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Mikami, Satoshi; Matsuda, Norihiro; Ando, Masaki; Kinase, Sakae; Kitano, Mitsuaki; Kawase, Keiichi; Matsumoto, Shinichiro; Yamamoto, Hideaki; Saito, Kimiaki
Radioisotopes, 64(9), p.589 - 607, 2015/09
This article presents the features of regional distributions and temporal changes in air dose rate and radionuclide deposition densities in Fukushima on the basis of analyses on large-scale environmental monitoring results using diverse methods. The continuity of decontamination effects is discussed according to repeated monitoring data after the decontamination model project. Further, some examples are shown on the projection of air dose rates together with the ecological half lives for different land uses.
Donomae, Takako; Tachi, Yoshiaki; Matsumoto, Shinichiro
JAEA-Research 2006-033, 35 Pages, 2006/07
JAEA-Research-2006-033.pdf:8.59MB
no abstracts in English
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
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.
Mitsutake, Toru*; Akimoto, Hajime; Misawa, Takeharu; Kureta, Masatoshi*; Katsuyama, Kozo*; Nagamine, Tsuyoshi*; Matsumoto, Shinichiro*
Proceedings of 4th World Congress on Industrial Process Tomography, Vol.1, p.348 - 353, 2005/00
An inside-structure observation of a tight-lattice 7-rod bundle was made, using the high-energy X-ray computer tomography(CT) apparatus. The two-dimensional configurations of all rods were obtained at seventy-six axial height positions over the whole length of the bundle. The measured results of the rod positions showed small rod position displacements, about 0.5 millimeters at maximum, from the lattice positions. Based on these measured rod position displacement results, the flow area, equivalent hydraulic diameter, rod-rod clearance, and rod-shroud clearance were calculated. The effect of rod position displacement on critical power was estimated by a sub-channel analysis. The result showed that the rod position displacement effect has only a small effect on critical power calculations. The calculated critical power still overestimated the measured value.
Katsuyama, Kozo; Nagamine, Tsuyoshi; Matsumoto, Shinichiro
JNC TY9410 2004-001, 54 Pages, 2004/09
JNC-TY9410-2004-001.pdf:14.44MB
In order to contribute to the development of cooling technique for the Tight-Lattice Core used in Reduced-Moderation Water Reactor, which was mainly studied in Japan Atomic Energy Research Institute, the inner condition of Dummy Assembly made of the Tight-Lattice Core was observed with X-ray Computer Tomography (CT) technique. In the observation using X-ray CT, the non-destructive examination technique for the un-irradiated specimens was also established. The results obtained from this study are following.
Miyaji, Noriko; Nagamine, Tsuyoshi; Katsuyama, Kozo; Kikuchi, Shin; Matsumoto, Shinichiro
JNC TN9410 2003-012, 45 Pages, 2004/03
JNC-TN9410-2003-012.pdf:1.84MB
Post irraiated fuel pins which irradiated in JOYO PFC030 by eddy current test (ECT) were carried out. The results of the tests, we have some possibility to find FCCI points using gamma scanning result Cs137. And thecorrelation between FCCI quantity and eddy current signal was within that of trial FCCI.
Katsuyama, Kozo; Nagamine, Tsuyoshi; Matsumoto, Shinichiro
JNC TN9400 2004-016, 38 Pages, 2004/03
JNC-TN9400-2004-016.pdf:1.34MB
In order to evaluate the irradiation behavior of fuel pin, X-ray CT test was carried out for the fuel assembly irradiated in the experimental fast reactor Joyo and fuel pin deflection were measured based on the analysis of CT image. It was observed that the deflection of the fuel pins loaded in the outermost array of the fuel assembly were large as compared with the fuel pins loaded in the inner region and the fuel pins fuel situated fronting on wrapper tube were markedly displaced in the direction of wrapper tube.
Katsuyama, Kozo; Nagamine, Tsuyoshi; Matsumoto, Shinichiro; Asaka, Takeo; Ito, Masahiko; Furuya, Hirotaka
2004 ANS Winter Meeting, 91, 0 Pages, 2004/00
Non-destructive X-ray computed tomography (X-ray CT scanning) is a powerful technique for characterizing the morphology in structural materials as used in medical field. This X-ray CT scanning technique was developed for the purpose of post irradiation examinations (PIE), and applied to the fuel assemblies irradiated in the experimental fast reactor Joyo.
Katsuyama, Kozo; Fujishima, Tadatsune; Nagamine, Tsuyoshi; Matsumoto, Shinichiro
JNC TN9410 2003-006, 40 Pages, 2003/08
JNC-TN9410-2003-006.pdf:1.04MB
85Kr, which is one of gaseous nuclides generated in nuclear fissions, can be detected by gamma spectrum measurement. It is possible to calculate the fission gas amount discharged into the gas plenum of fuel pin and the inner pressure, based on the measurement data. In this study, the measurement and calculation were applied to the fuel pins irradiated in the experimental fast reactor JOY0. Then puncture testing was carried out for the applied fuel pins to measure fission gas amount and real inner pressure. As a result, it was confirmed that that calculated data were appropriate in general, compared with those gained by puncture testing. (1)The error of inner pressure calculated on the basis of gamma spectrum measurement is less than 25%, compared with the puncture test results. (2)As the result of this method applied to the fuels irradiation test rig (No.PFB090), the highest pressure was calculated in one of fuel pins loaded into N0.5 compartment, which burn-up was over 110 GWd/t. The pressure was about 50 Kg/cm2. This value was sufficiently less than that used in the fuel design.
Katsuyama, Kozo; Nagamine, Tsuyoshi; Matsumoto, Shinichiro
Genshiryoku eye, 49(12), p.58 - 61, 2003/00
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.
Katsuyama, Kozo; Nagamine, Tsuyoshi; Matsumoto, Shinichiro;
Journal of Nuclear Science and Technology, 40(4), p.220 - 223, 2003/00
Times Cited Count：18 Percentile：74.43(Nuclear Science & Technology)None
; ; Matsumoto, Shinichiro
JNC TN9410 2002-012, 43 Pages, 2002/08
It is recognized that one of main factors limiting fuel life in a wrapping wire typed fuel assembly is BDI (Bundle-Duct Interaction). In order to observe this phenomenon occurring in a fuel assembly with a non-destructive method, the X-ray computer tomography (X-ray CT) apparatus was developed and used as a tool of post-irradiation-examinations. Several fuel assemblies have been tested with the X-ray CT. The data of CT image can show the location of fuel pins and wrapping wires. However, numerical analysis should be applied to the CT image to obtain the displacements of fuel pins and so on quantitatively. The numerical analysis was developed on the basis of the computer program made for the out of pile tests of fuel pin bundle compression using the X-ray CT. In this report, the numerical analysis system and the results gained by applying the system to the fuel assembly irradiated in Joyo are described. As the results, it was confirmed that significant change of flow area in outermost sub-channels and meaningful bowing in outermost fuel pins occurred even in case hat the swelling of cladding and wrapper tube was very small.
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.
Nagamine, Tsuyoshi; Katsuyama, Kozo; Matsumoto, Shinichiro;
Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(2), p.209 - 219, 2002/00
None
Katsuyama, Kozo; Nagamine, Tsuyoshi; Matsumoto, Shinichiro;
Journal of Nuclear Science and Technology, 39(7), 804 Pages, 2001/00
Times Cited Count：15 Percentile：67.86(Nuclear Science & Technology)None
; ; Matsumoto, Shinichiro
JNC TN9410 2001-022, 41 Pages, 2000/12
JNC-TN9410-2001-022.pdf:2.34MB
The X-ray CT apparatus for post-irradiation examination (PIE) was developed and installed in the Fuel Monitoring Facility (FMF). The apparatus started the common use for PIE in 1999. In this paper, the practical applicability of the CT image of this apparatus, based on the CT data of JOYO fuel subassembly (PFD512) is described. The results are as follows. (1)By the three-dimensional visualization of the CT images, the visibility to observation of the inside situation of the fuel assemblies was remarkably improved. (2)CT image analysis provides quantitative information such as the fuel pin rearrangements. It is expected as the data, which can reflect in the sub-channel analysis, etc. (3)By the CT data, it was confirmed that the information of the density variation of fuel pellets and ducts was obtained. Though the comparison with the destructive tests was necessity, this data is useful for evaluation when the swelling is big. (4)The apparatus measured fuel pellet center void diameters with an accuracy of about 
0.1mm. This data is useful for confirming irradiation conditions and for selecting the position for optical macrograph observations. (5)The three-dimensional image provides fuel stack length and overall pin length without dismantling the fuel subassembly. The X-ray CT apparatus for PIE is useful for the early detection of fuel subassembly abnormalities and intermediate inspections of continuous irradiation rigs where dismantling is not permitted. The apparatus is also usefu1 for the selection of pins and observation positions in detailed destructive tests.
; ; ; Matsumoto, Shinichiro
JNC TN9410 2000-009, 65 Pages, 2000/09
JNC-TN9410-2000-009.pdf:4.36MB
In order to evaluate irradiation behavior of(U, Pu) C and (U, Pu) N fuel using fast reactor, (U, Pu) C and (U, Pu) N fuel pins were irradiated in JOYO for the fist time in Japan. In this study, one (U, Pu) C fuel pin and two (U, Pu) N fuel pins were irradiated to maximum burn up about 40GWd/t. Post irradiation examination of (U, Pu) C and (U, Pu) N fuel pins started in Fuel Monitoring Facility (FMF) at JNC from October 1999, and it ended in March, 2000. The results of non-destructive post irradiation examination reported in this document. Main results are shown in the following. (1)The soundness of all (U,Pu) C and (U,Pu) N fuel pins were confirmed from the non-destructive examination result. (2)The fuel stack elongation of (U,Pu) C and (U,Pu) N is bigger than it of the MOX fuel for fast reactor. (3)The singular behavior from the gamma ray scanning measurement in the stack area was not confirmed. The migration of Cs137 to lower insulator pellet and outside of the pellet was confirmed in (U,Pu) N B9NO2 pin. In (U,Pu) C fuel, the migration of Cs137 was not confirmed. (4)In (U,Pu) C B9CO1 pin and (U,Pu) N B9NO2 pin in which the gap width was small, diameter of cladding increase around 50 
m in the stack area which originates for FCMI was confirmed. In (U,Pu) N B9NO1 pin in which the gap width was wide, the ovality which originates from the relocation of the pellet was confirmed. (5)Fission gas release rate of (U,Pu) N were 3.3% and 5.2%, and the low value compared to the MOX fuel was shown.
Kikuchi, Shin; Kitazawa, Takeo; ; Matsumoto, Shinichiro
JNC TN9410 2001-003, 84 Pages, 2000/07
JNC-TN9410-2001-003.pdf:2.12MB
Eddy current techniques have been tested for future Post irradiated Experiment ;PIE applications outside hot cell(the following, cell outside). As the result, applicability to the defects inspection such as the cladding tube material was able to be confirmed, and an outlook to the application to the irradiation material was obtained. The last time, report described results of the external surface defects, inside defects, and open holes outside hot cell except for Fuel-Cladding Chemical Interaction (FCCI) measurement testing This paper mainly describes the results of the trial FCCI measurement testing outside hot cell. Other tests include the results of external surface defects, inside defects, and open holes in the proofreading tests. The proofreading tests used a standard defect pin inside hot cell. In the trial FCCI measurement testing outside hot cell, the correlation between reduction in thickness and eddy current signal value was comfirmed, and the prospect of FCCI measurement by the eddy current testing was examined. As the result, the optimum conditions for measuring the FCCI quantity are respectively (1)carrier speed of the pin :20mm/sec, (2) test frequency : 32kHz, (3)phase : ODEG, (4) gain :-10dB, (5)filter : 0. The correlation between trial FCCI quantity and eddy current signal value was found on the basis of the test result, and the prospect which could detect FCCI was obtained when there is reduction in thickness of over 50 m for the cladding tube with wall thickness quantity of the 300 m order. And, the proofreading test inside hot cell on eddy current measurements were confirmed to be equivalent to the performance test outside hot cell.
