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JAEA Reports

Results of pilot borehole investigation in -500m access/research gallery-south (12MI32 borehole)

Kawamoto, Koji; Kuroiwa, Hiroshi; Yamada, Nobuto; Onuki, Kenji; Omori, Kazuaki; Takeuchi, Ryuji; Ogata, Nobuhisa; Omori, Masaki; Watanabe, Kazuhiko

JAEA-Technology 2014-011, 92 Pages, 2014/07

JAEA-Technology-2014-011.pdf:24.65MB
JAEA-Technology-2014-011-appendix(DVD).zip:331.54MB

This document summarizes the data of pilot boreholes (12MI32) in the -500m Access/Research Gallery-South. The geological, hydraulic and geochemical data were obtained. In addition, groundwater monitoring system was installed to observe the groundwater pressure in initial condition and change during the excavation of gallery. The results of investigation, biotite granite with medium to coarse-grained equigranular texture are characterized. Rock mass classification is B from CM class. Minor fault with fault breccia are observed around 48.90mabh. However, S200_13 fault and IF_SB3_13_3 fault (that were presumed by an original model) were not observed. Density of fracture is large in the section of 40.00 to 80.00mabh. Water inflow was a maximum of 600 L/min in 78.83mabh. Permeability ranges from 2.0E-9 to 1.5E-08m/sec at the zone with low inflow, from 1.1E-05 to 1.6E-05m/sec at the zone with high inflow, respectively. Groundwater chemistry is rich in Na and Cl ion.

Journal Articles

TiCrV hydrogen storage alloy studied by positron annihilation spectroscopy

Kawasuso, Atsuo; Arashima, Hironobu*; Maekawa, Masaki; Ito, Hideaki*; Kabutomori, Toshiki*

Journal of Alloys and Compounds, 486(1-2), p.278 - 283, 2009/06

 Times Cited Count:9 Percentile:48.55(Chemistry, Physical)

We have studied the degradation process of TiCrV hydrogen storage alloy alloy using positron annihilation spectroscopy. As the hydrogen storage capacity decreased with the number of pressure swing cycles, positron lifetime increased. The increase in positron lifetime is due to the volume expansion caused by hydride formation. After degassing at 500 $$^{circ}$$C, the hydrogen storage capacity recovered to the initial level. However, the positron lifetime was still longer than the initial level suggesting the survival of dislocations. The degradation of hydrogen storage capacity is probably caused by both hydride formation and the generation of dislocations.

Journal Articles

Positron lifetime study on degradation of TiCrV hydrogen storage alloy

Kawasuso, Atsuo; Arashima, Hironobu*; Maekawa, Masaki; Ito, Hideaki*; Kabutomori, Toshiki*

Materials Science Forum, 607, p.122 - 124, 2008/11

Using positron lifetime spectroscopy, we examined the evolution of defects in the Ti$$_{24}$$Cr$$_{36}$$V$$_{40}$$ alloy prepared by the arc-melting method during hydriding cycles. After one hydriding cycle dislocations were responsible for positron trapping. The dislocation-related lifetime showed no significant change with increasing the hydriding cycle suggesting that the dislocation density is well above the dynamic range of positron trapping rate. After 20 hydriding cycles, prolonged lifetime components (0.4-0.5 ns and 1.9-2 ns) were obtained. These lifetimes were nearly constant during the further hydriding cycles while their intensities increased. Vacancy defects were generated and slowly developed to microvoids during the hydriding cycles. After 200 hydriding cycles the rechargeable hydrogen capacity decreased to 90% relative to the initial amount. It is thus inferred that the reduction of rechargeable hydrogen capacity is partly caused by the formation of microvoids and dislocations.

Journal Articles

Development and operational experiences of the JT-60U tokamak and power supplies

Hosogane, Nobuyuki; Ninomiya, Hiromasa; Matsukawa, Makoto; Ando, Toshiro; Neyatani, Yuzuru; Horiike, Hiroshi*; Sakurai, Shinji; Masaki, Kei; Yamamoto, Masahiro; Kodama, Kozo; et al.

Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.368 - 385, 2002/09

 Times Cited Count:2 Percentile:17.07(Nuclear Science & Technology)

This paper reviews developments of the JT-60U tokamak and coil power supplies and their operational experiences obtained to date. The JT-60U is a large tokamak upgraded from the original JT-60 to obtain high plasma current, large plasma volume and highly elongated divertor configurations. In the modification, all components inside the bore of toroidal magnetic field coils, a vacuum vessel, poloidal magnetic field coils (PF-coils), divertor etc., were renewed. Furthermore, boron carbide converted CFC tiles were used as divertor tiles to reduce erosion of carbon-base tiles. Later, a semi-closed divertor with pumps was installed in the replacement of the open divertor. Various technologies and ideas introduced to develop these components their operational experiences provide important data for designing future tokamaks. Also, major troubles that had influence on the JT-60U operations are described. As a maintenance issue for tokamaks using deuterium fueling gas, a method for reducing radiation exposure of in-vessel workers are introduced.

Oral presentation

Degradation of TiCrV hydrogen storage alloy

Kawasuso, Atsuo; Maekawa, Masaki; Arashima, Hironobu*; Ito, Hideaki*; Kabutomori, Toshiki*

no journal, , 

no abstracts in English

Oral presentation

Advanced ORIENT cycle study (Phase I), 2; Separation of rare metal, 1; PGMs, Tc and Re

Yamagishi, Isao; Koyama, Shinichi; Ozawa, Masaki; Kanamura, Shohei*; Mizuguchi, Koji*; Omori, Takashi*

no journal, , 

Electro-deposition of light platinum group metals, PGMs (Ru, Rh and Pd), and Tc from high-level liquid waste (HLLW) has been studied for development of an advanced nuclear fuel cycle (Adv.-ORIENT Cycle). PGMs and Tc deposited on Pt electrode are to be used for hydrogen production by catalytic electrolysis of water with its electrode. In nitric acid media, 88.1% of Pd were deposited form a simulated HLLW. In hydrochloric acid media, deposition ratios of Ru, Rh and Re (Tc simulator) were 77.8, 94.8 and 85.2%, respectively.

Oral presentation

Buckling analysis of gravity support legs for JT-60SA vacuum vessel

Ejiri, Mitsuru*; Kitamura, Kazunori*; Araki, Takao*; Omori, Junji*; Asano, Shiro*; Hayakawa, Atsuro*; Shibama, Yusuke; Masaki, Kei; Sakasai, Akira

no journal, , 

In the operation of tokamak, such loads as electromagnetic and seismic are assumed to be imposed on the vacuum vessel (VV), and not a little thermal expansion takes place when VV is baked. The gravity support leg (GS) has to support the loads described above in addition to the dead weight of VV including in-vessel components and compensate deformation. The GS is equipped with plate spring (PS) to have both stiffness and flexibility. In this study, the buckling strength of the PSs was evaluated. The effect of the initial imperfection of the PSs which is assumed to result from machining or welding process on the buckling strength was also studied. It is concluded that GS has sufficient buckling strength against assumed initial imperfections.

Oral presentation

Development of divertor IR thermography for ITER

Sugie, Tatsuo; Takeuchi, Masaki; Ishikawa, Masao; Shimada, Takahiko; Katsunuma, Atsushi*; Kitazawa, Daisuke*; Omori, Keisuke*; Itami, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Gravity support design and manufacturing of the JT-60SA vacuum vessel

Ejiri, Mitsuru*; Asano, Shiro*; Omori, Junji*; Okuyama, Toshihisa*; Takahashi, Nobuji*; Yamada, Masahiro*; Araki, Takao*; Kai, Toshiya*; Shibama, Yusuke; Masaki, Kei; et al.

no journal, , 

In the operation of Tokamak device, such loads as electromagnetic and seismic are assumed to be imposed on the vacuum vessel (VV), and not a little thermal expansion takes place when VV is baked. The gravity support (GS) has to support the loads described above in addition to the dead weight of VV including in-vessel components and compensate deformation. The GS is equipped with leaf spring that has both stiffness and flexibility. In this study, the FEM analysis-based design and assembly procedure of the GS is reported. The manufacturing process of GS components is also reported with trial manufacturing results.

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