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Asakura, Kazuki; Shimomura, Yusuke; Donomae, Yasushi; Abe, Kazuyuki; Kitamura, Ryoichi; Miyakoshi, Hiroyuki; Takamatsu, Misao; Sakamoto, Naoki; Isozaki, Ryosuke; Onishi, Takashi; et al.
JAEA-Review 2021-020, 42 Pages, 2021/10
JAEA-Review-2021-020.pdf:2.95MB
The disposal of radioactive waste from the research facility need to calculate from the radioactivity concentration that based on variously nuclear fuels and materials. In Japan Atomic Energy Agency Oarai Research and Development Institute, the study on considering disposal is being advanced among the facilities which generate radioactive waste as well as the facilities which process radioactive waste. This report summarizes a study result in FY2020 about the evaluation method to determine the radioactivity concentration in radioactive waste on Oarai Research and Development Institute.
Asakura, Kazuki; Shimomura, Yusuke; Donomae, Yasushi; Abe, Kazuyuki; Kitamura, Ryoichi
JAEA-Review 2020-015, 66 Pages, 2020/09
JAEA-Review-2020-015.pdf:4.27MB
The disposal of radioactive waste from the research facility need to calculated from the radioactivity concentration that based on variously nuclear fuels and materials. In Japan Atomic Energy Oarai Research and Development Institute, the study on considering disposal is being advanced among the facilities which generate radioactive waste as well as the facilities which process radioactive waste. This report summarizes a study result in FY2019 about the evaluation method to determine the radioactivity concentration in radioactive waste on Oarai Research and Development Institute.
Ichikawa, Shoichi; Abe, Kazuyuki; Haga, Hiroyuki; Kajima, Hisashi*; Sakurai, Satoshi*; Katsuyama, Kozo; Maeda, Koji; Nishinoiri, Kenji
JAEA-Technology 2011-032, 46 Pages, 2012/01
JAEA-Technology-2011-032.pdf:8.46MB
The assembly technique to the capsular irradiation rig newly developed was established. In the irradiation examination, the assembling disassembling and reassembling to PFB110 "B11(1), B11(2)" and PFB140 "B14" that built in Am-MOX fuel pin was achieved. The reassembly technique by recycling the irradiation material was established in the assembly of B11(2). This time, the assembly and disassembly of B11 (1) were reported. Moreover, the assembly of B14 which improved the assembly technology of B11 (1) was reported.
Abe, Jun; Arakawa, Masashi*; Hattori, Takanori; Arima, Hiroshi; Kagi, Hiroyuki; Komatsu, Kazuki*; Sano, Asami; Uwatoko, Yoshiya*; Matsubayashi, Kazuyuki*; Harjo, S.; et al.
Review of Scientific Instruments, 81(4), p.043910_1 - 043910_5, 2010/04
Times Cited Count：6 Percentile：30.96(Instruments & Instrumentation)A compact cubic-anvil high-pressure device was developed for in situ neutron powder diffraction studies. In this device, a cubic shaped pressure medium is compressed by six anvils, and neutron beam pass through gaps between the anvils. The first high-pressure experiment using this device was conducted at J-PARC and clearly showed the neutron diffraction patterns of Pb. Combining the cubic-anvil high-pressure device with a pulsed neutron source will prove to be a useful tool for neutron diffraction experiments.
Matsui, Yoshinori; Takahashi, Hiroyuki; Yamamoto, Masaya; Nakata, Masahito; Yoshitake, Tsunemitsu; Abe, Kazuyuki; Yoshikawa, Katsunori; Iwamatsu, Shigemi; Ishikawa, Kazuyoshi; Kikuchi, Taiji; et al.
JAEA-Technology 2009-072, 144 Pages, 2010/03
JAEA-Technology-2009-072.pdf:45.01MB
"R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant" was carried out from FY2006 in a fund of a trust enterprise of the Ministry of Education, Culture, Sports, Science and Technology. The coupled irradiations or single irradiation by JOYO fast reactor and JRR-3 thermal reactor were performed for about two years. The irradiation specimens are very important materials to establish of "Evaluation of Irradiation Damage Indicator" in this research. For the acquisition of the examination specimens irradiated by the JOYO and JRR-3, we summarized about the overall plan, the work process and the results for the study to utilize these reactors and some facilities of hot laboratory (WASTEF, JMTR-HL, MMF and FMF) of the Oarai Research-and-Development Center and the Nuclear Science Research Institute in the Japan Atomic Energy Agency.
Ishimi, Akihiro; Katsuyama, Kozo; Abe, Kazuyuki; Nagamine, Tsuyoshi; Nakamura, Yasuo
JAEA-Technology 2009-003, 58 Pages, 2009/05
JAEA-Technology-2009-003.pdf:8.95MB
Japan Atomic Energy Agency executed the irradiation examination of the MA content mixed oxide fuel by Experimental Fast Reactor "JOYO". This examination was used that the mixed oxide fuel that contained Americium by 3% and 5%, and the mixed oxide fuel of Americium and Neptunium that contained 2% for each. The irradiation examination executed a short term irradiation (For ten minutes and 24 hours) by the high linear heat, and achieved maximum linear heat about 430 W/cm in "JOYO". After it had irradiated it, the post irradiation examination of the fuel pin was executed in the Fuels Monitoring facilities. On the results of X ray CT examination, the result that the density decrease is forecast to the vicinity of the center of the fuel was obtained for ten minutes in the irradiation. The formation of the central void was confirmed to the center of the fuel in 24 hour irradiation.
Sasaki, Shinji; Abe, Kazuyuki; Nagamine, Tsuyoshi
JAEA-Conf 2008-010, p.362 - 371, 2008/12
An innovative technique to measure the deformation of irradiated wrapper tube of FBR fuel assembly was developed, and installed in the hot cell of the Fuels Monitoring Facility in JAEA. In order to confirm the performance of this instrument, a number of measurements were carried out in the wrapper tubes irradiated to high burnup in the experimental fast reactor Joyo. In the instrument used until now, only three face to face distances in the hexagonal wrapper tube have been measured along the axial direction. On the other hand, in the instrument developed in this technique the face to face distances could be continuously measured along the lateral direction in the outer surfaces of wrapper tube. Using data obtained by this technique, the detailed analyses of deformation can be done throughout a whole wrapper tube.
Abe, Kazuyuki; Kobayashi, Takashi*; Kajima, Hisashi*; Yoshikawa, Katsunori; Nagamine, Tsuyoshi; Nakamura, Yasuo
JAEA-Technology 2008-008, 53 Pages, 2008/03
JAEA-Technology-2008-008.pdf:19.28MB
MARICO-2 is a Testing Rig for the continuous irradiation examination of ODS ferrite steel etc.. It was necessary to re-assemble of MARICO-2 in Fuel Monitoring Facility (FMF). However, MARICO-2 is not applicable a past technology of re-assembly because it is a Rig of the total length about 11 m and its hex-tube must be welded by remote control. Then, MARICO-2 re-assembly technology development was executed, the device was designed, it produced, and the procedure of re-assembly by remote control was established.
Abe, Kazuyuki; Sasaki, Shinji; Kikuchi, Shin; Katsuyama, Kozo; Nagamine, Tsuyoshi; Matsumoto, Shinichiro
JNC TN9430 2002-003, 52 Pages, 2002/05
JNC-TN9430-2002-003.pdf:2.98MB
Irradiation tests of Absorber Material Irradiation Rig (AMIR) have been continuously conducted, using the experimental fast reactor Joyo. AMIR-6, which was submitted for post-irradiation-examinations (PIE) this time, was irradiated in order to evaluate the limit of failure in control rods and confirm the effect of method for suppression of relocation caused by cracking of boron carbide (B
C) pellets. According to this purpose, gap size between BC pellet and cladding tube (inner capsule tube), enrichment of 
B, thickness of cladding tube and its material were changed in this test. In addition, thin shroud tube wrapping BC pellets was used as the method for suppression of relocation. Capsules were loaded in compartments, which had the upper and lower stairs, and irradiation rig AMIR-6 was constructed of seven compartments in total. The irradiation capsule had double tubes, namely inner capsule tube and outer capsule tube. Between these tubes, sodium was filled. AMIR-6 was irradiated at the 6 raw in Joyo Mark-II core up to 106
10
cap/m
(max. burn-up) and 3.8210 n/m
(max, fluence). Irradiation temperatures were evaluated from 530 to 890 
C in design. Extraordinary results were observed for lower capsules by weight measurement performed. So, detailed visual inspection was carried out for these capsules. Consequently, sodium entered from the crack of screwhead attached to the outer tube in three irradiation capsules, whose weight increased. It was recognized that the sodium level between cladding tube and outer tube was lower in six capsules of lower stairs. Cladding crack was found out in three cladding tubes of lower irradiation capsule. It was suggested that the crack become for decrease of strength of cladding tube because those temperature increased at the position where sodium was not filled. The irradiation capsule using a shroud tube showed no diameter increase and ovality in the cladding.
; Abe, Kazuyuki; ; Matsumoto, Shinichiro
JNC TN9410 2002-011, 36 Pages, 2002/04
JNC-TN9410-2002-011.pdf:1.34MB
In the place adjacent to the Fuel Monitoring Faciliy (FMF) in the O-arai Engineering Center, FMF-Extension was constructed to examine large subassemblies irradiated in the prototype fast breeder reactor "MONJU" and so on. Until now, in order to confirm the performances of subassembly vertical examination machine, which is one of main apparatus installed in FMF-Extension, it has been experimentally conducted, to measure six subassemblies irradiated in the experimental fast reactor "JOYO". This machine has multi-functions such as appearance inspection, various size measurements and dismantling a subassembly. As to the size measurements, it is possible to measure subassembly length, hexagonal wrapper tube face-to-face distance, corner-to-comer distance, bowing and twisting automatically. Furthermore, this machine has a function of grasping the cross section form of hexagonal wrapper tube, using a new special tool. The results measured by this machine were compared with the data of the same subassemblies with the exiting machine in FMF, which was calibrated already. For the date of subassembly length, hexagonal wrapper tube face-to-face distance and corner-to-corner distance, the difference of both machines was within a measurement error. In some results of bowing, the difference was over 1mm. It was thought that the difference was not a considerable error when taking into account the characteristics of these machines that the error was easy to propagate. The results of cross section from of hexagonal wrapper tube newly introduced in this machine were in a good agreement within a measurement error, compared with the data calculated on the basis of size measurement results. The existing machine in FMF could not treat this cross section form measurement.
Yamanaka, Shinsuke*; Abe, Kazuyuki
JNC TY9400 2000-004, 78 Pages, 2000/03
JNC-TY9400-2000-004.pdf:2.39MB
no abstracts in English
; Abe, Kazuyuki; Sato, Isamu
Journal of Nuclear Materials, 281(-), p.117 - 128, 2000/00
Times Cited Count：17 Percentile：72(Materials Science, Multidisciplinary)None
Kajitani, Yukio; ; Abe, Kazuyuki; Osaka, Masahiko; ; Hirosawa, Takashi; Koyama, Shinichi
PNC TN9440 97-004, 186 Pages, 1997/02
The 25th anniversary meeting of the Alpha-Gamma Facility (AGF) at O-arai Engineering Center of PNC was held on February 7. The AGF started to examine irradiated materials on october 1 and fuel pins irradiated in the Dounreay Fast Reactor, DFR332/2 on December 1, 1971. The contents in this paper of the anniversary meeting are as follows. (1)25 years history and challenging plan for 2000 year. (2)Maintenance logbook of the facility, apparatus and manipulators for 25 years. (3)Recent results of melting temperature, thermal conductivity and lattice constants in irradiated MOX fuels. (4)Development on fission products release measuring apparatus and results of cold run tests. (5)Post irradiated examination results operated at the metallography cell in the Fuels Monitoring Facility (FMF). (6)Development on chemical analysis method for minor actinides (MA) in irradiated MOX fuels. (7)Refurbishment for MA containing MOX fuels, status and specifications for the fabrication and quality control apparatus.
; Murakami, Yoshio; ; Hiroki, S.; ; *; *; *
Journal of Nuclear Materials, 133-134, p.754 - 759, 1985/00
Times Cited Count：16 Percentile：85.3(Materials Science, Multidisciplinary)no abstracts in English
Hiroki, S.; *; ; ; ; Murakami, Yoshio
Shinku, 28(5), p.300 - 303, 1985/00
no abstracts in English
; ; Hiroki, S.; ; Murakami, Yoshio
Shinku, 27(5), p.339 - 342, 1984/00
no abstracts in English
; ; Murakami, Yoshio
Shinku, 27(5), p.410 - 413, 1984/00
no abstracts in English
Hiroki, S.; ; *; ; ; Murakami, Yoshio
Shinku, 27(5), p.386 - 388, 1984/00
no abstracts in English
; Murakami, Yoshio; ; Hiroki, S.; ; *; *; *; *
Shinku, 27(5), p.394 - 397, 1984/00
no abstracts in English
Murakami, Yoshio; ; ; *
JAERI-M 8513, 40 Pages, 1979/10
no abstracts in English
