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Mukaida, Kyoko; Kato, Atsushi; Kamiya, Masayoshi; Ishii, Katsunori
Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 10 Pages, 2019/05
The levelized cost of electricity is one of key indicator to evaluate economic competitiveness of energy systems. This report estimated the levelized cost of SFR system considering additional safety measures identified after the 1F incident and social cost, using major calculation tools: G4-ECONS and the calculation tool developed by the Governmental WG in Japan (CEWG-tool). The calculation results of G4-ECONS showed that the additional safety measures raise 160% of levelized cost in the case of the safety enhanced SFR system with 1500 MWe of twin looped cooling system. As a result of calculation with 3% discount rate and social cost, the levelized cost of the safety enhanced SFR system with 1200 MWe of Single looped cooling system was estimated 84 mills/kWh by CEWG-tool. This result is almost equal to the estimated levelized cost of similar standard LWR system, and it was indicated the economic competitiveness of the future SFR system.
Mukaida, Kyoko; Kato, Atsushi; Kamiya, Masayoshi; Ishii, Katsunori
Nihon Genshiryoku Gakkai-Shi ATOMO
, 61(1), p.40 - 47, 2019/01
Japan Atomic Energy Agency has proceeded on the research and development (R&D) of fast neutron rector fuel cycle with a system which has economic competitiveness in contrast with light water reactor systems as one of development objectives, from the start of its development. This report shows the evaluation results of generation cost of fast reactor fuel cycle in light of additional safety measure cost and social cost, based on the design of fast reactor and related fuel cycle facilities which considered in FaCT phase I.
Washiya, Tadahiro; Yano, Kimihiko; Kaji, Naoya; Yamada, Seiya*; Kamiya, Masayoshi
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05
On March 11, 2011, a severe nuclear accident occurred at Tokyo Electric Power Company (TEPCO)'s Fukushima Daiichi Nuclear Power Plant (hereinafter called as F1). After the accident, the Council for the Decommissioning was established, mainly by the government and TEPCO, and a road map for the F1 decommissioning was drawn up. In the road map, the fuel debris removal from the reactors is scheduled to launch around 2020. In this study, the characteristics and technological issues of each potential treatment scenario were extracted, and the scenarios were prioritized in advance of formal evaluations in the future. The preliminary evaluation results show that long term storage and direct disposal have more positive aspects in terms of economic efficiency and radioactive waste generation. On the other hand, stabilizing processing, aqueous processing, and pyrochemical processing have been estimated to have more disadvantages in such aspects.
Shibata, Atsuhiro; Yano, Kimihiko; Kamiya, Masayoshi; Nakamura, Kazuhito; Washiya, Tadahiro; Chikazawa, Takahiro*; Kikuchi, Toshiaki*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 8(3), p.245 - 253, 2009/09
Behavior of Cs in U crystallization process of advanced aqueous reprocessing system was investigated with simulated dissolver solution. Beaker-scale U crystallization experiments were carried out with some simulated dissolver solutions. The results show that possibility of generation of CsNO
,Cs
UO (NO)
or Cs-FP complex salt is small. Precipitation experiments of Cs-U(IV) complex salts were also carried out with nitrate solution of U(IV) and Cs. It was found that Cs-U(IV) complex salt was precipitated in higher acidity than 5 mol/dm
. It is suggested that Cs-Pu(IV) precipitates can be generated in the U crystallization process, under specific solution condition.
Nomura, Kazunori; Hinai, Hiroshi; Nakahara, Masaumi; Kaji, Naoya; Kamiya, Masayoshi; Oyama, Koichi; Sano, Yuichi; Washiya, Tadahiro; Komaki, Jun
Proceedings of 3rd International ATALANTE Conference (ATALANTE 2008) (CD-ROM), 5 Pages, 2008/05
Nakahara, Masaumi; Sano, Yuichi; Koma, Yoshikazu; Kamiya, Masayoshi; Shibata, Atsuhiro; Koizumi, Tsutomu; Koyama, Tomozo
Journal of Nuclear Science and Technology, 44(3), p.373 - 381, 2007/03
Times Cited Count：27 Percentile：85.03(Nuclear Science & Technology)Actinides recovery was attempted by the simplified solvent extraction process using TBP as an extractant for U, Pu and Np co-recovery and the SETFICS process for Am and Cm recovery with a view to decreasing the environmental impact. Uranium, Pu and Np co-recovery was conducted under the condition with high nitric acid concentration in the feed solution or scrubbing solution. High nitric acid concentration in the feed solution availed to the Np oxidation not only in the feed solution, but also at the extraction section. This oxidation reaction permitted the Np extraction with U and Pu. In the SETFICS process, a TRUEX solvent of 0.2M CMPO/1.4M TBP was employed to increase the loading of metals. In place of sodium nitrate, HAN was applied to this experimental flow sheet for "salt-free" concept. This experiment was succeeded in Am and Cm product. On high-loading flow sheet, the flow rate of aqueous effluents and spent solvent was expected to decrease in 47% and 54%, respectively.
Nakahara, Masaumi; Sano, Yuichi; Koma, Yoshikazu; Kamiya, Masayoshi; Shibata, Atsuhiro; Koizumi, Tsutomu; Koyama, Tomozo
Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 5 Pages, 2005/10
Concerning the advanced aqueous reprocessing system named NEXT process, the behavior of actinide elements was investigated in main two extraction processes of NEXT process, i.e. the simplified PUREX process for U, Pu and Np recovery, and SETFICS process for Am and Cm recovery.
Koyama, Tomozo; Sano, Yuichi; Kamiya, Masayoshi; Shibata, Atsuhiro
Program and Abstracts, p.50, P. 50, 2005/02
Small scale hot tests have been conducted with irradiated fuel pins of the experimental Fat Reactor
Complex for Super-DIREX ProcessKamiya, Masayoshi; Miura, Sachiko; Nomura, Kazunori; Koyama, Tomozo; Ogumo, Shinya*; Mori, Yukihide*; Enokida, Yoichi*
CD-ROM, P1-35, 4P., 4 Pages, 2004/00
Super-DIREX is a new reprocessing method which has high economical efficiency. Experimental study of this process was started on the direct extraction of U and Pu from irradiated MOX fuel by the supercritical carbon dioxide (SFCO) containing TBP-HNO complex. This report describes direct extraction of U and Pu with TBP-HNO3 complex at atmospheric pressure, as the first test for irradiated fuel, in order to investigate the applicability of SFCO containing TBP-HNO complex. In this test, dependency on dissolution temperature, Pu content, fuel/ TBP-HNO complex ratio and effect of voloxidation were investigated. From these results, TBP-HNO complex was found to be effective in the respect of the recovery of U and Pu. The number of the process step in dissolution and co-extraction is small, and amount of waste can be reduced. It is applicable to the direct extraction in Super-DIREX.
Takata, Takeshi; Koma, Yoshikazu; Sato, Koji; Kamiya, Masayoshi; Shibata, Atsuhiro; Nomura, Kazunori; Ogino, Hideki; Koyama, Tomozo; Aose, Shinichi
Journal of Nuclear Science and Technology, 41(3), 307 Pages, 2004/00
Times Cited Count：29 Percentile：85.25(Nuclear Science & Technology)The design study of aqueous reprocessing system has been progressed for the feasibility study on commercialized fast reactor cycle systems. Based on the PUREX process,an aqueous reprocessing process with the addition of a uranium crystallization step and
Koma, Yoshikazu; Takata, Takeshi; Kamiya, Masayoshi; Sato, Koji
JNC TN9410 2003-010, 112 Pages, 2003/12
JNC-TN9410-2003-010.pdf:4.73MB
This report summarizes the design work made bay the reprocessing Technoplogy Group in 2002 FYJ and includes the followings: advanced aqueous reprocesing, supercritical liquid direct extraction as an alternative, Am and Cm recovery and FP recovery.
Miura, Sachiko; Kamiya, Masayoshi; Nomura, Kazunori; Miyachi, Shigehiko; Koyama, Tomozo; Ogumo, Shinya*; Shimada, Takashi*
Abstracts P.30, 30 Pages, 2003/00
None
; ; Sato, Koji; Kamiya, Masayoshi; Shibata, Atsuhiro; Nomura, Kazunori
Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), P. P380, 2003/00
None
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JNC TY9400 2002-019, 226 Pages, 2002/09
JNC-TY9400-2002-019.pdf:16.3MB
no abstracts in English
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JNC TY9400 2001-014, 489 Pages, 2001/04
JNC-TY9400-2001-014.pdf:17.82MB
no abstracts in English
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JNC TN9400 2001-034, 157 Pages, 2001/01
JNC-TN9400-2001-034.pdf:5.07MB
In Japan Nuclear Cycle Development Institute, the feasibility study has been carried out in order to evaluate various methods of FBR cycle technology and to propose candidate concepts as practical technology. As a part of this, we investigated a process flow diagram and material balance of various recovery systems
for Am and Cm from high level radioactive liquid waste, and we preliminarily evaluated the equipment scale, the cost and waste generation rate of these systems. As a result, it was obtained that these values are about 1.1-1.4, 0.9-1.4 and 1.2-1.5 times, respectively, of the SETFICS process. From these results, the systems we evaluated are considered to be same for the equipment scale at conceptual design stage, and each system is applicable as the recovery system of Am and Cm. But these results suggest that the facility may be much larger than the PUREX plant, in spite of small contents of the materials (Am and Cm) that is to be recovered. Therefore, whichever method is applied to the recovery system of Am and Cm, we need to develop the process in order to make the system more compact and economical. And then, we need to continue to collect information of these systems and new systems and to comparatively evaluate each system. And we should select finally a practical system of recovery for Am and Cm. *1 : various recovery systems to : (1)DIAMEX process + SANEX process (France - CEA) (2)TRPO process + Cyanex process (China) (3)DIDPA process (Japan-JAERI) (4)TALSPEAK process (U.S.A.-ORNL etc.)
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Proceedings of International Conference on; Back-End of the Fuel Cycle; From Research to Solutions (GLOBAL 2001), 0 Pages, 2001/00
None
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JNC TY9400 2000-025, 280 Pages, 2000/07
JNC-TY9400-2000-025.pdf:10.32MB
no abstracts in English
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JNC TN9400 2000-084, 115 Pages, 2000/07
JNC-TN9400-2000-084.pdf:3.24MB
ln JAPAN NUCLEAR CYCLE DEVELOPMENT INSTITUTE, the feasiblity study has been carried out in order to evaluate various methods of FBR cycle technology and to propose candidate concepts of practical technology. As a part of this, we investigated material balance and a process flow diagram of SETFICS process for the recovery system of Am and Cm from high level radioactive liquid waste, and we preliminarily evaluated the equipment scale, the cost and waste generation rate of this system. As a result, it was obtained that these values are about 17, 15 and 10%, respectively, of the recycle plant based on the simplified PUREX process. ln addition, we investigated preliminary flowsheets of 4 recovery systems for Am and Cm, and compared each to each of them. lt was evaluated that the equipment scale of any process was also equivalent. From these results, each system is applicable as the recovery system of Am and Cm. But these results suggest that the facility may be much larger than the PUREX plant, in spite of small contents of the recovery materials in each system. Therefore, whichever method is applied to the recovery system of Am and Cm, we need to develop the process in order to make the system more compact and economical.
