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Segawa, Tomoomi; Kawaguchi, Koichi; Kato, Yoshiyuki; Ishii, Katsunori; Suzuki, Masahiro; Fujita, Shunya*; Kobayashi, Shohei*; Abe, Yutaka*; Kaneko, Akiko*; Yuasa, Tomohisa*
Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 9 Pages, 2019/05
A solution of plutonium nitrate and uranyl nitrate is converted into a mixed oxide by microwave heating denitration method. In the present study, for improving the efficiency of microwave heating and achieving high-temperature uniformity to produce homogeneous UO
powder, the microwave heating test of potassium chloride and uranyl nitrate solution, and numerical simulation analysis were conducted. The potassium chloride agar was adjusted to the dielectric loss, which is close to that of the uranyl nitrate solution and the optimum support table height was estimated to be 50 mm for denitration of the uranyl nitrate solution by microwave heating. The adiabator improved the efficiency of microwave heating denitration. Moreover, the powder yield was improved by using the adiabator owing to ease of scraping of the denitration product from the bottom of the denitration vessel.
Watanabe, Hitoshi; Nakano, Masanao; Fujita, Hiroki; Kono, Takahiko; Inoue, Kazumi; Yoshii, Hideki*; Otani, Kazunori*; Hiyama, Yoshinori*; Kikuchi, Masaaki*; Sakauchi, Nobuyuki*; et al.
JAEA-Review 2015-030, 115 Pages, 2015/12
JAEA-Review-2015-030.pdf:25.28MB
Based on the regulations (the safety regulation of Tokai reprocessing plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and bylaw of Ibaraki prefecture), the effluent control of liquid waste discharged from the Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency has been performed. This report describes the effluent control results of the liquid waste in the fiscal year 2014. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other nuclear fuel material usage facilities were much lower than the limits authorized by the above regulations.
Watanabe, Hitoshi; Nakano, Masanao; Fujita, Hiroki; Kono, Takahiko; Inoue, Kazumi; Yoshii, Hideki*; Otani, Kazunori*; Hiyama, Yoshinori*; Goto, Ichiro*; Kibe, Satoshi*; et al.
JAEA-Review 2014-040, 115 Pages, 2015/01
JAEA-Review-2014-040.pdf:4.26MB
Based on the regulations (the safety regulation of Tokai reprocessing plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and bylaw of Ibaraki prefecture), the effluent control of liquid waste discharged from the Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency has been performed. This report describes the effluent control results of the liquid waste in the fiscal year 2013. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other nuclear fuel material usage facilities were much lower than the limits authorized by the above regulations.
Cheng, S.; Tagami, Hirotaka; Yamano, Hidemasa; Suzuki, Toru; Tobita, Yoshiharu; Takeda, Shohei*; Nishi, Shimpei*; Nishikido, Tatsuya*; Zhang, B.*; Matsumoto, Tatsuya*; et al.
Journal of Nuclear Science and Technology, 51(9), p.1096 - 1106, 2014/09
Times Cited Count：25 Percentile：87.38(Nuclear Science & Technology)Cheng, S.; Tagami, Hirotaka; Yamano, Hidemasa; Suzuki, Toru; Tobita, Yoshiharu; Nakamura, Yuya*; Takeda, Shohei*; Nishi, Shimpei*; Zhang, B.*; Matsumoto, Tatsuya*; et al.
Mechanical Engineering Journal (Internet), 1(4), p.TEP0022_1 - TEP0022_16, 2014/08
Sumiya, Shuichi; Watanabe, Hitoshi; Miyagawa, Naoto; Nakano, Masanao; Fujita, Hiroki; Kono, Takahiko; Inoue, Kazumi; Yoshii, Hideki; Otani, Kazunori*; Hiyama, Yoshinori*; et al.
JAEA-Review 2013-041, 115 Pages, 2014/01
JAEA-Review-2013-041.pdf:19.01MB
Based on the regulations (the safety regulation of Tokai reprocessing plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, and the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and bylaw of Ibaraki prefecture), this report describes the effluent control results of liquid waste discharged from the JAEA's Nuclear Fuel Cycle Engineering Laboratories in the fiscal year 2012, from 1st April 2012 to 31st March 2013. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other facilities were much lower than the authorized limits of the above regulations.
Cheng, S.; Yamano, Hidemasa; Suzuki, Toru; Tobita, Yoshiharu; Nakamura, Yuya*; Takeda, Shohei*; Nishi, Shimpei*; Zhang, B.*; Matsumoto, Tatsuya*; Morita, Koji*
Proceedings of 21st International Conference on Nuclear Engineering (ICONE-21) (DVD-ROM), 8 Pages, 2013/07
Sugimoto, Masayoshi; Imai, Tsuyoshi; Okumura, Yoshikazu; Nakayama, Koichi*; Suzuki, Shohei*; Saigusa, Mikio*
Journal of Nuclear Materials, 307-311(Part2), p.1691 - 1695, 2002/12
Times Cited Count：2 Percentile：17.03(Materials Science, Multidisciplinary)International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based intense neutron source for fusion reactor materials development. Each one of the two accelerator modules needs to have a capability to provide the 40MeV/125mA deuteron beam continuously. Although the technology to produce the 7MeV/100mA proton beam is already verified using 350 MHz linac in the past, an engineering study using a prototype is necessary to verify the performance of IFMIF 175 MHz deuteron linac, and Engineering Validation Phase (EVP) is planned for this purpose. Some critical design parameters, like final and transition energies of linacs or RF source characteristics, are needed to be optimised for the prototype. As it is also important to verify the essential component technology, e.g. ion source, RFQ beam matching, rf system components, etc., the present status and expected results of such undergoing verification tests are described. An integrated concept of prototype accelerator is shown as a Japanese proposal for EVP to provide for the international discussion.
Sawa, Kazuhiro; Sumita, Junya; Ueta, Shohei; Takahashi, Masashi; Tobita, Tsutomu*; Hayashi, Kimio; Saito, Takashi; Suzuki, Shuichi*; Yoshimuta, Shigeharu*; Kato, Shigeru*
JAERI-Research 2002-012, 39 Pages, 2002/06
JAERI-Research-2002-012.pdf:3.12MB
no abstracts in English
Ino, Hiroichi*; Ueta, Shohei; Suzuki, Hiroshi; Tobita, Tsutomu*; Sawa, Kazuhiro
JAERI-Tech 2001-083, 46 Pages, 2002/01
JAERI-Tech-2001-083.pdf:6.31MB
no abstracts in English
Sawa, Kazuhiro; Sumita, Junya; Ueta, Shohei; Suzuki, Shuichi*; Tobita, Tsutomu*; Saito, Takashi; Minato, Kazuo; Koya, Toshio; Sekino, Hajime
Journal of Nuclear Science and Technology, 38(6), p.403 - 410, 2001/06
Times Cited Count：7 Percentile：48.68(Nuclear Science & Technology)no abstracts in English
Sawa, Kazuhiro; Tobita, Tsutomu*; Ueta, Shohei; Suzuki, Shuichi*; Sumita, Junya; Sekita, Kenji; Aoki, Kazunori*; Ouchi, Hiroshi
JAERI-Research 2001-002, 33 Pages, 2001/02
JAERI-Research-2001-002.pdf:1.42MB
no abstracts in English
Kato, Shohei; Inoue, Yasushi*; Kaneko, Masato*; Kai, Michiaki*; Fujimoto, Kenzo*; Suzuki, Seishiro*; Takaue, Tamiji*; Kumagai, Tetsuyuki*
Hoken Butsuri, 35(3), p.319 - 326, 2000/09
no abstracts in English
Nakamura, Yuya*; Gondai, Yoji*; Cheng, S.*; Takeda, Shohei*; Zhang, B.*; Matsumoto, Tatsuya*; Morita, Koji*; Yamano, Hidemasa; Tagami, Hirotaka; Suzuki, Toru; et al.
no journal, ,
In order to clarify the characteristics of debris bed behavior in the post accident heat removal phase in the core disruptive accidents of FBR, an experimental study to simulate the coolant boiling in debris bed by gas injection from the bottom of the bed and basic knowledge on the self-leveling characteristic for large vapor velocity was obtained.
Nishimura, Kazuaki; Tanaka, Hideki; Kobayashi, Daisuke; Suzuki, Shohei; Numata, Shinji; Nakamichi, Hideo; Kurita, Tsutomu; Iida, Masayoshi*; Tajiri, Kazuma*; Sukegawa, Katsumi*
no journal, ,
no abstracts in English
Suzuki, Seiya; Arai, Yoichi; Okamura, Nobuo; Watanabe, Masayuki; Kawano, Shohei*; Kawarada, Yoshiyuki*
no journal, ,
The water glass type neutron absorber has been developed as a measure to precaution of re-criticality during fuel debris retrieval. Since the neutron absorber covers the surface of the fuel debris, the drying of the water content of the fuel debris was suggested to be hindered. The drying test using the mock test piece was carried out in order to evaluate the effect on the drying behavior when the surface of the fuel debris is covered with the neutron absorber. We investigate the drying characteristic curve of the mock test piece by thermogravimetric analysis, and report the evaluation of drying behavior.
Arai, Yoichi; Suzuki, Seiya; Okamura, Nobuo; Watanabe, Masayuki; Kawano, Shohei*; Kawaharada, Yoshiyuki*
no journal, ,
The water glass type neutron absorber has been developed as a measure to precaution of re-criticality during fuel debris retrieval from nuclear reactor, etc. Since the surface of the fuel debris is covered with the neutron absorber, the coating of the neutron absorber was suggested to inhibit the evaporation of water in the debris during the drying process of fuel debris. The drying test using the mock test piece was carried out in order to evaluate the effect on the drying behavior when the surface of the fuel debris is covered with the neutron absorber. The outline and basic study of the drying test will be reported in this presentation.
Suzuki, Seiya; Arai, Yoichi; Watanabe, Masayuki; Kawano, Shohei*; Kawaharada, Yoshiyuki*
no journal, ,
The water glass type neutron absorber has been developed as a measure to precaution of re-criticality during fuel debris retrieval at the Fukushima Daiichi Nuclear Power Plant. The drying test using the mock test piece was carried out in order to evaluate the effect on the drying behavior. In this report, the scale-up tests was shown.
