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Komuro, Michiyasu; Kanazawa, Hiroyuki; Kokusen, Junya; Shimizu, Osamu; Honda, Junichi; Harada, Katsuya; Otobe, Haruyoshi; Nakada, Masami; Inagawa, Jun
JAEA-Technology 2021-042, 197 Pages, 2022/03
JAEA-Technology-2021-042.pdf:16.87MB
Plutonium Research Building No.1 was constructed in 1960 for the purpose of establishing plutonium handling technology and studying its basic physical properties. Radiochemical research, physicochemical research and analytical chemistry regarding solutions and solid plutonium compounds had been doing for the research program in Japan Atomic Energy Agency (JAEA). In 1964, the laboratory building was expanded and started the researching plutonium-uranium mixed fuel and reprocessing of plutonium-based fuel, playing an advanced role in plutonium-related research in Japan. Since then, the research target has been expanded to include transplutonium elements, and it has functioned as a basic research facility for actinides. The laboratory is constructed by concrete structure and it has the second floor, equipped with 15 glove boxes and 4 chemical hoods. Plutonium Research Building No.1 was decided as one of the facilities to be decommissioned by Japan Atomic Energy Agency Reform Plan in September 2014. So far, the contamination survey of the radioactive materials in the controlled area, the decontamination of glove boxes, and the consideration of the equipment dismantling procedure have been performed as planned. The radioisotope and nuclear fuel materials used in the facility have been transfer to the other facilities in JAEA. The decommissioning of the facility is proceeding with the goal of completing by decommissioning the radiation controlled area in 2026. In this report, the details of the decommissioning plan and the past achievements are reported with the several data.
Kokusen, Junya; Akasaka, Shingo*; Shimizu, Osamu; Kanazawa, Hiroyuki; Honda, Junichi; Harada, Katsuya; Okamoto, Hisato
JAEA-Technology 2020-011, 70 Pages, 2020/10
JAEA-Technology-2020-011.pdf:3.37MB
The Uranium Enrichment Laboratory in the Japan Atomic Energy Agency (JAEA) was constructed in 1972 for the purpose of uranium enrichment research. The smoke emitting accident on 1989 and the fire accident on 1997 had been happened in this facility. The research on uranium enrichment was completed in JFY1998. The decommissioning work was started including the transfer of the nuclear fuel material to the other facility in JFY2012. The decommissioning work was completed in JFY2019 which are consisting of removing the hood, dismantlement of wall and ceiling with contamination caused by fire accident. The releasing the controlled area was performed after the confirmation of any contamination is not remained in the target area. The radioactive waste was generated while decommissioning, burnable and non-flammable are 1.7t and 69.5t respectively. The Laboratory will be used as a general facility for cold experiments.
Honda, Junichi; Matsui, Hiroki; Harada, Akio; Obata, Hiroki; Tomita, Takeshi
JAEA-Technology 2012-022, 35 Pages, 2012/07
JAEA-Technology-2012-022.pdf:3.58MB
The advanced utilization of Light Water Reactor (LWR) fuel is progressed in Japan to save the power generating cost and the volume of nuclear wastes. The electric power companies have been continued the approach to extend the burnup and to rise up the thermal power of the commercial fuel. The government should be accumulating the detailed information of the newest technologies to make the regulations and guidelines for the safety of the advanced nuclear fuels. The remote controlled Electron Prove Micro Analyzer attached with crystal orientation analyzer (EPMA) has been developed in Japan Atomic Energy Agency (JAEA) to evaluate the fuel behavior effected by the cladding microstructure under the accident condition. The device was modified to the airtight and earthquake resistant structure for the examination of high radioactive elements. This paper describes the specification of EPMA and the test results of the cold mock-up to confirm their performances and reliabilities.
Honda, Junichi; Matsui, Hiroki; Harada, Akio; Obata, Hiroki; Tomita, Takeshi
JAEA-Technology 2012-021, 17 Pages, 2012/07
JAEA-Technology-2012-021.pdf:4.17MB
The advanced utilization of Light Water Reactor (LWR) fuel is progressed in Japan to save the power generating cost and the volume of nuclear wastes. The electric power companies have been continued the approach to extend the burnup and to rise up the thermal power of the commercial fuel. The government should be accumulating the detailed information of the newest technologies to make the regulations and guidelines for the safety of the advanced nuclear fuels. The ion milling for post irradiation examination has been developed in Japan Atomic Energy Agency (JAEA) to investigate cladding microstructure. This device has been modified to operate the high radioactive elements remotely and have the performance of earthquake resistant. This paper describes the specification of the device which were specialized for post irradiation examination and the test results of the cold mock-up to confirm their performances and reliabilities.
Onozawa, Atsushi; Harada, Akio; Honda, Junichi; Nakata, Masahito; Kanazawa, Hiroyuki; Sagawa, Tamio
JAEA-Conf 2008-010, p.325 - 332, 2008/12
The measurement technique for hydrogen concentration using Backscattered Electron Image analysis (BEI method) had been developed by Studsvik Nuclear AB. The hydride in claddings is identified using BEIs with SEM and the hydrogen concentration is calculated from the area fractions of the hydride in those BEIs. In the RFEF, the sample polishing techniques and image processing procedure for BEI method were improved to measure the hydrogen concentration in the irradiated fuel claddings more precisely. In the previous tests using the un-irradiated fuel claddings, it is confirmed improved BEI method has high reliability. The radial and axial hydrogen concentration profiles of the irradiated fuel claddings were measured with improved BEI method. As the results of these measurements, the local hydrogen concentration could be indicated more precisely with the improved BEI method compared to the other methods for the hydrogen concentration measurement and observation.
Iwai, Takashi; Nakajima, Kunihisa; Kikuchi, Hironobu; Honda, Junichi; Hatakeyama, Yuichi; Ono, Katsuto; Matsui, Hiroki; Arai, Yasuo
JAEA-Research 2007-026, 75 Pages, 2007/03
JAEA-Research-2007-026.pdf:13.6MB
A plutonium nitiride fuel pin containing inert matrix such as ZrN and TiN was encapsuled in 01F-51A and irradiated in JMTR. Minor actinides are surrogated by plutonium. Average linear powers and burnups were 408W/cm, 30000MWd/t(Zr+Pu)(132000MWd/t-Pu) for (Zr,Pu)N and 355W/cm, 38000MWd/t(Ti+Pu)(153000MWd/t-Pu) for (TiN,PuN). The irradiated capsule was transported to Reactor Fuel Examination Facility and subjected to non-destructive and destructive post irradiation examinations. Any failure was not observed in theirradiated fuel pin. Very low fission gas release rate of about 1.6% was measured. The inner surface of cladding tube did not show any signs of chemical interaction with fuel pellets.
Onozawa, Atsushi; Harada, Akio; Honda, Junichi; Yasuda, Ryo; Nakata, Masahito; Kanazawa, Hiroyuki; Nishino, Yasuharu
JAEA-Conf 2006-003, p.212 - 221, 2006/05
In the Reactor Fuel Examination Facility (RFEF), a measuring method of hydrogen concentration by backscattered electron image analysis was improved to obtain more local hydrogen concentration data in fuel claddings. The sample preparation and image analysis procedures of this were able to measure hydrogen concentration efficiently and precisely.
Onozawa, Atsushi; Harada, Akio; Honda, Junichi; Yasuda, Ryo; Nakata, Masahito; Kanazawa, Hiroyuki; Nishino, Yasuharu
JAEA-Technology 2006-010, 19 Pages, 2006/03
JAEA-Technology-2006-010.pdf:2.3MB
A measurement technique for hydrogen concentration using Backscattered Electron Image analysis (BEI method) had been developed by Studsvik Nuclear AB, Sweden. The hydrides in claddings are identified using BEIs which are imaged with Scanning Electron Microscope, and the hydrogen concentrations are calculated from the area fractions of the hydrides in the matrix. The BEI method is very useful for the measurement in local hydrogen concentrations of fuel claddings. In the Reactor Fuel Examination Facility, a sample preparation, imaging conditions of SEM and image analysis procedures for the BEI method were improved. In addition, the hydrogen concentrations obtained by the improved BEI method and Hot Vacuum Extraction (HVE) method were compared to confirm the reliability of the improved BEI method. The results showed, the improved BEI method has the same reliability as that of HVE method and can be applied for the Post-Irradiation Examination.
Kizaki, Minoru; Honda, Junichi; Usami, Koji; Ouchi, Asao*; Oeda, Etsuro; Matsumoto, Seiichiro
JAERI-Tech 2000-087, 50 Pages, 2001/02
JAERI-Tech-2000-087.pdf:2.78MB
no abstracts in English
Hamada, Kazuya; Kato, Takashi; Kawano, Katsumi; *; *; *; Imahashi, Koichi*; Otsu, K.*; Tajiri, F.*; Ouchi, T.*; et al.
Teion Kogaku, 33(7), p.467 - 472, 1998/00
no abstracts in English
Yanagisawa, Kazuaki; Katanishi, Shoji; *; Sasajima, Hideo; ; Horiki, Oichiro; Mimura, Hideaki; ; ; ; et al.
JAERI-M 92-015, 211 Pages, 1992/02
no abstracts in English
Yanagisawa, Kazuaki; Sasajima, Hideo; Katanishi, Shoji; *; ; Horiki, Oichiro; Mimura, Hideaki; ; ; ; et al.
JAERI-M 91-220, 186 Pages, 1992/01
no abstracts in English
Yanagisawa, Kazuaki; ; Sasajima, Hideo; ; ; Ishijima, Kiyomi; ; ; ; ; et al.
JAERI-M 90-091, 171 Pages, 1990/06
no abstracts in English
Shirasu, Noriko; Kuramoto, Kenichi*; Yamashita, Toshiyuki; Honda, Junichi; Hatakeyama, Yuichi; Ichise, Kenichi
no journal, ,
no abstracts in English
Matsui, Hiroki; Iwai, Takashi; Honda, Junichi; Hatakeyama, Yuichi; Mita, Naoaki; Arai, Yasuo
no journal, ,
no abstracts in English
Nakamura, Jinichi; Amaya, Masaki; Honda, Junichi; Hatakeyama, Yuichi; Fuketa, Toyoshi; Kinoshita, Motoyasu*
no journal, ,
Based on the micro-X-ray diffraction results, lattice parameters and diffraction peak broadenings (increase of FWHM of diffraction peak) of high burnup UO
pellets were measured. Crystallite diameter, which corresponds to subdivided grain diameter, and strain distribution between crystallites can be evaluated from the increase of FWHM of diffraction peak by using Willamson-Hall method. Basesd on these data, the crystal microstructural change during irradiation was examined and the effects of irradiation for microstructure.
Sugiyama, Tomoyuki; Tomiyasu, Kunihiko; Sasajima, Hideo; Umeda, Miki; Nagase, Fumihisa; Fuketa, Toyoshi; Okawara, Masami; Honda, Junichi
no journal, ,
no abstracts in English
Onozawa, Atsushi; Harada, Akio; Honda, Junichi; Yasuda, Ryo; Nakata, Masahito; Kanazawa, Hiroyuki; Nishino, Yasuharu
no journal, ,
Honda, Junichi; Onozawa, Atsushi; Fuketa, Toyoshi; Udagawa, Yutaka; Mita, Naoaki; Kikuchi, Hiroyuki
no journal, ,
no abstracts in English
Matsui, Hiroki; Honda, Junichi; Ono, Katsuto; Kitagawa, Isamu; Owada, Isao; Kikuchi, Hiroyuki
no journal, ,
