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Journal Articles

Anisotropic creep property related to non-spherical shape of mechanically alloyed powder of oxide dispersion strengthened F82H

Sakasegawa, Hideo; Nakajima, Motoki*; Kato, Taichiro*; Nozawa, Takashi*; Ando, Masami*

Materials Today Communications (Internet), 40, p.109659_1 - 109659_8, 2024/08

 Times Cited Count:1 Percentile:30.18(Materials Science, Multidisciplinary)

Nanometric oxide particles play an important role in improving the creep property of Oxide Dispersion Strengthened (ODS) steels. In our previous research, we examined a microstructural feature known as prior particle boundary (PPB). PPB refers to the surface of mechanically alloyed (MA) powders before consolidation. We revealed that the ODS steel with fine PPBs produced from smaller MA powders, exhibited shorter creep rupture times, compared to that with coarse PPBs produced from larger MA powders. The size of MA powders had an impact on the creep property. In this study, we examined the shape of MA powders, which were non-spherical shapes. Such shapes have the potential to induce anisotropic creep behavior. We conducted small punch creep tests on specimens with two different orientations to study the possible anisotropy. The results revealed that the creep rupture times varied depending on the orientation of specimen, thus indicating anisotropic creep property.

Journal Articles

Measurement of neutron scattering cross section of nano-diamond with particle diameter of approximately 5 nm in energy range of 0.2 meV to 100 meV

Teshigawara, Makoto; Tsuchikawa, Yusuke*; Ichikawa, Go*; Takata, Shinichi; Mishima, Kenji*; Harada, Masahide; Oi, Motoki; Kawamura, Yukihiko*; Kai, Tetsuya; Kawamura, Seiko; et al.

Nuclear Instruments and Methods in Physics Research A, 929, p.113 - 120, 2019/06

 Times Cited Count:21 Percentile:87.98(Instruments & Instrumentation)

A nano-diamond is an attractive neutron reflection material below cold neutron energy. The total neutron cross section of a nano-diamond was derived from a neutron transmission measurement over the neutron energy range of 0.2 meV to 100 meV because total neutron cross section data were not available. The total cross section of a nano-diamond with particle size of approximately 5 nm increased with a decrease in neutron energy to 0.2 meV. It was approximately two orders of magnitude larger than that of graphite at 0.2 meV. The contribution of inelastic scattering to the total cross section was to be shown negligible small at neutron energies of 1.2, 1.5, 1.9, 2.6, and 5.9 meV in the inelastic neutron scattering measurement. Moreover, small-angle neutron scattering measurements of the nano-diamond showed a large scattering cross section in the forward direction for low neutron energies.

Journal Articles

Recent issues encountered by AMATERAS; A Cold-neutron disk-chopper spectrometer

Nakajima, Kenji; Kawamura, Seiko; Kikuchi, Tatsuya*; Kofu, Maiko; Kawakita, Yukinobu; Inamura, Yasuhiro; Kambara, Wataru*; Aoyama, Kazuhiro*; Wakai, Daisuke*; Harada, Masahide; et al.

Journal of Physics; Conference Series, 1021(1), p.012031_1 - 012031_5, 2018/06

 Times Cited Count:6 Percentile:94.24(Nuclear Science & Technology)

Journal Articles

Corrosion properties of F82H in flowing high temperature pressurized water

Nakajima, Motoki; Hirose, Takanori; Tanigawa, Hisashi; Enoeda, Mikio

Journal of Plasma and Fusion Research SERIES, Vol.11, p.69 - 72, 2015/03

Water-cooled blanket is an attractive concept for its compactness and its compatibility with the conventional technologies for PWR. For blanket application, the structural material is required to be as thin as possible for tritium breeding. On the other hand, it is also required the pressure tightness to withstand 15 MPa of internal pressure. Therefore it is necessary to understand the corrosion mechanism in high temperature pressurized water. The effects of water flow and DO in the test water on corrosion properties were investigated using rotating disk specimen in autoclave. In summary, the weight loss by flowing was occurred except for test with DO 8 ppm, and it was more pronounced at lower DO concentration. Since Fe$$_{2}$$O$$_{3}$$ was observed on the specimen of small weight change, and the iron-poor layer thickness increased with decreasing the specimen weight, it seemed that the formation of Fe$$_{2}$$O$$_{3}$$ was effective for the suppression of weight loss.

Journal Articles

Corrosion behavior of F82H exposed to high temperature pressurized water with a rotating apparatus

Kanai, Akihiko*; Kasada, Ryuta*; Nakajima, Motoki; Hirose, Takanori; Tanigawa, Hisashi; Enoeda, Mikio; Konishi, Satoshi*

Journal of Nuclear Materials, 455(1-3), p.431 - 435, 2014/12

 Times Cited Count:2 Percentile:15.09(Materials Science, Multidisciplinary)

Journal Articles

R&D status on water cooled ceramic breeder blanket technology

Enoeda, Mikio; Tanigawa, Hisashi; Hirose, Takanori; Nakajima, Motoki; Sato, Satoshi; Ochiai, Kentaro; Konno, Chikara; Kawamura, Yoshinori; Hayashi, Takumi; Yamanishi, Toshihiko; et al.

Fusion Engineering and Design, 89(7-8), p.1131 - 1136, 2014/10

 Times Cited Count:22 Percentile:82.64(Nuclear Science & Technology)

The development of a Water Cooled Ceramic Breeder (WCCB) Test Blanket Module (TBM) is being performed as one of the most important steps toward DEMO blanket in Japan. Regarding the fabrication technology development using F82H, the fabrication of a real scale mockup of the back wall of TBM was completed. Also the assembling of the complete box structure of the TBM mockup and planning of the pressurization testing was studied. The development of advanced breeder and multiplier pebbles for higher chemical stability was performed for future DEMO blanket application. From the view point of TBM test result evaluation and DEMO blanket performance design, the development of the blanket tritium simulation technology, investigation of the TBM neutronics measurement technology and the evaluation of tritium production and recovery test using D-T neutron in the Fusion Neutronics Source (FNS) facility has been performed.

Journal Articles

Evaluation of high-temperature tensile properties of reduced activation ferritic steels by small punch test

Nakata, Toshiya; Komazaki, Shinichi*; Nakajima, Motoki*; Kono, Yutaka*; Tanigawa, Hiroyasu; Shiba, Kiyoyuki; Koyama, Akira*

Nihon Kinzoku Gakkai-Shi, 70(8), p.642 - 645, 2006/08

 Times Cited Count:4 Percentile:33.36(Metallurgy & Metallurgical Engineering)

no abstracts in English

Journal Articles

Evidence for magnetic-field-induced quadrupolar ordering in the heavy-fermion superconductor PrOs$$_{4}$$Sb$$_{12}$$

Kogi, Masafumi*; Iwasa, Kazuaki*; Nakajima, Motoki*; Metoki, Naoto; Araki, Shingo; Bernhoeft, N.*; Mignot, J.-M.*; Gukasov, A.*; Sato, Hideyuki*; Aoki, Yuji*; et al.

Journal of the Physical Society of Japan, 72(5), p.1002 - 1005, 2003/05

 Times Cited Count:199 Percentile:97.08(Physics, Multidisciplinary)

no abstracts in English

Oral presentation

Current status of development of water cooled ceramic breeder blanket system

Hirose, Takanori; Tanigawa, Hisashi; Nakajima, Motoki; Gwon, H.; Miyata, Satoru; Sato, Satoshi; Kawamura, Yoshinori; Yamanishi, Toshihiko

no journal, , 

no abstracts in English

Oral presentation

Cross section measurement of hydrogen containing materials, 1; Light water and ethanol

Harada, Masahide; Abe, Yutaka*; Teshigawara, Makoto; Oi, Motoki; Ikeda, Yujiro; Oikawa, Kenichi; Nakajima, Kenji; Kawamura, Seiko

no journal, , 

By using neutron instruments, NOBORU and AMATERAS, in J-PARC spallation neutron source, we started to measure temperature dependent total and scattering cross section data of hydrogenous material ranging in thermal and cold neutron region. The cross section data of light water and ethanol were measured.

Oral presentation

Measurement of cross sections for hydrogenous materials

Harada, Masahide; Abe, Yutaka*; Oikawa, Kenichi; Kawasaki, Takuro; Kawamura, Seiko; Nakajima, Kenji; Inamura, Yasuhiro; Takahashi, Ryuta*; Teshigawara, Makoto; Oi, Motoki; et al.

no journal, , 

no abstracts in English

Oral presentation

Compatibility of F82H in flowing high temperature and high pressure water, 1; Effect of testing environment on corrosion behaviour

Nakajima, Motoki; Kanai, Akihiko*; Hirose, Takanori; Tanigawa, Hisashi; Enoeda, Mikio

no journal, , 

no abstracts in English

Oral presentation

Compatibility of F82H in flowing high temperature and high pressure water, 2; Microstructural analysis on corroded surface

Kanai, Akihiko*; Kasada, Ryuta*; Konishi, Satoshi*; Nakajima, Motoki; Hirose, Takanori; Tanigawa, Hisashi; Enoeda, Mikio

no journal, , 

no abstracts in English

Oral presentation

Effect of test temperature on corrosion properties of F82H in high temperature pressurized water

Nakajima, Motoki; Hirose, Takanori; Tanigawa, Hisashi; Kawamura, Yoshinori

no journal, , 

As the primary candidate of ITER-TBM of Japan, development of WCCB TBM is being performed. In this blanket, the high temperature pressurized water was used as the coolant. Therefore it is necessary to understand the corrosion mechanism in high temperature pressurized water. Additionally, it is also required that understanding of corrosion properties of temperature ranging from 543K to 593K, because inlet and outlet temperatures of TBM are 543K and 593K, respectively. In this study, the corrosion test was performed at temperature ranging from 543K to 593K in high temperature water. Based on the results of corrosion test, the corrosion amount was increased with increasing the test temperature. The corrosion amount of outlet water was two times larger than that of inlet water.

Oral presentation

Evaluation of strength and pressure integrity for fusion blanket structure

Tanigawa, Hisashi; Gwon, H.; Hirose, Takanori; Nakajima, Motoki; Kawamura, Yoshinori

no journal, , 

Blanket in fusion nuclear reactor has three functions such as neutron shielding, heat recovery and tritium breeding. Blankets with ceramic breeder materials has a box structure made of reduced activation ferritic/martensitic steel, and pebbles of breeder and neutron multiplier materials are packed into the box. Heat and neutron loads on the blanket are cooled by high temperature and pressure coolant such as water and helium. In this study, strength and pressure integrity are assessed for the water-cooled ceramic breeder blanket developed in JAEA. Existing design standards for pressure equipment are used in the analysis and their applicability to the fusion blanket is discussed.

Oral presentation

Material properties of weld joints of reduced activation ferritic/martensitic steel, F82H

Hirose, Takanori; Sakasegawa, Hideo; Nakajima, Motoki; Tanigawa, Hiroyasu

no journal, , 

Weld joints of a reduced activation ferritic/martensitic steel, F82H were prepared using Tungsten-Inert-Gas (TIG) and Electron Beam (EB) welding. Physical properties and mechanical properties of these weld joints were investigated in this work. Moreover, effects of Post Weld Heat Treatment (PWHT) was also investigated. After PWHT at 720 $$^{circ}$$C, most of physical properties of weld metal were very similar to those of F82H base metal. Coefficient of thermal expansion and thermal diffusivity of weld metal demonstrated 10% of degradation compared to the base metal. Although weld metal and heat affected zone heated above transformation temperature demonstrated hardening and embrittlement, PWHT above 750 $$^{circ}$$C successfully moderated the hardening without softening in the base metal.

Oral presentation

Effect of dissolved oxygen on corrosion properties of F82H in high temperature pressurized water

Nakajima, Motoki; Hirose, Takanori; Tanigawa, Hisashi; Kawamura, Yoshinori

no journal, , 

For blanket application, the structural material is required to be as thin as possible for tritium breeding. On the other hand, the pressure tightness is required to withstand 15 MPa of internal pressure. Therefore it is necessary to understand the corrosion mechanism in high temperature pressurized water. This work reports results of corrosion tests on a reduced activation ferritic/martensitic steel, F82H as a structural material for the blanket. Moreover, the effects of water flow and dissolved oxygen (DO) on corrosion properties were investigated using rotating disk specimen in autoclave. In previous study, it was reported that the weight loss by water flow becomes significant with lowering DO concentration. Based on the XRD and EPMA results, it seemed that the formation of Fe$$_{2}$$O$$_{3}$$ was effective for the suppression of weight loss. In this study, we discussed the relationship between stable oxide film and corrosion.

Oral presentation

Corrosion properties of RAFM, F82H in high temperature pressurized water

Nakajima, Motoki

no journal, , 

Reduced activation ferritic/martensitic steel, F82H is the most promising candidate structural material for fusion blanket. Water-cooled ceramic breeder blanket is an attractive concept for its compactness and its compatibility with the technologies in conventional pressurized water reactor (PWR). For blanket application, the structural material is required to be as thin as possible for tritium breeding. On the other hand, it is also required the pressure tightness which could withstand internal pressure of 15 MPa. Therefore it is necessary to determine corrosion allowance for cooling tubes precisely. This work reports corrosion properties of F82H in high temperature pressurized water. Moreover, the effects of water flow on corrosion properties were investigated using rotating disk specimen in autoclave.

Oral presentation

Thermal response characteristics of blanket caused by decay heat under LOCA

Gwon, H.; Tanigawa, Hisashi; Nakajima, Motoki; Hirose, Takanori; Kawamura, Yoshinori

no journal, , 

It is expected that the neutron wall loading in DEMO is larger than that in ITER, over 0.78 MW/m$$^{2}$$. It is concerned that the decay heat due to the large neutron wall loading will lead to excessive temperature rising in blanket. In present study, the thermal response characteristics of blanket caused by the decay heat under LOCA were evaluated. In addition we considered how to effectively mitigate the excessive temperature rising based on the evaluation results.

Oral presentation

Phase stability of long term creep tested F82H and its correlation with irradiation resistance

Tanigawa, Hiroyasu*; Nakajima, Motoki*; Sakasegawa, Hideo; Ando, Masami*; Watanabe, Yoshiyuki*; Nozawa, Takashi*; Kato, Yutai*; Nakata, Toshiya*

no journal, , 

26 (Records 1-20 displayed on this page)