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Kawasaki, Kohei; Shinada, Kenta; Okamoto, Naritoshi; Kageyama, Tomio; Eda, Takashi; Okazaki, Hiro; Suzuki, Hiromichi; Yamamoto, Kazuya; Otabe, Jun
JAEA-Technology 2020-025, 80 Pages, 2021/03
JAEA-Technology-2020-025.pdf:3.72MB
Plutonium Fuel Production Facility was built in 1988 for the purpose of mainly producing MOX fuel of the prototype fast breeder reactor MONJU, and large glove boxes were installed for handling unsealed nuclear fuel material remotely. The panels of these glove boxes are made of acrylic, except for those installed after December 2013. For fires inside the glove box, automatic fire extinguishing systems using halides have been introduced since the beginning of construction, but for fires outside the glove box, there have been issues with direct measures for acrylic. Therefore, we have developed a fireproof sheet that mitigates the effect of fire outside the glove box on the panels as much as possible. As a result, fire-retardant sheets have been selected and attached to the glove box panels. We conducted a flammability test of the acrylic plate attached with these fireproof sheets and a usage environment influence test of fireproof sheets, and obtained good results. In addition, we set up a working group in the Plutonium Fuel Development Center in view of reducing external exposure during the work of attaching fireproof sheets, in which we discussed and examined the work procedure, and summarized it in the basic procedure manual.
Noda, Yohei*; Koizumi, Satoshi*; Masui, Tomomi*; Mashita, Ryo*; Kishimoto, Hiromichi*; Yamaguchi, Daisuke; Kumada, Takayuki; Takata, Shinichi; Oishi, Kazuki*; Suzuki, Junichi*
Journal of Applied Crystallography, 49(6), p.2036 - 2045, 2016/12
Times Cited Count：22 Percentile：76.88(Chemistry, Multidisciplinary)Amamoto, Ippei; Kobayashi, Hidekazu; Kitamura, Naoto*; Takebe, Hiromichi*; Mitamura, Naoki*; Tsuzuki, Tatsuya*; Fukayama, Daigen*; Nagano, Yuichi*; Jantzen, T.*; Hack, K.*
Journal of Nuclear Science and Technology, 53(10), p.1467 - 1475, 2016/10
Times Cited Count：5 Percentile：37.50(Nuclear Science & Technology)The iron phosphate glass (IPG) medium is known to be a high-efficiency glass medium, therefore we try to evaluate its applicability to immobilize sludge bearing radioactive nuclides arising from treatment of contaminated water at the stricken Fukushima Daiichi Nuclear Power Plant. For this study, many physical and chemical properties of target materials are necessary to evaluate the behaviours of IPG medium and its waste forms. Inevitably, it will entail the need for many and varied types of experiments to be carried out under high temperature. It is therefore rational to apply appropriate theoretical analysis first so as to reduce the number of experimental run. For this reason, some necessary thermodynamic values for theoretical analysis were estimated by CALPHAD approach followed by making up the calculated phase diagrams. By comparison with experimental results, they were found to be reliable for evaluating the behaviours of IPG medium and its waste forms.
Takamatsu, Misao; Kawahara, Hirotaka; Ito, Hiromichi; Ushiki, Hiroshi; Suzuki, Nobuhiro; Sasaki, Jun; Ota, Katsu; Okuda, Eiji; Kobayashi, Tetsuhiko; Nagai, Akinori; et al.
Nihon Genshiryoku Gakkai Wabun Rombunshi, 15(1), p.32 - 42, 2016/03
In the experimental fast reactor Joyo, it was confirmed that the top of the irradiation test sub-assembly of "MARICO-2" (material testing rig with temperature control) had been broken and bent onto the in-vessel storage rack as an obstacle and had damaged the upper core structure (UCS). This paper describes the results of the in-vessel repair techniques for UCS replacement, which are developed in Joyo. UCS replacement was successfully completed in 2014. In-vessel repair techniques for sodium cooled fast reactors (SFRs) are important in confirming its safety and integrity. In order to secure the reliability of these techniques, it was necessary to demonstrate the performance under the actual reactor environment with high temperature, high radiation dose and remained sodium. The experience and knowledge gained in UCS replacement provides valuable insights into further improvements for In-vessel repair techniques in SFRs.
Ito, Hiromichi; Suzuki, Nobuhiro; Kobayashi, Tetsuhiko; Kawahara, Hirotaka; Nagai, Akinori; Sakao, Ryuta*; Murata, Chotaro*; Tanaka, Junya*; Matsusaka, Yasunori*; Tatsuno, Takahiro*
Proceedings of 2015 International Congress on Advances in Nuclear Power Plants (ICAPP 2015) (CD-ROM), p.1058 - 1067, 2015/05
In the experimental fast reactor Joyo (Sodium-cooled Fast Reactor (SFR)), it was confirmed that the top of the irradiation test sub-assembly had bent onto the in-vessel storage rack as an obstacle and had damaged the upper core structure (UCS). There is a risk of deformation of the UCS and guide sleeve (GS) caused by interference between them unless inclination is controlled precisely. To mitigate the risk, special jack-up equipment for applying three-point suspension was developed. The existing damaged UCS (ed-UCS) jack-up test using the jack-up equipment was conducted on May 7, 2014. As a result of this test, it was confirmed that the ed-UCS could be successfully jacked-up to 1000 mm without consequent overload. The experience and knowledge gained in the ed-UCS jack-up test provides valuable insights and prospects not only for UCS replacement but also for further improving and verifying repair techniques in SFRs.
Nakamura, Mitsutaka; Kambara, Wataru; Krist, T.*; Shinohara, Takenao; Ikeuchi, Kazuhiko*; Arai, Masatoshi; Kajimoto, Ryoichi; Nakajima, Kenji; Tanaka, Hiromichi; Suzuki, Junichi*; et al.
Nuclear Instruments and Methods in Physics Research A, 737, p.142 - 147, 2014/02
Times Cited Count：3 Percentile：25.09(Instruments & Instrumentation)The efficiency of inelastic neutron scattering measurements using a chopper spectrometer can be markedly improved by utilizing multiple incident energies (Multi-Ei method). However, in conventional chopper systems, optimization of the experimental condition for all incident energies is absolutely impossible. We developed a new Fermi chopper with a supermirror-coated slit package in order to overcome the problem and experimentally demonstrated that the full optimization of the experimental condition for multiple incident energies is nearly achieved.
as the dominant sludge constituent generated from the treatment of water used for cooling the stricken power reactorsAmamoto, Ippei; Kobayashi, Hidekazu; Yokozawa, Takuma; Yamashita, Teruo; Nagai, Takayuki; Kitamura, Naoto*; Takebe, Hiromichi*; Mitamura, Naoki*; Tsuzuki, Tatsuya*
Proceedings of the ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM2013) (CD-ROM), 8 Pages, 2013/09
The great amount of water used for cooling the stricken power reactors at Fukushima Dai-ichi has resulted in accumulation of "remaining water". As the remaining water is subsequently contaminated by FPs, etc., it is necessary to decontaminate it in order to reduce the volume of liquid radioactive waste and to reuse it again for cooling the reactors. Various techniques are being applied to remove FP, etc. and to make stable waste forms. One of the methods using the iron phosphate glass as a medium is being developed to stabilize the strontium-bearing sludge whose main component is BaSO. From the results hitherto, the iron phosphate glass is regarded as a potential medium for the target sludge.
Kobayashi, Hidekazu; Amamoto, Ippei; Yokozawa, Takuma; Yamashita, Teruo; Nagai, Takayuki; Kitamura, Naoto*; Takebe, Hiromichi*; Mitamura, Naoki*; Tsuzuki, Tatsuya*
Proceedings of the ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM2013) (CD-ROM), 6 Pages, 2013/09
no abstracts in English
Ijiri, Yuji*; Hattori, Hiromichi*; Suzuki, Shunichi*; Oishi, Masaya*; Kubota, Shigeru*; Adachi, Tetsuya*; Yamamoto, Takuya*
JNC TJ8400 2001-010, 143 Pages, 2001/03
JNC-TJ8400-2001-010.pdf:17.19MB
The evaluation of uncertainty of geological environment is a key issue in assessing a performance of a deep geological disposal system for high-level nuclear waste. The geological environment uncertainty is arose from data obtained from surveys and model used for a performance assessment.The objectives of this study is to develop a rational planning methodology of site characterization using the Horonobe site as a model case, and to establish a modeling methodology using the Tono site as a model case. At the Horonobe site, first, a conceptual model is constructed based on the information at every stage of site characterization procedure. A sensitivity analysis is performed using various conceptual models and data. If conceptual models uncertainty have a great impact on the result of performance assessment analysis, surveys that detect the most appropriate conceptual model are conducted in the next stage of site characterization. If data uncertainty have a great impact on the result of performance assessment analysis, surveys that decrease the data uncertainty are conducted. Thus, a rational site characterization methodology in which the most sensitive items are preferentially detected in the next stage of site characterization is developed. This concept of a rational site characterization methodology is described in this report. In addition, preliminary conceptual model is developed based on geological information around Horonobe site, and data uncertainty for the sensitivity analysis which will be conducted in next year is investigated. At the Tono site, literature on model uncertainty is surveyed, and data obtained at the Tono site is reviewed from modeling point of view.
Ijiri, Yuji*; Hattori, Hiromichi*; Suzuki, Shunichi*; Oishi, Masaya*; Kubota, Shigeru*; Adachi, Tetsuya*; Yamamoto, Takuya*; Igarashi, Takafumi*; Sugihara, Yutaka*
JNC TJ8400 2001-009, 41 Pages, 2001/03
JNC-TJ8400-2001-009.pdf:6.69MB
no abstracts in English
Akiyama, Kazuhiko; Zhao, Y.*; Sueki, Keisuke*; Tsukada, Kazuaki; Haba, Hiromitsu; Nagame, Yuichiro; Kodama, Takeshi*; Suzuki, Shinzo*; Otsuki, Tsutomu*; Sakaguchi, Masahiko*; et al.
Journal of the American Chemical Society, 123(1), p.181 - 182, 2001/01
Times Cited Count：67 Percentile：84.71(Chemistry, Multidisciplinary)no abstracts in English
Nagao, Seiya; Nakaguchi, Yuzuru*; Suzuki, Yasuhiro*; Hiraki, Keizo*; Fujitake, Nobuhide*; Ogawa, Hiromichi
Proceedings of International Conference on the Biogeochemistry of Trace Elements (ICOBTE2001), P. 666, 2001/00
no abstracts in English
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glass system in waterKitamura, Naoto*; Saito, Akira*; Takebe, Hiromichi*; Amamoto, Ippei; Kobayashi, Hidekazu; Tsuzuki, Tatsuya*; Mitamura, Naoki*
no journal, ,
no abstracts in English
Ushiki, Hiroshi; Ito, Hiromichi; Okuda, Eiji; Suzuki, Nobuhiro; Sasaki, Jun; Ota, Katsu; Kawahara, Hirotaka; Takamatsu, Misao; Nagai, Akinori; Okawa, Toshikatsu
no journal, ,
In the experimental fast reactor Joyo, it was confirmed that the top of the irradiation test sub-assembly of MARICO-2 (material testing rig with temperature control) had bent onto the in-vessel storage rack as an obstacle and had damaged the upper core structure (UCS) in 2007. As a part of the restoration work, UCS replacement was begun at March 24, 2014 and was completed at December 17. In-vessel repair (including observation) for sodium-cooled fast reactors (SFRs) is distinct from that for light water reactors and necessitates independent development. Application of developed in-vessel repair techniques to operation and maintenance of SFRs enhanced their safety and integrity. There is little UCS replacement experience in the world and this experience and insights, which were accumulated in the replacement work of in-vessel large sturucture (UCS) used for more than 30 years, are expected to improve the in-vessel repair techniques in SFRs.
on the properties and structure of iron phosphate glassNomura, Akira*; Kitamura, Naoto*; Saito, Akira*; Sakamoto, Tatsuaki*; Takebe, Hiromichi*; Kobayashi, Hidekazu; Amamoto, Ippei; Nakamura, Hiroki*; Mitamura, Naoki*; Tsuzuki, Tatsuya*
no journal, ,
no abstracts in English
Suzuki, Hiromichi; Sato, Mitsuhiro; Taguchi, Yusuke; Kageyama, Tomio; Ninagawa, Junichi; Shiromo, Hideo
no journal, ,
Ensuring robust nuclear security measures are required for the facilities located Plutonium Fuel Development Center as one of licensees of nuclear facilities that have multiple category I facilities. In order to continuously ensure and strengthen nuclear security measures in those facilities, an active cultivation of nuclear security culture implemented by both entire organization and individual persons is vitally essential. Therefore, Plutonium Fuel Development Center has conducted various activities such as case-study education and training, yearly posters and patrolling the site by upper-level management that all employees hold a deep-rooted belief that there is a credible insider and outsider threat, and that nuclear security is important. These activities are conducted in order to establish the foundation of beliefs and attitudes of effective nuclear security culture. This report introduces our activities fostering nuclear security culture in Plutonium Fuel Development Center that the evaluation and the continuous improvement of bidirectional activities by both top-down from multiple management levels and bottom-up from individual employee.
Nakamura, Mitsutaka; Kambara, Wataru; Shinohara, Takenao; Ikeuchi, Kazuhiko*; Kajimoto, Ryoichi*; Krist, T.*; Tanaka, Hiromichi; Suzuki, Junichi*; Harada, Masahide; Oikawa, Kenichi; et al.
no journal, ,
Amamoto, Ippei; Kobayashi, Hidekazu; Yamashita, Teruo; Nagai, Takayuki; Kitamura, Naoto*; Takebe, Hiromichi*; Mitamura, Naoki*; Tsuzuki, Tatsuya*; Fukayama, Daigen*; Nagano, Yuichi*; et al.
no journal, ,
no abstracts in English
Kobayashi, Hidekazu; Amamoto, Ippei; Kitamura, Naoto*; Takebe, Hiromichi*; Mitamura, Naoki*; Tsuzuki, Tatsuya*
no journal, ,
no abstracts in English
by the IPG mediumAmamoto, Ippei; Kobayashi, Hidekazu; Yokozawa, Takuma; Yamashita, Teruo; Nagai, Takayuki; Kitamura, Naoto*; Takebe, Hiromichi*; Mitamura, Naoki*; Tsuzuki, Tatsuya*
no journal, ,
no abstracts in English
