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Journal Articles

Status of studies on HLW glass performance for confirming its validity in assessment

Inagaki, Yaohiro*; Mitsui, Seiichiro*; Makino, Hitoshi*; Ishiguro, Katsuhiko*; Kamei, Gento*; Kawamura, Kazuhiro*; Maeda, Toshikatsu; Ueno, Kenichi*; Bamba, Tsunetaka*; Yui, Mikazu*

Genshiryoku Bakkuendo Kenkyu, 10(1-2), p.69 - 84, 2004/03

no abstracts in English

JAEA Reports

Report on Collaboration Research Meeting with Belgian Nuclear Research Center(SCK/CEN) -CORALUS:An Integrated in Situ Corrosion Test on Alpha Active HLW Glass-

Kawamura, Kazuhiro; Ueno, Kenichi

JNC TN8200 2003-002, 248 Pages, 2003/11

JNC-TN8200-2003-002.pdf:21.8MB

Collaboration Research Meeting with Belgian Nuclear Research Center(SCK/CEN) -CORALUS:An integrated in situ corrosion test on alpha active HLW glass- was held on October 29 and 30th, 2003 at Avignon, France. Scientific achievements obtained in the last year were presented and results on modelling of nuclide migration were discussed. It is necessary to get data in situ tests and to compare with the modelling results.

JAEA Reports

Hydraulic characteristics of buffer material-II; The influence which saline water exert on hydraulic properties of bentonite buffer material

Kikuchi, Hirohito*; Tanai, Kenji; Matsumoto, Kazuhiro*; Sato, Haruo; Ueno, Kenichi; Tetsu, Takeshi*

JNC TN8430 2003-002, 47 Pages, 2003/03

JNC-TN8430-2003-002.pdf:2.11MB

By the second progress report(H12) on research and development for the geological disposal of HLW in Japan, Japan Nuclear Cycle Development Institute (JNC) extended the database on basic properties of compacted bentonite, and this was mainly obtained by using distilled water as test fluid. This report presents influence of dry densities, silica sand content and temperature on the hydraulic properties of compacted bentonite under condition of marine-based groundwater, which was simulated by use of synthesized seawater. We found that hydraulic conductivity increases with increasing temperature, and the relationship between effective clay density and intrinsic permeability is obtained by the following equation. $$kappa$$ = exp(-47.155 + 15.138 $$rho_{b}$$ -7.878 $$rho_{b}^{2}$$) where $$kappa$$ is intrinsic permeability[m$$^{2}$$], $$rho_{b}$$ is effective clay density[Mg/m$$^{3}$$]. Intrinsic permeability using synthetic seawater as test fluid is about ten times higher then that under distilled water condition. Difference between them however becomes smaller with increasing dry density. We also examined the smectite layers distance after test samples, but remarkable change was not found between them.

Journal Articles

New technique for the determination of trace elements using multiparameter coincidence spectrometry

Hatsukawa, Yuichi; Toh, Yosuke; Oshima, Masumi; Hayakawa, Takehito; Shinohara, Nobuo; Kushita, Kohei; Ueno, Takashi; Toyoda, Kazuhiro*

Journal of Radioanalytical and Nuclear Chemistry, 255(1), p.111 - 113, 2003/01

 Times Cited Count:12 Percentile:62.23(Chemistry, Analytical)

no abstracts in English

JAEA Reports

FBR fuel reprocessing plused column equipment test; Operating characteristics of pulsed ploto columms on the condition of the qqueous continous phase

*; Kishimoto, Yoichiro; Kawata, Tomio*; Hayashi, Shotaro; *; Kitamura, Koichiro; Ojima, Hisao; *; *; Ueno, Kazuhiro

PNC TN8410 87-081, 98 Pages, 1986/12

PNC-TN8410-87-081.pdf:9.76MB

no abstracts in English

Oral presentation

Study on ageing behavior of reprocessing plants, 9; Effect of ageing on mechanical properties of nickel based refractory alloys

Ishijima, Yasuhiro; Takada, Juntaro; Ueno, Fumiyoshi; Yamamoto, Masahiro; Uchiyama, Gunzo; Nojima, Yasuo*; Fujine, Sachio*; Kimura, Kazuhiro*

no journal, , 

Effect of ageing on mechanical properties of nickel based refractory alloy was evaluated for study on ageing behavior of nuclear fuel reprocessing plants. Solution treated and aged Alloy 625 was elected to test material. Creep tests and tensile tests were carried out at 1027 K. From test results, aged alloy 625 showed linear relationship between test stress and secondary creep rate. On the other hand, solution treated alloy 625 showed deformation behavior change at 100 MPa. This result indicates that the ageing behavior of reducing furnace can evaluate by straight line extrapolation. Aged alloy 625 showed remarkable decreasing of ductility at room temperature. This result suggests that room temperature embrittlement should be considered on the ageing behavior of reducing furnace.

Oral presentation

Excitation functions for fusion reaction with projectiles of different deformation

Toda, Kosuke*; Ueno, Shingo*; Takahashi, Naruto*; Kasamatsu, Yoshitaka*; Yokokita, Takuya*; Oe, Kazuhiro; Yokoyama, Akihiko*

no journal, , 

In order to study the effect of the degree of deformation on the fusion reaction, we have researched for the fusion reaction of $$^{nat}$$Lu + $$^{16}$$O and $$^{165}$$Ho + $$^{20}$$Ne. In the systems, the projectile nucleus $$^{16}$$O is spherical, while $$^{20}$$Ne is deformed. Thus they are fusion reactions of deformed-spherical nuclei and deformed-deformed nuclei, respectively. Besides, latter system has the same compound nucleus, $$^{185}$$Ir, as the $$^{169}$$Tm + $$^{16}$$O reaction in previous work. The evaporation residue cross sections were measured by using a stack technique and a gas-jet technique for the projectile energies of 50 to 155 MeV. The cross sections were compared with the theoretical values calculated by HIVAP code. The measured excitation functions were found to agree fairly well with theoretical values. The results are consistent with the idea that the degree of deformation makes an effect on the rising edge of excitation functions near the Coulomb barrier.

Oral presentation

Effect of immersion history in hot artificial seawater on strength property of fuel cladding tube irradiated in BWR

Suzuki, Kazuhiro; Toyokawa, Takuya; Motooka, Takafumi; Tsukada, Takashi; Ueno, Fumiyoshi; Terakawa, Yuto; Suzuki, Miho; Ichise, Kenichi; Numata, Masami; Kikuchi, Hiroyuki

no journal, , 

no abstracts in English

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