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Journal Articles

Effect of uniaxial tensile strain on binding energy of hydrogen atoms to vacancy-carbon-hydrogen complexes in $$alpha$$-iron

Hirayama, Shintaro*; Sato, Koichi*; Kato, Daiji*; Iwakiri, Hirotomo*; Yamaguchi, Masatake; Watanabe, Yoshiyuki*; Nozawa, Takashi*

Nuclear Materials and Energy (Internet), 31, p.101179_1 - 101179_9, 2022/06

 Times Cited Count:3 Percentile:68.71(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Pitting damage in metals by mercury cavitation with MIMTM

Yoshiie, Toshimasa*; Futakawa, Masatoshi; Naoe, Takashi; Komatsu, Masao*; Sato, Koichi*; Xu, Q.*; Kawai, Masayoshi*

Materia, 52(8), p.390 - 394, 2013/08

In the liquid mercury target for the spallation neutron source, pressure waves occurs owing to the high-intense proton beam bombardment. The pressure waves induces the cavitation in the interface between the mercury and the target vessel through the propagation process. Erosion damage composed of micro-pits clusters is formed by the micro-jets and shock waves emitted from cavitation bubble collapse. In this paper, researches for damage structure of the material that was examined using the electroMagnetic IMpact Testing Machine (MIMTM) form the viewpoint of high-speed deformation. The result showed that the 200$$sim$$300 m/s of collision velocity for micro-jet impacting which was estimated from the numerical simulation is reasonable value.

Journal Articles

Transfer of tritium in concrete coated with hydrophobic paints

Fukada, Satoshi*; Edao, Yuki*; Sato, Koichi*; Takeishi, Toshiharu*; Katayama, Kazunari*; Kobayashi, Kazuhiro; Hayashi, Takumi; Yamanishi, Toshihiko; Hatano, Yuji*; Taguchi, Akira*; et al.

Fusion Engineering and Design, 87(1), p.54 - 60, 2012/01

 Times Cited Count:4 Percentile:31.96(Nuclear Science & Technology)

An experimental study on tritium (T) transfer in porous concrete for the tertiary T safety containment is performed to investigate (1) how fast HTO penetrates through concrete walls, (2) how well concrete walls contaminated with water-soluble T are decontaminated by a solution-in-water technique, and (3) how well hydrophobic paint coating works as a protecting film against HTO migrating through concrete walls. The epoxy paint coating can work as a HTO diffusion barrier and the PRF value is around 1/10. The silicon paint coating cannot work as the anti-T permeation barrier, because water deteriorates contact between the paint and cement or mortar.

Journal Articles

Positron annihilation lifetime measurements of vanadium alloy and F82H irradiated with fission and fusion neutrons

Sato, Koichi*; Inoue, Kazuya*; Yoshiie, Toshimasa*; Xu, Q.*; Wakai, Eiichi; Kutsukake, Chuzo; Ochiai, Kentaro

Journal of Nuclear Materials, 386-388, p.203 - 205, 2009/04

 Times Cited Count:2 Percentile:17.7(Materials Science, Multidisciplinary)

V-4Cr-4Ti F82H, Ni and Cu were irradiated with fission and fusion neutrons at room temperature and 473 K. Defect structures were analyzed and compared using positron annihilation lifetime measurement, and microstructural evolution was discussed. The mean lifetime of positrons (the total amount of residual defects) increased with the irradiation dose. The effect of cascade impact was detected in Ni at room temperature. The size and the number of vacancy clusters were not affected by the displacement rate in the fission neutron irradiation at 473 K for the metals studied. The vacancy clusters were not formed in V Cr Ti irradiated at 473 K in the range of 10$$^{-6}$$-10$$^{-3}$$ dpa. In F82H irradiated at 473 K, the defect evolution was prevented by pre-existing defects. The mean lifetime of positrons in fission neutron irradiation was longer than that in fusion neutron irradiation in V Cr Ti at 473 K. It was interpreted that more closely situated subcascades were formed in the fusion neutron irradiation and subcascades interacted with each other, and consequently the vacancy clusters did not grow larger.

Journal Articles

Reaction kinetics analysis of damage evolution in accelerator driven system beam windows

Yoshiie, Toshimasa*; Xu, Q.*; Sato, Koichi*; Kikuchi, Kenji; Kawai, Masayoshi*

Journal of Nuclear Materials, 377(1), p.132 - 135, 2008/06

 Times Cited Count:11 Percentile:59.16(Materials Science, Multidisciplinary)

Reaction kinetic analysis was used to estimate the damage evolution in window materials of 800 MWth ADS. Parameters were fitted to F82H of the STIP-II experiment and EC316LN of the STIP-I experiment. In F82H, the concentration of bubbles was almost constant and the bubble size increased, while the concentration of interstitial type dislocation loops increased and their size was constant between 3$$times$$10$$^{-3}$$ and 300 dpa. EC316LN showed almost the same behavior. Swelling increased almost linearly with irradiation dose above 3 dpa between 673 K and 773 K.

Journal Articles

Analytical representation for neutron streaming through slits in fusion reactor blanket by Monte Carlo calculation

Sato, Satoshi; Maki, Koichi*

Fusion Engineering and Design, 65(4), p.501 - 524, 2003/07

 Times Cited Count:8 Percentile:49.89(Nuclear Science & Technology)

no abstracts in English

Journal Articles

2-D overall shielding analysis of ITER tokamak machine

Sato, Satoshi; Takatsu, Hideyuki; *; *; Iida, Hiromasa; R.Santoro*

Fusion Technology 1996, 0, p.1587 - 1590, 1997/00

no abstracts in English

Journal Articles

Evaluation of the environmental gamma-ray dose rate by skyshine analysis during the maintenance of an activated TFC in ITER

Sato, Satoshi; Takatsu, Hideyuki; *; *; Mori, Seiji*; Iida, Hiromasa; R.Santoro*

Journal of Fusion Energy, 16(3), p.211 - 218, 1997/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Shielding analysis for toroidal field coils around exhaust duct in fusion experimental reactors

Sato, Satoshi; Takatsu, Hideyuki; *; Seki, Yasushi

J. Fusion Eng. Des., 30(3), p.1076 - 1080, 1996/12

no abstracts in English

Journal Articles

Nuclear design for fusion reactors

*; Seki, Yasushi; Sato, Satoshi; *

Purazuma, Kaku Yugo Gakkai-Shi, 71(10), p.987 - 1001, 1995/10

no abstracts in English

JAEA Reports

Shielding analysis of the ITER/EDA NBI duct

S.Zimin*; *; Takatsu, Hideyuki; Sato, Satoshi; Tsunematsu, Toshihide; Inoue, Takashi; Ohara, Yoshihiro

JAERI-Tech 94-015, 37 Pages, 1994/08

JAERI-Tech-94-015.pdf:0.92MB

no abstracts in English

Journal Articles

Evaluation of radiation streaming through the annular gaps around divertor cooling pipes in fusion experimental reactors

Sato, Satoshi; *; Seki, Yasushi; Takatsu, Hideyuki; Mori, Seiji*

Proc. of the 8th Int. Conf. on Radiation Shielding, 0, p.1039 - 1046, 1994/00

no abstracts in English

Journal Articles

Evaluation of skyshine dose rate due to gamma-rays from activated cooling water in fusion experimental reactors

Sato, Satoshi; *; Seki, Yasushi; Takatsu, Hideyuki; Mori, Seiji*

Proc. of the 8th Int. Conf. on Radiation Shielding, 0, p.946 - 953, 1994/00

no abstracts in English

JAEA Reports

Two-dimensional over-all neutronics analysis of the ITER device

S.Zimin*; Takatsu, Hideyuki; Mori, Seiji*; *; Seki, Yasushi; Sato, Satoshi; Tada, Eisuke

JAERI-M 93-141, 75 Pages, 1993/07

JAERI-M-93-141.pdf:2.22MB

no abstracts in English

JAEA Reports

Streaming through the gaps around divertor pipings in ITER

Sato, Satoshi; *; Seki, Yasushi; Takatsu, Hideyuki; Mori, Seiji*; Kuroda, Toshimasa*; S.Zimin*

JAERI-M 93-093, 29 Pages, 1993/03

JAERI-M-93-093.pdf:0.86MB

no abstracts in English

JAEA Reports

Heterogeneous effects on shielding characteristics in fusion reactor neutronics calculations

Sato, Satoshi; *; Seki, Yasushi; Takatsu, Hideyuki; Kuroda, Toshimasa*; S.Zimin*

JAERI-M 92-093, 53 Pages, 1992/07

JAERI-M-92-093.pdf:1.54MB

no abstracts in English

JAEA Reports

Some ITER shield problems examination

S.Zimin*; Sato, Satoshi; *; Takatsu, Hideyuki; Kuroda, Toshimasa*; Seki, Yasushi

JAERI-M 92-063, 45 Pages, 1992/05

JAERI-M-92-063.pdf:1.4MB

no abstracts in English

JAEA Reports

Japanese contributions to blanket design for ITER

Kuroda, Toshimasa*; Yoshida, Hiroshi; Takatsu, Hideyuki; Seki, Yasushi; Noda, Kenji; Watanabe, H.; Koizumi, Koichi; Nishio, Satoshi; *; *; et al.

JAERI-M 91-133, 191 Pages, 1991/08

JAERI-M-91-133.pdf:5.79MB

no abstracts in English

JAEA Reports

Conceptual design study of fusion experimental reactor (FY86 FER); Reactor configuration/structure design

; ; Mizoguchi, Tadanori*; *; *; *; Watanabe, Takashi*; Mori, Seiji*; Adachi, Junichi*; *; et al.

JAERI-M 87-139, 355 Pages, 1987/09

JAERI-M-87-139.pdf:8.78MB

no abstracts in English

30 (Records 1-20 displayed on this page)