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Miyamoto, Yutaka; Yasuda, Kenichiro; Magara, Masaaki
Journal of Radioanalytical and Nuclear Chemistry, 309(1), p.303 - 308, 2016/07
Times Cited Count：2 Percentile：19.57(Chemistry, Analytical)The technique of sequential separation for U, Th, Pb, lanthanides and Pu using a single anion-exchange column and mixed acids media were developed. An automatic system utilizing a small column and pressurized gas was assembled for this sequential separation. By adjusting the eluent chemical composition for Pu separation, this separation technique has been achieved. Some pieces of tree ring sample were digested, and ultra-trace U and Pu in the samples were separated by this system. The analytical results of U and Pu measured by mass spectrometry will be mentioned.
Tsuchiya, Harufumi; Kitatani, Fumito; Maeda, Makoto; Kureta, Masatoshi
Proceedings of INMM 57th Annual Meeting (Internet), 6 Pages, 2016/07
From a viewpoint of nuclear safeguards and nuclear security, it has recently become important to develop a non-destructive assay (NDA) system that accurately determines the amount of special nuclear materials (SNMs) in various samples such as spent fuels, next generation MA-Pu fuels and fuel debris. One candidate of those NDA techniques is neutron resonance transmission analysis (NRTA). It relies on a neutron time-of-flight measurement and is a well-established method to apply for the accurate evaluations of nuclear data, including total cross sections and resonance parameters. The potential of NRTA to quantify SNM in complex materials has been already demonstrated by performing NRTA measurement at IRMM/GELINA under collaboration of JAEA and JRC. However, a present NRTA system usually has a large electron accelerator facility to generate intense neutrons, whereas this is very difficult to apply to various facilities that need to measure SNM. Therefore a compact NRTA system would be required for practical applications of quantifying SNM in a variety of samples. In order to realize a compact NRTA system, we are developing a prototype with a D-T neutron generator that has a pulse width of 10 
s and an average maximum neutron yield ranging from 
n/s to 
n/s. Numerical calculations were used to optimize the system performance to quantify SNM and MA in spent and MA-Pu fuels. In this presentation, those numerical calculation results, together with a brief description of the prototype, are presented. In addition, we discuss a future prospect of a compact NRTA system equipped with a neutron source with a shorter pulse width (ex. 100 ns) and a more intense neutron yield.
Miyamoto, Yutaka; Suzuki, Daisuke; Esaka, Fumitaka; Magara, Masaaki
Analytical and Bioanalytical Chemistry, 407(23), p.7165 - 7173, 2015/09
Times Cited Count：8 Percentile：31.16(Biochemical Research Methods)Age of individual uranium-plutonium mixed particles with various U/Pu atomic ratios were determined by inductively-coupled plasma mass spectrometry. Micron-sized particles were prepared from U and Pu certified reference materials. The Pu reference was stored for 4-6 years since the last purification. The Pu purification age was obtained from the 
Am/Pu ratio which was calculated from the product of three measured ratios of Pu and Am isotopes in the eluted fractions. Am, U and Pu in a sample solution were sequentially separated a small anion-exchange column. The Am/Pu ratio was accurately determined by spiking pure 
Am to the sample solution. The determined age of particles with various U/Pu ratios was in good agreement with the expected age with high accuracy and high precision.
Miyamoto, Yutaka; Yasuda, Kenichiro; Magara, Masaaki
Analyst, 140(13), p.4482 - 4488, 2015/07
Times Cited Count：6 Percentile：21.49(Chemistry, Analytical)Uranium, Thorium, lead, and the lanthanides were automatically and sequentially separated with a single anion-exchange column. This separation was achieved using eluents consisting of simple and highly pure acid mixture of HCl, HNO
, acetic acid, and HF. This simple, automatic system is driven with pressurized nitrogen gas, and controlled by a computer program. For an evaluation examination, a reference powdered rock sample was separated by using this system. Abundances of objective elements, including 0.23 ng of lutetium, were accurately determined without corrections of chemical recovery yield or subtraction of processing blank. This separation technique saves time and effort for chemical processing, and it is useful for ultra-trace quantitative and isotopic analyses of elements in small environmental samples.
Ishimoto, Takayuki*; Kawasuso, Atsuo; Ito, Hisayoshi
Applied Surface Science, 194(1-4), p.43 - 46, 2002/06
Times Cited Count：9 Percentile：45.19(Chemistry, Physical)no abstracts in English
Usuda, Shigekazu; Adachi, Takeo; Watanabe, Kazuo; Magara, Masaaki; Hanzawa, Yukiko; Esaka, Fumitaka; Miyamoto, Yutaka; Yasuda, Kenichiro; Gunji, Hideho; Tsuruta, Yasuhiro; et al.
Proceedings of Seminar on Strengthening of Safeguards: Integrating the New and the Old, p.477 - 481, 2000/00
no abstracts in English
Hanzawa, Yukiko; Magara, Masaaki; Esaka, Fumitaka; Watanabe, Kazuo; Usuda, Shigekazu; Miyamoto, Yutaka; Gunji, Katsubumi; Yasuda, Kenichiro; Nishimura, Hideo; Adachi, Takeo
Proceedings of OECD/NEA Workshop on Evaluation of Speciation Technology, p.167 - 172, 1999/00
no abstracts in English
Hanzawa, Yukiko; Magara, Masaaki; Esaka, Fumitaka; Watanabe, Kazuo; Usuda, Shigekazu; Gunji, Katsubumi; Yasuda, Kenichiro; Takahashi, Tsukasa; Nishimura, Hideo; Adachi, Takeo; et al.
Proceedings of the Institute of Nuclear Materials Management 40th Annual Meeting (CD-ROM), 7 Pages, 1999/00
no abstracts in English
Usuda, Shigekazu
Heisei-7-Nendo Shin Shisshiki Saishori Shisutemu Gijutsu Kaihatsu To Seika Hokokusho, 0, p.60 - 72, 1996/03
no abstracts in English
8, 1991, Takasaki, JapanTakeshita, Hidefumi; Naramoto, Hiroshi
Journal of Nuclear Science and Technology, 29(4), p.408 - 411, 1992/04
Times Cited Count：1 Percentile：87.25(Nuclear Science & Technology)no abstracts in English
-ray spectra by a semiconductor detector; Pulse height analysis technologyRadioisotopes, 17(10), p.44 - 46, 1968/00
no abstracts in English
Okubo, Ayako; Esaka, Fumitaka; Magara, Masaaki; Shinohara, Nobuo
no journal, ,
To elucidate the final purification date of uranium material namely age-dating is important subject on nuclear forensic analysis. Age-dating of uranium using 
U-
Th nuclide pair was established in the field of geochemical science, and has been applied for nuclear forensics. Recently, safeguard analysis also demand age-dating of uranium materials. In order to measure a small amount of Th by ICP-MS, anion exchange column separation is commonly conducted to eliminate U tailing effect. However, column separation step could raise procedural blank of Th. In contrast, TIMS can separately ionize U and Th in filament heating step using the difference of optical ionization temperature of these elements. We developed analytical method for age-dating of single particle uranium material by TIMS.
Wakaida, Ikuo; Oba, Hironori; Miyabe, Masabumi; Akaoka, Katsuaki; Oba, Masaki; Kato, Masaaki; Ruas, A.
no journal, ,
no abstracts in English
Wakaida, Ikuo; Miyabe, Masabumi; Akaoka, Katsuaki; Oba, Hironori; Taira, Takunori*
no journal, ,
no abstracts in English
Koyama, Shinichi; Ikeuchi, Hirotomo
no journal, ,
no abstracts in English
Koyama, Shinichi
no journal, ,
Current status of JAEA's activities related to fuel debris analysis is introduced.
