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Journal Articles

Resonant inelastic X-ray scattering study of intraband charge excitations in hole-doped high-$$T_c$$ cuprates

Wakimoto, Shuichi; Ishii, Kenji; Kimura, Hiroyuki*; Ikeuchi, Kazuhiko*; Yoshida, Masahiro*; Adachi, Tadashi*; Casa, D.*; Fujita, Masaki*; Fukunaga, Yasushi*; Gog, T.*; et al.

Physical Review B, 87(10), p.104511_1 - 104511_7, 2013/03

 Times Cited Count:9 Percentile:43.58(Materials Science, Multidisciplinary)

JAEA Reports

Investigation on integrity of JMTR reactor building

Oto, Tsutomu; Kimura, Tadashi; Fukasaku, Akitomi; Kusunoki, Tsuyoshi

JAEA-Review 2010-066, 22 Pages, 2011/01

JAEA-Review-2010-066.pdf:3.94MB

The refurbishment of JMTR is scheduled from the beginning of FY 2007 to the end of FY 2010. An integrity investigation for concrete structures of the JMTR buildings was carried out in early phase of the refurbishment. This paper describes investigated results and repair work of the vent stack, trenches, canal building and the filter bank. Investigated items were the concrete surface deterioration, rebound number (nondestructive estimation of strength), comprehensive strength using drilled concrete core test piece, carbonation depth, reinforced bar corrosion and chloride ion content. The integrity of these concrete structures was confirmed by these investigations. Based on the investigation results, repair works such as re-painting were carried out from the viewpoint of preventive maintenance for the vent stack, trenches and canal building.

JAEA Reports

Post irradiation examination of type 316 stainless steels for in-pile Oarai Water Loop No.2 (OWL-2)

Shibata, Akira; Kimura, Tadashi; Nagata, Hiroshi; Aoyama, Masashi; Kanno, Masaru; Omi, Masao

JAEA-Testing 2010-003, 22 Pages, 2010/11

JAEA-Testing-2010-003.pdf:8.82MB

Type 316 stainless steels (SSs) were used for tube material of the Oarai water loop No.2 (OWL-2) in the reactor. But data of highly irradiated Type 316 SSs has been insufficient since OWL-2 was installed. Therefore surveillance tests of type 316 SSs which were irradiated up to 3.4 $$times$$ 10$$^{25}$$ n/m$$^{2}$$ in fast neutron fluence ($$>$$1 MeV) were performed. But type 316 SSs were widely used in JMTR, then additional data of type 316 SSs irradiated higher was required. Therefore PIEs of type 316 SSs surveillance specimens which were irradiated up to 1.0 $$times$$ 10$$^{26}$$ n/m$$^{2}$$ in fast neutron fluence were performed and reported in this paper. Tendency of results has good agreement with results of 10$$^{24}$$-10$$^{25}$$ n/m$$^{2}$$ in fast neutron fluence. More than 37 % in total elongation was confirmed in all test conditions. It is confirmed that type 316 SS irradiated up to 1.0 $$times$$ 10$$^{26}$$ n/m$$^{2}$$ in fast neutron fluence has enough ductility as structure material.

JAEA Reports

Investigation on integrity of canal expanded joint

Oto, Tsutomu; Kimura, Tadashi; Miyauchi, Masaru; Nemoto, Nobuaki; Tobita, Kenji; Fukasaku, Akitomi; Takahashi, Kunihiro

JAEA-Review 2010-017, 21 Pages, 2010/07

JAEA-Review-2010-017.pdf:7.68MB

An integrity investigation of a Canal Expanded Joint was carried out as one of the integrity investigation of the JMTR reactor building related facilities and components, before the repair or replacement work of the JMTR related facilities that had begun in FY2007. The Canal Expanded Joint will be used for long-term after the JMTR restart. In the integrity investigation, the visual inspection, the performance test (Surface observations, Durometer hardness test) were investigated respectively and the integrity of the Canal Expanded Joint was confirmed. In order to use the Canal Expanded Joint continuously for long-term, it is important for maintaining the integrity of the Canal Expanded Joint by the periodical maintenance and the repairing work including that has been conducted up to now.

JAEA Reports

Investigation on integrity of JMTR concrete structure

Miyauchi, Masaru; Kimura, Tadashi; Oto, Tsutomu; Nemoto, Nobuaki; Tobita, Kenji; Fukasaku, Akitomi; Takahashi, Kunihiro

JAEA-Review 2010-008, 106 Pages, 2010/06

JAEA-Review-2010-008.pdf:8.89MB

An integrity investigation was carried out for the JMTR Concrete Structure (Vent Stack, Trench, Canal Building, Filter Bank), which was the concrete structure and would be used for the long-term after JMTR restart, before the repair or replacement work of the JMTR related facilities that had begun in FY2007. In the integrity investigation, the concrete surface deterioration, the rebound number (nondestructive strength test), compressive strength using drilled concrete core test piece, the static modules of elasticity, the carbonation depth, the reinforced bar corrosion and the chloride ion content were investigated respectively and the integrity of concrete was confirmed. After the investigation, repair works such as re-painting of the Vent Stack and Trench were carried out from the viewpoint of prevention of flaking off, floating of the painting and the thinning due to the investigation results. In order to use the JMTR concrete structure continuously for long-term, it is important for maintaining the integrity of a concrete structure by the periodical maintenance and the repairing work including the building outer-wall surface painting that has been conducted up to now.

JAEA Reports

Investigation on integrity of JMTR UCL elevated water tank

Kimura, Tadashi; Oto, Tsutomu; Miyauchi, Masaru; Nemoto, Nobuaki; Tobita, Kenji; Fukasaku, Akitomi; Takahashi, Kunihiro

JAEA-Review 2010-001, 27 Pages, 2010/03

JAEA-Review-2010-001.pdf:18.81MB

In order to investigate an integrity of the UCL (Utility Cooling Line) elevated water tank to be used for a long term after the JMTR restart, investigation on the base of the UCL elevated tank, especially for the part which had a significant aged effect, was carried out before the refurbishment work of the JMTR related facilities which had begun in FY2007. In the integrity investigation, it was confirmed that some part of the base bolts had significant aged effects, there were no evidence of crack and false indication in the welding region though thinning were observed in some parts of the base plate and the surrounding plate. After the investigation, repair works such as re-painting of the UCL elevated water tank were carried out from the viewpoint of prevention of flaking off, floating of the painting and the thinning due to corrosion based on the investigation results. In order to maintain the integrity of the UCL elevated tank, the periodical maintenance and the repair works of the base of the UCL elevated tank are important for continuous use of it in future.

JAEA Reports

Investigation on integrity of JMTR reactor building

Kimura, Tadashi; Oto, Tsutomu; Miyauchi, Masaru; Nemoto, Nobuaki; Tobita, Kenji; Fukasaku, Akitomi; Takahashi, Kunihiro

JAEA-Review 2009-054, 73 Pages, 2010/03

JAEA-Review-2009-054.pdf:6.79MB

An integrity investigation was carried out for the JMTR reactor building, which was the concrete structure and would be used for the long-term after JMTR restart, before the repair or replacement work of the JMTR related facilities that had begun in FY2007. In the integrity investigation, the concrete surface deterioration, the rebound number (nondestructive strength test), compressive strength using drilled concrete core test piece, the static modules of elasticity, the carbonation depth, the reinforced bar corrosion and the chloride ion content were investigated respectively and the integrity of concrete was confirmed. In order to use the JMTR reactor building continuously for long-term, it is important for maintaining the integrity of a concrete structure by the periodical maintenance and the repairing work including the building outer-wall surface painting that has been conducted up to now.

JAEA Reports

The Outline of investigation on integrity of JMTR concrete structures, cooling system and utility facilities

Ebisawa, Hiroyuki; Hanakawa, Hiroki; Asano, Norikazu; Kusunoki, Hidehiko; Yanai, Tomohiro; Sato, Shinichi; Miyauchi, Masaru; Oto, Tsutomu; Kimura, Tadashi; Kawamata, Takanori; et al.

JAEA-Technology 2009-030, 165 Pages, 2009/07

JAEA-Technology-2009-030.pdf:69.18MB

The condition of facilities and machinery used continuously were investigated before the renewal work of JMTR on FY 2007. The subjects of investigation were reactor building, primary cooling system tanks, secondary cooling system piping and tower, emergency generator and so on. As the result, it was confirmed that some facilities and machinery were necessary to repair and others were used continuously for long term by maintaining on the long-term maintenance plan. JMTR is planed to renew by the result of this investigation.

Journal Articles

Charge excitations in the stripe-ordered La$$_{5/3}$$Sr$$_{1/3}$$NiO$$_{4}$$ and La$$_{2-x}$$(Ba,Sr)$$_{x}$$CuO$$_{4}$$ superconducting compounds

Wakimoto, Shuichi; Kimura, Hiroyuki*; Ishii, Kenji; Ikeuchi, Kazuhiko; Adachi, Tadashi*; Fujita, Masaki*; Kakurai, Kazuhisa; Koike, Yoji*; Mizuki, Junichiro; Noda, Yukio*; et al.

Physical Review Letters, 102(15), p.157001_1 - 157001_4, 2009/04

 Times Cited Count:25 Percentile:75.04(Physics, Multidisciplinary)

JAEA Reports

Investigation waste disposal procedure of spent ion exchange resin using overseas consignment

Kimura, Tadashi; Oto, Tsutomu; Izumo, Hironobu; Nagao, Yoshiharu; Kawamura, Hiroshi

JAEA-Review 2008-080, 16 Pages, 2009/03

JAEA-Review-2008-080.pdf:3.11MB

The ion exchange resin is used for the purification system of the primary cooling water and the pool canal water in the JMTR. The spent ion exchange resin is stored in the liquid waste tank. The amount of the spent ion exchange resin in the liquid waste tank increases with reactor operation. The possibility of the spent ion exchange resin processing for oversea processing facilities was examined as a procedure for processing of the spent ion exchange resin. As the results, technical, regulations, and social issues were extracted from the procedure of spent ion exchange resin processing at oversea processing facilities. Furthermore, the conditions of oversea processing were indicated.

Journal Articles

Investigation of waste disposal procedure of spent ion exchange resin

Kimura, Tadashi; Izumo, Hironobu; Nagao, Yoshiharu; Kawamura, Hiroshi

UTNL-R-0471, p.5_3_1 - 5_3_10, 2009/03

no abstracts in English

Journal Articles

The H-Invitational Database (H-InvDB); A Comprehensive annotation resource for human genes and transcripts

Yamasaki, Chisato*; Murakami, Katsuhiko*; Fujii, Yasuyuki*; Sato, Yoshiharu*; Harada, Erimi*; Takeda, Junichi*; Taniya, Takayuki*; Sakate, Ryuichi*; Kikugawa, Shingo*; Shimada, Makoto*; et al.

Nucleic Acids Research, 36(Database), p.D793 - D799, 2008/01

 Times Cited Count:51 Percentile:71.37(Biochemistry & Molecular Biology)

Here we report the new features and improvements in our latest release of the H-Invitational Database, a comprehensive annotation resource for human genes and transcripts. H-InvDB, originally developed as an integrated database of the human transcriptome based on extensive annotation of large sets of fulllength cDNA (FLcDNA) clones, now provides annotation for 120 558 human mRNAs extracted from the International Nucleotide Sequence Databases (INSD), in addition to 54 978 human FLcDNAs, in the latest release H-InvDB. We mapped those human transcripts onto the human genome sequences (NCBI build 36.1) and determined 34 699 human gene clusters, which could define 34 057 protein-coding and 642 non-protein-coding loci; 858 transcribed loci overlapped with predicted pseudogenes.

JAEA Reports

Subsurface temperature in non-Quaternary volcanic regions in Japan

Yamakawa, Tadashi; Takeda, Seiji; Kimura, Hideo; Hyodo, Hiroshi*

JAEA-Research 2007-040, 21 Pages, 2007/03

JAEA-Research-2007-040.pdf:2.95MB

Radionuclide migration toward human society through geologic processes is to be assessed as part of safety assessments of geologic disposal for radioactive waste. A subsurface temperature in non-Quaternary volcanic regions was focused as one of the changes in this study. The study was conducted to extract features of subsurface temperature in non-Quaternary volcanic regions throughout Japan. After delineating Quaternary volcanic regions, features in non-Quaternary volcanic regions were studied in various aspects. The present study clarified that a relationship between subsurface temperature and its depth was expressed by an equation in non-Quaternary volcanic regions far from about 24 km of Quaternary volcanic centers. This led to about 16$$^{circ}$$C/km in general geothermal gradient in non-Quaternary volcanic areas, which was lower than 20$$^{circ}$$C/km of the previous study.

JAEA Reports

Boundary delineation for regional groundwater flow through Geographic Information System (Contract research)

Yamakawa, Tadashi; Munakata, Masahiro; Kimura, Hideo; Hyodo, Hiroshi*

JAEA-Research 2007-039, 26 Pages, 2007/03

JAEA-Research-2007-039.pdf:4.68MB

Radionuclide migration toward human society through geologic processes is to be assessed as part of long-term safety assessments of geologic disposal for radioactive waste. This study was conducted to develop methodologies of boundary delineation for regional groundwater flow system. Geographic Information System, GIS, was applied to Miyakoji in the Abukuma as an area of interest. The present study revealed that, taking the groundwater flows and fracture characteristics of the area into consideration, the groundwater flow system in Miyakoji drainage basin should be bounded by the Otakine mountain area and the northern part of Tokoha drainage basin, which occupies a larger area than understood before.

JAEA Reports

Study of hydraulic behavior for reactor upper plenum in sodium-cooled fast reactor; Verification analysis of water experiment and applicability of vortex prediction method

Fujii, Tadashi; Chikazawa, Yoshitaka; Konomura, Mamoru; Kamide, Hideki; Kimura, Nobuyuki; Nakayama, Okatsu; Ohshima, Hiroyuki; Narita, Hitoshi*; Fujimata, Kazuhiro*; Itooka, Satoshi*

JAEA-Research 2006-017, 113 Pages, 2006/03

JAEA-Research-2006-017.pdf:14.98MB

A conceptual design study of the sodium-cooled fast reactor is in progress in the Feasibility Study on Commercialized Fast Reactor Cycle Systems. Reduced scale water experiments are being performed in order to clarify the flow pattern in the upper plenum of the reactor which has higher velocity condition than the past design. In this report, the hydraulic analyses of the water experiments using the general-purpose thermal hydraulic analysis program were executed; and the applicability to evaluation of flow pattern and vortex cavitations for the designed reactor was examined. (1) Steady-state analyses under the Froude number similar condition were carried out for the 1/10th reduced scale plenum experiments. Analyses results reproduced the characteristic flow patterns in the upper plenum, such as gushed flow from the inside of the upper internal structure to reactor vessel wall and the jet flow from the slit of the upper internal structure. Further, it was confirmed that the calculated flow pattern of a designed reactor system agreed with that of the water experiment qualitatively. Moreover, the influence which setting of numerical solution and boundary condition etc. in analyzing causes to flow pattern in the plenum became clear. (2) The distribution of the vortices under the dipped plate region in the 1/10th plenum model was evaluated using the prediction method of a submerged vortex which is based on the stretching vortex theory. In case of the same velocity condition as the reactor, it identified the two vortices which were sucked into the hot leg piping from the cold leg piping wall as the submerged vortex cavitations. From this analysis result, it confirmed that the submerged vortex cavitations, which may occur in the reactor upper plenum steadily, could be identified using this prediction method.

Journal Articles

Experimental study on flow optimization in upper plenum of reactor vessel for a compact sodium-cooled fast reactor

Kimura, Nobuyuki; Hayashi, Kenji; Kamide, Hideki; Ito, Masami*; Sekine, Tadashi*

Nuclear Technology, 152(2), p.210 - 222, 2006/03

 Times Cited Count:21 Percentile:79.08(Nuclear Science & Technology)

An innovative sodium cooled fast reactor has been investigated on the feasibility study of FBR cycle system in Japan. A compact reactor vessel (R/V) and a column type upper inner structure (UIS) with a radial slit for an arm of a fuel-handling machine (FHM) are adopted. Dipped plates (D/P) are set in the R/V below the free surface to prevent gas entrainment. We performed an 1/10th scaled model water experiment for the upper plenum of the R/V. Gas entrainment was not observed in the experiment under the same velocity condition as the reactor. Three vortex cavitations were observed near the hot leg (H/L) inlet. A vertical rib on the R/V wall was found inlet to restrict the rotating flow near the H/L. The vortex cavitation between the R/V wall and the H/L was suppressed by the rib under the same cavitation factor condition as in the reactor. The cylindrical plug was installed through the hole in the D/P for FHM to reduce the flow toward the free surface. It was effective when the plug was submerged into the middle height in the upper plenum. This combination of two components had a possibility to optimize the flow in the compact R/V.

JAEA Reports

Hydraulic Experiment on Flow Optimization in Compact Reactor Vessel; Effects of double dipped plates and outer shell of UIS

Nakayama, Oukatsu; Kimura, Nobuyuki; Kamide, Hideki; Ito, Masami*; Sekine, Tadashi*

JNC TN9400 2005-032, 103 Pages, 2005/03

JNC-TN9400-2005-032.pdf:33.44MB

On the FBR feasibility study, an innovative sodium cooled fast reactor has been investigated in Japan Nuclear Cycle Development Institute. In order to reduce the construction cost of reactor, the compact reactor vessel is designed. Gas entrainment at the free surface is one of issues to be solved because of high velocity in the upper plenum vessel. We performed an 1/10th scaled model water experiment for the upper plenum of reactor vessel and investigated flow fields in the plenum in order to optimize flow. In the last experiment, we established flow optimization structures for reduction of flow toward to the free surface and restraint on the vortex cavitations near H/L inlet, i.e., plug into the dipped plate hole to install a fuel handling mechanism (FHM) and a flow splitter at vessel wall. In this report, effects of double dipped plates (D/Ps) and outer shell of upper inner structure (UIS) are investigated. In the result, we could confirm that the double D/P structure set below the free surface is effective to reduce flow toward the free surface between reactor vessel wall and guide tube of fuel transfer machine. An FHM plug, which has a step structure at mid height between double D/Ps, showed that it reduced flow velocity through the gap between the plug and the D/P. A perforated outer shell was set around the UIS to reduce vortex strength developed from the cold legs to the hot leg intake and also to restrain the vortex cavitation. It was shown that the onset condition of vortex cavitation at reactor vessel wall was reduced and the cavitation occurred easily. At the cold leg the onset condition of the caviation was not advanced. The flow distribution through the perforated outer shell should be optimized.

JAEA Reports

Hydraulic experiment for compact reactor vessel; Measurement of flow field and flow optimization in upper plenum

Kimura, Nobuyuki; Hayashi, Kenji; Ito, Masami*; Sekine, Tadashi*; Igarashi, Minoru; Sato, Hiroyuki; Kamide, Hideki

JNC TN9400 2003-032, 214 Pages, 2003/03

JNC-TN9400-2003-032.pdf:111.0MB

An innovative sodium cooled fast reactor has been investigated on the FBR feasibility study. The design of the reactor is undergoing in order to reduce the construction cost of the reactor. For example, thermal output is increased against the reactor size and an upper inner structure (UIS) has a slit for the arm of the fuel-handling machine to simplify the fuel exchanging system. The dipped plates (D/P) are set below the free surface to prevent gas entrainment at free surface. We performed an 1/10th scaled model water experiment for the upper plenum of reactor vessel and investigated flow fields in the plenum in order to optimize flow. In the upper plenum, all of main components were set up as well as the reactor design. In addition, the D/P has a hole in front of the slit of the UIS to insert the fuel handling machine(FHM). As the experimental parameters, the core outlet velocity was varied from the condition of the Froude number similarity to the same value as the real reactor. The local velocity was measured by the particle image velocimetry and the ultrasound Doppler velocimetry. In the experimental results, gas entrainment at the free surface was not observed in the range from the Froude number similarity condition to the same velocity condition as the real reactor. However, the free surface was bulged on a large scale in front of the UIS slit. At the neighborhood of the H/L intake, three vortex cavitations were observed. The vortex cavitations were broken out under the same cavitation coefficient condition based on the H/L velocity as that in the real reactor. A vertical rib was set on the reactor vessel wall near the H/L inlet to restrict the rotating flow at the neighborhood of the H/L. As the result, the vortex cavitation at the region between the reactor vessel wall and the H/L was supressed under the same cavitation factor condition as the real reactor. A vertical cylinder, named FHM plug, was installed to close the hole in the D/P fbr FHM.

Journal Articles

Experimental Study on Flow Optimization in Upper Plenum of Reactor Vessel for a Compact Sodium Cooled Fast Reactor

Kimura, Nobuyuki; Hayashi, Kenji; Igarashi, Minoru; Kamide, Hideki; Ito, Masami*; Sekine, Tadashi*

Proceedings of 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), CD-RO, K0102 Pages, 2003/00

An innovative sodium cooled fast reactor has been investigated on the feasibility study of FBR cycle system in JNC. A compact reactor vessel (R/V) and a column type upper inner structure (UIS) with a radial slit for an arm of a fuel-handling machine (FHM) are adopted. Dipped plates (D/P) are set in the R/V below the free surface to prevent gas entrainment at free surface. We performed an 1/10th scaled model water experiment for the upper plenum of the R/V. Gas entrainment at the free surface was not observed in the experiment under the same velocity condition as the designed reactor. However, the free surface rose in front of the UIS slit due to upward flow through the gap between the D/P and the R/V wall. The upward flow will cause free surface vortex and also the gas entrainment. Three vortex cavitations were observed near the hot leg (H/L) inlet. The vortex cavitations were broken out under the same cavitation factor condition as the reactor. A vertical rib was set on the R/V wall

JAEA Reports

Development of quick-response area-averaged void fraction meter; Application to BWR condition

Iguchi, Tadashi; Watanabe, Hironori; Kimura, Mamoru*; Anoda, Yoshinari

JAERI-Research 2001-032, 111 Pages, 2001/05

JAERI-Research-2001-032.pdf:4.14MB

no abstracts in English

30 (Records 1-20 displayed on this page)