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Riyana, E. S.*; Suda, Shoya*; Ishibashi, Kenji*; Matsuura, Hideaki*; Katakura, Junichi*; Sun, G. M.*; Katano, Yoshiaki
Journal of Nuclear Science and Technology, 56(5), p.369 - 375, 2019/05
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)Nuclear reactors produce a great number of electron antineutrinos mainly from beta-decay chains of fission products. Such neutrinos have energies mostly in MeV range. We are interested in neutrinos in a region of keV, since they may have information on fuel burn-up and may be detected in future with advanced measurement technology. We calculate reactor antineutrino spectra especially in the low energy region. In this work we present neutrino spectra from various reactors such as typical PWR reactor and others types of reactors for comparison. Our result shows the electron antineutrino flux in the low energy region increases with burn-up of nuclear fuel by accumulated nuclides with low Q values in beta decay.
Yamaguchi, Tetsuji; Shimada, Taro; Ishibashi, Makoto*; Akagi, Yosuke*; Kurosawa, Mitsuru*; Matsubara, Akiyoshi*; Matsuda, Yuki*; Sato, Shigeyoshi*
Genshiryoku Bakkuendo Kenkyu (CD-ROM), 22(2), p.21 - 27, 2015/12
It is predictable from previous studies that radiocesium hardly migrate into surrounding soils and groundwater from soils contaminated by the Fukushima Daiichi Nuclear Power Plant accident if they are buried and covered with indigenous soils. This study demonstrated the prediction by performing in-situ migration experiments over a year in a public park in Miho, Ibaraki prefecture and in two public parks in Misato, Saitama prefecture. Contaminated soils were buried at a depth range of 0.3 - 1.0 m or at 0.3 - 1.3 m and covered with indigenous soil layer of 0.3 m, and were sprinkled with water to accelerate the radiocesium migration. Migration of radiocesium was not observed from radiometric analyses of boring cores and soil water samples. Laboratory column and sorption experiments revealed that the radiocesium hardly leach out of the soil and even if they leach out from the contaminated soil, radiocesium is sorbed on surrounding soils and hardly migrate through the soli layer. Simulation of Cs-137 migration for 100 years by an advection-diffusion model showed that Cs-137 hardly migrate and decay out in the contaminated soil.
Sato, Takahiro*; Iwasaki, Atsushi*; Ishibashi, Kazuki*; Okino, Tomoya*; Yamanouchi, Kaoru*; Adachi, Junichi*; Yagishita, Akira*; Yazawa, Hiroki*; Kannari, Fumihiko*; Aoyama, Makoto; et al.
Europhysics News, 42(5), P. 10, 2011/09
The resonant and non-resonant two-photon single ionization processes of He were investigated using intense free electron laser light in the extreme ultraviolet (XUV) region (53.4-61.4 nm) covering the 1s-2p and 1s-3p resonant transitions of He. On the basis of the dependences of the yield of He
on the XUV light-field intensity at 53.4, 58.4, 56.0 and 61.4 nm, the absolute values of the two-photon ionization cross sections of He at the four different wavelengths and their dependence on the light-field intensity were determined for the first time.
Sato, Takahiro*; Iwasaki, Atsushi*; Ishibashi, Kazuki*; Okino, Tomoya*; Yamanouchi, Kaoru*; Adachi, Junichi*; Yagishita, Akira*; Yazawa, Hiroki*; Kannari, Fumihiko*; Aoyama, Makoto; et al.
Journal of Physics B; Atomic, Molecular and Optical Physics, 44(16), p.161001_1 - 161001_5, 2011/08
Times Cited Count：36 Percentile：83.28(Optics)The resonant and non-resonant two-photon single ionization processes of He were investigated using intense free electron laser light in the extreme ultraviolet (XUV) region (53.4-61.4 nm) covering the 1s-2p and 1s-3p resonant transitions of He. On the basis of the dependences of the yield of He on the XUV light-field intensity at 53.4, 58.4, 56.0 and 61.4 nm, the absolute values of the two-photon ionization cross sections of He at the four different wavelengths and their dependence on the light-field intensity were determined for the first time.
Yasuda, Atsushi; Ueta, Shohei; Aihara, Jun; Ishibashi, Hideharu*; Sawa, Kazuhiro
JAEA-Technology 2008-083, 11 Pages, 2009/01
JAEA-Technology-2008-083.pdf:3.14MB
The Very-High-Temperature Reactor (VHTR) is one of the candidates for the Generation IV nuclear energy system. ZrC coated fuel particles are expected to make the performance of the VHTR higher. Therefore, we are investigating the ZrC-coating process. From April 2007 to March 2008, ZrC-outer pyrolytic carbon (OPyC) layer continuous coating tests were carried out with the nonnuclear particles and we succeeded to coat continuously the ZrC layer and the OPyC layer with the thicknesses up to about 27 and about 48 
m, respectively, in the batch scale of 100 g.
Aihara, Jun; Ueta, Shohei; Yasuda, Atsushi; Ishibashi, Hideharu; Mozumi, Yasuhiro; Sawa, Kazuhiro; Motohashi, Yoshinobu*
Journal of the American Ceramic Society, 92(1), p.197 - 203, 2009/01
Times Cited Count：7 Percentile：42.24(Materials Science, Ceramics)The ZrC coating layer was fabricated with bromide process at JAEA. In a later stage of the project, we have successfully kept nominal deposition temperature almost constant. Microstructures of the ZrC layers, of which nominal deposition temperatures were able to measure, were characterized by means of TEM and STEM and the results were compared and discussed with those obtained for different batches including those reported in a previous study. The ZrC grains were oriented in the ZrC layers deposited at about 1630 K. This feature was rather different from that reported in the previous study. The formation of fairly different PyC structures was found on the PyC/ZrC boundary as well as around the pores existing near the boundary. Fibrous carbons were observed on the PyC/ZrC boundary produced in a batch deposited at a higher temperature (nominal temperature was 1769 K); no such fibrous carbons were found in a batch deposited at a lower temperature (nominal temperature was 1632 K).
Sato, Kazuhiko; Ishibashi, Makoto*; Kawatsuma, Shinji
Dekomisshoningu Giho, (38), p.2 - 10, 2008/11
Clearance of materials and disposal of radioactive waste generated from uranium utilizing facilities which include uranium conversion and enrichment facilities, and fuel fabrication facility among the nuclear fuel cycle has been discussed in Japan. These materials are supposed to be contaminated with long-lived natural nuclide, i.e. uranium. Uranium is widely distributed among the environment, e.g. soil, rock, river-water, groundwater and so on. Furthermore, uranium is also contained in some building materials and consumer goods. Literature survey about distribution of uranium in the environment and measurement of uranium concentration in some materials were carried out. As a result, it is revealed that range of U-238 activities in soils in Japan is from 0.001 Bq/g to about 1 Bq/g. Addition to that, the range of building materials is overlapped by that of soils, while some consumer goods showed relatively high activities. Futermore, dose contribution of uranium series nuclides to the environmental radiation dose were discussed. It is suggested that, sum of environmental radiation dose in Japan is about 1.5 mSv/yr and dose contribution of uranium series nuclides is about 0.8 mSv/yr.
Ishibashi, Makoto*; Sato, Kazuhiko; Kawatsuma, Shinji
Proceedings of 16th Pacific Basin Nuclear Conference (PBNC-16) (CD-ROM), 6 Pages, 2008/10
no abstracts in English
Ueta, Shohei; Aihara, Jun; Yasuda, Atsushi; Ishibashi, Hideharu; Takayama, Tomoo; Sawa, Kazuhiro
Journal of Nuclear Materials, 376(2), p.146 - 151, 2008/05
Times Cited Count：58 Percentile：95.76(Materials Science, Multidisciplinary)The Very-High-Temperature Reactor (VHTR) is the one of the most promising candidates for the Generation IV Nuclear Energy System. The VHTR fuel should exhibit excellent safety performance up to burn-ups of about 15 to 20%FIMA and fluences of 6
10
n/m
(E
0.1 MeV). There is no experimental data which has proved the intactness of conventional SiC-coated fuel particles under such severe condition. Japan Atomic Energy Agency (JAEA) developed Zirconium carbide (ZrC)-coated fuel particles which is expected to maintain its intactness under higher temperature and burn-up compared with SiC-coating layer. JAEA has newly started the development of coating process by large-scale and of inspection method, and the irradiation of ZrC-coated particles from 2004. The fabrication tests of ZrC-coating have been started by new-series coater, and uniform ZrC coating layer has successfully been fabricated by the improvement of temperature control technique.
Ueta, Shohei; Aihara, Jun; Yasuda, Atsushi; Ishibashi, Hideharu; Mozumi, Yasuhiro; Sawa, Kazuhiro; Minato, Kazuo
Hyomen, 46(4), p.222 - 232, 2008/04
Japan Atomic Energy Agency (JAEA) is developing the zirconium carbide (ZrC) coated fuel particle which has better refractoriness and chemical stability than the conventional silicon carbide (SiC) coated fuel particle. In the present study, ZrC coating tests were carried out by the enlarged 200 g-scale ZrC coater comparing with the previous study. Finally, the stoichiometric ZrC layer was successfully fabricated by obtaining relationships between properties of ZrC, coating temperature and batch size through coating tests. In addition, not only inspection methods for coating thickness and density, but also treatment technique to remove pyrocarbon (PyC) layer were developed in order to evaluate the quality of the ZrC coated fuel particle. Present R&D will contribute to the practicability of the ZrC coated fuel particle as a fuel for the advanced high temperature gas cooled reactor such as the Very High Temperature Reactor (VHTR).
Aihara, Jun; Ueta, Shohei; Yasuda, Atsushi; Ishibashi, Hideharu; Takayama, Tomoo; Sawa, Kazuhiro; Motohashi, Yoshinobu*
Journal of the American Ceramic Society, 90(12), p.3968 - 3972, 2007/12
Japan Atomic Energy Agency (JAEA) has started to study and develop ZrC coated fuel particles for advanced high temperature gas cooled reactors. This paper mainly focuses on the microstructures of the ZrC and isotropic dense pyrolytic carbon (PyC) coating layer produced in the early stage of the project. The structure of free carbon region in the ZrC coating layer appears to be such that c-plane was along with the ZrC grain boundary. It appears that the existence of the free carbon phase, especially with such structure, deteriorates the fission product (FP) retention performance in addition to the mechanical strength of ZrC. The PyC coating layer appears to be a medium-range ordered amorphous structure.
Takayama, Tomoo*; Ueta, Shohei; Aihara, Jun; Yasuda, Atsushi*; Ishibashi, Hideharu*; Sawa, Kazuhiro
JAEA-Research 2007-061, 32 Pages, 2007/09
JAEA-Research-2007-061.pdf:15.93MB
As the conventional SiC coated fuel particle, the ZrC coated fuel particle is proposed as a fuel for the Very High Temperature Gas-cooled Reactor (VHTR) which is one of Generation IV nuclear reactors. Applicability of inspection methods of SiC-coated fuel particle for ZrC-coated fuel particle has been examined by comparing properties of ZrC with SiC. It was suggested that hardness, absorption X-ray coefficient, density, oxidation-resistant and chemical stability of SiC were dominant properties for conventional inspection methods such as SiC coating layer thicknesses, coating layers densities for both SiC and O-PyC layers, thorough-coatings failure fraction and SiC coating layer failure fraction. With regards to the applicability of the inspection for the SiC-coated particle, some difficulties are revealed on coating layers densities for both ZrC and O-PyC layers and of ZrC failure fraction, and it was suggested that they were major issues to be solved.
Tsujimura, Seiichi; Funabashi, Hideyuki; Ishibashi, Makoto*; Takase, Toshio*; Kurosawa, Mitsuru*
JAEA-Research 2007-030, 105 Pages, 2007/03
JAEA-Research-2007-030.pdf:7.72MB
Uranium waste has characteristics that it is rarely expected to decay its radioactivity and it is not almost recessary to consider external exposure to radiation from waste package. We studied resonable sub-surface disposal concepts for uranium waste considering the characteristics. It showed feasibility of this system. In 2006, the study was done to evaluate the correlation between dose to the public and the parameter in consideration of the uncertainty of the parameter by comprehensive sensitivity analysis calculating repeatedly dose with the data sets by random sampling in parameter ranges given adequately, because last year's study was an evaluation intended for a limited site. The result was that two parameters, "flow velocity of underground water of repository neighborhood" and "distribution coefficient of uranium in natural barrier", had correlation with dose to the public.
Tsujimura, Seiichi; Funabashi, Hideyuki; Ishibashi, Makoto*; Takase, Toshio*; Kurosawa, Mitsuru*
JAEA-Research 2006-029, 96 Pages, 2006/07
JAEA-Research-2006-029.pdf:3.97MB
Uranium waste has characteristics that it is rarely expected to decay its radioactivities and it is not almost necessary to consider external exposure to radiation from waste package. We studied reasonable sub-surface disposal concepts for uranium waste in 2004 and 2005 considering the characteristics. In 2005, we studied necessity of engineered barrier for the disposal of uranium waste, considering change of chemical condition around disposal facilities over long periods of time. Safety assessment was made to analyze effect of difference in sorption parameters at reduction and oxidation conditions. The assessment showed that change from reduction to oxidation around disposal facilities did not lead to increase dose to the public. The assessment with realistic sorption parameters showed that dose to the public was not more than 10 Sv/y. The results proved that it was not necessary to keep reduction conditions around disposal facilities. This two-year- study showed that there was possibility of sub-surface disposal system without engineered barrier for uranium waste.
Yamamoto, Sekika*; Ishibashi, Yasuhiko*; Inamura, Yasuhiro; Katayama, Yoshinori; Mishina, Tomobumi*; Nakahara, Junichiro*
Journal of Chemical Physics, 124(14), p.144511_1 - 144511_5, 2006/04
Times Cited Count：12 Percentile：38.31(Chemistry, Physical)High pressure X-ray diffraction measurements on liquid carbon disulfide up to 1.2 GPa are performed by using an energy dispersion method. The results are compared with a molecular dynamics calculation with usual Lennard-Jones potential. They give very good agreement for all pressures measured. It becomes clear that the liquid structure changes like hard core liquid up to the pressure just below crystallizing point. The relation between structural change and optical response at high pressure is discussed.
Yamamoto, Masayuki*; Ishibashi, Makoto*
JNC TJ8440 2005-001, 72 Pages, 2005/03
JNC-TJ8440-2005-001.pdf:0.49MB
Uranium waste has features that the main nuclide is long-lived uranium and it is not almost necessary to consider radiation influence from waste package. Although the many studies for subsurface disposal concept of uranium waste have been done, the wastes features were not carefully considered in the former studies. The following reasonable disposal concepts have been designed considering the features in this study. (1) Concrete vault disposal concept in rock cavern (2) Monolithic disposal concept in rock cavern (3) Trench disposal concept in rock cavern / The safety of the disposal concepts during operation and after control phase has been investigated in this study. As the result, it has been shown that the exposure dose of workers due to waste package is not high. And it has been shown that the exposure dose of the public does not change so much, even if the engineered barrier has been reduced. Besides some issues regarding regulation, operation and monitoring have been picked up.
Ueta, Shohei; Aihara, Jun; Yasuda, Atsushi; Ishibashi, Hideharu; Sawa, Kazuhiro
no journal, ,
Developments of the technology for Zirconium Carbide (ZrC) coated fuel particle, which is one of candidates as Very High Temperature gas-cooled Reactor (VHTR) fuels, are on the progress. The following studies were carried out to investigate the irradiation performance of ZrC coating layer; a irradiation test, post irradiation examinations with ZrC coated dummy particle and fuel performance modeling for fuel and safety design. For the irradiation test, it can be said that the performance of ZrC coating layer against neutron irradiation is the most important. In this viewpoint, irradiation test will be carried out by High Flux Isotope Reactor (HFIR) in Oak Ridge National Laboratory (ORNL), and irradiation condition should be settled over 610n/m of fast neutron flux, as much as that of VHTR condition. For post irradiation examinations, failure integrity measurement, ceramography and SEM observation should be carried out to develop fuel failure model of ZrC coated fuel particles.
Aihara, Jun; Ueta, Shohei; Yasuda, Atsushi; Ishibashi, Hideharu; Sawa, Kazuhiro; Motohashi, Yoshinobu*
no journal, ,
no abstracts in English
Aihara, Jun; Ueta, Shohei; Yasuda, Atsushi; Ishibashi, Hideharu; Sawa, Kazuhiro; Motohashi, Yoshinobu*
no journal, ,
Japan Atomic Energy Agency (JAEA) has started to study and develop ZrC coated fuel particles for advanced high temperature gas cooled reactors. The ZrC coating layers were fabricated with bromide process at JAEA. We report in this study the microstructures of the ZrC coating layers deposited in the second year of the project. We already reported the microstructure of the one deposited in the first year of the project last year. The ZrC coating layer deposited at lower temperatures contains less free carbons. The crystal grains of ZrC were columner in shape and oriented in the region containing less free carbons. The orientation was different from the one reported in the last year. In addition to the stoichiometry of the ZrC layer, the microstructure of PyC/ZrC boundary also depended on the deposition temperature. The fibrous carbon structure is observed at PyC/ZrC boundary when the ZrC layer is deposited at higher temperature but not when ZrC layer is deposited at lower temperature.
Kawatsuma, Shinji; Takebe, Shinichi; Ouchi, Masaru; Kozawa, Kazushige; Yagi, Naoto; Sato, Kazuhiko; Morimoto, Yasuyuki; Fukushima, Tadashi; Ishibashi, Makoto*
no journal, ,
no abstracts in English
