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Okadome, Yoshihiro; Aoyama, Yoshio; Sasaki, Yu; Fukushima, Mineo
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04
Aoyama, Yutaka*; Kataoka, Takahiro*; Nakagawa, Shinya*; Sakoda, Akihiro*; Ishimori, Yuu; Mitsunobu, Fumihiro*; Yamaoka, Kiyonori*
Iranian Journal of Radiation Research, 9(4), p.221 - 229, 2012/03
The aim of this study was to analyze the effects of thoron and thermal treatment for aging-related diseases in humans. All subjects inhaled thoron with a high concentration (about 4900 Bq/m
) for 2 weeks. Blood pressures were measured and blood samples were collected after each treatment 1, 2 and 3 weeks after the first treatment. The 
-atrial natriuretic peptide level of the rheumatoid arthritis group was increased and the blood pressure was significantly decreased. Superoxide dismutase activity of rheumatoid arthritis group was significantly increased by treatment. In addition, thoron and thermal treatment significantly enhanced the concanavalin A-induced mitogen response and increased the level of CD4-positive cells; it decreased the level of CD8-positive cells. The results suggest that thoron and thermal treatment activates antioxidative function. Furthermore, these findings suggest that thoron and thermal treatment prevents diabetic ketoacidosis and contributes to the prevention of aging-related diseases. Thoron and thermal therapy may be part of the mechanism for the alleviation of diabetes mellitus and rheumatoid arthritis.
Ito, Chikara; Araki, Yoshio; Naito, Hiroyuki; Iwata, Yoshihiro; Aoyama, Takafumi
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 12 Pages, 2012/00
no abstracts in English
Kataoka, Takahiro*; Nishiyama, Yuichi*; Toyota, Teruaki*; Yoshimoto, Masaaki*; Sakoda, Akihiro; Ishimori, Yuu; Aoyama, Yutaka*; Taguchi, Takehito*; Yamaoka, Kiyonori*
Inflammation, 34(6), p.559 - 567, 2011/12
Times Cited Count：22 Percentile：49.49(Cell Biology)We assessed whether radon inhalation provided protection from carbon tetrachloride induced hepatic and renal damage in mice. Mice were subjected to intraperitoneal injection of CCl
after inhaling approximately 18 kBq/m radon for 6 h. Radon inhalation significantly increased total glutathione content and glutathione peroxidase activity in the liver and kidney. Injection of CCl was associated with significantly higher levels of glutamic oxaloacetic transaminase and alkaline phosphatase activity and creatinine level in serum, and pretreatment with radon significantly decreased the GOT and ALP activity and creatinine level associated with CCl injection, suggesting that radon inhalation alleviates CCl-induced hepatic and renal damage. The t-GSH contents an GPx activity in the liver and kidney of animals pretreated with radon were significantly higher than those of the CCl-only group. These findings suggested that radon inhalation activated antioxidative functions and inhibited CCl-induced hepatic and renal damage in mice.
Ito, Hideaki; Maeda, Shigetaka; Naito, Hiroyuki; Akiyama, Yoichi; Miyamoto, Kazuyuki; Ashida, Takashi; Noguchi, Koichi; Ito, Chikara; Aoyama, Takafumi
JAEA-Technology 2010-049, 129 Pages, 2011/03
JAEA-Technology-2010-049.pdf:6.99MB
The in-vessel gamma dose rate was measured in the experimental fast reactor Joyo to evaluate the activation of reactor structural components and the radiation exposure of the fiber scope used for in-vessel visual inspection. The measurement system, which requires a wide sensitivity range and high durability in a high-temperature environment, was specifically developed for use in the sodium cooled fast reactor. Using this system, the in-vessel gamma dose rate with cooling times of 450 and 720 days after reactor shutdown was measured in Joyo, which has been operated for 71,000 hours over approximately 30 years. The gamma dose rate was calculated using QAD-CGGP2 code with the gamma source intensity obtained by the ORIGEN2 code. The neutron flux used as input to the ORIGEN2 was evaluated by the Joyo dosimetry method. The ratio between the calculated and experimental values ranged from 1.1 to 2.4, confirming the accuracy of gamma dose rate and component activation calculation.
dose rate distribution in JoyoMaeda, Shigetaka; Naito, Hiroyuki; Ito, Chikara; Aoyama, Takafumi
Progress in Nuclear Science and Technology (Internet), 1, p.182 - 185, 2011/02
In-vessel rate measurements have been conducted in the experimental fast reactor Joyo to obtain experimental data and to verify the analysis method. The in-vessel dose with cooling times of 500 and 700 days after reactor shutdown was measured in Joyo which had been operated for approximately 30 years. The dose was calculated using QAD code with the source obtained by ORIGEN2 code. The ratios between the calculated and experimental value was ranged 1.3 and 2.7. The accuracy of analys method for the amount and distribution of radioactive products and ray dose inside reactor vessel was confirmed for the in-vessel inspection or repair.
Kamei, Gento; Honda, Akira; Mihara, Morihiro; Oda, Chie; Murakami, Hiroshi; Masuda, Kenta; Yamaguchi, Kohei; Nakanishi, Hiroshi*; Sasaki, Ryoichi*; Ichige, Satoru*; et al.
JAEA-Research 2007-067, 130 Pages, 2007/09
JAEA-Research-2007-067.pdf:28.78MB
After the publication of the 2nd progress report of geological disposal of TRU waste in Japan, policy and general scheme of future study for the waste disposal in Japan was published by ANRE and JAEA. This annual report summarized aim and progress of individual problem, which was assigned into JAEA in the published policy and general scheme. The problems are as follows; characteristics of TRU waste and its geologic disposal, treatment and waste production, quality control and inspection methodology for waste, mechanical analysis of near-field, data acquisition and preparation on radionuclides migration, cementitious material transition, bentonite and rock alteration in alkaline solution, nitrate effect, performance assessment of the disposal system and decomposition of nitrate as an alternative technology.
Ito, Chikara; Ito, Hideaki; Ishida, Koichi; Hatoori, Kazuhiro; Oyama, Kazuhiro; Sukegawa, Kazuya*; Murakami, Takanori; Kaito, Yasuaki; Nishino, Kazunari; Aoyama, Takafumi; et al.
JNC TN9410 2005-003, 165 Pages, 2005/03
JNC-TN9410-2005-003.pdf:12.66MB
At experimental fast reactor JOYO, appraisal of detection efficiency of behavior and FFD and FFDL of the fission product which is discharged inside the furnace as one of safety research of the country, is carried out. In MK-II core, the slit in the gas plenum part of the test sub-assembly, the test which irradiates this(1985 April, FFDL in-pile test(I)), providing the slit in the fuel column part of the test sub-assembly, the test which it irradiates(1992 November, FFDL in-pile test(II)) were carried out.MK-III reactor core replacement was completed and started in 2004. That the behavior in the system of FP with the reactor core replacement and so on changes in the MK-III reactor core and to have an influence on the sensitivity and the replying of FFD and FFDL are thought of. Therefore, behavior of FP in the fuel failure in the MK-III reactor core, the performance of FFD and FFDL must be confirmed beforehand. Moreover, to prepare for the fuel failure and the RTCB test which is doing a future plan, and to confirm a plant operation procedure in the fuel failure in MK-III reactor core operation and to attempt for the correspondency to improve are important.Therefore, in the period from 2004 November 11th to November 29th, it carried out the FFDL in-pile(III). It did a series of plant operation to stop a nuclear reactor after loading a reactor core center with the fuel element for the test which provided an artificial slit for the fuel cladding in the MK-III reactor core and irradiating it and detecting fuel damaging and to take out fuel. And it confirmed the operation procedure of the fast reactor in the fuel failure.Also, the improvement items such as the improvement of the operation and the procedure and the remodeling and the service of the facilities could be picked up. In the future, it attempts these compatible, and it prepares for the MK-III reactor core operation and it incorporates a final examination result by the improvement of the safety of FBR.
Okutsu, Kazuo*; Morikawa, Seiji*; Shimbo, Hiroshi*; Kuroyanagi, Mikio*; Sahara, Fumihiro*; Murakami, Takeshi*; Aoyama, Yuji*
JNC TJ8400 2005-013, 117 Pages, 2005/02
JNC-TJ8400-2005-013.pdf:3.24MB
To integrate the system for evaluation of long-term hydraulic condition in near field of TRU waste disposal, the engineered barrier, which consists of bentonite buffer and cementitious materials, was employed in the series of laboratory tests. On the bentonite buffer, with the aim of investigating of the effect of (i) interlayer cation in bentonite, (ii) content of siliceous sand and (iii) the ionic strength of ground water on its mechanical and hydraulic properties, series of laboratory tests were conducted. The same lot of bentonite was used in the series of tests to obtain consistent data. In addition, the swelling test of the laminated bentonite with caliumization front was conducted for verification of the proposed constitutive model. On cementitious materials, the altered specimen that produced immersing was investigated the water permeation and also characteristics. The hardened cement paste specimens with W/C=40 to 105% were immersed into deionized water and alteration behavior under diffusion condition was investigated.
Okutsu, Kazuo*; Morikawa, Seiji*; Shimbo, Hiroshi*; Kuroyanagi, Mikio*; Sahara, Fumihiro*; Murakami, Takeshi*; Aoyama, Yuji*
JNC TJ8400 2005-012, 272 Pages, 2005/02
JNC-TJ8400-2005-012.pdf:7.05MB
To integrate the system for evaluation of long-term hydraulic condition in near field of TRU waste disposal, the engineered barrier, which consists of bentonite buffer and cementitious materials, was employed in the series of laboratory tests.On the bentonite buffer, with the aim of investigating of the effect of (i)interlayer cation in bentonite, (ii)content of siliceous sand and (iii)the ionic strength of ground water on its mechanical and hydraulic properties, series of laboratory tests were conducted. The same lot of bentonite was used in the series of tests to obtain consistent data. In addition, the swelling test of the laminated bentonite with caliumization front was conducted for verification of the proposed constitutive model.On cementitious materials, the altered specimen that produced immersing was investigated the water permeation and also characteristics. The hardened cement paste specimens with W/C=40 to 105% were immersed into deionized water and alteration behavior under diffusion condition was investigated.
Fukuda, Yuji; Akahane, Yutaka; Aoyama, Makoto; Inoue, Norihiro*; Ueda, Hideki; Nakai, Yoshiki*; Tsuji, Koichi*; Yamakawa, Koichi; Hironaka, Yoichiro*; Kishimura, Hiroaki*; et al.
Applied Physics Letters, 85(21), p.5099 - 5101, 2004/11
Times Cited Count：11 Percentile：42.77(Physics, Applied)We have demonstrated diffraction from Si(111) crystal using X-rays from highly ionized Ar ions produced by laser irradiation with an intensity of 6
10
W/cm
and a pulse duration of 30 fs acting upon micron-sized Ar clusters. The measured total photon flux and line width in the He
line (3.14 keV) were 410
photons/shot/4
sr and 3.7 eV (FWHM), respectively, which is sufficient to utilize as a debris-free light source for time-resolved X-ray diffraction studies.
Okutsu, Kazuo*; Morikawa, Seiji*; Taguchi, Katsunori*; Kuroyanagi, Mikio*; Sahara, Fumihiro*; Takase, Hiroyasu*; Aoyama, Yuji*
JNC TJ8400 2003-087, 199 Pages, 2004/02
JNC-TJ8400-2003-087.pdf:4.82MB
The system development for evaluating the long-term alteration of hydraulic field in near field was examined. The "Evidential Support Logic" for ensuring the long-term stability of the repository was developed and evaluated. Furthermore, the developed chemical/mechanical alteration action analysis system was verified and improved. The system was coupled for the long-term alteration evaluation analysis.
Okutsu, Kazuo*; Morikawa, Seiji*; Taguchi, Katsunori*; Kuroyanagi, Mikio*; Sahara, Fumihiro*; Takase, Hiroyasu*; Aoyama, Yuji*
JNC TJ8400 2003-086, 426 Pages, 2004/02
JNC-TJ8400-2003-086.pdf:11.01MB
The system development for evaluating the long-term alteration of hydraulic field in near field was examined. The "Evidential Support Logic" for ensuring the long-term stability of the repository was developed and evaluated. Furthermore, the developed chemical/mechanical alteration analysis system was verified and improved. The system was coupled for the long-term alteration evaluation analysis.
Takase, Hiroyasu*; Metcalfe, R.*; Inagaki, Manabu*; Noguchi, Toshihide*; Aoyama, Yuji*; Takase, Kyoko*; Tabara, Michiko*
JNC TJ5400 2003-006, 264 Pages, 2004/02
JNC-TJ5400-2003-006(errata).pdf:0.08MBJNC-TJ5400-2003-006-1.pdf:83.88MBJNC-TJ5400-2003-006-2.pdf:15.97MB
none
Aoyama, Yuji*; Takase, Hiroyasu*
JNC TJ8400 2003-001, 55 Pages, 2003/03
JNC-TJ8400-2003-001.pdf:1.52MB
A hydrodynamics analysis system for a precise crack model was developed using a cellular automata method and the applicability of the system was investigated. Since the Reynolds number of the target fluid is low, the lattice gas method, for which the computation cost is relatively small, was applied. As for the mesh, a four dimensional face-centered hyperbolic cube projecting onto the three dimensional space was used. The hydrodynamic and migration model was developed for the lattice gas method. The system was evaluated using Snow's law of hydrodynamics in a parallel plate. The system was also applied to a crack model based on LABROCK data. Several trial crack models were generated using fractal theory and the relationship between the configuration and hydrodynamics of a crack was investigated.
Kobayashi, Katsuhei*; Iguchi, Tetsuo*; Iwasaki, Shin*; Aoyama, Takafumi*; Shimakawa, Satoshi; Ikeda, Yujiro; Odano, Naoteru; Sakurai, Kiyoshi; Shibata, Keiichi; Nakagawa, Tsuneo; et al.
JAERI 1344, 133 Pages, 2002/01
The JENDL Dosimetry File 99 (JENDL/D-99) has been prepared for determinations of neutron flux/fluence and energy spectrum at specific neutron fields. This file contains data for 67 reactions with 47 nuclides. Cross sections for 33 major dosimetry reactions and their covariance data were simultaneously generated and the other 34 reaction data were mainly adopted from the first version, JENDL/D-91. The GMA code was mainly used for most of the evaluation procedures by referring the basic experimental data in EXFOR. The resultant data are given in the neutron energy region below 20 MeV in both of point-wise and group-wise files in the ENDF-6 format. In order to confirm reliability of the data, several integral tests have been carried out: comparison with the data in IRDF-90V2 and average cross sections measured in fission neutron fields, fast/thermal reactor spectra, DT neutron fields and Li(d,n) neutron fields. The contents of JENDL/D-99 and the results of the integral tests are described in this report. All of the dosimetry cross sections are shown in a graphical form in the Appendix.
Aoyama, Takafumi; Suzuki, Toshiaki; Takatsuto, Hiroshi; Oowada, Toshio; Oyama, Nobumi; Emori, Shuichi
PNC TN9418 97-006, 93 Pages, 1997/12
non
Aoyama, Takafumi; ; Suzuki, Toshiaki; ; ; Emori, Shuichi
Donen Giho, (104), p.3 - 93, 1997/12
None
*; Horita, M.*; Ishii, T.*; Yamamoto, Isamu*; Horie, Y.*; Hokari, T.*; *
PNC TJ1060 92-006, 128 Pages, 1992/11
None
*; *; *; *; *; *; *; *; *; Yonehara, Hidenori*; et al.
EUR-13013-2, p.817 - 828, 1991/00
no abstracts in English
