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Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.
Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07
This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.
Okano, Masanori; Akiyama, Kazuki; Taguchi, Katsuya; Nagasato, Yoshihiko; Omori, Eiichi
Dekomisshoningu Giho, (57), p.53 - 64, 2018/03
The construction of Tokai Reprocessing Plant (TRP) was initiated in June 1971, and its hot test using spent fuel started in September 1977. Thereafter TRP had been operated to reprocess 1,140 tons of spent fuel for approximately 30 years until May 2007, according to the reprocessing contract with domestic electric power companies. JAEA announced a policy of TRP in report of JAEA reform plan published in September 2014. The policy shows that TRP will shift to a decommissioning stage by economic reasons. Based on the policy, application of approval for TRP decommissioning plan was submitted to Nuclear Regulation Authority (NRA) in June 2017. This plan provides basic guidelines such as procedures for decommissioning and specific activities for risk reduction, and implementation divisions of decommissioning, management of spent fuels and radioactive wastes, decommissioning budget, and decommissioning schedule. The process of TRP decommissioning is planned to continue for approximately 70 years until the release of controlled areas of approximately 30 facilities.
Nakahara, Masaumi; Kaji, Naoya; Yano, Kimihiko; Shibata, Atsuhiro; Takeuchi, Masayuki; Okano, Masanori; Kuno, Takehiko
Journal of Chemical Engineering of Japan, 46(1), p.56 - 62, 2013/01
Times Cited Count：1 Percentile：6.16(Engineering, Chemical)The influence of HNO
concentration in the solution on the formation of Cs
Pu(NO)
was evaluated in the U crystallization process. The solubility of CsPu(NO) in a uranyl nitrate solution was found to decrease with increasing HNO concentration in the solution. In the U crystallization experiments with the dissolver solution of irradiated fast reactor fuel, CsPu(NO) formed with 6.5 mol/dm
HNO concentration in the mother liquor, and the decontamination factor of Cs for the uranyl nitrate hexahydrate crystals was low. Meanwhile, CsPu(NO) did not precipitate with uranyl nitrate hexahydrate crystals under the condition of 4.0 mol/dm HNO concentration in the mother liquor, and Cs could be separated from the uranyl nitrate hexahydrate crystals.
Sr and 
Sr in water accumulated in turbine building at Fukushima DaiichiAsai, Shiho; Okano, Masanori; Kameo, Yutaka
Hosha Kagaku Nyusu, (25), p.25 - 28, 2012/03
no abstracts in English
Nakahara, Masaumi; Yano, Kimihiko; Shibata, Atsuhiro; Takeuchi, Masayuki; Okano, Masanori; Kuno, Takehiko
Procedia Chemistry, 7, p.282 - 287, 2012/00
Times Cited Count：1 Percentile：55.63(Chemistry, Analytical)For decontamination of Cs and Pu compound, CsPu(NO), precipitated in the U cooling crystallization method, solubility measurement of CsPu(NO) in a uranyl nitrate solution and a U crystallization experiments were carried out with the dissolver solution derived from irradiated fast neutron reactor core fuel. The solubility of CsPu(NO) in the uranyl nitrate solution decreased with decreasing temperature. In the crystallization experiments, the decontamination factors of Cs and Pu for uranyl nitrate hexahydrate crystal decrease with increasing the Cs concentration in the feed solution because CsPu(NO) formed in the course of U crystallization. Basic data were obtained for the formation behavior of CsPu(NO) in the U crystallization process.
Okano, Masanori; Jitsukata, Shu*; Kuno, Takehiko; Yamada, Keiji
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12
Okano, Masanori; Kuno, Takehiko; Nemoto, Hirokazu*; Yamada, Keiji; Watahiki, Masaru; Hiyama, Toshiaki
Proceedings of INMM 50th Annual Meeting (CD-ROM), 9 Pages, 2009/07
no abstracts in English
Okano, Masanori; Kuno, Takehiko; Takahashi, Ichiro*; Shirozu, Hidetomo; Charlton, W. S.*; Wells, C. A.*; Hemberger, P. H.*; Yamada, Keiji; Sakai, Toshio
JAEA-Technology 2006-055, 38 Pages, 2006/12
JAEA-Technology-2006-055.pdf:3.33MB
The amount of Pu in the spent fuel was evaluated from Xe isotopic ratio in off-gas in reprocessing facility, is related to burnup. Six batches of dissolver off-gas at spent fuel dissolution process were sampled from the main stack in Tokai Reprocessing Plant during BWR fuel reprocessing campaign. Xenon isotopic ratio was determined with GC/MS. Burnup and generated amount of Pu were evaluated with Noble Gas Environmental Monitoring Application code (NOVA), developed by Los Alamos National Laboratory. Inferred burnup evaluated by Xe isotopic measurements and NOVA were in good agreement with those of the declared burnup in the range from -3.8% to 7.1%. Also, the inferred amount of Pu in spent fuel was in good agreed with those of the declared amount of Pu calculated by ORIGEN code in the range from -0.9% to 4.7%. The evaluation technique is applicable for both burnup credit to achieve efficient criticality safety control and a new measurement method for safeguards inspection.
Kuno, Takehiko; Nakamura, Yoshinobu; Okano, Masanori; Sato, Soichi; Watahiki, Masaru
Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 3 Pages, 2005/10
The elemental composition and amount of insoluble materials in highly active liquid waste (HALW) were measured at the Tokai Reprocessing Plant. To evaluate the composition of the insoluble material between the treatment and storage processes, samples from the evaporator and two vessels which differ in the storage period, were taken. The concentration of insoluble material evaluated by both its weight on filter paper after filtration as well as by filtration volume showed no difference for three different samples. Inductively coupled plasma atomic emission spectrometry and isotope dilution mass spectrometry were used to determine the elements in samples dissolved by sulfate fusion. Analytical data revealed that Zr and Mo were the main components of the insoluble material in three samples, but low levels of Rh, Ru and Pd were also present. These results suggest that most of insoluble material had re-precipitated from the HALW solution during the concentration process.
Okano, Masanori; Kuno, Takehiko; Charlton, W. S.*; Wells, C. A.*; Hemberger, P. H.*
46th Annual Meeting of the INMM, Final Program, Abstract 352, 0 Pages, 2005/07
According to achieve the International Atomic Energy Agency's safeguards criteria, development of simple and rapid determination method of Pu amount in the spent fuel has been required. It is known that stable xenon isotopes produced with fission reflect spent fuel characteristics (fuel type, burn up, Pu amount). Since dissolver off-gas which is released with dissolution of spent fuel in reprocessing facility, contains most of gaseous fission products, xenon isotopic ratio in dissolver off-gas sampled from the stack would be expected to provide a new measurement method for application to safeguards inspection. We have studied a new technique to evaluate Pu isotopic ratio and its amount in the fuel from Xe isotopic ratio, which is related to burn up. The technique is also applicable for evaluating burn up credit to achieve efficient critical safety control. Six batches of off gas from dissolution process, DOG: Dissolver off gas, were obtained with press pump from the stack in Tokai Reprocessing Plant at BWR fuel (approx. 30GWD/MTU) reprocessing campaign. Xe isotopic ratio was determined with Gas Chromatography- Quadrupole Mass Spectrometer, GC-QMS. Xe concentrations in the DOGs sampled at the stack were 1,000 to 10,000 ppm, which were enough concentrations for determining minor Xe isotopes. We evaluate burn up and Pu amount with NOVA, Noble Gas Environmental Monitoring Application code, developed by Los Alamos National Laboratory. Inferred burn up was realized 94% of confidences level, which is the conventional definition based on the standard deviation of the results. We also calculated Pu amount in the spent fuel by ORIGEN code based on declared burn up. Based on the two different evaluations for Pu amount, we found that there is 7% difference between NOVA and ORIGEN code. It is summarized that there is possibility of developed method being used newly burn up monitoring and safeguards technique.
Okano, Masanori; Kuno, Takehiko; Takahashi, Ichiro*; Charlton, W. S.*; Wells, C. A.*; Hemberger, P. H.*
46th Annual Meeting of the INMM, Final Program, Abstract 352, 0 Pages, 2005/07
We have studied a new technique to evaluate Pu amount in the spent fuel from Xe isotopic ratio in off-gas in reprocessing facility, which is related to burn up. The technique is applicable for both burn up credit to achieve efficient criticality safety control and a new measurement method for safeguards inspection. Six batches of dissolver off-gas (DOG) at spent fuel dissolution process were sampled with press pump from the main stack in Tokai Reprocessing Plant (TRP) during BWR fuel (approx. 30GWD/MTU) reprocessing campaign. Xe isotopic ratio was determined with Gas Chromatography-Quadrupole Mass Spectrometer (GC-QMS). Burn up and Pu amount were evaluated with NOVA, Noble Gas Environmental Monitoring Application code, developed by Los Alamos National Laboratory. Agreement between declared burn up and inferred burn up evaluated by Xe isotopic measurements and NOVA was at the 94% confidence level. We found that Pu amount in spent fuel evaluated by developed method agreed with declared value calculated by ORIGEN code in the range of -0.9% to 4.7%.
Konomura, Mamoru; Ogawa, Takashi; Okano, Yasushi; Yamaguchi, Hiroyuki; Murakami, Tsutomu; Takaki, Naoyuki; Nishiguchi, Youhei; Sugino, Kazuteru; Naganuma, Masayuki; Hishida, Masahiko; et al.
JNC TN9400 2004-035, 2071 Pages, 2004/06
JNC-TN9400-2004-035.pdf:76.42MB
The attractive concepts for Sodium-, lead-bismuth-, helium- and water-cooled FBRs have been created through using typical plant features and employing advanced technologies. Efforts on evaluating technological prospects of feasibility have been paid for these concepts. Also, it was comfirmed if these concepts satisfy design requierments of capability and performance presumed in the feasibilty study on commertialization of Fast Breeder Reactor Systems. As results, it was concluded that the selection of sodium-cooled reactor was most rational for practical use of FBR technologies in 2015.
Kuno, Takehiko; Okano, Masanori; Sato, Soichi; ; Jitsukata, Shu*
Final Program Abst. P.60, 60 Pages, 2003/00
Sr, Sr in high radioactive liquid wastes of Fukushima Daiichi Nuclear Power StationOkano, Masanori; Jitsukata, Shu*; Nemoto, Hirokazu*; Asai, Shiho; Kameo, Yutaka; Kuno, Takehiko; Yamada, Keiji
no journal, ,
no abstracts in English
nuclides in the high radioactive Cs component samples by the Solid-phase extraction disk for removal of Cs / spectrometryYamazaki, Yuki*; Okano, Masanori; Jitsukata, Shu*; Kuno, Takehiko; Kurosawa, Akira
no journal, ,
no abstracts in English
Suwa, Toshio; Okano, Masanori; Jitsukata, Shu*; Nemoto, Hirokazu*; Kuno, Takehiko; Kurosawa, Akira
no journal, ,
no abstracts in English
Hashimoto, Kowa; Okano, Masanori; Taguchi, Katsuya; Nagasato, Yoshihiko
no journal, ,
The Tokai Reprocessing Plant has many facilities, various installation and complicated systems, which are contaminated by radioactive materials. Based on this feature, JAEA estimated its waste generation and the cost for decommissioning by using common and reasonable condition for many and complicated facilities.
Okano, Masanori; Kuno, Takehiko; Yamada, Keiji; Sakai, Toshio
no journal, ,
no abstracts in English
Igarashi, Kazuto*; Nemoto, Hirokazu*; Okano, Masanori; Yamada, Keiji; Sakai, Toshio
no journal, ,
no abstracts in English
Okano, Masanori; Igarashi, Kazuto*; Nemoto, Hirokazu*; Yamada, Keiji; Sakai, Toshio
no journal, ,
no abstracts in English
