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Journal Articles

Multi-aspect characterization of low-temperature tempering behaviors in high-carbon martensite

Zhang, Y.*; Marusawa, Kenji*; Kudo, Kohei*; Morooka, Satoshi; Harjo, S.; Miyamoto, Goro*; Furuhara, Tadashi*

ISIJ International, 64(2), p.245 - 256, 2024/01

Journal Articles

Chemical composition of aerosols generated by heating prototypic fuel debris samples

Journeau, C.*; Delacroix, J.*; Gu$'e$var, C.*; Testud, V.*; Brackx, E.*; Porcheron, E.*; Bouland, A.*; Berlemont, R.*; Ikeda, Atsushi

Science Talks (Internet), 6, p.100215_1 - 100215_9, 2023/05

JAEA Reports

Study on rational treatment/disposal of contaminated concrete waste considering leaching alteration (Contract research); FY2021 Nuclear Energy Science & Technology and Human Resource Development Project

Collaborative Laboratories for Advanced Decommissioning Science; Hokkaido University*

JAEA-Review 2022-038, 102 Pages, 2023/01

JAEA-Review-2022-038.pdf:4.76MB

The Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Japan Atomic Energy Agency (JAEA), had been conducting the Nuclear Energy Science & Technology and Human Resource Development Project (hereafter referred to "the Project") in FY2021. The Project aims to contribute to solving problems in the nuclear energy field represented by the decommissioning of the Fukushima Daiichi Nuclear Power Station, Tokyo Electric Power Company Holdings, Inc. (TEPCO). For this purpose, intelligence was collected from all over the world, and basic research and human resource development were promoted by closely integrating/collaborating knowledge and experiences in various fields beyond the barrier of conventional organizations and research fields. The sponsor of the Project was moved from the Ministry of Education, Culture, Sports, Science and Technology to JAEA since the newly adopted proposals in FY2018. On this occasion, JAEA constructed a new research system where JAEA-academia collaboration is reinforced and medium-to-long term research/development and human resource development contributing to the decommissioning are stably and consecutively implemented. Among the adopted proposals in FY2020, this report summarizes the research results of the "Study on rational treatment/disposal of contaminated concrete waste considering leaching alteration" conducted in FY2021. The present study aims to understand migration behaviors of radionuclides in relation to the properties of concrete altered by leaching, to develop a model to predict concentration profiles, and to analyze waste management scenarios, with a focus on underground concrete structures in contact with contaminated water. Migration behaviors depend on radionuclides and their chemical species. Sorption of I$$^{-}$$ is less significant on C-S-H and C-A-S-H than on hardened cement paste with two orders of magnitude smaller distribution coefficient $$K_{d}$$, while $$K_{d}$$ of U was the same …

Journal Articles

A Multi-technique tomography-based approach for non-invasive characterization of additive manufacturing components in view of vacuum/UHV applications; Preliminary results

Grazzi, F.*; Cialdai, C.*; Manetti, M.*; Massi, M.*; Morigi, M. P.*; Bettuzzi, M.*; Brancaccio, R.*; Albertin, F.*; Shinohara, Takenao; Kai, Tetsuya; et al.

Rendiconti Lincei. Scienze Fisiche e Naturali, 32(3), p.463 - 477, 2021/09

 Times Cited Count:3 Percentile:22.01(Multidisciplinary Sciences)

Journal Articles

Neutron diffraction study on full-shape Japanese sword

Harjo, S.; Kawasaki, Takuro; Grazzi, F.*; Shinohara, Takenao; Tanaka, Manako*

Materialia, 7, p.100377_1 - 100377_9, 2019/09

Journal Articles

Development of security and safety fuel for Pu-burner HTGR; Test and characterization for ZrC coating

Ueta, Shohei; Aihara, Jun; Goto, Minoru; Tachibana, Yukio; Okamoto, Koji*

Mechanical Engineering Journal (Internet), 5(5), p.18-00084_1 - 18-00084_9, 2018/10

To develop the security and safety fuel (3S-TRISO fuel) for Pu-burner high temperature gas-cooled reactor (HTGR), R&D on zirconium carbide (ZrC) directly coated on yttria stabilized zirconia (YSZ) has been started in the Japanese fiscal year 2015. As results of the direct coating test of ZrC on the dummy YSZ particle, ZrC layers with 18 - 21 microns of thicknesses have been obtained with 0.1 kg of particle loading weight. No deterioration of YSZ exposed by source gases of ZrC bromide process was observed by Scanning Transmission Electron Microscope (STEM).

Journal Articles

Study on Pu-burner high temperature gas-cooled reactor in Japan; Test and characterization for ZrC coating

Ueta, Shohei; Aihara, Jun; Mizuta, Naoki; Goto, Minoru; Fukaya, Yuji; Tachibana, Yukio; Okamoto, Koji*

Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive), 7 Pages, 2018/10

The security and safety fuel (3S-TRISO fuel) employs the coated fuel particle with a fuel kernel made of plutonium dioxide (PuO$$_{2}$$) and yttria stabilized zirconia (YSZ) as an inert matrix. Especially, a zirconium carbide (ZrC) coating is one of key technologies of the 3S-TRISO, which performs as an oxygen getter to reduce the fuel failure due to internal pressure during the irradiation. R&Ds on ZrC coating directly on the dummy CeO$$_{2}$$-YSZ kernel have been carried in the Japanese fiscal year 2017. As results of ZrC coating tests by the bromide chemical vapor deposition process, stoichiometric ZrC coatings with 3 - 18 microns of thicknesses were obtained with 0.1 kg of particle loading weight.

Journal Articles

Development of security and safety fuel for Pu-burner HTGR, 5; Test and characterization for ZrC coating

Ueta, Shohei; Aihara, Jun; Goto, Minoru; Tachibana, Yukio; Okamoto, Koji*

Proceedings of 25th International Conference on Nuclear Engineering (ICONE-25) (CD-ROM), 4 Pages, 2017/07

To develop the security and safety fuel (3S-TRISO fuel) for Pu-burner high temperature gas-cooled reactor (HTGR), R&D on zirconium carbide (ZrC) directly coated on yttria stabilized zirconia (YSZ) has been started in the Japanese fiscal year 2015. As results of the direct coating test of ZrC on the dummy YSZ particle, ZrC layers with 18 - 21 microns of thicknesses have been obtained with 0.1 kg of particle loading weight. No deterioration of YSZ exposed by source gases of ZrC bromide process was observed by Scanning Transmission Electron Microscope (STEM).

Journal Articles

Characterization of cryogenically cooled dual symmetric silicon geometry, Si(111)/Si(311), for the double-crystal monochromator on BL11XU at SPring-8

Tozawa, Kazukiyo*; Kiriyama, Koji*; Mitsui, Takaya; Shiwaku, Hideaki; Harami, Taikan

AIP Conference Proceedings 705, p.671 - 674, 2004/00

Liquid-N$$_{2}$$-cooled Si crystals replaced water-cooled diamond crystals for the double-crystal monochromator on BL11XU at SPring-8. To use the whole energy from 6keV to 70keV, we adopted the system of alternative dual symmetric Si geometry, Si(111)/Si(311), which can be switched by a horizontal translation (X) stage perpendicular to the beam axis. Before the experiment on BL11XU, the off-line evaluation was performed to estimate the degree of the crystal strain, which may arise from the way of assembling. With MoK$$alpha$$$$_{1}$$, rocking curves from the crystals were measured for the second crystal of the double-crystal diffractometer of parallel setting. Each of the observed FWHM was almost constant and identical to the calculated value wherever X-rays hit on the crystal surface. By the use of synchrotron radiation from the undulator the crystals were tested and then the characterization was performed. The observed intensities and rocking curves resulted in that each crystal was good for BL11XU and that the performance of X-ray reflection was improved.

JAEA Reports

Proceedings of the 3rd International Symposium on Material Chemistry in Nuclear Environment (MATERIAL CHEMISTRY '02, MC '02); March 13-15, 2002, Tsukuba

MC'02 Sympsoium Committee

JAERI-Conf 2003-001, 451 Pages, 2003/05

JAERI-Conf-2003-001.pdf:30.73MB

The volume contains all presented papers during the the 3rd International Symposium on Material Chemistry in Nuclear Environment: MATERIAL CHEMISTRY '02 (MC'02), held March 13-15, 2002. The purpose of this symposium is to provide an international forum for the discussion of recent progress in the field of materials chemistry in nuclear environments. This symposium intends to build on the success of the previous symposiums held in Tsukuba in 1992 and 1996. The topics discussed in the symposium MC'02 are Chemical Reaction and Thermodynamics, Degradation Phenomena, New Characterization Technology, Fabrication and New Materials, Composite Materials, Surface Modification, and Computational Science.

Journal Articles

Characterization and evaluation studies on some JAERI dosimetry systems

Kojima, Takuji; Sunaga, Hiromi; Tachibana, Hiroyuki; Takizawa, Haruki; Tanaka, Ryuichi

IAEA-TECDOC-156, p.91 - 98, 2000/06

no abstracts in English

Journal Articles

Development of a new method for high temperature in-core characterization of solid surfaces

Yamawaki, Michio*; Suzuki, Atsushi*; Yokota, Toshihiko*; Luo, G.*; Yamaguchi, Kenji*; Hayashi, Kimio

Proceedings of 1st Information Exchange Meeting on Basic Studies on High-Temperature Engineering, p.357 - 364, 1999/09

no abstracts in English

JAEA Reports

HRB-22 capsule irradiation test for HTGR fuel; JAERI/USDOE collaborative irradiation test

Minato, Kazuo; Sawa, Kazuhiro; Fukuda, Kosaku; Baldwin, C. A.*; Gabbard, W. A.*; O.F.Kimball*; Malone, C. M.*; F.C.Montgomery*; B.F.Myers*; N.H.Packan*

JAERI-Research 98-021, 187 Pages, 1998/03

JAERI-Research-98-021.pdf:13.23MB

no abstracts in English

JAEA Reports

Sample preparation and characterization of technetium metal

Minato, Kazuo; Serizawa, Hiroyuki; Fukuda, Kosaku; Ito, Mitsuo

JAERI-Research 97-077, 17 Pages, 1997/10

JAERI-Research-97-077.pdf:1.09MB

no abstracts in English

Journal Articles

Characterization of natural and synthesized FeTiO$$_{3}$$ crystals with RBS/PIXE/XRD

R.Q.Zhang*; Yamamoto, Shunya; Dai, Z.*; Narumi, Kazumasa; Aoki, Yasushi*; Naramoto, Hiroshi; Miyashita, Atsumi

International Journal of PIXE, 7(3&4), p.265 - 275, 1997/00

no abstracts in English

JAEA Reports

Preirradiation characterization of HTGR fuel for HRB-22 capsule irradiation test; JAERI/USDOE collaborative irradiation test for HTGR fuel

Minato, Kazuo; ; Sawa, Kazuhiro; Tobita, Tsutomu; Fukuda, Kosaku

JAERI-Tech 95-056, 45 Pages, 1996/01

JAERI-Tech-95-056.pdf:3.02MB

no abstracts in English

Journal Articles

Application of high-performance gel permeation chromatography to aquatic humic substances in natural waters

Nagao, Seiya;

Humic Substances and Organic Matter in soil and Water Environments: Characterization,Transformations, 0, p.71 - 79, 1996/00

no abstracts in English

Journal Articles

ROSA/AP600 characterization tests and analysis of 1-inch cold leg break test

R.R.Schultz*; J.M.Cozzuol*; R.A.Shaw*; Yonomoto, Taisuke; Kukita, Yutaka

NUREG/CP-0140 (Vol. 2), 0, p.217 - 238, 1995/00

no abstracts in English

JAEA Reports

On fabrication of UO$$_{2}$$ microspheres by internal gelation process

X.Cao*; Minato, Kazuo; Kobayashi, Fumiaki; Fukuda, Kosaku

JAERI-M 89-180, 14 Pages, 1989/11

JAERI-M-89-180.pdf:0.88MB

no abstracts in English

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