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Journal Articles

Upgrading of X-ray CT technology for analyses of irradiated FBR MOX fuel

Ishimi, Akihiro; Katsuyama, Kozo; Maeda, Koji; Nagamine, Tsuyoshi; Asaka, Takeo; Furuya, Hirotaka

Journal of Nuclear Science and Technology, 49(12), p.1144 - 1155, 2012/12

 Times Cited Count:7 Percentile:53.66(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis on the co-localization of asbestos bodies and Fas or CD163 expression in asbestos lung tissue by in-air micro-PIXE

Dobashi, Kunio*; Shimizu, Yasuo*; Matsuzaki, Shinichi*; Nagamine, Takeaki*; Sato, Takahiro; Okubo, Takeru; Yokoyama, Akihito; Ishii, Yasuyuki; Kamiya, Tomihiro; Arakawa, Kazuo*; et al.

JAEA-Review 2011-043, JAEA Takasaki Annual Report 2010, P. 87, 2012/01

JAEA Reports

Establishment of the disassembling technique of the driver fuel assembly irradiated in JOYO

Ichikawa, Shoichi; Haga, Hiroyuki; Kikukawa, Kiyohide*; Fukasaku, Hironobu*; Kurosawa, Yoichi*; Katsuyama, Kozo; Maeda, Koji; Nagamine, Tsuyoshi

JAEA-Technology 2011-020, 32 Pages, 2011/07

JAEA-Technology-2011-020.pdf:6.56MB

Disassembling technique of the driver fuel assembly irradiated in the experimental fast reactor JOYO has been established at Fuel Monitoring Facility in JAEA. This technique made it possible to remove the fuel pins from the driver fuel assembly without the fuel pin sectioning. After disassembling the fuel assembly, some selected fuel pins can be reassembled into the new irradiation vehicle for the continuous irradiation at JOYO. This technique enables us to obtain the irradiation data of high burn-up fuel and high neutron dose material.

Journal Articles

Development of the high resolution X-ray CT technique

Katsuyama, Kozo; Ishimi, Akihiro; Nagamine, Tsuyoshi; Asaka, Takeo

Kensa Gijutsu, 16(2), p.12 - 18, 2011/02

no abstracts in English

Journal Articles

Application of X-ray computer tomography for observing the central void formations and the fuel pin deformations of irradiated FBR fuel assemblies

Katsuyama, Kozo; Nagamine, Tsuyoshi; Furuya, Hirotaka

IEEE Transactions on Instrumentation and Measurement, 57(5), p.2714 - 2718, 2010/10

In order to observe the structural change in the interior of irradiated fuel assembly, the non-destructive post irradiation examination technique using X-ray computer tomography (X-ray CT) was developed. In this X-ray CT system, the 12 MeV X-ray pulses was used in synchronization with the switch-in of the detector to minimize the effects of the $$gamma$$ ray emissions from the irradiated fuel assembly, and then clear cross section CT image could be successfully obtained.

Journal Articles

Development of high resolution X-ray CT technique for irradiated fuel pellets

Katsuyama, Kozo; Ishimi, Akihiro; Nagamine, Tsuyoshi; Asaka, Takeo

Proceedings of 47th Annual Meeting of the Working Group "Hot Laboratories and Remote Handling" (HOTLAB 2010) (CD-ROM), 4 Pages, 2010/09

In order to observe the structural change in the interior of irradiated fuel assembly, the non-destructive post irradiation examination technique using X-ray computer tomography (X-ray CT) was developed. In this X-ray CT system, the 12 MeV X-ray pulse was used in synchronization with the switch-in of the detector to minimize the effects of the $$gamma$$ ray emissions from the irradiated fuel assembly. In this study, this X-ray CT technique was upgraded for observing the inner condition of the fuel pellet using the high resolution X-ray CT image. In this paper, we describe following two items; (1) Development of high resolution X-ray CT technique, and (2) Result of high resolution X-ray CT image of an irradiated fuel pellet.

Journal Articles

Helium release from the uranium-plutonium mixed oxide (MOX) fuel irradiated to high burn-up in a fast breeder reactor (FBR)

Katsuyama, Kozo; Ishimi, Akihiro; Maeda, Koji; Nagamine, Tsuyoshi; Asaka, Takeo

Journal of Nuclear Materials, 401(1-3), p.86 - 90, 2010/06

 Times Cited Count:3 Percentile:26.36(Materials Science, Multidisciplinary)

The helium releases were investigated in FBR fuel pins irradiated to high burn-up. The released amounts of helium gas increased with the increase of burn-up, but their data were scattered in the region of high burn-up region. This was understood to be caused by the differences of $$^{241}$$Am contents among fuel pellets, because this nuclide generates $$^{242}$$Cm which undergoes alpha decay at a short half life.

Journal Articles

Analysis on the Co-localization of asbestos bodies and Fas or CD163 expression in asbestos lung tissue by in-air micro-PIXE

Matsuzaki, Shinichi*; Shimizu, Yasuo*; Dobashi, Kunio*; Nagamine, Takeaki*; Sato, Takahiro; Okubo, Takeru; Yokoyama, Akihito; Ishii, Yasuyuki; Kamiya, Tomihiro; Arakawa, Kazuo*; et al.

International Journal of Immunopathology and Pharmacology, 23(1), p.1 - 11, 2010/01

Journal Articles

Three-dimensional X-ray CT image of an irradiated FBR fuel assembly

Katsuyama, Kozo; Maeda, Koji; Nagamine, Tsuyoshi; Furuya, Hirotaka

Nuclear Technology, 169(1), p.73 - 80, 2010/01

 Times Cited Count:3 Percentile:26.36(Nuclear Science & Technology)

Three-dimensional X-ray CT (computer tomography) images were successfully taken of a fast breeder reactor fuel assembly which had been irradiated to high burn-up. The interior and outside of the fuel assembly can be clearly observed on any cross section from any angle. Using these images, it is possible to analyze the deformation of fuel pins, abnormalities in the fuel assembly, and microstructural change in the fuel pins. 127 central void sizes were tentatively analyzed as a function of linear heat rating. Compared with conventional non-destructive and destructive post irradiation examination (PIEs), this X-ray CT technique has great advantages including the number of PIE data acquisitions in a short time, reduced PIE costs, reduced radioactive waste generation, and physical protection of nuclear materials.

Journal Articles

Development of an eddy current testing technique for inspecting inner corrosion of cladding

Miyaji, Noriko; Katsuyama, Kozo; Nagamine, Tsuyoshi

Proceedings of 46th Annual Meeting of "Hot Laboratories and Remote Handling" Working Group (HOTLAB 2009) (CD-ROM), 5 Pages, 2009/09

An eddy current testing (ECT) technique was developed to check the soundness of irradiated fuel pins non-destructively. Here, the technique was applied to detect the decrease in wall thickness of the fuel pin cladding due to corrosion occurrence which had been irradiated in the experimental fast reactor Joyo. Dummy cladding provided with simulated inner corrosion was used to ascertain the technique applicability. This test confirmed that the decrease in wall thickness with simulated inner corrosion exceeding 30 $$mu$$m in depth could be detected. In the case of irradiated fuel pins, the decrease in wall thickness due to corrosion occurrence was not detected because the depth was too small; the maximum depth of the inner corrosion was 14 $$mu$$m. In addition, it should be noted that the physical changes on the cladding due to irradiation might have an influence on the signal.

Journal Articles

Remote maintenance technology for a large scale hot laboratory

Sakamoto, Naoki; Yoshikawa, Katsunori; Kushida, Naoya; Katsuyama, Kozo; Nagamine, Tsuyoshi

Proceedings of 46th Annual Meeting of "Hot Laboratories and Remote Handling" Working Group (HOTLAB 2009) (CD-ROM), 5 Pages, 2009/09

The large-scale post irradiation examination facility for fast breeder reactor fuel assemblies has been operated since 1978 in JAEAs Oarai Research and Development Center. The facility has several hot cells and irradiated fuel assemblies are dismantled in the examination cell which is 6 m in length, 19.5 m in width and 7 m in height. Remote maintenance technology for use in the hot laboratory was established using electromechanical manipulators, in-cell cranes and a repair hoist system installed in the examination cell. The test equipment which is used for post irradiation examinations can be repaired using the electromechanical manipulators and in-cell cranes by remote handling. In addition, the electromechanical manipulators and in-cell cranes are designed to permit self-repair using the repair hoist system in the cell by remote handling.

JAEA Reports

Post irradiation examination results of MA containing MOX fuel; Non-destructive examination results of the fuel pins

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.

Journal Articles

Measurement of deformation of FBR fuel assembly wrapper tube by an innovative technique

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.

JAEA Reports

Re-assembly technology establishment of Material Testing Rig with Temperature Control (MARICO-2)

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.

Journal Articles

Three-dimensional X-ray CT image of irradiated FBR fuel assembly

Katsuyama, Kozo; Nagamine, Tsuyoshi; Nakamura, Yasuo; Asaka, Takeo; Furuya, Hirotaka

Transactions of the American Nuclear Society, 97(1), p.620 - 621, 2007/11

no abstracts in English

Journal Articles

Development of design technology on thermal-hydraulic performance in tight-lattice rod bundle, 3; Numerical estimation on rod bowing effect based on X-ray CT data

Misawa, Takeharu; Onuki, Akira; Mitsutake, Toru*; Katsuyama, Kozo; Misawa, Susumu*; Nagamine, Tsuyoshi; Nakamura, Yasuo; Akimoto, Hajime

Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 8 Pages, 2007/04

JAEA Reports

Development of eddy current testing technique for irradiated fuel pins, 2; ECT results of irradiated fuel pins of high burn up

Miyaji, Noriko; Nagamine, Tsuyoshi; Katsuyama, Kozo

JAEA-Technology 2006-036, 41 Pages, 2006/06

JAEA-Technology-2006-036.pdf:3.91MB

Eddy current testing (ECT) technique has been developed in order to check the soundness of irradiated fuel pins non-destructively. This paper describes the results that it was examined if corrosions were detected using an imitation fuel pin, made of 15Ni-15Cr-Ti and same type of the fuel pins irradiated in JOYO. As the results of experimental for an imitation pin, ECT detected the corrosions using frecquency 32kHz. And, the signal of eddy current became larger as the thickness of the cladding became smaller, because there was some correlation between the signal and thickness. As for the irradiated fuel pins, inner corrosions were not recognized from the signal because their sizes were too small. However, outside corrosions by sodium as coolant might have an influence on the signal. And, as well as a change of the electromagnetic characteristics of cladding by irradiation, inner pressure by FP gas and PCMI might have an influence on the signal.

Journal Articles

Measurement of the fuel pin deflection in an assembly irradiated in FBR "JOYO"

Katsuyama, Kozo; Nagamine, Tsuyoshi; Nakamura, Yasuo; Matsumoto, Shinichiro; Asaka, Takeo; Furuya, Hirotaka

Transactions of the American Nuclear Society, 94(1), p.771 - 772, 2006/06

no abstracts in English

JAEA Reports

Study on the fuel damage limit examination device at transition for irradiated fuel pin

Katsuyama, Kozo; Toyoda, Hiromasa*; Nagamine, Tsuyoshi

JAEA-Technology 2006-004, 30 Pages, 2006/02

JAEA-Technology-2006-004.pdf:2.44MB

no abstracts in English

JAEA Reports

Rod displacement measurements by X-ray CT and its impact on thermal-hydraulics in tight-lattice rod bundle (Joint research)

Mitsutake, Toru*; Katsuyama, Kozo*; Misawa, Takeharu; Nagamine, Tsuyoshi*; Kureta, Masatoshi*; Matsumoto, Shinichiro*; Akimoto, Hajime

JAERI-Tech 2005-034, 55 Pages, 2005/06

JAERI-Tech-2005-034.pdf:7.76MB

In tight-lattice bundles with about 1mm gap between rods, a rod displacement might affect thermal-hydraulic characteristics. The inside-structure observation of the simulated seven-rod bundle of RMWR was made with the high-energy X-ray CT of JNC. The CT view assured that the rod position was almost the same as expected by design. In the heat transfer experiments, all thermocouples on the center rod showed almost simultaneous BT-induced temperature increase and on the same axial heights showed quite similar time-variation behaviors in the vapor cooling heat transfer regime. It showed that the effect of the geometrical asymmetry was small on the BT characteristics. The calculated critical power by subchannel analysis with the input of the CT measured rod position was smaller by about 5% than that with the designed rod position. It concluded that the error in the calculated critical power was attributable not to the asymmetry in the rod position, but to the models in the subchannel analysis code.

65 (Records 1-20 displayed on this page)