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Journal Articles

Fundamental welding R&D results for manufacturing vacuum vessel of JT-60SA

Asano, Shiro*; Okuyama, Toshihisa*; Onawa, Toshio*; Yanagi, Yutaka*; Ejiri, Mitsuru*; Kanahara, Toshio*; Ichihashi, Koji*; Kikuchi, Atsushi*; Mizumaki, Shoichi*; Masaki, Kei; et al.

Fusion Engineering and Design, 86(9-11), p.1816 - 1820, 2011/10

 Times Cited Count:10 Percentile:30.97(Nuclear Science & Technology)

The real vacuum vessel (VV) manufacturing of JT-60SA has started since Nov. 2009 at Toshiba. Prior to starting manufacturing, fundamental welding R&Ds had been performed by three stages. In the first stage, primary tests for screening welding method were performed. In the second stage, the trial welding for 1m-long straight and curved double shell samples were conducted. The dependences of welding quality and distortion on the welding conditions, such as arc voltage and current, setting accuracy, welding sequence, the shape of grooves, etc. were measured. In addition, welding condition with low heat input was explored. In the last stage, fabrication sequence was confirmed and established by the trial manufacturing of the 20$$^{circ}$$ upper half mock-up. This poster presents the R&D results obtained in the first and second stages.

Journal Articles

Fuels and materials irradiation test plan at JMTR

Ise, Hideo; Ogiyanagi, Jin; Nakamura, Jinichi; Sasajima, Hideo; Takasa, Akira; Hanawa, Satoshi; Kawaguchi, Yoshihiko; Chimi, Yasuhiro; Nishiyama, Yutaka; Nakamura, Takehiko

FAPIG, (180), p.22 - 25, 2010/02

Refurbishment of Japan Materials Testing Reactor (JMTR) is conducted in Japan Atomic Energy Agency (JAEA) in order to solve irradiation related issues for safe long-term operation of current light water reactors (LWRs) and development of advanced LWRs. JMTR will restart its operation in FY 2011. Manufacturing and installation of the irradiation test facilities on safety research of fuels and materials are also in progress. The outline of the fuels and materials irradiation test plan is described in this report.

Journal Articles

New JMTR irradiation test plan on fuels and materials

Nakamura, Takehiko; Nishiyama, Yutaka; Chimi, Yasuhiro; Sasajima, Hideo; Ogiyanagi, Jin; Nakamura, Jinichi; Suzuki, Masahide; Kawamura, Hiroshi

Proceedings of 16th Pacific Basin Nuclear Conference (PBNC-16) (CD-ROM), 6 Pages, 2008/10

In order to maintain and enhance safety of light water reactors in long-term and up-graded operations, proper understanding of irradiation behavior of fuels and materials is essentially important. Japanese government and the Japan Atomic Energy Agency have decided to refurbish the JMTR and to install new tests rigs, in order to play an active role for solving irradiation related issues on plant aging and high-duty uses of the current LWRs and on development of next-generation reactors. New tests on fuel integrity under simulated abnormal transients and high-duty irradiation conditions are planned in the JMTR. Power ramp tests of new design fuel rods will also be performed in the first stage of the program, which is expected to start in year 2011 after refurbishment of the JMTR. Combination of the JMTR tests with simulated reactivity initiated accident tests in the NSRR and loss of coolant accident tests in hot laboratories would serve as the integrated fuel safety research on the high performance fuels at extended burnups, covering from the normal to the accident conditions, including abnormal transients. For the materials irradiation, fracture toughness of reactor vessel steels and stress corrosion cracking behavior of stainless steels are being studied in addition to basic irradiation behavior of nuclear materials such as hafnium. The irradiation studies would contribute not only to solve the current problems but also to identify possible seeds of troubles and to make proactive responses.

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:50 Percentile:23.82(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.

Journal Articles

Large-scale identification and characterization of alternative splicing variants of human gene transcripts using 56 419 completely sequenced and manually annotated full-length cDNAs

Takeda, Junichi*; Suzuki, Yutaka*; Nakao, Mitsuteru*; Barrero, R. A.*; Koyanagi, Kanako*; Jin, L.*; Motono, Chie*; Hata, Hiroko*; Isogai, Takao*; Nagai, Keiichi*; et al.

Nucleic Acids Research, 34(14), p.3917 - 3928, 2006/00

 Times Cited Count:33 Percentile:42.83(Biochemistry & Molecular Biology)

We report the first genome-wide identification and characterization of alternative splicing in human gene transcripts based on analysis of the full-length cDNAs. Applying both manual and computational analyses for 56 419 completely sequenced and precisely annotated full-length cDNAs selected for the H-Invitational human transcriptome annotation meetings, we identified 6877 alternative splicing genes with 18 297 different alternative splicing variants. A total of 37 670 exons were involved in these alternative splicing events. The encoded protein sequences were affected in 6005 of the 6877 genes. Notably, alternative splicing affected protein motifs in 3015 genes, subcellular localizations in 2982 genes and transmembrane domains in 1348 genes. Genome-wide annotations of alternative splicing, relying on full-length cDNAs, should lay firm groundwork for exploring in detail the diversification of protein function which is mediated by the alternative splicing variants.

Journal Articles

R&D of a MW-class solid-target for spallation neutron source

Kawai, Masayoshi*; Furusaka, Michihiro*; Kikuchi, Kenji; Kurishita, Hiroaki*; Watanabe, Ryuzo*; Li, J.*; Sugimoto, Katsuhisa*; Yamamura, Tsutomu*; Hiraoka, Yutaka*; Abe, Katsunori*; et al.

Journal of Nuclear Materials, 318, p.35 - 55, 2003/05

R&D works for MW class solid target composed of tungsten to produce pulsed intense neutron source has been made in order to construct a future scattering facility. Three methods were investigated to prevent corrosion of tungsten from water; those are hipping, brazing and electric coating in molten salt bath. Hipping condition was optimized to be 1500 degree C in the previous work: here small punch test shows highest load for crack initiation of hipped materials at the boundary of W/Ta. The basic techniques for the other two methods were developed. Erosion test showed that uncovered W is susceptible of flowing water velocity. At high velocity w is easy to be eroded. For solid target design slab type and rod type targets were studied. As long as the optimized neutron performance is concerned, 1MW solid target is better than mercury target.

JAEA Reports

Development of fabrication technology for ITER vacuum vessel

Nakahira, Masataka; Shibanuma, Kiyoshi; Kajiura, Soji*; Shibui, Masanao*; Koizumi, Koichi; Takeda, Nobukazu; Kakudate, Satoshi; Taguchi, Ko*; Oka, Kiyoshi; Obara, Kenjiro; et al.

JAERI-Tech 2002-029, 27 Pages, 2002/03

JAERI-Tech-2002-029.pdf:2.04MB

The ITER vacuum vessel (VV) R&D has progressed with the international collaborative efforts by the Japan, Russia and US Parties during the Engineering Design Activities (EDA). Fabrication and testing of a full-scale VV sector model and a port extension have yielded critical information on the fabrication and assembly technologies of the vacuum vessel, magnitude of welding distortions, dimensional accuracy and achievable tolerances during sector fabrication and field assembly. In particular, the dimensional tolerances of $$pm$$3 mm for VV sector fabrication and $$pm$$10 mm for VV sector field assembly have been achieved and satisfied the requirements of $$pm$$5 mm and $$pm$$20 mm, respectively. Also, the basic feasibility of the remote welding robot has been demonstrated. This report presents detailed fabrication and assembly technologies such as welding technology applicable to the thick wall without large distortion, field joint welding technology between sectors and remote welding technology through the VV R&D project.

Journal Articles

Development of optical devices based on neutron refractive optics

Oku, Takayuki*; *; *; Yamagata, Yutaka*; Omori, Hitoshi*; Adachi, Tomohiro*; Shimizu, Hirohiko*; *; *; Iwasa, Hirokatsu*; et al.

JAERI-Conf 2001-002, p.537 - 541, 2001/03

no abstracts in English

JAEA Reports

2nd power-up test for JRR-2

Kambara, Toyozo; Uno, Hidero; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Takayanagi, Hiroshi; Fujimura, Tsutomu; Morita, Morito; Ichihara, Masahiro; et al.

JAERI 1045, 11 Pages, 1963/03

JAERI-1045.pdf:0.72MB

no abstracts in English

Oral presentation

Fundamental studies on integrity of hafnium as control rods, 1; Microstructure observations and crystal orientation measurement of unirradiated materials

Chimi, Yasuhiro; Ogiyanagi, Jin; Shimada, Sachio*; Nishiyama, Yutaka; Nakamura, Takehiko; Abe, Katsuhiro*

no journal, , 

In order to understand basic irradiation behavior of hafnium (Hf) which is used as the control rod for the Boiling Water Reactor (BWR), we are planning irradiation tests of Hf at Japan Materials Testing Reactor (JMTR). Prior to the irradiation tests, some of the fundamental properties of unirradiated Hf were obtained. In the present report, we discuss the results of optical microscope and SEM observations, and crystal orientation measurement.

Oral presentation

Fundamental studies on integrity of hafnium as control rods, 2; Tensile and micro-Vickers hardness test of unirradiated materials

Shimada, Sachio*; Ogiyanagi, Jin; Chimi, Yasuhiro; Nishiyama, Yutaka; Nakamura, Takehiko; Abe, Katsuhiro*

no journal, , 

no abstracts in English

Oral presentation

Fuels and materials irradiation test plan at JMTR, 1; Outline of the project

Nakamura, Takehiko; Nishiyama, Yutaka; Sasajima, Hideo; Chimi, Yasuhiro; Ogiyanagi, Jin; Nakamura, Jinichi

no journal, , 

In order to contribute to development and safety research on light water reactors, Japan Atomic Energy Agency is planning to re-start the Japan Materials Testing Reactor (JMTR) in 2011, after its refurbishment. Irradiation test facilities of the fuels and materials are being installed in the JMTR, in parallel to the refurbishment. Outlines of the project is presented in a series of three presentations.

Oral presentation

Fundamental studies on integrity of hafnium as control rods, 3; Terminal solid solubility of hydrogen of unirradiated materials

Ogiyanagi, Jin; Chimi, Yasuhiro; Shimada, Sachio*; Nishiyama, Yutaka; Nakamura, Takehiko; Abe, Katsuhiro*

no journal, , 

no abstracts in English

Oral presentation

Safety research program of LWR fuels and materials using the Japan Material Testing Reactor

Hanawa, Satoshi; Ogiyanagi, Jin; Chimi, Yasuhiro; Sasajima, Hideo; Nakamura, Jinichi; Nishiyama, Yutaka; Nakamura, Takehiko

no journal, , 

A continuous endeavor for solving irradiation-related issues on the fuels for high-duty uses and the plant aging are essential to realize the up-graded uses of LWR safely. In order to respond adequately to these demand, Japanese regulator has decided to install new irradiation test facilities in the Japan Material Testing Reactor (JMTR) at the Japan Atomic Energy Agency (JAEA). For the fuels tests, transient tests facility is being constructed for the power transient tests of new design BWR fuels. For the materials tests, the irradiation test loops under well controlled environment simulating BWR water chemistry condition and a large irradiation capsule, which can accommodate 1 inch-thickness compact tension specimens in an inert gas environment, are being prepared for the researches on stress corrosion cracking and irradiation embrittlement, respectively. These fuels and materials irradiation tests will be started in 2011 after refurbishment of JMTR.

Oral presentation

Outlines and status of safety research on fuels and materials using JMTR

Nakamura, Takehiko; Nishiyama, Yutaka; Chimi, Yasuhiro; Hanawa, Satoshi; Ogiyanagi, Jin; Nakamura, Jinichi; Sasajima, Hideo; Suzuki, Masahide

no journal, , 

In parallel to the refurbishment, installation of new tests rigs for fuel and material irradiation research is progressing in the JMTR. The new test program will contribute to solve irradiation related issues on plant aging and high-duty uses of the current LWRs and on development of next-generation reactors. New tests on fuel integrity under simulated abnormal transients and high-duty irradiation conditions are planned in the JMTR. Power ramp tests of new- design fuel rods will also be performed in the first stage of the program, which is expected to start in year 2011 after refurbishment of the JMTR. For the materials irradiation, fracture toughness of reactor vessel steels and IASCC behavior of stainless steels are being studied in addition to basic irradiation behavior of nuclear materials such as hafnium. The irradiation studies would contribute not only to solve the current problems but also to identify possible seeds of troubles and to make proactive responses.

Oral presentation

Trial manufacturing of vacuum vessel for JT-60SA

Asano, Shiro*; Ejiri, Mitsuru*; Yanagi, Yutaka*; Ichihashi, Koji*; Kikuchi, Atsushi*; Mizumaki, Shoichi*; Okuyama, Toshihisa*; Masaki, Kei; Shibama, Yusuke; Katayama, Masahiro*; et al.

no journal, , 

no abstracts in English

Oral presentation

Real product manufacturing of vacuum vessel for JT-60SA

Asano, Shiro*; Ejiri, Mitsuru*; Okuyama, Toshihisa*; Yanagi, Yutaka*; Kikuchi, Atsushi*; Mizumaki, Shoichi*; Shibama, Yusuke; Masaki, Kei; Sakasai, Akira

no journal, , 

Based on the R&Ds including trial manufacturing of 20 deg. upper half mock-up, the real product manufacturing of vacuum vessel for JT-60SA has started since November 2009 at TOSHIBA Keihin Product Operations. The cross section of the VV is D-shaped and made of low cobalt content SUS316L. The height and outer diameter of the torus are 6.6m and 9.95m respectively. The weight is about 150 ton. The present status of the manufacturing is introduced in this poster presentation. 2009 for the inboard (IB) and since August, 2010 for the outboard (OB). Completed IB and OB 20-degree upper or lower segments for VV-D02 and VV-D03 will be connected into full 40-degree IB and OB segments from December, 2010. The welding between 40-degree IB and OB segments of the first 40-degree sector (VV-D02) is to be started at JAEA Naka Fusion Institute in 2011.

Oral presentation

Fatigue behavior on welded joint for JT-60SA vacuum vessel

Yanagi, Yutaka*; Shibui, Masanao*; Kanahara, Toshio*; Mochida, Tsutomu*; Ejiri, Mitsuru*; Asano, Shiro*; Shibama, Yusuke; Masaki, Kei; Sakasai, Akira

no journal, , 

JT-60SA Vacuum Vessel (VV) has D-shaped cross section and double-walled structure. It consists of the inner and outer wall reinforced by poloidal ribs and is made of SUS316L (Co$$<$$0.05wt%). The welding outer wall on rib (so called continuous plug) is performed from the outside of double-wall. Since it is difficult to confirm the penetration bead from the inside of double-wall, an incomplete penetration is assumed to be included in this welded joint. In this study, the fatigue test of continuous plug welded joint with an artificial incomplete penetration was performed to investigate the effect of the incomplete penetration on fatigue behavior and fatigue strength.

Oral presentation

Present status of a new pulsed neutron imaging instrument in J-PARC MLF

Shinohara, Takenao; Kai, Tetsuya; Segawa, Mariko; Oi, Motoki; Oikawa, Kenichi; Harada, Masahide; Nakatani, Takeshi; Sakai, Kenji; Iikura, Hiroshi; Aizawa, Kazuya; et al.

no journal, , 

no abstracts in English

Oral presentation

Present status of a new pulsed neutron imaging instrument at J-PARC

Segawa, Mariko; Shinohara, Takenao; Kai, Tetsuya; Iikura, Hiroshi; Oi, Motoki; Oikawa, Kenichi; Harada, Masahide; Sakai, Kenji; Soyama, Kazuhiko; Aizawa, Kazuya; et al.

no journal, , 

22 (Records 1-20 displayed on this page)