| 126. | H. Watanabe, T. Arinaga, K. Ochiai, T. Muroga, N. Yoshida, Microstructure of Vanadium Alloys during Ion Irradiated with Stepwise Change of Temperature, Journal of Nuclear Materials, 10.1016/S0022-3115(00)00307-X, 283, 286-290, Vol. 283-287 286-290, 2000.10. |
| 127. | D. Hamaguchi, T. Muroga, H. Watanabe, N. Yoshida, Influence of Variable Temperatures Irradiation on Microstructural Evolution in Phosphorus Doped Fe-Cr-Ni alloys, Journal of Nuclear Materials, 10.1016/S0022-3115(00)00133-1, 283, 319-323, Vol. 283-287 319-323, 2000.10. |
| 128. | 室賀健夫、吉田直亮、渡辺英雄、栗下裕明 , Correlation of Hardening and Microstructure of Tantalum Irradiated with Heavy Ions , Effects of Radiation on Materials, 1186-1211, ASTM STP 1366,1186-1211, 1999.10. |
| 129. | 渡辺英雄、F.A.Garner, Influence of Silicon and Titanium on the Microstructural Evolution of Fe-Cr-35Ni Alloys , Effects of Radiation on Materials, 10.1520/STP12437S, 1366, 859-873, ASTM STP 1366, 859-873, 1999.10. |
| 130. | 落合建壮、渡辺英雄、室賀健夫、吉田直亮、松井秀樹, Microstructural Evolution in Vanadium Irradiated during Ion Irradiation at Constant and Varying Temperature , Journal of Nuclear Materials, 10.1016/S0022-3115(98)00751-X, 271, 376-380, Vol.271-272, 381-384, 1999.05. |
| 131. | 室賀健夫、渡辺英雄、吉田直亮, Fluence Dependence of Defect Evolution in Austenitic Stainless Steels during Fission Neutron Irradiaton , Journul of Nuclear Materials, 10.1016/S0022-3115(98)00752-1, 271, 381-384, Vol.271-272, 381-384, 1999.05. |
| 132. | 室賀健夫、渡辺英雄、松江隆、吉田直亮, Void Swelling of Pure Copper and Copper Alloys induced by Heavy Ion Irradiation, Effects of Radiation on Materials, ASTM STP 1325, 991—998, 1999.04. |
| 133. | 室賀健夫、渡辺英雄、吉田直亮、栗下裕明, Microstructures in Neutron Irradiated Fe-Cr-Ni-P-Ti Model Austenitic Alloys doped with 10B , Effects of Radiation on Materials, ASTM STP 1325, 689-700, 1999.04. |
| 134. | 安永和史、渡辺英雄、室賀健夫、吉田直亮、野田信明, Microstructure of tantalum irradiated with heavy ions, Journul of Materials, 10.1016/S0022-3115(98)00261-X, 258, 879-882, Vol.258-263, 879-882, 1998.10. |
| 135. | 室賀健夫、渡辺英雄、吉田直亮, Effects of solid transmutans and helium in copper studied by mixed-spectrum neutron Irradiation , Journul of Nuclear Materials, 10.1016/S0022-3115(98)00123-8, 258, 955-960, Vol.258-263, 955-960, 1998.10. |
| 136. | 岩切宏友、脇本博章、渡辺英雄、室賀健夫、吉田直亮, Hardening behavior of molybdenum by low energy He and D ion irradiation, Journul of Nuclear Materials, 10.1016/S0022-3115(98)00260-8, 258, 873-878, Vol.258-263, 873-878, 1998.10. |
| 137. | 渡辺英雄、室賀健夫、吉田直亮, オーステナイト系ステンレス鋼の耐中性子照射特性の改善, まてりあ, 第３７号, 第５号, ３７９, 1998.05. |
| 138. | 岩切宏友、渡辺英雄、吉田直亮, 超微小押し込み試験法によるイオン照射したモリブデンの硬度評価, 九州大学応用力学研究所所報, 第82号 p.197, 1997.11. |
| 139. | 安永和史、渡辺英雄、室賀健夫、吉田直亮, 高速中性子照射されたNb-1Zr合金の内部組織変化に及ぼす熱処理の効果, 九州大学総合理工学研究科報告, 第18巻, ４号, 303-307, 1997.03. |
| 140. | 渡辺英雄、室賀健夫、吉田直亮、秋場真人, Microstructure of Neutron Irradiated Graphite/Cu Joint, Fusion Technology, 30, 3, 774-777, Vol.30 p.774, 1996.12. |
| 141. | 渡辺英雄、室賀健夫、吉田直亮, The Effect of Oversized Solute Addition on Microstructural Evolution in Fe-Cr-Ni Alloys during Electron Irradiation , Journal of Nuclear Materials, Vol.239 95-98, 1996.12. |
| 142. | 除ギュウ、渡辺英雄、室賀健夫、吉田直亮, Microstructural Evolution in Fe-Cr-Ni Alloy Irradiated with Ni Ion under Varing Temperature , Journal of Nuclear Materials, 10.1016/S0022-3115(96)00118-3, 233, 1057-1061, Vol.223-237 1057-1061, 1996.10. |
| 143. | 渡辺英雄、室賀健夫、吉田直亮, he Influence of Heat Treatments on Neutron Irradiated Nb-1Zr Alloy, Journal of Nuclear Materials, 10.1016/S0022-3115(96)00244-9, 233, 577-580, Vol.223-237 233-237, 1996.10. |
| 144. | 渡辺英雄、室賀健夫、吉田直亮, The Temperature Dependent Role of Phosphorus and Titanium in Microstructural Evolution of Fe-Cr-Ni alloys Irradiated in FFTF , Jouanal of Nuclear Materials, 10.1016/0022-3115(96)80004-3, 228, 3, 261-274, Vol.228 p.261, 1996.07. |
| 145. | 室賀健夫、渡辺英雄、吉田直亮、栗下裕明, Microstructure and Tensile Properties of Neutron Irradiated Cu and Cu-5Mn Containing Isotopically Controlled Boron , Journal of Nuclear Materials, 10.1016/0022-3115(95)00027-5, 225, 137-145, Vol.225 p.137, 1995.10. |
| 146. | 渡辺英雄、F.A.Garner, 室賀健夫、吉田直亮, The Influence of Silicon and Phosphorus additions on Neutron Induced Microstructural Evolution of Fe-Cr-Ni Ternary Alloys at 646-703K , Journal of Nuclear Materials, 10.1016/0022-3115(94)00442-0, 225, 76-84, Vol.225 p.76, 1995.10. |
| 147. | 渡辺英雄、高橋伸幸、宮本好雄、室賀健夫、吉田直亮, Fe-Cr-Ni合金の照射組織、組成変化に及ぼすニオブ添加効果, 九州大学応用力学研究所所報, 第78号 p.155, 1995.10. |
| 148. | 吉田直亮、徐ギュウ、渡辺英雄, 照射温度変動下での欠陥反応過程, 吉田直亮、徐ギュウ、渡辺英雄, 第78号 p.155, 1995.10. |
| 149. | 渡辺英雄、室賀健夫、吉田直亮, Defect Formation in Austenitic Stainless Steels durinｇ Shutdown procedure of FFTF , Journal of Nuclear Materials, 10.1016/0022-3115(94)90318-2, 217, 1-2, 178-186, Vol.217 p.178 , 1994.12. |
| 150. | 渡辺英雄、F. A. Garner, Void Swelling of Pure Copper, Cu-5Ni and Cu-5Mn Alloys Irradiated with Fast Neutrons, Jounal of Nuclear Materials, 10.1016/0022-3115(94)90088-4, 212, 370-374, Vol.212-215 p.370, 1994.10. |
| 151. | 渡辺英雄、室賀健夫、吉田直亮, The Influence of Combined Addition of Phosphorus and Titianium on Void Swelling of Austenitic Fe-Cr-Ni Alloys at 646-700K , Jounal of Nuclear Materials, 10.1016/0022-3115(94)90112-0, 212, 503-508, Vol.212-215 p.503, 1994.10. |
| 152. | 室賀健夫、三原邦照、渡辺英雄、吉田直亮 , Free Defect Production Efficiency for Heavy Ion Irradiation Estimated by Loop Growth Measurements , Journal of Nuclear Materials, 10.1016/0022-3115(94)90056-6, 212, 203-206, Vol.212-215 p.203, 1994.10. |
| 153. | 徐ギュウ、渡辺英雄、室賀健夫、吉田直亮, Effects of Temperature Variation on Damage Microstructures in Fe-Cr-Ni Alloy Induced by Heavy Ion Irradiation , Journal of Nuclear Materials, 10.1016/0022-3115(94)90067-1, 212, 258-262, Vol.212-215 p.258 , 1994.10. |
| 154. | 栗下裕明、室賀健夫、渡辺英雄、吉田直亮、茅野秀夫、M. L. Hamilton, Effect of FFTF Irradiation on Tensile Properties of P- and Ti-modified Model Austenitic Alloys with Small Amounts of Boron , Journal of Nuclear Materials, 10.1016/0022-3115(94)90115-5, 212, 519-524, Vol.212-215 p.519 , 1994.10. |
| 155. | 吉田直亮、徐ギュウ、渡辺英雄、宮本好雄、室賀健夫, Effect of Cyclic Temperature Change on Microstructural Evolution in Austenitic Stainless Steels under Fission Neutron Irradiation , Journal of Nuclear Materials, 10.1016/0022-3115(94)90106-6, 212, 471-475, Vol.212-215 p.471, 1994.10. |
| 156. | 室賀健夫、渡辺英雄、吉田直亮, The Influence of １０B Addition on the Swellling Suppression by Phosphorus and Titanium in Fe-Cr-Ni, Journal of Nuclear Materials, 10.1016/0022-3115(94)90108-2, 212, 482-486, Vol.212-215 p.482, 1994.10. |
| 157. | 渡辺英雄、室賀健夫、吉田直亮, The Effect of Phosphorus on the Microstructure of an Fe-16Cr-17Ni Austenitic Ternary Induced by Fast Neutron Irradiation , Effects of Radiation on Materials, 10.1520/STP23982S, 1175, 951-963, ASTM STP 1175 P.951 , 1994.01. |
| 158. | 渡辺英雄、室賀健夫、吉田直亮, Microstructural Evolution of Phosphorus Modified Austenitic Steels during Irradiation in JOYO , Materials Trans. JIM, 34, 11, 1012-1017, Vol.34 No.11 p.1012, 1993.11. |
| 159. | F. A. Garner, 関村直人, M. L. Grossbeck, A. M. Ermi, J. W. Newkirk, 渡辺英雄、桐谷道雄
, nfluence of details of reactor history on microstructual development during neutron irradiation , Journal of Nuclear Materials, Vol. 205 p.206, 1993.10. |
| 160. | 徐ギュウ、渡辺英雄、宮本好雄、室賀健夫、吉田直亮, ＪＭＴＲ温度制御照射によるＦｅ－Ｃｒ－Ｎｉ合金の損傷初期過程に関する研究 , 九州大学応用力学研究所所報, 第75号 p.1, 1993.09. |
| 161. | 吉田直亮、徐ギュウ、渡辺英雄、室賀健夫、桐谷道雄, Low dose fission neutron irradiation on P- and Ti modified austenitic alloys with improved temperature control , Journal of Nuclear Materials, Vol. 191-192 p.1114, 1992.12. |
| 162. | 渡辺英雄、室賀健夫、吉田直亮, 高速中性子照射したオーステナイト鋼のボイドスエリングの及ぼすリンの効果, 日本金属学会誌, 第56巻, 第１号, p.619 , 1992.06. |
| 163. | 渡辺英雄、B. Kabius, B. Roas, K. Urban, YBa２Cu３0７－ｘの173MeV Xeイオン照射効果, 日本金属学会誌 , 第56巻, 第１号, p.38 , 1992.01. |
| 164. | B. Kabius, 渡辺英雄、K. Urban, B. Roas, S. Klaumuenzer and G. Saemann-Iscenko
, The Influence of 173MeV Xe-ion Irradiation on the Microstructure of YBa2Cu3O7 Thin Films , Physica C, Vol. 179 p.75, 1991.11. |
| 165. | 渡辺英雄、B. Kabius, B. Roas, K. Urban, The Influence of 173 MeV 129Xe Ion Irradiation on the superconduction Properties and on the Microstructure of YBa2Cu307 Thin Films, Proc. ICMC '90 Topical Conference on Materials Aspects of High-Temeperature Superconductors , p.611, 1991.10. |
| 166. | 渡辺英雄、青木彰伸、室賀健夫、吉田直亮, Effect of Combined Addition of Phosphorus and Titanium on Microstructural Evolution in Fe-Cr-Ni Alloys , Journal of Nuclar Materials , 10.1016/0022-3115(91)90142-T, 179, 529-533, Vol.179-181 p.529, 1991.07. |
| 167. | 室賀健夫、渡辺英雄、吉田直亮, Corrrelation of Fast Neutron, Fusion Neutron and Electron Irradiations Based on the Dislocation Loop Density , Journal of Nuclear Materials, 10.1016/0022-3115(90)90241-E, 174, 2-3, 282-288, Vol.174 p.282, 1990.11. |
| 168. | 渡辺英雄、室賀健夫、吉田直亮, The Effect of Radiation-induced Segregation on Void Swelling in Electron-irradiated Fe-Cr-Ni-Ti-P Alloys , Proc. 12th Int. Cong. on Electron Microscopy, p.932, 1990.08. |
| 169. | 渡辺英雄、B. Kabius, B. Roas, K. Urban, Xenon Ion Irradiation of Superconducting YBa2Cu3O7 Thin Films , roc. 12th Int. Cong. on Electron Microscopy , p.92, 1990.08. |
| 170. | B. Roas, B. Hensel, S. Henke, S. Klaumuenzer, B. Kabius, G. Saemann-Ischenko, L. Schultz, 渡辺英雄、K. Urban, Effect of 173 MeV １２９Xe Ion Irradiation on Epitaxial YBa２Cu３Oｘ Films , Europhysics Letters, 11(7) p.66, 1990.04. |
| 171. | 渡辺英雄、蔵元英一、吉田直亮, Positron Annihilation Lifetime Measurement of Electron Irradiated Fe-Cr-Ni-P Alloy , Trans. Japan Institute of Metals , Vol.29, No.10, 769-773, 1989.10. |
| 172. | 渡辺英雄、蔵元英一、吉田直亮, Interaction between Vacancy and Phosphorus in Austenitic Stainless Steel, Ann. Rep. Res. Reactor Institute, Kyoto Univ, Vol.21 p.109, 1988.12. |
| 173. | 渡辺英雄、青木彰伸、室賀健夫、吉田直亮, オーステナイトステンレス鋼の照射欠陥挙動と析出物形成に及ぼすチタンの効果, 九州大学総合理工学研究科報告, 第10巻 ２号, 1988.10. |
| 174. | 渡辺英雄、青木彰伸、室賀健夫、吉田直亮, オーステナイトステンレス鋼の電子線照射における欠陥挙動と析出物形成に及ぼすリン、チタンの複合添加効果 , 日本金属学会誌, 第53巻, 第10号, p.981, 1988.10. |
| 175. | 渡辺英雄、室賀健夫、吉田直亮、北島一徳, Precipitate Resolution in an Electron Irradiated Ni-Si Alloy , Journal of Nuclear Materials, 10.1016/0022-3115(88)90167-5, 158, 179-187, Vol.158 p.179, 1988.09. |
| 176. | 吉田直亮、室賀健夫、渡辺英雄、荒木邦明、宮本好雄, Effects of Purity on Damage Evolution in Ni Irradiated by 14MeV Neutrons , Journal of Nuclear Materials, 10.1016/0022-3115(88)90500-4, 155, 1222-1226, Vol.155-157 p.1222, 1988.08. |
| 177. | 室賀健夫、宮本好雄、渡辺英雄、吉田直亮, Defects Accumulation in JPCA and Its High Purity Model Alloys Irradiated with D-T Neutrons , Journal of Nuclear Materials, 10.1016/0022-3115(88)90421-7, 155, 810-814, Vol.155-157 p.810, 1988.08. |
| 178. | 室賀健夫、渡辺英雄、荒木邦明、吉田直亮, Fission-Fusion Correlation of Void Swelling in Pure Nickel, Journal of Nuclear Materials, 10.1016/0022-3115(88)90513-2, 155, 1290-1295, Vol.155-157 p.1290 , 1988.08. |
| 179. | 渡辺英雄、青木彰伸、村上英邦、室賀健夫、吉田直亮, Effects of Phosphorus on Defect Behavior, Solute Segregation and Void Swelling in Electron Irradiated Fe-Cr-Ni Alloys , Journal of Nuclear Materials, 10.1016/0022-3115(88)90422-9, 155, 815-822, Vol.155-157 p.815, 1988.08. |
| 180. | 渡辺英雄、青木彰伸、村上英邦、室賀健夫、吉田直亮, オーステナイトステンレス鋼の照射欠陥挙動と組織変化に及ぼす微量リン添加の効果, 日本金属学会誌, 第52巻, 第6号, p.536, 1988.06. |
| 181. | 渡辺英雄、安部博信、蔵元英一、吉田直亮, Positron Annihilation and Resistivity Recovery of Ni-Si Alloys Irradiated by 28MeV Electrons at 77K , Annu. Rep. Res. Reactor Institute, Kyoto Univ, Vol.20 p.146, 1987.12. |
| 182. | 渡辺英雄、青木彰伸、室賀健夫、吉田直亮, Ｆｅ－Ｃｒ－Ｎｉ合金の照射欠陥挙動に及ぼすリンの効果, 九州大学応用力学研究所所報, 第65号 p.425, 1987.12. |
| 183. | 渡辺英雄、室賀健夫、吉田直亮、北島一徳, Ｎｉ－Ｓｉ合金における照射誘起現象, 九州大学応用力学研究所所報, 第63号 p.225 , 1987.01. |
| 184. | 渡辺英雄、室賀健夫、吉田直亮、北島一徳, Precipitate Resolution and Surface Segregation in Electron Irradiated Ni-Si Alloys , Proc. 11th Int. Cong. on Electron Microscopy, p.1115, 1986.08. |
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