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Journal Articles

Modelling concrete degradation by coupled non-linear processes

Oda, Chie; Kawama, Daisuke*; Shimizu, Hiroyuki*; Benbow, S. J.*; Hirano, Fumio; Takayama, Yusuke; Takase, Hiroyasu*; Mihara, Morihiro; Honda, Akira

Journal of Advanced Concrete Technology, 19(10), p.1075 - 1087, 2021/10

 Times Cited Count:0 Percentile:0.00(Construction & Building Technology)

Concrete in a transuranic (TRU) waste repository is considered a suitable material to ensure safety, provide structural integrity and retard radionuclide migration after the waste containers fail. In the current study, coupling between chemical, mass-transport and mechanical, so-called non-linear processes that control concrete degradation and crack development were investigated by coupled numerical models. Application of such coupled numerical models allows identification of the dominant non-linear processes that will control long-term concrete degradation and crack development in a TRU waste repository.

Journal Articles

A Coupled modeling simulator for near-field processes in cement engineered barrier systems for radioactive waste disposal

Benbow, S. J.*; Kawama, Daisuke*; Takase, Hiroyasu*; Shimizu, Hiroyuki*; Oda, Chie; Hirano, Fumio; Takayama, Yusuke; Mihara, Morihiro; Honda, Akira

Crystals (Internet), 10(9), p.767_1 - 767_33, 2020/09

 Times Cited Count:2 Percentile:23.05(Crystallography)

Details are presented of the development of a coupled modeling simulator for assessing the evolution in the near-field of a geological repository for radioactive waste disposal where concrete is used as a backfill. The simulator uses OpenMI, a standard for exchanging data between simulation software programs at run-time, to form a coupled chemical-mechanical-hydrogeological model of the system. The approach combines a tunnel scale stress analysis finite element model, a discrete element model for accurately modeling the patterns of emerging cracks in the concrete, and a finite element and finite volume model of the chemical processes and alteration in the porous matrix and cracks in the concrete, to produce a fully coupled model of the system. Combining existing detailed simulation software in this way with OpenMI has the benefit of not relying on simplifications that might be necessary to combine all of the modeled processes in a single piece of software.

Journal Articles

Program of the analysis and research laboratory for Fukushima-Daiichi and advanced techniques to be applied in the laboratory

Sekio, Yoshihiro; Yoshimochi, Hiroshi; Kosaka, Ichiro; Hirano, Hiroyasu; Koyama, Tomozo; Kawamura, Hiroshi

Proceedings of 52nd Annual Meeting of Hot Laboratories and Remote Handling Working Group (HOTLAB 2015) (Internet), 8 Pages, 2015/09

Due to the Fukushima Daiichi Nuclear Power Plant accident in March 2011, the safe and secure implementations of the decommissioning for Fukushima Daiichi Nuclear Power Plant has been positioned as the urgent tasks in Japan. Japan Atomic Energy Agency has a critical mission of analysing radioactive wastes having generated by the accident for long-term storage and disposal methods. This will be performed in two hot laboratories to be constructed in Okuma Analysis and Research Center at Fukushima Daiichi Nuclear Power Plant site. In one laboratory, radioactive wastes such as rubbles and secondary wastes will be treated, whereas debris such as fuel debris and high dose structural materials will be handled in the other laboratory. The detail considerations for advanced techniques and experimental apparatus to be installed are underway.

Journal Articles

Development of short stroke shearing technology for FBR fuel pin

Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Tasaka, Masayuki*; Washiya, Tadahiro; Kobayashi, Tsuguyuki*

Journal of Power and Energy Systems (Internet), 4(1), p.244 - 251, 2010/04

no abstracts in English

Journal Articles

Design and fabrication of the FBR fuel disassembly system

Kitagaki, Toru; Tasaka, Masayuki; Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Washiya, Tadahiro; Kobayashi, Tsuguyuki*

Proceedings of 17th International Conference on Nuclear Engineering (ICONE-17) (CD-ROM), 5 Pages, 2009/06

JAEA has been developing a reliable disassembly system for FBR fuel reprocessing as a part of Fast Reactor Cycle Technology Development (FaCT). We fabricated the disassembly system testing machine. In this paper, we described design of it.

Journal Articles

None

Hirano, Hiroyasu

Saikuru Kiko Giho, (23), 0 Pages, 2004/00

Focusing on the cover layer materials (as the Radon Barrier Materials), which could have the effect to restrain the radon from scattering into the air and the effect of the radiation shielding, we produced the radon barrier materials with crude bentonite on an experimental basis, using the rotary type comprehensive unit for grinding and mixing, through which we carried out the evaluation of the characteristics thereof.

Journal Articles

Waste Minimization in Actinides(III)/Lanthanides(III) Separation Process from High Level Liquid Waste

; Hirano, Hiroyasu; Koyama, Tomozo

OECD/NEA 7th information exchange meeting, 0 Pages, 2002/00

None

Journal Articles

None

Hirano, Hiroyasu; ; ; Koyama, Kenji

Donen Giho, (70), p.104 - 108, 1989/06

Journal Articles

None

; Hirano, Hiroyasu; ; Tanaka, Yasumasa; Kawata, Tomio

International Conference on Envilonmental of Fuel, , 

None

Journal Articles

None

Hirano, Hiroyasu; Nomura, Kazunori; ; ; ;

International Information Exchange Programe on Actinide & Fission Product Separation & Transmutation, , 

None

Journal Articles

None

Hirano, Hiroyasu; ; ; Nomura, Kazunori; ;

International Information Exchange Programe on Actinide & Fission Product Separation & Transmutation, , 

None

Oral presentation

Development of FBR fuel disassembly and pin bundle shearing technology, 14; Short stroke shearing test using simulated fuel pin bundle

Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Kitagaki, Toru; Takeuchi, Masayuki; Washiya, Tadahiro; Kobayashi, Tsuguyuki*

no journal, , 

no abstracts in English

Oral presentation

Effect of operational condition on fluidity in centrifugal contactor

Kunii, Kanako*; Misumi, Ryuta*; Nishi, Kazuhiko*; Kaminoyama, Meguru*; Hirano, Hiroyasu; Ogino, Hideki; Sano, Yuichi

no journal, , 

no abstracts in English

Oral presentation

FaCT phase-I evaluation on advanced aqueous reprocessing process, 5; Uranium crystallization technology for dissolver solution of spent fuel

Shibata, Atsuhiro; Yano, Kimihiko; Sambommatsu, Yuji; Nakahara, Masaumi; Takeuchi, Masayuki; Hirano, Hiroyasu; Nakajima, Yasuo; Washiya, Tadahiro

no journal, , 

no abstracts in English

Oral presentation

Study on ageing behavior of reprocessing plants, 7; Effect of metal ions in heating nitric acid solution on corrosion behavior of Ti-5Ta in nitric acid condensates

Sano, Yuichi; Takeuchi, Masayuki; Hoshi, Masayuki; Sakauchi, Nobuyuki; Hirano, Hiroyasu; Uchiyama, Gunzo; Nojima, Yasuo*; Fujine, Sachio*

no journal, , 

no abstracts in English

Oral presentation

The Effect of rotor speeds and flow rates on the flow pattern in an annular centrifugal extractor

Kunii, Kanako*; Misumi, Ryuta*; Nishi, Kazuhiko*; Kaminoyama, Meguru*; Hirano, Hiroyasu; Ogino, Hideki; Sano, Yuichi

no journal, , 

The flow patterns at 1750 and 3500 rpm of a rotor speed were compared each other. In both cases, the liquid is flowing along a rotational direction of the rotor in the region surrounded by two vanes on the vessel bottom and the vessel wall, and then the liquid goes into the separation zone in the rotor. At lower speed, the mean velocities are roughly proportional to flow rates. At higher speed, the liquid is separated into two regions in the height direction, that is, one of them is near the vanes and another is around a lower side of the rotor. The mean velocities around the vessel bottom are not proportional to flow rates. The reason is inferred that the liquid fed in the vessel takes a shortcut and goes into the rotor instead of passing through between two vanes.

Oral presentation

Effect of scale up condition on fludity in centrifugal contactor

Todoroki, Kei*; Misumi, Ryuta*; Nishi, Kazuhiko*; Kaminoyama, Meguru*; Hirano, Hiroyasu; Ogino, Hideki; Sano, Yuichi; Sakamoto, Atsushi

no journal, , 

no abstracts in English

Oral presentation

Study on ageing behavior of reprocessing plants, 10; Factors controlling Ti-5Ta corrosion in nitric acid condensates

Sano, Yuichi; Takeuchi, Masayuki; Hoshi, Masayuki; Sakauchi, Nobuyuki; Hirano, Hiroyasu; Uchiyama, Gunzo; Nojima, Yasuo*; Fujine, Sachio*

no journal, , 

no abstracts in English

Oral presentation

Analysis of fluid pattern in centrifugal contactor

Sakamoto, Atsushi; Sano, Yuichi; Ogino, Hideki; Hirano, Hiroyasu; Todoroki, Kei*; Misumi, Ryuta*; Nishi, Kazuhiko*; Kaminoyama, Meguru*

no journal, , 

no abstracts in English

Oral presentation

Estimation of fuel debris properties by experimental approach for Fukushima Daiichi NPS

Takano, Masahide; Hirano, Hiroyasu; Yano, Kimihiko; Mitsugi, Takeshi; Washiya, Tadahiro

no journal, , 

Fuel debris was generated in the reactor core in the Fukushima Daiichi Nuclear Power Station (hereafter, 1F) where the severe accident occurred in March, 2011. The information of debris properties is essential in the entire course of the decommissioning work: debris removal process, storage, treatment and disposal. The Japan Atomic Energy Agency (JAEA) is a member of International Research Institute for Nuclear Decommissioning (IRID) who has been conducting studies to estimate the fuel debris properties and to contribute to the decommissioning. In this conference, outline of these research and development in CLADS will be reported.

40 (Records 1-20 displayed on this page)