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Namie, Masanari; Saito, Junichi
Computational Materials Science, 239, p.112963_1 - 112963_7, 2024/04
Saito, Junichi; Monbernier, M.*
Surfaces and Interfaces (Internet), 41, p.103248_1 - 103248_8, 2023/10
Times Cited Count：0 Percentile：0.01(Chemistry, Physical)Saito, Junichi; Kobayashi, Yohei*; Shibutani, Hideo*
Materials Transactions, 62(10), p.1524 - 1532, 2021/10
Times Cited Count：5 Percentile：41.35(Materials Science, Multidisciplinary)no abstracts in English
Saito, Junichi; Kobayashi, Yohei*; Shibutani, Hideo*
Nihon Kinzoku Gakkai-Shi, 85(3), p.110 - 119, 2021/03
Times Cited Count：1 Percentile：8.06(Metallurgy & Metallurgical Engineering)Kawaguchi, Munemichi; Saito, Junichi; Daido, Hiroyuki*; Suemoto, Toru*
UVSOR-47, P. 85, 2020/08
To elucidate theoretically the transparent metallic sodium in the vacuum ultraviolet (VUV) spectral range, the aim of this research is to obtain the accurate spectrum using UVSOR. We confirmed the validity for the transmittance measurement in UVSOR by the measurement of transmittance of CaF
windows. However, the transparency phenomenon of VUV in the metallic sodium has never been confirmed by our group. In the future, we will improve the sodium sample and conduct the measurement again.
Kawaguchi, Munemichi; Saito, Junichi; Daido, Hiroyuki*; Suemoto, Toru*
UVSOR-46, P. 89, 2019/08
To elucidate theoretically the transparent metallic sodium in the vacuum ultraviolet spectral range, the aim of this research is to obtain the accurate spectrum using UVSOR. The sodium sample maintained metallic luster by designing the special cells to prevent from oxidizing. The results of UVSOR measurement showed the possibility to occur the intransparent layer for vacuum ultraviolet light on the MgF windows. In the near future, we will improve the sodium sample to solve the problems and conduct the measurement again
Kudo, Hideyuki*; Otani, Yuichi*; Hara, Masahide*; Kato, Atsushi; Ishikawa, Nobuyuki; Otaka, Masahiko; Nagai, Keiichi; Saito, Junichi; Ara, Kuniaki; Ide, Akihiro*
Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 10 Pages, 2019/05
A next generation SFR in Japan has adopted an advanced dry cleaning system which consists of the argon gas blowing process to reduce the amount of metallic residual sodium remaining on spent fuel assemblies. This paper describes experimental and analytical work focusing on the amount of residual sodium remaining on a fuel pin bundle before and after the argon gas blowing process. The experiments were conducted using a sodium test loop and a short specimen consisting of a 7 pin bundle. The effects of the blowing gas velocity and the blowing time were quantitatively analyzed in the experiments. On the basis of these experimental results, evaluation models predicting the amount of the residual sodium were constructed.
Ide, Akihiro*; Kudo, Hideyuki*; Inuzuka, Taisuke*; Hara, Masahide*; Kato, Atsushi; Ishikawa, Nobuyuki; Otaka, Masahiko; Nagai, Keiichi; Saito, Junichi; Ara, Kuniaki
Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 10 Pages, 2019/05
A next generation SFR in Japan has adopted an advanced dry cleaning system which consists of the following process of argon gas blowing to reduce the amount of metallic sodium, moist argon gas blowing to deactivate the residual sodium, and direct storage in the SFP without using storage containers. This three-step process increases economic competitiveness and reduces waste products. In this Research and Development work, the amount of residual sodium and performance of the dry cleaning process were investigated. This paper describes experimental and analytical work for all parts of a fuel assembly except for a fuel pin bundle.
Ichikawa, Kenta*; Kanda, Hironori; Yoshioka, Naoki*; Ara, Kuniaki; Saito, Junichi; Nagai, Keiichi
Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), 6 Pages, 2018/07
Studies on the suppression of the reactivity of sodium itself have been performed on the basis of the concept of suspended nanoparticles in liquid sodium (sodium nanofluid). According to the experimental and theoretical results of studies for sodium nanofluid, velocity and heat of sodium nanofluid-water reaction are lower than those of the pure sodium-water reaction. The analytical model for the peak temperature of a sodium nanofluid-water reaction jet has been developed in consideration of these suppression effects by the authors. In this paper, the prediction method for mitigation effects for a damage of adjacent tubes in a steam generator tube rupture (SGTR) accidents is arranged by applying this analytical model for the peak temperature of the reaction jet. On the assumption that the sodium nanofluid is used for the secondary coolant of sodium-cooled fast reactor (SFR), mitigation effects under the design-base accident (DBA) condition and the design-extension condition (DEC) of SGTR are estimated by using this method. As a result, there is a possibility to reduce the number of damaged tubes and to suppress the pressure generated by SGTR accidents by using sodium nanofluid in the secondary coolant.
Abe, Yuta; Nagai, Keiichi; Maie, Mitsuyoshi*; Nakano, Natsuko*; Kawashima, Yuichi*; Takesue, Naohisa*; Saito, Junichi
Dai-23-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 5 Pages, 2018/06
no abstracts in English
Saito, Junichi
Nihon Kikai Gakkai Doryoku Enerugi Shisutemu Bumon Nyusu Reta, (56), p.2 - 3, 2017/09
no abstracts in English
Itami, Toshio*; Saito, Junichi; Ara, Kuniaki
Metals, 5(3), p.1212 - 1240, 2015/09
Times Cited Count：2 Percentile：4.14(Materials Science, Multidisciplinary)A new kind of suspension liquid was developed by dispersing Ti nanoparticles (10 nm) in liquid Na, which was then determined by TEM (transmission electron microscopy) analysis. The volume fraction was estimated to be 0.0088 from the analyzed Ti concentration (2 at.%) and the densities of Ti and Na. This suspension liquid, Liquid Sodium containing nanoparticles of titanium (LSnanop), shows, despite only a small addition of Ti nanoparticles, many striking features, namely a negative deviation of 3.9% from the ideal solution for the atomic volume, an increase of 17% in surface tension, a decrease of 11% for the reaction heat to water, and the suppression of chemical reactivity to water and oxygen. The decrease in reaction heat to water seems to be derived from the existence of excess cohesive energy of LSnanop. The excess cohesive energy was discussed based on simple theoretical analyses, with particular emphasis on the screening effect. The suppression of reactivity is discussed with the relation to the decrease of heat of reaction to water or the excess cohesive energy, surface tension, the action as a plug of Ti oxide, negative adsorption on the surface of LSnanop, and percolation.
Saito, Junichi; Itami, Toshio; Ara, Kuniaki
Journal of Nanoparticle Research, 14(12), p.1298_1 - 1298_17, 2012/12
Times Cited Count：4 Percentile：19.69(Chemistry, Multidisciplinary)Saito, Junichi; Ara, Kuniaki
Transactions of the American Nuclear Society, 107(1), p.433 - 436, 2012/11
no abstracts in English
Nishimura, Masahiro; Nagai, Keiichi; Onojima, Takamitsu; Saito, Junichi; Ara, Kuniaki; Sugiyama, Kenichiro*
Journal of Nuclear Science and Technology, 49(1), p.71 - 77, 2012/01
Times Cited Count：4 Percentile：31.96(Nuclear Science & Technology)Oxidation in the early stage of sodium combustion is especially important regarding the aspect of reaction continuity. The purpose of this study is to understand the sodium reaction precisely in order to apply the knowledge of the sodium reaction to promoting further safety of FRs.
Saito, Junichi; Ara, Kuniaki
Nuclear Engineering and Design, 240(10), p.2664 - 2673, 2010/10
Times Cited Count：9 Percentile：52.91(Nuclear Science & Technology)no abstracts in English
Saito, Junichi; Ara, Kuniaki; Sugiyama, Kenichiro*; Kitagawa, Hiroshi*; Nakano, Haruyuki*; Ogata, Kan*; Yoshioka, Naoki*
Proceedings of 16th International Conference on Nuclear Engineering (ICONE-16) (CD-ROM), 4 Pages, 2008/05
no abstracts in English
Saito, Junichi; Ara, Kuniaki; Sugiyama, Kenichiro*; Kitagawa, Hiroshi*; Oka, Nobuki*; Yoshioka, Naoki*
Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 5 Pages, 2007/04
Liquid sodium is used as the coolant of the fast breeder reactor (FBR), because of its high thermal conductivity and wide temperature range of liquid. However the chemical reactivity with water and oxygen of sodium is very high. So an innovative technology to control the reactivity is desired. The purpose of this study is to reduce the chemical reactivity of liquid sodium by dispersing the nanometer-size metallic particles into liquid sodium. Sub-themes of this study are nanoparticles production, evaluation of reaction control of liquid sodium, and feasibility study to FBR. In this paper, we describe the research program of them.
Miyahara, Shinya; Ohno, Shuji; Yamamoto, Nobuhiro; Saito, Junichi; Hirabayashi, Masaru
Proceedings of 14th International Conference on Nuclear Engineering (ICONE-14) (CD-ROM), 7 Pages, 2006/07
The experimental study has been carried out to investigate reaction, transport and settling behavior of lead-bismuth eutectic (LBE) in flowing liquid sodium. In the test, 168 g of LBE were poured into flowing sodium from the top of a vertical-type sodium loop which contained 23.2 kg of sodium. The initial temperature of LBE and sodium was 673 K. The flow rate and the maximum velocity of sodium in the loop were controlled and measured at 20 dm
/min and 1 m/sec, respectively, using an electro-magnetic pump and an electro-magnetic flow meter. The sodium loop has a settling chamber at the lower part to investigate the concentration decrease behavior of solid particle reaction products in the sodium due to the settling effect. The concentration was measured by sodium sampling from the 11 positions of the loop during the experiment and its post-test chemical analysis. The temperature changes at the various parts of the loop were also measured during the experiment by thermo-couples attached on the outer surface of the loop. Ultrasonic detectors were attached on the outer surface of the loop below the position of a LBE pour nozzle to demonstrate the utility as a leak detector.
Saito, Junichi
Proceedings of 13th International Conference on Nuclear Engineering (ICONE-13), 0 Pages, 2005/05
The reaction tests between sodium and lead-bismuth eutectic (LBE) have been carried out changing test temperature and the amount of LBE as the parameters in order to make clear the reaction behavior. From the experiments, it is elucidated that the temperature of liquid sodium rises immediately by dropping LBE. It shows the exothermic reaction between LBE and liquid sodium. Amounts of dissolution of lead and bismuth in sodium increase when the temperature rise is large. They change depending largely on the temperature of reaction. Many fine reaction products are observed in sodium, and the amount of reaction products depends on the amount of dropped LBE. The dominant reaction product is BiNa
which is one of sodium-bismuth binary compounds. A reaction heat calculated from the temperature rise of liquid sodium is comparable to a reaction heat estimated by the standard enthalpy of BiNa. The reaction behavior between sodium and LBE is clarified on the basis of these experimental results.
