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Fukahori, Tokio
JAEA-Conf 2020-001, p.17 - 20, 2020/12
After 9 years from the accident at TEPCO Fukushima Daiichi Nuclear Power Station, the "on-site" research and development (R&D) situation has been changed into new phase. It can be considered from understanding to predicting by many direct and indirect measurements and analyses. In this presentation, nuclear data needs for 1F decommissioning are revisited according to these situation. The needs for accident evolution characteristics, criticality management, debris storage, waste management, etc. are considered with the view point of R&D on prediction what is going on and will be happened in each stage of decommissioning.
-ray irradiated polyethylene with KOH treatment and SEM-EDSShimada, Akihiko; Sugimoto, Masaki; Yoshikawa, Masahito
JAEA-Review 2014-050, JAEA Takasaki Annual Report 2013, P. 30, 2015/03
In case of the accelerated ageing test on polymer cable insulation used for the nuclear power facility, it is very important to recognize whether oxygen penetrates in the polymer wholly or not. To confirm this, there are the method by which polymer is soaked in the KOH solution at 70
C for 5 minutes, dried and observed by a SEM-EDS, only for ethylene propylene rubber, one of the polymers. This study is to apply that method for polyethylene. Polyethylene sheet of 2 mm thickness was irradiated by ray at a dose rate of 2 kGy/h for 400 h. A piece of irradiated polyethylene was picked up and the piece was soaked in the KOH solution for 24 h. After that, the piece was observed by a SEM-EDS. At the region within 70 micro meters from the surface, potassium is observed. It means that oxidation is occurred in this region. From now on, optimum soaking time will be examined.
Yasuda, Ryo; Nishino, Yasuharu; Mita, Naoaki; Nakata, Masahito; Harada, Katsuya; Nozawa, Yukio; Amano, Hidetoshi
JAERI-Tech 2002-081, 34 Pages, 2002/10
JAERI-Tech-2002-081.pdf:11.76MB
Information about the fuel behavior under high burn-up operation is needed to assess the safety of the high burn-up fuels. Microstructures in irradiated fuel pellets and Zircaloy tubes influence on their integrity. The fundamental information about microstructures is necessary to estimate the formation mechanism and change in the properties of the fuels.The Field Emission type Scanning Electron Microscope (FE-SEM) has been hence installed at the Reactor Fuel Examination Facility (RFEF). FE-SEM is designed for the remote handling type to use high radioactive materials and has equipments to keep safety for operators. Charctarization tests were carried out using Zircaloy cladding tubes with oxide films and hydrides to confirm machine performance. In the results of the tests, high-resolution images with a magnification of 30,000 were obtained. Those results show that the apparatus is maintained high performance as well as standard type.
Hojo, Kiichi
Purazuma, Kaku Yugo Gakkai-Shi, 72(8), p.760 - 771, 1996/08
no abstracts in English
; ; Yonezawa, Minoru; Kajiro, Tadashi; Mineo, Yukinobu; Habara, Takako; ; ; Habara, Tadashi
Dai-31-Kai Joho Kagaku Gijutsu Kenkyu Shukai Happyo Rombunshu, 0, p.123 - 129, 1995/00
no abstracts in English
E.A.Kenik*; Hojo, Kiichi
Journal of Nuclear Materials, 191-194, p.1331 - 1335, 1992/00
Times Cited Count：38 Percentile：93.34(Materials Science, Multidisciplinary)no abstracts in English
Yanagihara, Satoshi; ; ; Fujiki, Kazuo
1st JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.65 - 70, 1991/00
no abstracts in English
D.R.Champ*; J.O.Jirovec*; J.L.Young*; Kumata, Masahiro
Transport and Mass Exchange Processes in Sand and Gravel Aquifers; Field and Modelling Studies,Vol. 2, p.725 - 736, 1991/00
no abstracts in English
Kobutsugaku Zasshi, 19(5), p.289 - 293, 1990/07
no abstracts in English
Murakami, Yoshio
Enerugi Fuoramu, 0(9), 112 Pages, 1989/00
no abstracts in English
;
FAO/IAEA No Advisory Group Meeting on Decontamination of Animal Feeds by Irradiation Deno Togi Shiryo, p.15 - 31, 1979/00
no abstracts in English
Sakashita, Hiroto*; Kawakami, Taira*; Ono, Ayako; Yoshida, Hiroyuki
no journal, ,
This study measured the critical heat flux on a bottom surface for bottom and volume heated particulate beds, where small spherical metal particles were placed on a 75mm diameter heating surface and internally heated by induction heating. The data were obtained by varying the particle size and the volumetric heated rates in the particulate beds. The CHF on the bottom surface decreases with decreasing the particle size and is unaffected by the volumetric heated rates of the particulate beds. The previously proposed CHF correlations, which were derived based on the assumption that the CHF is triggered by hydrodynamic phenomena of liquid and vapor flows through the particulate beds, are not applicable to the CHF for bottom and volume heated particulate beds.
-ray irradiated polyethylene with KOH treatmentShimada, Akihiko; Sugimoto, Masaki; Yoshikawa, Masahito
no journal, ,
In case of the accelerated ageing test on polymer cable insulation used for the nuclear power facility, it is very important to recognize whether oxygen penetrates in the polymer wholly or not. To confirm this, there are the method by which polymer is soaked in the KOH solution at 70 degree for 5 minutes, dried and observed by a SEM-EDS, only for ethylene propylene rubber, one of the polymers. This study is to apply that method for polyethylene. Polyethylene sheet of 2 mm thickness was irradiated by ray at a dose rate of 2 kGy/h for 400 h. A piece of irradiated polyethylene was picked up and the piece was soaked in the KOH solution for 24 h. After that, the piece was observed by a SEM-EDS. At the region within 70 micro meters from the surface, potassium is observed. It means that oxidation is occurred in this region. From now on, optimum soaking time will be examined.
Yano, Kimihiko; Kitagaki, Toru; Ogino, Hideki; Washiya, Tadahiro; Pascal, P.*; Jean-Fran
ois, H.*; Patricia, C.*; Anne, B.*; Brissonneau, L.*; Brigitte, T.*; et al.
no journal, ,
In a collaborative agreement with Commissariat 
l'
nergie atomique et aux 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.
