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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

Journal Articles

Oral presentation

Characterization of fuel debris (27'A), 8; Characterization of MCCI test products for post severe accident

Yano, Kimihiko; Kitagaki, Toru; Ogino, Hideki; Washiya, Tadahiro; Pascal, P.*; Jean-Fran$c{c}$ois, H.*; Patricia, C.*; Anne, B.*; Brissonneau, L.*; Brigitte, T.*; et al.

no journal, , 

In a collaborative agreement with Commissariat $`a$ l'$'e$nergie atomique et aux $'e$nergies alternatives (CEA), the characterization of MCCI products was carried out using the materials that CEA produced in its past large-scale MCCI test. Samples of a corium oxide phase and an interface of corium/concrete phases were selected. They were observed by SEM/EDS and measured by Vickers Hardness Tester.

Oral presentation

Isolation and characterization of a novel fermentative bacterium in the phylum Bacteroidetes from a deep subsurface diatomaceous mudstone formation

Tamazawa, Satoshi*; Ueno, Akio*; Tamaki, Hideyuki*; Tamamura, Shuji*; Murakami, Takuma*; Kiyama, Tamotsu*; Inomata, Hidenori*; Miyakawa, Kazuya; Naganuma, Takeshi*; Kaneko, Katsuhiko*

no journal, , 

no abstracts in English

Oral presentation

Characterization of sludge generated from decontamination device in Fukushima Daiichi NPS

Hinai, Hiroshi; Sato, Daisuke; Shibata, Atsuhiro; Myodo, Masato; Koma, Yoshikazu; Nomura, Kazunori

no journal, , 

We have been analyzing and characterizing the contaminated water generated in Fukushima Daiichi Nuclear Power Station (NPS) and secondary waste of the contaminated water treatment system for investigation of their waste management. As one of the contaminated water treatment system, Decontamination Device was operated from June until September 2011. The operation of this device generated secondary waste of sludge that have a high dose rate. In this device, the contaminated water was mixed with several reagents to remove some radioactive nuclides. As the result, the sludge was generated as a complex of chemically stable substances. This sludge has been stored in a concrete pit and is required to transport to another place of the site and treat for further storage. For the purposes and upcoming disposal, a small amount of the sludge was analyzed for its radioactivity, particle size distribution and others. For radiochemical analysis, the sludge was successfully dissolved into solutions and was measured for its radioactivity composition; the main nuclides were Sr-90 and Cs-137. The concentration of Sr-90 (6.6E7 [Bq/cm$$^{3}$$]) was about 10 times higher than that of Cs-137 in the sludge. And small amount of Pu-238 as alpha-ray emitting nuclide was determined. The sludge mainly contained small particles of 10 micro meter or less in diameter. The rate of sedimentation and behavior of mixing also investigated.

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