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Fukidome, Hirokazu*; Abe, Shunsuke*; Takahashi, Ryota*; Imaizumi, Kei*; Inomata, Shuya*; Handa, Hiroyuki*; Saito, Eiji*; Enta, Yoshiharu*; Yoshigoe, Akitaka; Teraoka, Yuden; et al.
Applied Physics Express, 4(11), p.115104_1 - 115104_3, 2011/11
Times Cited Count：35 Percentile：78.45(Physics, Applied)Fukidome, Hirokazu*; Takahashi, Ryota*; Abe, Shunsuke*; Imaizumi, Kei*; Handa, Hiroyuki*; Kang, H. C.*; Karasawa, Hiromi*; Suemitsu, Tetsuya*; Otsuji, Taiichi*; Enta, Yoshiharu*; et al.
Journal of Materials Chemistry, 21(43), p.17242 - 17248, 2011/11
Times Cited Count：28 Percentile：63.34(Chemistry, Physical)Sekimoto, Shun*; Utsunomiya, Takashi*; Yashima, Hiroshi*; Ninomiya, Kazuhiko*; Omoto, Takashi*; Nakagaki, Reiko*; Shima, Tatsushi*; Takahashi, Naruto*; Shinohara, Atsushi*; Kinoshita, Norikazu*; et al.
Progress in Nuclear Science and Technology (Internet), 1, p.89 - 93, 2011/02
In this work, we tried to determine reaction cross sections for Y and Tb induced by neutrons at 300 MeV, which have never been reported. The irradiations were carried out using neutrons produced through 
Li(p, n) reaction at N0 beam line in the Research Center for Nuclear Physics (RCNP), Osaka University. To estimate quasi-monoenergetic neutron induced cross sections, the target stacks of Y and Tb were irradiated on the two angles of 0 degree and 30 degree for the axis of the primary proton beam. Neutron cross sections were estimated by subtracting the activities produced in the samples placed on 30 degree from those of 0 degree to correct the contribution of the low energy tail in the neutron spectrum.
Ueda, Nobuyuki*; Fukushima, Masahiro; Okajima, Shigeaki; Takeda, Toshikazu*; Kitada, Takanori*; Nauchi, Yasushi*; Kinoshita, Izumi*; Matsumura, Tetsuo*
Proceedings of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09) (CD-ROM), p.9493_1 - 9493_9, 2009/05
A series of critical experiments were carried out in the JAEA fast critical facility (FCA) named FCA XXIII cores with placing emphases on the reflector reactivity worth and the sodium void reactivity which are especially important from the view point of safety features of the 4S. The analyses of those physics mockup experiments have been carried out by the neutron transport calculation methods with continuous energy Monte Carlo code MVP and 70 energy-group discrete ordinate P0-S8 transport code DANTSYS using libraries processed from JENDL-3.3 data file. The results showed that combination of the stochastic and deterministic transport calculation methods (Monte Carlo and Sn) provided good prediction bases for criticality, reflector worth, sodium void reactivity, reaction rate ratios and absorber reactivity worth for the 4S nuclear design.
Fukushima, Masahiro; Okajima, Shigeaki; Mori, Takamasa; Takeda, Toshikazu*; Kinoshita, Izumi*
Proceedings of International Conference on the Physics of Reactors, Nuclear Power; A Sustainable Resource (PHYSOR 2008) (CD-ROM), 7 Pages, 2008/09
The criticality was measured in a series of mock-up cores simulated small fast reactor with massive reflector at FCA facility of JAEA in order to evaluate the prediction accuracy of the current analysis code system. In the analyses, the effective cross sections were obtained by using an ultra-fine group cell calculation code. The JENDL-3.3 cross section library was used. The core calculations for the criticality were performed by using a three-dimensional S
transport code. Conventional calculations with a standard 70 energy group structure and under the P
transport approximation overestimated the experimental values up to 1.5%
/. Furthermore, the calculation parameters were investigated concerning the fine energy group structure and the higher Legendre order of anisotropic scattering cross section. Consequently, the calculation accuracy for the criticality was improved by about 1%/ with a 140 energy group structure and under the P
approximation.
Nishi, Yoshihisa*; Ueda, Nobuyuki*; Kinoshita, Izumi*; Miyakawa, Akira; Kato, Mitsuya*
Proceedings of 14th International Conference on Nuclear Engineering (ICONE-14) (CD-ROM), 10 Pages, 2006/07
CERES is plant system analysis code for LMRs developed by the Central Research Institute of Electric Power Industry (CRIEPI). CERES has a function of calculating multidimensional flow in the plena of a coolant in addition to that in one-dimensional plant network calculation. To verify the CERES code, analyses were performed by using the result of the plant trip test from the partial power operation of the prototype FBR "MONJU" that had been executed in December, 1995. The verification work was performed as a joint research of CRIEPI and JAEA. (1)Analysis concerning the primary/secondary/auxiliary cooling system (the plenum in the reactor vessel (R/V) is modeled in R-Z 2-dimension). (2)Analysis concerning the flow pattern in the plenum of R/V (the plenum is modeled in 3-dimension). (3)Analysis concerning the flow pattern inside the IHX plenum (the plenum in the IHX is modeled in 3-dimension). Analytical results by the CERES code showed good agreement with the results of the test of the "MONJU". Fundamental abilities of the CERES as a plant dynamics calculation code had been verified through these analyses. Additionally, some characteristic flows in plena of "MONJU" became clear by these analyses.
Furukawa, Tomohiro; Nishi, Yoshihisa*; Aoto, Kazumi; Kinoshita, Izumi*
JAEA-Research 2006-037, 36 Pages, 2006/06
JAEA-Research-2006-037.pdf:11.89MB
In 2002, the Japan Atomic Energy Agency (past organization name: Japan Nuclear Cycle Development Institute) was made a contract with the Central Research Institute of Electric Power Industry on the research work for utilizing technology of the lead bismuth eutectic. In the contract, research on corrosion of FBR materials in high temperature lead bismuth eutectic was performed. This work was composed of two stages. In the first stage, corrosion test of high chromium martensitic steel, which was one candidate material for structures of advanced fast reactor, was performed in oxygen controlled lead bismuth eutectic at 923K. Effect of chromium on corrosion in the lead bismuth eutectic was estimated. In this second research, corrosion test of oxide dispersion strengthened ferritic steels whose chemical compositions of chromium and aluminum were differed has been performed in the lead bismuth eutectic for up to 4,000 hours. As the results, although chromium effect on corrosion has not been observed, good corrosion resistance by aluminum oxide formation on the surface has been obtained.
Nishi, Yoshihisa*; Ueda, Nobuyuki*; Kinoshita, Izumi*; Miyakawa, Akira; Kato, Mitsuya*
JNC TY2400 2005-001, 66 Pages, 2005/06
JNC-TY2400-2005-001.pdf:7.59MB
Multi-dimensional thermal-hydraulic characteristic of the coolant in the reactor vessel (R/V) influences the temperature at the plant transitional condition of fast breeder reactor (FBR). CRIEPI is developing plant dynamics calculation code CERES for FBR that adds multi-dimensional thermal-hydraulic analysis function to one-dimensional system calculation code to evaluate the temperature distribution in high accuracy. The temperature distribution affects the integrity of equipments of FBR. To verify the CERES code, analyses were performed by using the result of the plant trip test from the partial power operation of the prototype fast breeder reactor
Nishi, Yoshihisa*; Kinoshita, Izumi*; Furukawa, Tomohiro; Aoto, Kazumi
JNC TY9400 2003-027, 19 Pages, 2004/01
JNC-TY9400-2003-027.pdf:2.08MB
Research Work for Utilizing Technology of the Lead-Bismuth Eutectic - Research on the corrosion resistance of 12 chrome steels in high temperature lead-bismuth eutectic under oxygen concentration control -
Sakai, Takaaki; Enuma, Yasuhiro; Soman, Yoshindo; Nishi, Yoshihisa*; Kinoshita, Izumi*
JNC TY9400 2003-012, 51 Pages, 2003/09
JNC-TY9400-2003-012.pdf:1.73MB
In System analysis has been performed to evaluate the thermal-hydraulics effect of the tube rapture accident. In addition, lifted flow rate by gas injection in the lead-bismuth has been measured to confirm the applicability of existing void fraction correlations based on the drift-flux model by Zuber-Findlay. As a result, it is clarified that the cooling capability is successfully maintained also in case of the tube rapture accident, because the flow reversal is limited to only 1/8 sector of downward flow area due to the tube support wall structure in the steam generator. And also, the applicability of existing void fraction correlations to Lead-Bismuth is confirmed by the gas injection experiment.
Ara, Hiroshige*; Fukumitsu, Kenji*; Iizuka, Yunosuke*; Ishii, Takashi*; Izumiya, Yasushi*; Imazu, Masanori*; Utsugida, Yoshizo*; Hasegawa, Makoto*; Maeda, Masaya*; Yabe, Yukio*; et al.
PNC TJ199 84-04VOL1, 20 Pages, 1984/03
PNC-TJ199-84-04VOL1.pdf:0.88MB
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Furukawa, Tomohiro; Aoto, Kazumi; Nishi, Yoshihisa*; Kinoshita, Izumi*
no journal, ,
no abstracts in English
Takahashi, Ryota*; Handa, Hiroyuki*; Abe, Shunsuke*; Inomata, Shuya*; Imaizumi, Kei*; Fukidome, Hirokazu*; Teraoka, Yuden; Yoshigoe, Akitaka; Kotsugi, Masato*; Okochi, Takuo*; et al.
no journal, ,
no abstracts in English
Inomata, Shuya*; Handa, Hiroyuki*; Abe, Shunsuke*; Takahashi, Ryota*; Imaizumi, Kei*; Fukidome, Hirokazu*; Teraoka, Yuden; Yoshigoe, Akitaka; Kotsugi, Masato*; Okochi, Takuo*; et al.
no journal, ,
no abstracts in English
Inomata, Shuya*; Handa, Hiroyuki*; Abe, Shunsuke*; Takahashi, Ryota*; Imaizumi, Kei*; Fukidome, Hirokazu*; Teraoka, Yuden; Yoshigoe, Akitaka; Kotsugi, Masato*; Okochi, Takuo*; et al.
no journal, ,
no abstracts in English
Kinoshita, Setsuo; Koizumi, Tsutomu; Kobayashi, Hirohide; Sukegawa, Masato
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no abstracts in English
Koizumi, Tsutomu; Kinoshita, Setsuo; Kobayashi, Hirohide; Sukegawa, Masato
no journal, ,
no abstracts in English
Sambonsuge, Shota*; Abe, Shunsuke*; Takahashi, Ryota*; Imaizumi, Kei*; Handa, Hiroyuki*; Yoshigoe, Akitaka; Teraoka, Yuden; Kotsugi, Masato*; Okochi, Takuo*; Kinoshita, Toyohiko*; et al.
no journal, ,
no abstracts in English
