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Journal Articles

2016 Professional Engineer (PE) test preparation course "Nuclear and Radiation Technical Disciplines"

Takahashi, Naoki; Yoshinaka, Kazuyuki; Harada, Akio; Yamanaka, Atsushi; Ueno, Takashi; Kurihara, Ryoichi; Suzuki, Soju; Takamatsu, Misao; Maeda, Shigetaka; Iseki, Atsushi; et al.

Nihon Genshiryoku Gakkai Homu Peji (Internet), 64 Pages, 2016/00

no abstracts in English

Journal Articles

Hydrogen adsorption on single-walled carbon nanotubes studied by core-level photoelectron spectroscopy and Raman spectroscopy

Tokura, Akio*; Maeda, Fumihiko*; Teraoka, Yuden; Yoshigoe, Akitaka; Takagi, Daisuke*; Homma, Yoshikazu*; Watanabe, Yoshio*; Kobayashi, Yoshihiro*

Carbon, 46(14), p.1903 - 1908, 2008/11

 Times Cited Count:18 Percentile:52.96(Chemistry, Physical)

We have investigated the adsorption of atomic hydrogen on vertically aligned carbon nanotube using ${it in situ}$ synchrotron-radiation-based core-level photoelectron spectroscopy and Raman spectroscopy. From C1s spectra, we identified a peak component due to CH bonds of carbon atoms in single-walled carbon nanotubes. We also found the suppression of $$pi$$-plasmon excitation, indicating that the hydrogen adsorption deforms the bonding structure. Raman spectra of the single-walled carbon nanotubes indicated that the radial-breathing-mode intensities decreased due to the adsorption-induced bonding-structure deformation. Moreover, the decrease for single-walled carbon nanotubes with small-diameter was more severe than that for large-diameter. Our results strongly suggest that the hydrogen adsorption, which induces the structure deformation from sp$$^{2}$$ to sp$$^{3}$$ bonding, depends on the diameter of SWCNTs.

JAEA Reports

Performance test results of mock-up model test facility with a full-scale reaction tube for HTTR hydrogen production system (Contract research)

Inagaki, Yoshiyuki; Hayashi, Koji; Kato, Michio; Fujisaki, Katsuo; Aita, Hideki; Takeda, Tetsuaki; Nishihara, Tetsuo; Inaba, Yoshitomo; Ohashi, Hirofumi; Katanishi, Shoji; et al.

JAERI-Tech 2003-034, 129 Pages, 2003/05

JAERI-Tech-2003-034.pdf:7.62MB

no abstracts in English

JAEA Reports

Evaluation of core characteristics with two-dimensional lattice calculations

Sato, Osamu*; Maeda, Akio*

JNC TJ9400 2003-008, 139 Pages, 2003/03

JNC-TJ9400-2003-008.pdf:3.49MB

Two-dimensional cell calculation is necessary to exactly treat the major heterogeneous structure of fuel pins and a wrapper tube in fast reactor fuel assemblies. JNC has been developing the new SLAROM, which includes a two-dimensional cell calculation routine. In this report, validity and effect of two-dimensional calculation were investigated. The validity was checked by comparing neutron flux in fuel assemblies and assembly averaged cross sections with those calculated by Monte Carlo code GMVP. The comparisons were made for the calculation model called "concentric layers of hexagon with equi-distance pin-rod array"(IGT=13) with a fuel assembly of JOYO and were also made for the model of a two-dimensional slab called "Quadrant of an octant symmetric assembly" (IGT=8) with SCF and DCF fuel cells in ZPPR=9. The calculated results with the new SLAROM and GMVP were agreed within statistical errors for the JOYO fuel assembly and the adequacy of the collision probability calculations in the new SLAROM was proved for a hexagonal fuel assembly. For a two-dimensional slab geometry, the assembly averaged absorption cross sections and total cross sections were 20% higher than those with Monte Carlo calculations below 24keV at which the large resonance of sodium exist. Further investigations are required to explain the differences. The results of core calculations with CITATION were performed and compared with the assembly-averaged cross sections using one-dimensional cell model and with the cross sections using two-dimentional cell model. THe differences caused by the cell calculation model were larger for radial blanket regions than for fuel regions. It revealed that the fewer numbers of fuel pins in radial blanket bring out the larger error of one-dimensional cell model.

JAEA Reports

Analytical study on creep behavior of a tube of coolant piping system in nuclear power plant (Contract research)

Miyazaki Noriyuki*; Hagiwara Seiya*; Chino, Eiichi*; Maruyama, Yu*; Hashimoto, Kazuichiro*; Maeda, Akio*

JAERI-Research 2001-047, 35 Pages, 2001/10

JAERI-Research-2001-047.pdf:1.63MB

no abstracts in English

Journal Articles

Research activities on advanced nuclear fuel cycle in NUCEF

Suzuki, Yasufumi; Dojiri, Shigeru; Ono, Akio; Maeda, Atsushi; Sugikawa, Susumu

Proceedings of International Conference on Back-End of the Fuel Cycle: From Research to Solutions (GLOBAL 2001) (CD-ROM), 7 Pages, 2001/09

no abstracts in English

Journal Articles

The Effect of temperature, pressure, and sulfur content on viscosity of the Fe-FeS melt

Terasaki, Hidenori*; Kato, Takumi*; Urakawa, Satoru*; Funakoshi, Kenichi*; Suzuki, Akio*; Okada, Taku; Maeda, Makoto*; Sato, Jin*; Kubo, Tomoaki*; Kasai, Shizu*

Earth and Planetary Science Letters, 190(1-2), p.93 - 101, 2001/07

 Times Cited Count:47 Percentile:68(Geochemistry & Geophysics)

The Fe-FeS melt is thought to be the major candidate of the outer core material. Its viscosity is one of the most important physical properties to study the dynamics of the convection in the outer core. We performed the in situ viscosity measurement of the Fe-FeS melt under high pressure using X-ray radiography falling sphere method with a novel sample assembly. Viscosity was measures in the temperature, pressure, and compositional conditions of 1233-1923 K, 1.5-6.9 GPa, and Fe-Fe $$_{72}$$ S $$_{28}$$ (wt %), respectively. The viscosity coefficients obtained by 17 measurements change systematically in the range of 0.008-0.036 Pa s. An activation energy of the viscous flow, 30 kJ/mol, and the activation volume, 1.5 cm $$^{3}$$ /mol, are determined as the temperature and pressure dependence, and the viscosity of the Fe $$_{72}$$ S $$_{28}$$ melt is found to be smaller than that of the Fe melt by 15 %. These tendencies can be well correlated with the structural variation of the Fe-FeS melt.

Journal Articles

Creep failure of reactor cooling system piping of nuclear power plant under severe accident conditions

Chino, Eiichi; Maruyama, Yu; Maeda, Akio*; Harada, Yuhei*; Nakamura, Hideo; Hidaka, Akihide; Shibazaki, Hiroaki*; Yuchi, Yoko; Kudo, Tamotsu; Hashimoto, Kazuichiro*

Proceedings of the 7th International Conference on Creep and Fatigue at Elevated Temperatures (CREEP7), p.107 - 115, 2001/06

no abstracts in English

Journal Articles

Revaporization of CsI aerosol in a horizontal straight pipe in a severe accident condition

Shibazaki, Hiroaki*; Maruyama, Yu; Kudo, Tamotsu; Hashimoto, Kazuichiro*; Maeda, Akio*; Harada, Yuhei*; Hidaka, Akihide; Sugimoto, Jun

Nuclear Technology, 134(1), p.62 - 70, 2001/04

 Times Cited Count:3 Percentile:28.03(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Reduction technique of welding defect in the welded joint of aluminum alloys base on GTAW

Maeda, Akio; Oba, Toshihiro; Kikuchi, Hiroyuki; Shibata, Katsuyuki

JAERI-Tech 2001-003, 48 Pages, 2001/02

JAERI-Tech-2001-003.pdf:5.95MB

no abstracts in English

Journal Articles

Modeling of hot tensile and short-term creep strength for LWR piping materials under severe accident conditions

Harada, Yuhei*; Maruyama, Yu; Maeda, Akio*; Chino, Eiichi; Shibazaki, Hiroaki*; Kudo, Tamotsu; Hidaka, Akihide; Hashimoto, Kazuichiro; Sugimoto, Jun

JAERI-Conf 2000-015, p.309 - 314, 2000/11

no abstracts in English

Journal Articles

Post-test creep analysis of piping failure tests in WIND project

Chino, Eiichi; Maruyama, Yu; Yuchi, Yoko; Shibazaki, Hiroaki*; Nakamura, Hideo; Hidaka, Akihide; Kudo, Tamotsu; Hashimoto, Kazuichiro; Maeda, Akio*

JAERI-Conf 2000-015, p.303 - 308, 2000/11

no abstracts in English

Journal Articles

Evaluation of high temperature tensile and greep properties of light water reactor coolant piping materials for severe accident analyses

Harada, Yuhei; Maruyama, Yu; Maeda, Akio*; Chino, Eiichi; Shibazaki, Hiroaki*; Kudo, Tamotsu; Hidaka, Akihide; Hashimoto, Kazuichiro; Sugimoto, Jun

Journal of Nuclear Science and Technology, 37(6), p.518 - 529, 2000/06

no abstracts in English

Journal Articles

Effect of microstructure on failure behavior of light water reactor coolant piping under severe accident conditions

Harada, Yuhei; Maruyama, Yu; Maeda, Akio; Shibazaki, Hiroaki*; Kudo, Tamotsu; Hidaka, Akihide; Hashimoto, Kazuichiro; Sugimoto, Jun

Journal of Nuclear Science and Technology, 36(10), p.923 - 933, 1999/10

 Times Cited Count:3 Percentile:29.56(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Cause finding experiments and environmental analysis on the accident of the fire and explosion in TRP bituminization facility

Fujine, Sachio; Murata, Mikio; Abe, Hitoshi; Takada, Junichi; Tsukamoto, Michio; Miyata, Teijiro*; Ida, Masaaki*; Watanabe, Makio; Uchiyama, Gunzo; Asakura, Toshihide; et al.

JAERI-Research 99-056, p.278 - 0, 1999/09

JAERI-Research-99-056.pdf:22.73MB

no abstracts in English

Journal Articles

Current status of criticality safety experiment in NUCEF and its enhancement of facility function toward Pu experiment

Takeshita, Isao; Ono, Akio; Izawa, Naoki*; Miyoshi, Yoshinori; Maeda, Atsushi; Sugikawa, Susumu; Miyauchi, Masakatsu

Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), p.1512 - 1576, 1999/09

no abstracts in English

Journal Articles

Present status and enchancement of facility capability in NUCEF for the safety research and development of base technology on nuclear fuel cycle

Tsubata, Yasuhiro; Maeda, Atsushi; Ono, Akio; Sugikawa, Susumu; Takayanagi, Masaji; Takeshita, Isao

Proceedings of International Conference on Future Nuclear Systems (GLOBAL '99) (CD-ROM), 7 Pages, 1999/08

no abstracts in English

Journal Articles

Current status of WIND project

Hashimoto, Kazuichiro; Harada, Yuhei; Maeda, Akio; Maruyama, Yu; Shibazaki, Hiroaki*; Kudo, Tamotsu; Hidaka, Akihide; Sugimoto, Jun

JAERI-Conf 99-005, p.161 - 164, 1999/07

no abstracts in English

Journal Articles

Metallurgical study of failed specimen and piping under LWR severe accident conditions

Harada, Yuhei; Maruyama, Yu; Maeda, Akio; Shibazaki, Hiroaki*; Kudo, Tamotsu; Hidaka, Akihide; Hashimoto, Kazuichiro; Sugimoto, Jun

JAERI-Conf 99-005, p.171 - 175, 1999/07

no abstracts in English

Journal Articles

Experimental and analytical studies on creep failure of reactor coolant piping

Maeda, Akio; Maruyama, Yu; Hashimoto, Kazuichiro; Harada, Yuhei; Shibazaki, Hiroaki*; Kudo, Tamotsu; Nakamura, Naohiko; Hidaka, Akihide; Sugimoto, Jun

JAERI-Conf 99-005, p.165 - 170, 1999/07

no abstracts in English

34 (Records 1-20 displayed on this page)