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; Ito, Masahito
Journal of Nuclear Science and Technology, 39(7), p.771 - 777, 2002/07
Times Cited Count：19 Percentile：74.68(Nuclear Science & Technology)None
; Hirosawa, Takashi
Journal of Nuclear Science and Technology, 39(7), p.771 - 777, 2002/00
None
; Hirosawa, Takashi
Journal of Nuclear Science and Technology, 36(7), p.596 - 604, 1998/10
Times Cited Count：13 Percentile：66.16(Nuclear Science & Technology)None
Sato, Isamu*; *; ; Arima, Tatsumi*;
PNC TY9606 98-003, 99 Pages, 1998/06
no abstracts in English
; Hirosawa, Takashi
Journal of Nuclear Science and Technology, 35(7), p.494 - 501, 1998/00
None
Koyama, Shinichi; ; ; Mitsugashira, Toshiaki; Morozumi, Katsufumi;
Journal of Nuclear Science and Technology, 35(6), 406 Pages, 1998/00
Times Cited Count：13 Percentile：70.9(Nuclear Science & Technology)None
Np transmutation characteristics with chemical analysis of neptunium dosimeter irradiated in "Joyo"Osaka, Masahiko; Koyama, Shinichi; Otsuka, Yuko; Mitsugashira, Toshiaki; Namekawa, Takashi; Konno, Koichi
PNC TN9410 98-020, 70 Pages, 1997/12
The purpose of this study is to evaluate transmutation characteristics such as dependence of Np transmutation rate to neutron energy spectrum and neutron fluences. Analysis of the Neptunium dosimeter, in which was irradiated in the experimental fast reactor "Joyo", was carried out by applying the technique for analysis of minor actinide nuclides in irradiated MOX fuel. It is necessary to remove Vanadium before analysis of Neptunium dosimeter because NpO
powder was enclosed in Neptunium dosimeter that was made of Vanadium capsule. The result of analysis and evaluations are as follows. (1)In order to recover Neptunium sample completely, sample was dissolved with capsule before removing the Vanadium from sample solution. Sample treatment method of whole capsule dissolution for chemical analysis of Neptunium dosimeter was established. (2)Np, Plutonium isotopes, 
Am and 
Cs in the dosimeter were analyzed using the method of whole capsule dissolution, alpha spectrometry, gamma spectrometry and isotopic dilution mass spectrometry. Transmutation rate of Np was calculated using the analyzed value. Tendency of transmutation rate was certified, which is higher fission ratio at the center and higher capture ratio at both upper and lower end. (3)Transmutation rate with error was evaluated by neutron fluences considering the neutron energy spectrum, and calculated value by "MAGI" code was agreed well with analysis value. Dependence of transmutation rate of Np to neutron energy spectrum was certified.
Koyama, Shinichi; ; Osaka, Masahiko; ; ; Mitsugashira, Toshiaki
Proceedings of International Conference on Future Nuclear Systems (Global'97), Vol.2, 0 Pages, 1997/10
no abstracts in English
Sato, Isamu*; *; ; Arima, Tatsumi*; ; Kajitani, Yukio
PNC TY9606 97-001, 117 Pages, 1997/07
no abstracts in English
; ; ; ; Hirosawa, Takashi; ;
PNC TN9440 97-006, 335 Pages, 1997/06
A seminar of the Alpha-Gamma section (AGS) at O-arai Engineering Center of PNC was held from October 21, 1994 to March 19, 1997 per month. The contents of discussion of the seminar are as follows. (1)Status report of refurbishlnent of minor actinides (MA) fuel fabrication line and of a maintenance logbook of manipulators and up-to-date PIE examination reports of sold fission products at high burnup MOX fuels. (2)Investigation report of methods of melting temperature on irradiated MOX fuel, criteria of leakage rate for cells and glove boxes, measurement methods of high temperature and evaluation of radiation shielding of the Alpha-Gamma Facility. (3)Abridged translation of radiation damage, FP behavior in irradiated fuel, safety aspects of fuel behavior during faults and accidents and fuel modeling at high burnup. (4)Lecture of evaluation on measurement error. (5)Translation for "Statistical Analysis of Measurement Errors" by J.L.Jaech. This report is compiled the above proceedings of the seminar.
Koyama, Shinichi; Osaka, Masahiko; Mitsugashira, Toshiaki; Konno, Koichi; Kajitani, Yukio
PNC TN9410 97-054, 44 Pages, 1997/04
For analysis of a small quantity of americium, it is necessary to separate from curium which has similar chemical property. As a chemical separation method for americium, and curium, the oxidation of americium with pentavalent bismuth and subsequent co-precipitation of trivalent curium with BIPO
were applied to analyze americium in irradiated MOX fuels which contained about 3Owt% plutonium and 0.9wt% Am before irradiation and were irradiated up to 26.2GWd/t in the experimental fast reactor Joyo. The purpose of this study is to measure isotopic ratio of americium and to evaluate the change of isotopic ratio with irradiation. Following results are obtained in this study, (1)The isotopic ratio of americium (Am, 
Am and 
Am) can be analyzed in the MOX fuels by isolating americium. The isotopic ratio of 
Am and Am increases up to 0.62at% and 0.82at% at maximum burnup, respectively. (2)The results of isotopic analysis indicates that the contents of Am decreases, whereas Am, Am increase linearly with increasing burnup.
Kajitani, Yukio; ; Abe, Kazuyuki; Osaka, Masahiko; ; Hirosawa, Takashi; Koyama, Shinichi
PNC TN9440 97-004, 186 Pages, 1997/02
The 25th anniversary meeting of the Alpha-Gamma Facility (AGF) at O-arai Engineering Center of PNC was held on February 7. The AGF started to examine irradiated materials on october 1 and fuel pins irradiated in the Dounreay Fast Reactor, DFR332/2 on December 1, 1971. The contents in this paper of the anniversary meeting are as follows. (1)25 years history and challenging plan for 2000 year. (2)Maintenance logbook of the facility, apparatus and manipulators for 25 years. (3)Recent results of melting temperature, thermal conductivity and lattice constants in irradiated MOX fuels. (4)Development on fission products release measuring apparatus and results of cold run tests. (5)Post irradiated examination results operated at the metallography cell in the Fuels Monitoring Facility (FMF). (6)Development on chemical analysis method for minor actinides (MA) in irradiated MOX fuels. (7)Refurbishment for MA containing MOX fuels, status and specifications for the fabrication and quality control apparatus.
Osaka, Masahiko; Koyama, Shinichi; Otsuka, Yuko; Mitsugashira, Toshiaki; Konno, Koichi; Kajitani, Yukio
PNC TN9410 96-297, 79 Pages, 1996/11
As a part of evaluation of irradiation behavior and burnup characteristics of MA nuclides such as Np, Am and Cm in MA containing MOX fuel, we are studying the quantitative analysis techniques for MA nuclides in irradiated fuel. In this study, we studied the mutual separation method for Am and Cm to establish the analysis method for Am and Cm following Np analysis by alpha spectrometry. The measurements of Am and Cm are difficult to analyze quantitatively because the amounts of some nuclides are too small and the number of nuclides are large, whose energies of the alpha radioactive rays are almost same. Therefore we selected to analyze the trace amount of Am and Cm isotopes using mass spectrometry, and have studied the techniques for mutual separation of Am and Cm using oxidation method of Am by NaBiO
for standard samples. We have also evaluated the availability of this method for irradiated fuel. Results are as follows. (1)Through the mutual separation tests, we have found the most suitable conditions for separation of both Am and Cm from each other element. The method obtaining Am which contains no Cm is used water for precipitation washing solution, containing Cm is achicved that the remaining ratio of Am (ratio of radioactivity of Am/
Cm against before separation) were reduced less than 1/10 for Cm. (2)Applying of this method to irradiated fuel, the coordinate remaining ratio and the chemical yield of Am and Cm were almost same as them in the separation tests. This method to apply various irradiated MOX Fuel is therefore possible. (3)The isotope ratio Am, Am and Am measured by mass spectrometry, which could not be analyzed by radioactive ray spectrometry causing less than detection limit, were 98.55% : 0.62% : 0.83%. We also measured zero of the mass number of 240 and 244 on the specimens and then certified no contamination of Cm to Am.
Am content and evaluation of burnup dependence in Am containing MOX fuel pinKoyama, Shinichi; Osaka, Masahiko; Otsuka, Yuko; Konno, Koichi; Kajitani, Yukio; Mitsugashira, Toshiaki
PNC TN9410 96-301, 61 Pages, 1996/10
We are studying quantitative analysis of Minor Actinides (Np, Am, Cm) in irradiated fuels as a part of the PNC research project for advanced nuclear fuel recycle system. In alpha-gamma section, irradiation behavior of MOX fuel and burning characteristic evaluation research of the MA nuclide which contain the minor actinide species are carrying out. We measured Am content of the MOX fuel pin which contained Am of about 0.9wt% before irradiation and were irradiated up to 26.2GWd/t in the JOYO reactor. The results are as follows. Burn-up dependence of the Am content in this samples was not observed. The Am content showed the fixed value of about 1% in the range from 0 to 28GWd/t. This reason is assumed that Am produced by 
-decay of Pu for cooling times between each cycles valances it in disappearance under irradiated in JOYO based on the calculated value by ORIGEN-II code.
