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Journal Articles

Effects of helium on irradiation response of reduced-activation ferritic-martensitic steels; Using nickel isotopes to simulate fusion neutron response

Kim, B. K.*; Tan, L.*; Sakasegawa, Hideo; Parish, C. M.*; Zhong, W.*; Tanigawa, Hiroyasu*; Kato, Yutai*

Journal of Nuclear Materials, 545, p.152634_1 - 152634_12, 2021/03

 Times Cited Count:1 Percentile:0.01(Materials Science, Multidisciplinary)

Journal Articles

Diffusion and sorption behavior of HTO, Cs, I and U in mortar

Akagi, Yosuke*; Kato, Hiroyasu*; Tachi, Yukio; Sakamoto, Hiroyuki*

Progress in Nuclear Science and Technology (Internet), 5, p.233 - 236, 2018/11

A large amount of radioactive contaminated concrete will be generated from the decommissioning in the Fukushima Dai-ichi Nuclear Power Plant (NPP). For developing the plans of decommissioning and waste management including decontamination and disposal, it is important to estimate radionuclides inventory and concentration distribution in the concrete materials. In this study, effective diffusivities (De) and distribution coefficients (Kd) of HTO, Cs, I and U in OPC mortar were measured by through-diffusion and batch sorption experiments. De values derived were in the sequence of HTO, I, Cs, U, implying that cation exclusion effects may be important mechanisms in OPC mortar. Kd values derived by batch tests were higher by more than one order of magnitude than the diffusion-derived Kd values, indicating that crushing of samples had a strong influence on sorption. Diffusion and sorption mechanisms in OPC mortar were evaluated to predict the penetration behavior of these radionuclides.

Journal Articles

Hydrogen behavior in primary precipitate of F82H steel; Atomistic calculation based on the density functional theory

Watanabe, Yoshiyuki; Iwakiri, Hirotomo*; Murayoshi, Norihiko*; Kato, Daiji*; Tanigawa, Hiroyasu

Plasma and Fusion Research (Internet), 10, p.1205086_1 - 1205086_2, 2015/12

In this paper, formation energy of isolated hydrogen atom in Cr$$_{23}$$C$$_{6}$$ has been theoretically investigated with atomistic calculation based on the density functional theory. The lowest calculated formation energy of a hydrogen atom is -0.48 eV with a trigonal bipyramidal configuration surrounded by five regular Cr lattice atoms. A comparison of the formation energy of hydrogen atom in bcc-iron may indicate that hydrogen atoms in F82H steel are more energetically favorable in Cr$$_{23}$$C$$_{6}$$-based precipitate rather than Fe-based matrix, leading to an increase of the tritium retention in the precipitate.

Journal Articles

Physical properties of F82H for fusion blanket design

Hirose, Takanori; Nozawa, Takashi; Stoller, R. E.*; Hamaguchi, Dai; Sakasegawa, Hideo; Tanigawa, Hisashi; Tanigawa, Hiroyasu; Enoeda, Mikio; Kato, Yutai*; Snead, L. L.*

Fusion Engineering and Design, 89(7-8), p.1595 - 1599, 2014/10

 Times Cited Count:36 Percentile:95.87(Nuclear Science & Technology)

The material properties, focusing on the properties used for design analysis were re-assessed and newly investigated for various heats including F82H-IEA. Moreover, irradiation effects on those properties were studied in this work. As for thermal properties, thermal conductivity that has significant impacts on the thermo-hydraulic properties of the blanket was investigated on several heats of F82H including F82H-IEA. According to the measurements, the thermal conductivity falls in the range 28.3$$pm$$1.1 W/m/K at 293 K. Although this is comparable with that of the other ferritic/martensitic steels, it is 20% lower than the published value for F82H-IEA. The re-assessment on the published value revealed that the thermal diffusivity was over-estimated. As for irradiation effects on the physical properties, electric resistivity was measured after irradiation up to 6 dpa at 573 K and 673 K. The reduction of resistivity in F82H and its welds were 3% and 6%, respectively.

Journal Articles

Reduction of contaminated concrete waste by recycling aggregate with the aid of pulsed power discharge

Arifi, E.*; Ishimatsu, Koichi*; Iizasa, Shinya*; Namihira, Takao*; Sakamoto, Hiroyuki*; Tachi, Yukio; Kato, Hiroyasu*; Shigeishi, Mitsuhiro*

Construction and Building Materials, 67(Part B), p.192 - 196, 2014/09

 Times Cited Count:3 Percentile:21.67(Construction & Building Technology)

The Fukushima Dai-ichi Nuclear Plant accident has resulted in a large amount of radioactively contaminated concrete. The possible application of the pulsed power discharge to reduce the amount of contaminated concrete as radioactive waste was investigated. The contaminated concrete was decontaminated by separating contaminated matrix from uncontaminated coarse aggregate under pulsed power discharge process. In this study, a stable Cs isotope was used to simulate radioactively contaminated concrete. As a result, while the volume of reclaimed aggregate from contaminated concrete could be reproduced was up to 60%, nevertheless Cs detected in the reclaimed aggregate was only approximately 3%. Thus most of the Cs were dissolved in water during the discharge process. It is expected that the pulsed power could reduce the contaminated concrete waste by reusing aggregate. Further investigations are requested to test the applicability of this method under the realistic conditions close to the actual waste.

Journal Articles

The Effect of alkaline alteration on sorption properties of sedimentary rock

Shimoda, Satoko*; Nakazawa, Toshiyuki*; Kato, Hiroyasu*; Tachi, Yukio; Seida, Yoshimi*

Materials Research Society Symposium Proceedings, Vol.1665, p.179 - 184, 2014/09

The potential effect of alkaline perturbation caused by the cementitious materials must be evaluated in the performance assessment for HLW geological disposal. In this study, sorption of Cs, Ni and Th was investigated using the altered and unaltered samples of sedimentary rock from Horonobe underground research laboratory. The K$$_{rm d}$$ values of Cs, Ni and Th measured by batch method using synthetic groundwater changed as a function of degrees of alteration. The K$$_{rm d}$$ values of Cs increased with increasing degrees of alteration, indicating secondary minerals contributes to the increase in Cs sorption by ion exchange mechanism. On the other hand, the K$$_{rm d}$$ values of Ni and Th decreased with the increase of degrees of alteration. This change may be caused by dissolution of clay minerals controlling Ni and Th sorption by surface complexation. These results imply that the effect of alkaline perturbation on K$$_{rm d}$$ values of rocks depend on the surface property of the altered rock and sorption mechanism.

JAEA Reports

Measurement of sorption, diffusion and pore physicality for granite sample

Kunimaru, Takanori; Morikawa, Keita; Tachi, Yukio; Kuno, Yoshio*; Hosoya, Shinichi*; Shimoda, Satoko*; Kato, Hiroyasu*; Nakazawa, Toshiyuki*; Ikuse, Hiroyuki*; Kubota, Masako*

JAEA-Data/Code 2012-013, 96 Pages, 2012/07

JAEA-Data-Code-2012-013.pdf:7.41MB
JAEA-Data-Code-2012-013(errata).pdf:0.13MB

For the purpose to understand the relationship between characteristic of mass transport and characteristic of fracture, the following experiments were carried out using core sample, which was sampled from the -300 m Stage. This paper compiled the results of these experiment. (1) Diffusion experiments of Cs, Sr, I and uranin in granite samples (2) Sorption experiments of Cs and Sr on crushed granite (3) Measurement of pore physicality by Mercury Intrusion and water saturation

Journal Articles

Single-shot observation of growing streamers using an ultrafast camera

Takahashi, Eiichi*; Kato, Susumu*; Furutani, Hirohide*; Sasaki, Akira; Kishimoto, Yasuaki*; Takada, Kenji*; Matsumura, Satoshi*; Sasaki, Hiroyasu*

Journal of Physics D; Applied Physics, 44(30), p.302001_1 - 302001_4, 2011/08

 Times Cited Count:7 Percentile:33(Physics, Applied)

A recently developed ultrafast camera that can acquire $$10^8$$ frames per second was used to investigate positive streamer discharge. It enabled single-shot evaluation of streamer evolution without the need to consider shot-to-shot reproducibility. This camera was used to investigate streamers in argon. Growing branches, the transition when a streamer forms a return stroke, and related phenomena were clearly observed.

Journal Articles

Irradiation temperature determination of HFIR target capsules using dilatometric analysis of silicon carbide monitors

Hirose, Takanori; Okubo, Nariaki; Tanigawa, Hiroyasu; Kato, Yutai*; Clark, A. M.*; McDuffee, J. L.*; Heatherly, D. W.*; Stoller, R. E.*

DOE/ER-0313/49, p.94 - 99, 2010/12

Journal Articles

Effect of heat treatments on tensile properties of F82H steel irradiated by neutrons

Wakai, Eiichi; Ando, Masami; Sawai, Tomotsugu; Tanigawa, Hiroyasu; Taguchi, Tomitsugu; Stroller, R. E.*; Yamamoto, Toshio; Kato, Yoshiaki; Takada, Fumiki

Journal of Nuclear Materials, 367-370(1), p.74 - 80, 2007/08

 Times Cited Count:9 Percentile:52.85(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Practical Availability of Radionuclide Transport Model based on the Interaction among Radionuclide, Colloid and Rock

Kurosawa, Susumi; Ueda, Shinzo*; Yui, Mikazu; Kato, Hiroyasu*; Hayashi, Kenichi*; *; Yoshikawa, Hideki

Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.460 - 468, 2003/12

None

Journal Articles

Microstructural analysis of mechanically tested reduced activation ferritc/martensitic steels

Tanigawa, Hiroyasu; Hirose, Takanori; Ando, Masami; Jitsukawa, Shiro; Kato, Yudai*; Koyama, Akira*

Journal of Nuclear Materials, 307-311(Part1), p.293 - 298, 2002/12

 Times Cited Count:9 Percentile:52.78(Materials Science, Multidisciplinary)

It has been a key issue to get the mechanical understanding of fracture process on microstructure basis, especially on neutron-irradiated materials, but not yet to be understood well enough as for the difficulty of making transmission electron microscope (TEM) thin film sample from mechanical-tested specimen. To solve this technical problem, the focused ion beam (FIB) micro-sampling system was installed to the Research Hot Laboratory of Japan Atomic Research Institute (JAERI), Japan. This system makes it possible to fabricate the TEM specimens from the critical points of mechanical-tested radioactive specimens, such as the crack initiation points of fatigue fracture on neutron irradiated specimen. In this paper, the microstructure of mechanical-tested specimen of Reduced Activation Ferritic/martensitic steels, RAFs are investigated focusing on the helium effects to fatigue fracture.

Journal Articles

Evaluation of hardening behavior of ion irradiated reduced activation ferritic/martensitic steels by an ultra-micro-indentation technique

Ando, Masami; Tanigawa, Hiroyasu; Jitsukawa, Shiro; Sawai, Tomotsugu; Kato, Yudai*; Koyama, Akira*; Nakamura, Kazuyuki; Takeuchi, Hiroshi

Journal of Nuclear Materials, 307-311(Part1), p.260 - 265, 2002/12

 Times Cited Count:37 Percentile:89.98(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Response of reduced activation ferritic steels to high-fluence ion-irradiation

Tanigawa, Hiroyasu; Ando, Masami; Kato, Yudai*; Hirose, Takanori*; Sakasegawa, Hideo*; Jitsukawa, Shiro; Koyama, Akira*; Iwai, Takeo*

Journal of Nuclear Materials, 297(3), p.279 - 284, 2001/09

 Times Cited Count:33 Percentile:89.66(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Effects of helium implantation on hardness of pure iron and a reduced activation ferritic-martensitic steel

Tanigawa, Hiroyasu; Jitsukawa, Shiro; Hishinuma, Akimichi; Ando, Masami*; Kato, Yudai*; Koyama, Akira*; Iwai, Takeo*

Journal of Nuclear Materials, 283-287(Part.1), p.470 - 473, 2000/12

 Times Cited Count:19 Percentile:76.13(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Study on solubility and leaching property of iodine-129 waste-forms for geological disposal

Yanagisawa, Ichiro*; Katsurai, Kiyomichi*; Izumi, Jun*; Saigusa, Moriyuki*; Kitao, Hideo*; Tsuzuki, Yasuo*; Neyama, Atsushi*; Kato, Hiroyasu*; Nakazawa, Toshiyuki*; Okada, Kenichi*

JNC TJ8400 2000-037, 61 Pages, 2000/02

JNC-TJ8400-2000-037.pdf:2.78MB

no abstracts in English

JAEA Reports

Development of database system for performance assessment (III)

Ueda, Shinzo*; Kato, Hiroyasu*; Kurosawa, Susumu*; Nakazawa, Toshiyuki*

JNC TJ8400 99-032, 338 Pages, 1999/02

JNC-TJ8400-99-032.pdf:8.88MB

JNC is preparing the second Performance Assessment Report for high level waste disposal. This research was carried out to prepare the database and assessment model for nuclide migration analysis for the report. The main results are as follows. (1)Quality assurance of nuclide migration database. Thermodynamic database for formation and complexation of 21 elements was developed. International researchers reviewed the database. The review comments, for example the analogousness of actinide elements, were reflected on the database. (2)Modeling study for bentonite porewater chemistry. The porewater chemistry was modeled with ion exchange reaction and surface complexation reaction. The predicted chemistry was compared with the empirical data. (3)Modeling study for nuclide sorption. The sorptivity of Cs, Ra/Sr, Pb, Ni, Am was modeled with ion exchange reaction and surface complexation reaction. The predicted sorptivity was compared with the empirical data and showed the good agreements. (4)Data acquisition for reliable assessment. Hydraulic tests and colloid transport tests with altered bentonite, nuclide diffusion experiments with bentonite and sorption experiments with rocks and bentonite were carried out. The hydraulic conductivity of the altered bentonite was 1.3$$sim$$5.1$$times$$10$$^{-12}$$m/s, the apparent diffusivities of the actinide elements were in the range of 10$$^{-13}$$$$sim$$$$sim$$10$$^{-14}$$m$$^{2}$$/s, and distribution coefficients of Sm were approximately 6 m$$^{3}$$/kg. (5)Evaluation of colloidal effect on nuclide migration. An evaluation of validity of analytical model for nuclide migration under existence of colloids (Hwang's model), and an analysis of nuclide migration including colloids filtration effect were carried out. As a result, it was indicated that a concept of the Hwang's model were appropriate, and it was suggested that nuclide migration was retarded by colloids filtration.

JAEA Reports

Development of database system for performance assessment (III)

Ueda, Shinzo*; Kato, Hiroyasu*; Kurosawa, Susumu*; Nakazawa, Toshiyuki*

JNC TJ8400 99-030, 54 Pages, 1999/02

JNC-TJ8400-99-030.pdf:1.95MB

JNC is preparing the second Performance Assessment Report for high level waste disposal. This research was carried out to prepare the database and assessment model for nuclide migration analysis for the report. The main results are as follows. (1)Quality assurance of nuclide migration database. Thermodynamic database for formation and complexation of 21 elements was developed. International researchers reviewed the database. The review comments, for example the analogousness of actinide elements, were reflected on the database. (2)Modeling study for bentonite porewater chemistry. The porewater chemistry was modeled with ion exchange reaction and surface complexation reaction. The predicted chemistry was compared with the empirical data. (3)Modeling study for nuclide sorption. The sorptivity of Cs, Ra/Sr, Pb, Ni, Am was modeled with ion exchange reaction and surface complexation reaction. The predicted sorptivity was compared with the empirical data and showed the good agreements. (4)Data acquisition for reliable assessment. Hydraulic tests and colloid transport tests with altered bentonite, nuclide diffusion experiments with bentonite and sorption experiments with rocks and bentonite were carried out. The hydraulic conductivity of the altered bentonite was 1.3$$sim$$5.1$$times$$10$$^{-12}$$m/s, the apparent diffusivities of the actinide elements were in the range of 10$$^{-13}$$$$sim$$$$sim$$10$$^{-14}$$m$$^{2}$$/s, and distribution coefficients of Sm were approximately 6 m$$^{3}$$/kg. (5)Evaluation of colloidal effect on nuclide migration. An evaluation of validity of analytical model for nuclide migration under existence of colloids (Hwang's model), and an analysis of nuclide migration including colloids filtration effect were carried out. As a result, it was indicated that a concept of the Hwang's model were appropriate, and it was suggested that nuclide migration was retarded by colloids filtration.

JAEA Reports

None

Mihara, Morihiro; Ito, Masaru; Kato, Hiroyasu*; Ueda, Shinzo*

PNC TN8410 95-199, 58 Pages, 1995/07

None

Oral presentation

Assessment of data uncertainty on the diffusion coefficients for nuclides in engineered and natural barriers

Sawaguchi, Takuma; Takeda, Seiji; Kozaki, Tamotsu*; Sekioka, Yasushi; Kato, Hiroyasu*; Kimura, Hideo

no journal, , 

no abstracts in English

38 (Records 1-20 displayed on this page)