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Nakamura, Shoji; Terada, Kazushi*; Kimura, Atsushi; Nakao, Taro*; Iwamoto, Osamu; Harada, Hideo; Uehara, Akihiro*; Takamiya, Koichi*; Fujii, Toshiyuki*
Journal of Nuclear Science and Technology, 56(1), p.123 - 129, 2019/01
Times Cited Count：1 Percentile：11.15(Nuclear Science & Technology)Accurate data of 
-ray emission probabilities are frequently needed when one quantitatively determines the amount of isotope by -ray measurements or obtains neutron capture cross-sections using them. Americium-243, one of the most important minor actinides, produces 
Am after neutron capture. The 744-keV -ray decaying from the ground state of Am has a relatively large -ray emission probability c.a. 66%, however, its uncertainty is as large as 29%. The uncertainty of the -ray emission probability leads to a major factor of the systematic uncertainty on determining an amount of isotope, and therefore the -ray emission probability was measured by using an activation method and an examined level structure of Cm. In this study, the emission probability of 744-keV ray was derived as 66.5
1.1%, and its uncertainty was improved from 29% to 2%.
Hidaka, Akihide; Kudo, Tamotsu; Nakamura, Takehiko; Uetsuka, Hiroshi
Journal of Nuclear Science and Technology, 39(3), p.273 - 275, 2002/03
Times Cited Count：10 Percentile：54.86(Nuclear Science & Technology)no abstracts in English
Maebara, Sunao
JAERI-Research 2000-061, 104 Pages, 2001/01
JAERI-Research-2000-061.pdf:9.71MB
no abstracts in English
Maebara, Sunao; Goniche, M.*; Kazarian, F.*; Seki, Masami; Ikeda, Yoshitaka; Imai, Tsuyoshi; Bibet, P.*; Froissard, P.*; Rey, G.*
Fusion Engineering and Design, 49-50, p.269 - 273, 2000/11
Times Cited Count：4 Percentile：32.52(Nuclear Science & Technology)no abstracts in English
-ray spectroscopic methodsFurutaka, Kazuyoshi
JNC TN8400 2000-028, 70 Pages, 2000/10
JNC-TN8400-2000-028.pdf:1.71MB
This report describes the study done by the author as a postdoctoral research associate at Japan Nuclear Cycle Development Institute. This report is divided into two parts: improvements in accuracy in determination of thermal neutron capture cross sections, and improvements in accuracy of photo-nuclear absorption cross section measurements using the HHS. (1)In the measurements of thermal neutron capture cross sections using an activation method, accuracies of the final results attained are limited by (1) accuracy of -ray peak detection efficiencies, and (2) accuracies of -ray emission probabilities. In this study; to determine thermal neutron capture cross sections more accurately, the following researches have been done using a newly developed three-dimensional coincidence measurement system: (1)accurate determination of -ray standard sources using a - coincidence method, for precise calibration of -ray peak detection efficiency, and (2) development of a 
- coincidence measurement system using a plastic scintillation detector as a -ray detector, for the determination of -ray emission probabilities of short-lived nuclides, and measurement of -ray emission probabilities of 
Tc nuclide using the coincidence system. (2)To transform radioactive nuclides with small thermal neutron capture cross sections, use of photonuclear absorption reaction has been suggested. In order to transform these nuclides efficiently using the reaction, one has to know detailed behavior of the photo-absorption cross sections. In this study, a Monte-Carlo simulation code has been used to create a standard set of -ray response functions of the high-resolution high-energy spectrometer (HHS), to enable reliable analyses of the data obtained by the spectrometer.
; ; ; Matsumoto, Shinichiro
JNC TN9410 2000-009, 65 Pages, 2000/09
JNC-TN9410-2000-009.pdf:4.36MB
In order to evaluate irradiation behavior of(U, Pu) C and (U, Pu) N fuel using fast reactor, (U, Pu) C and (U, Pu) N fuel pins were irradiated in JOYO for the fist time in Japan. In this study, one (U, Pu) C fuel pin and two (U, Pu) N fuel pins were irradiated to maximum burn up about 40GWd/t. Post irradiation examination of (U, Pu) C and (U, Pu) N fuel pins started in Fuel Monitoring Facility (FMF) at JNC from October 1999, and it ended in March, 2000. The results of non-destructive post irradiation examination reported in this document. Main results are shown in the following. (1)The soundness of all (U,Pu) C and (U,Pu) N fuel pins were confirmed from the non-destructive examination result. (2)The fuel stack elongation of (U,Pu) C and (U,Pu) N is bigger than it of the MOX fuel for fast reactor. (3)The singular behavior from the gamma ray scanning measurement in the stack area was not confirmed. The migration of Cs137 to lower insulator pellet and outside of the pellet was confirmed in (U,Pu) N B9NO2 pin. In (U,Pu) C fuel, the migration of Cs137 was not confirmed. (4)In (U,Pu) C B9CO1 pin and (U,Pu) N B9NO2 pin in which the gap width was small, diameter of cladding increase around 50 
m in the stack area which originates for FCMI was confirmed. In (U,Pu) N B9NO1 pin in which the gap width was wide, the ovality which originates from the relocation of the pellet was confirmed. (5)Fission gas release rate of (U,Pu) N were 3.3% and 5.2%, and the low value compared to the MOX fuel was shown.
; ;
JNC TN9400 2000-041, 29 Pages, 2000/03
JNC-TN9400-2000-041.pdf:1.18MB
Irradiation behavior and performance models were investigated in order to apply for nitride fuel options in feasibility study on fast breeder reactor and related recycle systems. (1)MechanicaI design of nitride fuel pin: The behaviors of fission gas release (increase of internal Pressure) and fuel-to-cladding chemical interaction (decrease of cladding thickness) are needed to evaluate cumulative damage fraction in case of fuel pin mechanical design. The behaviors of fission gas release and fuel-to-cladding chemical interaction were investigated from the past studies up to high burnuP, since the lower fission gas release in nitride fuel than in oxide fuel could contribute to reduce the plenum volume and result in the shortening of fuel Pin length. (2)Fuel pin smear density: The higher fuel smear density is preferred for the higher fissile density to improve the core characteristic. The behaviors of fuel pellet swelling were investigated from the past studies up to higher burnup, since the larger fuel pellet swelling in nitride fuel than in oxide fuel would restrict high burunp capability due to fuel-cladding mechanical interaction. (3)Compatibility of nitride fuel with high Temperature water: Compatibility of nitride fuel with high temperature water were investigated from the past studies to contribute water cooled fast breeder reactor options.
Sasajima, Hideo; Fuketa, Toyoshi; Nakamura, Takehiko; Nakamura, Jinichi; Uetsuka, Hiroshi; Kikuchi, Keiichi*; Abe, Tomoyuki*
JAERI-Research 99-060, p.62 - 0, 2000/03
JAERI-Research-99-060.pdf:12.05MB
no abstracts in English
Maebara, Sunao; ; Seki, Masami; Suganuma, Kazuaki; Ikeda, Yoshitaka; Imai, Tsuyoshi; Goniche, M.*; J.Brossaud*; V.Cano*; F.Kazarian-Vibert*; et al.
JAERI-Research 97-086, 29 Pages, 1997/11
JAERI-Research-97-086.pdf:1.33MB
no abstracts in English
Arai, Yasuo; Iwai, Takashi; ; Okamoto, Yoshihiro; Nakajima, Kunihisa; Niimi, Motoji; ; Yamahara, Takeshi;
JAERI-Research 95-008, 92 Pages, 1995/02
JAERI-Research-95-008.pdf:5.04MB
no abstracts in English
Arai, Yasuo; Iwai, Takashi; ; Nakajima, Kunihisa; ; ;
JAERI-Research 94-027, 66 Pages, 1994/11
JAERI-Research-94-027.pdf:4.09MB
no abstracts in English
Suzuki, Motoe; Saito, Hioraki*
JAERI-Data/Code 94-011, 178 Pages, 1994/09
JAERI-Data-Code-94-011.pdf:3.84MB
no abstracts in English
Iwai, Takashi; Arai, Yasuo; Maeda, Atsushi; ; ; ;
JAERI-M 94-036, 81 Pages, 1994/03
no abstracts in English
Hayashi, Takumi; Suzuki, Takumi; Okuno, Kenji
Journal of Nuclear Materials, 212-215, p.1431 - 1435, 1994/00
Times Cited Count：19 Percentile：82.28(Materials Science, Multidisciplinary)no abstracts in English
Se, 
Ho and 
Ir by a self-consistent method*; *; Mori, Chizuo*; Takeuchi, Norio; Genka, Tsuguo
Nuclear Instruments and Methods in Physics Research A, 339, p.203 - 208, 1994/00
Times Cited Count：10 Percentile：68.33(Instruments & Instrumentation)no abstracts in English
-counting system used for determining surface emission rate of calibration sources in radiation protection measurementsYoshida, Makoto; Kawasaki, Katsuya;
Radioisotopes, 41(6), p.316 - 319, 1992/06
no abstracts in English
Hayashi, Takumi; Amano, Junzo; Okuno, Kenji; Naruse, Yuji
Fusion Technology, 21, p.845 - 849, 1992/03
no abstracts in English
; Saito, Hioraki*; *
Transactions of the 11th Int. Conf. on Structural Mechanics in Reactor Technology,Vol. C, p.1 - 6, 1991/08
no abstracts in English
Nomura, Yasushi; *; *; *; *; Nishio, Gunji; *; *; *; Sugiyama, Toshihide*; et al.
Nihon Genshiryoku Gakkai-Shi, 33(4), p.318 - 328, 1991/04
no abstracts in English
