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Saito, Yuji; Fujiwara, Hidenori*; Yasui, Akira*; Kadono, Toshiharu*; Sugawara, Hitoshi*; Kikuchi, Daisuke*; Sato, Hideyuki*; Suga, Shigemasa*; Yamasaki, Atsushi*; Sekiyama, Akira*; et al.
Physical Review B, 102(16), p.165152_1 - 165152_8, 2020/10
Times Cited Count:1 Percentile:5.7(Materials Science, Multidisciplinary)Tazawa, Yujiro; Nishihara, Kenji; Sugawara, Takanori; Tsujimoto, Kazufumi; Sasa, Toshinobu; Eguchi, Yuta; Kikuchi, Masashi*; Inoue, Akira*
JAEA-Technology 2016-029, 52 Pages, 2016/12
Transmutation Physics Experimental Facility (TEF-P) planned in the J-PARC project uses minor actinide (MA) fuels in the experiments. These MA fuels are highly-radioactive, so the fuel handling equipment in TEF-P is necessary to be designed as remote-handling system. This report summarizes fabrication and test results of the testing equipment for fuel loading that is one of components of the testing equipment for remote-handling of MA fuels. The testing equipment which had a remote-handling system for fuel loading was fabricated. And the test in combination with the mock-up core was performed. Through the test, it was confirmed to load/take the dummy fuel pin to/from the mock-up core without failure. It was shown that the concept design of the fuel loading equipment of TEF-P was reasonable.
Eguchi, Yuta; Sugawara, Takanori; Nishihara, Kenji; Tazawa, Yujiro; Inoue, Akira; Tsujimoto, Kazufumi
JAEA-Technology 2015-052, 34 Pages, 2016/03
Transmutation Physics Experimental Facility (TEF-P) planned in the J-PARC project uses minor actinide (MA) fuel which has large decay heat. So it is necessary to consider the increase of the core temperature when the core cooling system is stopped. This change of the core temperature was evaluated by thermal conduction analysis. It was found that the impact of thermal insulation in the empty rectangular lattice matrix area was large. So it is necessary to verify reliability and accuracy of heat transfer effect used in this area. Testing equipment was fabricated to verify the accuracy of calculation model for the empty lattice matrix which was the free convection model of sealed fluid. By using this equipment, thermal distribution and one dimensional heat flow through the lattice were measured. It was observed that the actual equivalent thermal conductivity in the lattice was larger than the free convection model. It was also confirmed that the insertion of the aluminum block into the empty lattice could achieve the higher equivalent thermal conductivity. These results could be the useful data for the thermal conduction analysis.
Nishihara, Kenji; Tazawa, Yujiro; Inoue, Akira; Sugawara, Takanori; Tsujimoto, Kazufumi; Sasa, Toshinobu; Obayashi, Hironari; Yamaguchi, Kazushi; Kikuchi, Masashi*
JAEA-Technology 2015-051, 47 Pages, 2016/03
This report summarizes fabrication and test results of a testing equipment for fuel cooling that is a component of the testing equipment for remote-handling of highly-radioactive MA fuels in the transmutation physics experimental facility (TEF-P) planned in the J-PARC. Evaluation formula of pressure drop and temperature increase used in the design of TEF-P was validated by the test, and, feasibility of cooling concept was confirmed.
Yonemura, Hirotaka*; Sato, Akira*; Sugawara, Katsuhiko*; Sawada, Atsushi
Heisei-19 Nendo (2007 Nen) Shigen, Sozai Gakkai Shunki Taikai Koenshu (I) Shigen Hen, p.121 - 122, 2007/03
no abstracts in English
Sato, Akira*; Fukahori, Daisuke*; Sugawara, Katsuhiko*; Sawada, Atsushi; Takebe, Atsuji*
Advances in X-ray Tomography for Geomaterials, p.315 - 321, 2006/09
The two dimensional (2D) diffusion tests with the rock sample which has single plane crack were conducted, and the diffusion of non-sorbing tracer from the crack to rock matrix is visualized by X-ray CT in this study. It was found that the increment of CT value due to the 2D diffusion of the dense tracer from crack surface to the matrix of rock sample was observed. It was also found that the application of image processing techniques makes it possible to obtain the clear image data and that the precious analysis of diffusion phenomena becomes possible. The numerical simulation was also conducted in order to verify the experimental results. The results of 2D diffusion tests show good agreement with the numerical results, and the applicability of X-ray CT to the analysis of diffusion phenomena in a rock sample was verified together with the necessary image processing techniques.
Shimo, Michito*; Fumimura, Kenichi*; Obara, Yuzo*; Sato, Akira*; Sugawara, Katsuhiko*
JNC TJ8400 2003-091, 67 Pages, 2004/01
In this year, the method proposed in H14 study was applied to a natural rock fracture in a 10 cm block, which has been prepared for permeability and tracer tests in the future.
Shimo, Michito*; Fumimura, Kenichi*; Obara, Yuzo*; Sato, Akira*; Sugawara, Katsuhiko*
JNC TJ8400 2003-021, 82 Pages, 2003/02
Understanding the influence of small scale structure and its heterogeneity onto flow through rock fractures is important for improving the reliability of performance assessment of Geologic Disposal of High Level Nuclear Waste. An established technique for measuring the fracture aperture profile is required to achieve the above purpose. There are several aperture measuring techniques: (1) estimation of aperture from roughness measurement results, (2) direct measurement of the fracture from rock surface, (3) non-destructive method, such as tomography. Among above, tomography method, which is rather new technique and its applicability to aperture measurement is not well known, is expected to become an effective and feasible approach since the aperture profile can be obtained without destroying the rock specimen. In this work, we investigated problems associated with fracture aperture measurement using X-Ray, then we proposed several approaches to improve measurement accuracy, finally
; ; Yamaguchi, Akira; ; ; Sugawara, Satoru
PNC TN9410 92-352, 62 Pages, 1992/11
In-vessel thermohydraulic analysis with multi-dimensional code AQUA was conducted to investigate efficiency of a baffle ring and of a porous-type UIS (upper instrumentation structure) for preventation of gas entrainment to coolant from gas plenum of reactor vessel. Through the analysis using the AQUA code and the discussion based on their results, the following results have been obtained: [Baffle Ring Equipment] (1)In order to reduce maximum surface verocity, the effect with the width 40 cm of the baffle ring equipment better than the width 20 cm. (2)Maximum surface velocity is 40 cm/s using the baffle ring equipment of width 40 cm. [Porous-type UIS] (1)Effective mass flow ratio of the UIS porous to the UIS skirt is 50 % to decrease maximum surface velocity. (2)Maximum surface velocity is 52 cm/s using the porous-type UIS with the above mass flow distribution. Furthermore analysis with the AQUA code were carried out for the conbined condition of the baffle rings with 40 cm width and the porous-type UIS with the condition of the effective mass flow ratio 50 %. Maximum surface velocity 0.33 m/s closer to the MONJU condition (0.3 m/s) was obtained from the analysis.
Muramatsu, Toshiharu; Murata, Masayuki*; Ieda, Yoshiaki; Yamaguchi, Akira; Nagata, Takashi; Sugawara, Satoru
PNC TN9410 91-318, 48 Pages, 1991/10
In-vessel thermohydraulic analysis with multi-purpose three-dimensional code AQUA as conducted for transient simulating a pump coast down and reactor scram (manual reactor trip event) to confirm efficiency of partially dip plate equipments in a large-scale fast breeder reactor. Throught the analysis using the AQUA code and the discussion based on their results, the following results have been obtained: [Sodium Surface Velocity] Maximum surface velocity is 0.33m/s in the condition of D=0.75m and W=1.905m. The velocity is the same as that or the MONJU reactor. [Thermal Stratification] Maximum axial temperature gradient 445C/m was calculated. The gradient is nearly equal to the results in the MONJU reactor. [Main Loop Temperature Transient] Maximum temperature transients at the outlet nozzle of reactor vessel was -0.51C/s. [Circumferential Temperature Gradient] Maximum circumferential temperature gradient at the neighborhood of reactor vessel was 67C/m. The gradient is equivalent to five times of that when a partially dip plate is not adopted.
; *; ; Yamaguchi, Akira; ; Sugawara, Satoru
PNC TN9410 91-089, 130 Pages, 1991/03
In-vessel thermohydraulic analysis with multi-dimensional code AQUA was conducted for transient simulating a pump coast down and reactor scram (manual reactor trip event) to confirm efficiency of outer barrel equipments on a large-scale fast breeder reactor. Through the analysis using the AQUA code and the discussion based on their results, the following results have been obtained: [Main Loop Temperature Transient] The transient rate with the outer barrel equipments are approximately equal to the result when an inner barrel was adopted. [Thermal stratification] Axial temperature distributions are approximately equal to the result in the case without an inner barrel. Therefore appearance of an axial temperature distribution can be neglected from a structural design. [Circumferential Temperature Distribution] Maximum temperature gradient 104C/m was confirmed. The value is equivalent to three times of that when an inner barrel was not adopted. Further investigation on a thermal stress at reactor vessel is necessary. [Sodium Surface Velocity] Maximum velocity is the same as that described for the case without an inner barrel. From the above results, it is concluded that the outer barrel considered here is an efficient equipment to relax the main loop temperature transient.
Kobayashi, Takatoshi*; Sugawara, Akira*; Seki, Yuji*; Ikezawa, Hiroko*
PNC TJ206 71-11T, 30 Pages, 1971/08
As a continuation of the previous research, heterogeneity effects of neutron spectra and axial leakage have been examined. Spectra in a two-region cell were computed by a collision probability method and the heterogeneity effect was found to be small. The analysis of the axial leakage was carried out with the benoist's directional collision probability method and it turned out that the heterogeneity has negative contribution to the sodium void coefficient. Combining the results of the previous research and the current one, the heterogeneous void coefficient in a prototype fast reactor moves towards the positive direction from the homogeneous result.
Kobayashi, Takatoshi*; Sugawara, Akira*; Seki, Yuji*; Ikezawa, Hiroko*
PNC TJ206 70-01T, 40 Pages, 1970/08
As a continuation of the previous research, heterogeneity effects ofneutron spectra and axial leakage have been examined.Spectra in a two-region cell were computed by a collision probabilitymethed and the heterogeneity effect was found to be small.The analysis of the axial leakage was carried out with the Benoist'sdirectional collision probability method and it turned out that theheterogeneity has negative contribution to the sodium void coefficient. Combining the results of the previous research and the current one,the heterogeneous void coefficient in a prototype fast reactor moves towardsthe positive direction from the homegeneous result.
Sato, Akira*; Fukahori, Daisuke*; Sugawara, Katsuhiko*; Sawada, Atsushi; Takebe, Atsuji
no journal, ,
no abstracts in English
Sato, Akira*; Fukahori, Daisuke*; Sugawara, Katsuhiko*
no journal, ,
no abstracts in English
Yoshizawa, Reina*; Sugawara, Toshifumi*; Aritani, Hirofumi*; Shimada, Akihiko; Idesaki, Akira; Hakoda, Teruyuki; Sugimoto, Masaki; Yoshikawa, Masahito
no journal, ,
Carbon material which is manufactured after high temperature treatment of polymer is one of the candidates for the alternative of platinum cathode catalyst of polymer electrolyte fuel cell. In this study, we examine the influence of potential of oxygen reduction reaction by adding metal including material to polymer, precursor of carbon material. Specifically, 95 wt% of carboxymethyl cellulose (CMC) and 5 wt% of phthalocyanine (Pc) including metal or Pc were mixed. Adding water to this, the mixture of Pc-CMC were prepared. The mixture was irradiated by electron beam up to 100 kGy, dried and treated at 800 degree for 1 h in Ar gas. Then carbon material was manufactured. This was measured by electrochemical measurement. Then oxygen reduction reaction potential was calculated. The carbon material, CMC with Pc including Co has higher potential of 0.1 V than that with Pc including other metal or Pc. This phenomenon is the almost same as that manufactured by other polymer than CMC. It is estimated that Co is contributed to higher potential of oxygen reduction reaction.