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Journal Articles

Stratigraphy and AMS radiocarbon dates of cored sediments (IrBH-2) from the Irosin Caldera, the Philippines

Mirabueno, M. H. T.*; Torii, Masayuki*; Laguerta, E. P.*; Delos Reyes, P. J.*; Fujiki, Toshiyuki*; Bariso, E. B.*; Okuno, Mitsuru*; Nakamura, Toshio*; Danhara, Toru*; Kokubu, Yoko; et al.

Chigaku Zasshi, 123(5), p.751 - 760, 2014/10

Core drilling at site IRBH-2 within Irosin caldera, southern Luzon, reached 50 m. Systematic logging and documentation were done to describe the sediments. AMS $$^{14}$$C dates were obtained for plant fragments from the peaty layers. Lahars and fluvial deposits were the predominant deposits in the core sequence. The upper 12 m was comprised mostly by andesitic fluvial and minor lahars. Eight fallouts were intercalated with reworked sediments from depth interval of 20 to 50 m. The refractive index measurement of analyzed samples indicated that post-caldera eruptions generated andesite, dacite and minor rhyolite. The similarity in petrographic characteristics between the rhyolite fallout and the Irosin ignimbrite indicates that small-scale eruptions involving magma from the caldera event occurred during post-caldera stage.Young radiocarbon dates obtained from the peaty layers shows that volcaniclastic deposits in the upper levels were likely derived from the eruptions of Bulusan volcano.

Journal Articles

ITER magnet systems; From qualification to full scale construction

Nakajima, Hideo; Hemmi, Tsutomu; Iguchi, Masahide; Nabara, Yoshihiro; Matsui, Kunihiro; Chida, Yutaka; Kajitani, Hideki; Takano, Katsutoshi; Isono, Takaaki; Koizumi, Norikiyo; et al.

Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 8 Pages, 2013/03

The ITER organization and 6 Domestic Agencies (DA) have been implementing the construction of ITER superconducting magnet systems. Four DAs have already started full scale construction of Toroidal Field (TF) coil conductors. The qualification of the radial plate manufacture has been completed, and JA and EU are ready for full scale construction. JA has qualified full manufacturing processes of the winding pack with a 1/3 prototype and made 2 full scale mock-ups of the basic segments of TF coil structure to optimize and industrialize the manufacturing process. Preparation and qualification of the full scale construction of the TF coil winding is underway by EU. Procurement of the manufacturing equipment is near completion and qualification of manufacturing processes has already started. The constructions of other components of the ITER magnet systems are also going well towards the main goal of the first plasma in 2020.

Journal Articles

Installation and test programme of the ITER poloidal field conductor insert (PFCI) in the ITER test facility at JAEA Naka

Nunoya, Yoshihiko; Takahashi, Yoshikazu; Hamada, Kazuya; Isono, Takaaki; Matsui, Kunihiro; Oshikiri, Masayuki; Nabara, Yoshihiro; Hemmi, Tsutomu; Nakajima, Hideo; Kawano, Katsumi; et al.

IEEE Transactions on Applied Superconductivity, 19(3), p.1492 - 1495, 2009/06

 Times Cited Count:1 Percentile:12.1(Engineering, Electrical & Electronic)

The ITER Poloidal Field Conductor Insert (PFCI) was constructed to characterize the performance of selected cable-in-conduit NbTi conductors for the ITER Poloidal Field (PF) under relevant operating conditions. The PFCI was installed and tested inside the bore of the ITER CS model coil, which provides the background magnetic field. The PFCI is a single-layer solenoid, wound from about 50 m of a full-size ITER cable-in-conduit conductor. The winding diameter and height are about 1.5 m and 1 m, respectively. The nominal design current of the conductor is 45 kA at 6 T and 5 K. The main items in the PFCI test programme are current sharing temperature (Tcs) measurements, critical current (Ic) measurements and AC loss measurement. The key technology of the installation, the test methods and procedures, and some preliminary results of the testing campaigns are described and discussed in this paper.

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:71.25(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

Evaluation technology for burnup and generated amount of plutonium by measurement of xenon isotopic ratio in dissolver off-gas at reprocessing facility (Joint research)

Okano, Masanori; Kuno, Takehiko; Takahashi, Ichiro*; Shirozu, Hidetomo; Charlton, W. S.*; Wells, C. A.*; Hemberger, P. H.*; Yamada, Keiji; Sakai, Toshio

JAEA-Technology 2006-055, 38 Pages, 2006/12

JAEA-Technology-2006-055.pdf:3.33MB

The amount of Pu in the spent fuel was evaluated from Xe isotopic ratio in off-gas in reprocessing facility, is related to burnup. Six batches of dissolver off-gas at spent fuel dissolution process were sampled from the main stack in Tokai Reprocessing Plant during BWR fuel reprocessing campaign. Xenon isotopic ratio was determined with GC/MS. Burnup and generated amount of Pu were evaluated with Noble Gas Environmental Monitoring Application code (NOVA), developed by Los Alamos National Laboratory. Inferred burnup evaluated by Xe isotopic measurements and NOVA were in good agreement with those of the declared burnup in the range from -3.8% to 7.1%. Also, the inferred amount of Pu in spent fuel was in good agreed with those of the declared amount of Pu calculated by ORIGEN code in the range from -0.9% to 4.7%. The evaluation technique is applicable for both burnup credit to achieve efficient criticality safety control and a new measurement method for safeguards inspection.

Journal Articles

Implications of NbTi short-sample test results and analysis for the ITER Poloidal Field Conductor Insert (PFCI)

Zanino, R.*; Bagnasco, M.*; Baker, W.*; Bellina, F.*; Bruzzone, P.*; della Corte, A.*; Ilyin, Y.*; Martovetsky, N.*; Mitchell, N.*; Muzzi, L.*; et al.

IEEE Transactions on Applied Superconductivity, 16(2), p.886 - 889, 2006/06

 Times Cited Count:7 Percentile:40.69(Engineering, Electrical & Electronic)

As the test of the PFCI is foreseen at JAERI Naka, Japan, it is essential to consider in detail the lessons learned from the short NbTi sample tests, as well as the issues left open after them, in order to develop a suitable test program of the PFCI aimed at bridging the extrapolation gap between measured strand and future PF coil performance. Here we consider in particular the following issues: (1) the actual possibility to quench the PFCI conductor in the TCS tests before quenching the intermediate joint, (2) the question of the so-called sudden or premature quench, based on SULTAN sample results, applying a recently developed multi-solid and multi-channel extension of the Mithrandir code to a short sample analysis; (3) the feasibility of the AC losses calorimetry in the PFCI. These results show that Tcs measurement and the calorimetric measurement of AC losses will be carried out successfully. However, we need further analytic works for the problem of the sudden quench.

Journal Articles

Development of Analysis Method for Plutonium Amount and Burn up by Measurement of Xenon Isotopic Ratio in Dissolver Off-Gas at Reprocessing Facility

Okano, Masanori; Kuno, Takehiko; Charlton, W. S.*; Wells, C. A.*; Hemberger, P. H.*

46th Annual Meeting of the INMM, Final Program, Abstract 352, 0 Pages, 2005/07

According to achieve the International Atomic Energy Agency's safeguards criteria, development of simple and rapid determination method of Pu amount in the spent fuel has been required. It is known that stable xenon isotopes produced with fission reflect spent fuel characteristics (fuel type, burn up, Pu amount). Since dissolver off-gas which is released with dissolution of spent fuel in reprocessing facility, contains most of gaseous fission products, xenon isotopic ratio in dissolver off-gas sampled from the stack would be expected to provide a new measurement method for application to safeguards inspection. We have studied a new technique to evaluate Pu isotopic ratio and its amount in the fuel from Xe isotopic ratio, which is related to burn up. The technique is also applicable for evaluating burn up credit to achieve efficient critical safety control. Six batches of off gas from dissolution process, DOG: Dissolver off gas, were obtained with press pump from the stack in Tokai Reprocessing Plant at BWR fuel (approx. 30GWD/MTU) reprocessing campaign. Xe isotopic ratio was determined with Gas Chromatography- Quadrupole Mass Spectrometer, GC-QMS. Xe concentrations in the DOGs sampled at the stack were 1,000 to 10,000 ppm, which were enough concentrations for determining minor Xe isotopes. We evaluate burn up and Pu amount with NOVA, Noble Gas Environmental Monitoring Application code, developed by Los Alamos National Laboratory. Inferred burn up was realized 94% of confidences level, which is the conventional definition based on the standard deviation of the results. We also calculated Pu amount in the spent fuel by ORIGEN code based on declared burn up. Based on the two different evaluations for Pu amount, we found that there is 7% difference between NOVA and ORIGEN code. It is summarized that there is possibility of developed method being used newly burn up monitoring and safeguards technique.

Journal Articles

Development of Analysis Method for Plutonium amount and Burn up by Measurement of Xenon Isotopic Ratio in Dissolver Off-Gas at Reprocessing Facility

Okano, Masanori; Kuno, Takehiko; Takahashi, Ichiro*; Charlton, W. S.*; Wells, C. A.*; Hemberger, P. H.*

46th Annual Meeting of the INMM, Final Program, Abstract 352, 0 Pages, 2005/07

We have studied a new technique to evaluate Pu amount in the spent fuel from Xe isotopic ratio in off-gas in reprocessing facility, which is related to burn up. The technique is applicable for both burn up credit to achieve efficient criticality safety control and a new measurement method for safeguards inspection. Six batches of dissolver off-gas (DOG) at spent fuel dissolution process were sampled with press pump from the main stack in Tokai Reprocessing Plant (TRP) during BWR fuel (approx. 30GWD/MTU) reprocessing campaign. Xe isotopic ratio was determined with Gas Chromatography-Quadrupole Mass Spectrometer (GC-QMS). Burn up and Pu amount were evaluated with NOVA, Noble Gas Environmental Monitoring Application code, developed by Los Alamos National Laboratory. Agreement between declared burn up and inferred burn up evaluated by Xe isotopic measurements and NOVA was at the 94% confidence level. We found that Pu amount in spent fuel evaluated by developed method agreed with declared value calculated by ORIGEN code in the range of -0.9% to 4.7%.

Journal Articles

First test results for the ITER central solenoid model coil

Kato, Takashi; Tsuji, Hiroshi; Ando, Toshinari; Takahashi, Yoshikazu; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Koizumi, Norikiyo; Kawano, Katsumi; Oshikiri, Masayuki*; et al.

Fusion Engineering and Design, 56-57, p.59 - 70, 2001/10

 Times Cited Count:17 Percentile:74.85(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Control method for the cryogenic distillation column with a feedback stream

Yamanishi, Toshihiko; Enoeda, Mikio; Okuno, Kenji; Sherman, R. H.*

Fusion Technology, 29, p.232 - 243, 1996/03

no abstracts in English

Journal Articles

L X-ray spectra of Fe and Cu by 0.75 MeV/u H, He, Si and Ar ion impacts

Kageyama, H.*; Kawatsura, Kiyoshi*; Takahashi, R.*; Arai, Shigeyoshi*; Kambara, Tadashi*; Oura, Masaki*; Papp, T.*; Kanai, Yasuyuki*; Awaya, Yoko*; Takeshita, Hidefumi; et al.

Nuclear Instruments and Methods in Physics Research B, 107(1-4), p.47 - 50, 1996/00

 Times Cited Count:2 Percentile:31.89(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Beta-decay induced reaction studies of tritium by laser raman spectroscopy; T$$_{2}$$-CO system

Ohira, Shigeru; Nakamura, Hirofumi; Okuno, Kenji; Taylor, D. J.*; Sherman, R. H.*

Fusion Technology, 28(3), p.1239 - 1243, 1995/10

no abstracts in English

Journal Articles

Experimental and analytical study on membrane detritiation process

Hirata, Shingo*; Kakuta, Toshiya*; Ito, H.*; Suzuki, T.*; Hayashi, Takumi; Ishida, Toshikatsu*; Matsuda, Yuji; Okuno, Kenji

Fusion Technology, 28(3), p.1521 - 1526, 1995/10

no abstracts in English

Journal Articles

Operation of a simulated non-steady tokamak fuel loop using the tritium systems test assembly

Konishi, Satoshi; Yamanishi, Toshihiko; Enoeda, Mikio; Hayashi, Takumi; Ohira, Shigeru; Yamada, Masayuki; Suzuki, Takumi; Okuno, Kenji; Sherman, R. H.*; Willms, R. S.*; et al.

Fusion Engineering and Design, 28, p.258 - 264, 1995/00

 Times Cited Count:4 Percentile:43.46(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Separation characteristics of cryogenic distillation column having feedback stream; Separation experiment with H-D system

Yamanishi, Toshihiko; Hayashi, Takumi; Nakamura, Hirofumi; Okuno, Kenji; Sherman, R. H.*; Taylor, D.*; Barnes, J. W.*; Bartlit, J. R.*

JAERI-M 93-188, 31 Pages, 1993/10

JAERI-M-93-188.pdf:0.8MB

no abstracts in English

JAEA Reports

Joint operation of TSTA under the collaboration between JAERI and DOE; TSTA loop run October 1990, from October 1990 tritium run test plan and result, TTA-TP-100-19

Konishi, Satoshi; Ohira, Shigeru; Inoue, Masahiko*; Watanabe, Tetsuo*; Naruse, Yuji; Okuno, Kenji; Barnes, J. W.*; Sherman, R. H.*; Bartlit, J. R.*; Anderson, J. L.*

JAERI-M 93-085, 40 Pages, 1993/03

JAERI-M-93-085.pdf:0.8MB

no abstracts in English

JAEA Reports

Joint operation of the TSTA under the collaboration between JAERI and U.S.-DOE; TSTA extended loop operation with 100 grams of tritium on April-May, 1992

Hayashi, Takumi; Nakamura, Hirofumi; Konishi, Satoshi; Inoue, Masahiko*; Hirata, Kazuhiro*; Okuno, Kenji; Naruse, Yuji; Anderson, J. L.*; Sherman, R. H.*; Willms, R. S.*; et al.

JAERI-M 93-083, 54 Pages, 1993/03

JAERI-M-93-083.pdf:1.64MB

no abstracts in English

JAEA Reports

Joint operation of the TSTA with the J-FCU under the collaboration between JAERI and U.S.-DOE; A First integrated tritium test between J-FCU and ISS on October, 1991

Hayashi, Takumi; Nakamura, Hirofumi; Konishi, Satoshi; Yamanishi, Toshihiko; Inoue, Masahiko*; Hirata, Kazuhiro*; Okuno, Kenji; Naruse, Yuji; Anderson, J. L.*; Barnes, J. W.*; et al.

JAERI-M 93-081, 35 Pages, 1993/03

JAERI-M-93-081.pdf:1.19MB

no abstracts in English

Journal Articles

Extended operation of reactor-scale fusion fuel loop under US-Japan collaboration

Konishi, Satoshi; Hayashi, Takumi; Yamanishi, Toshihiko; Nakamura, Hirofumi; Naruse, Yuji; Okuno, Kenji; Sherman, R. H.*; Willms, R. S.*; Barnes, J. W.*; Bartlit, J. R.*; et al.

Proceedings of 15th IEEE/NPSS Symposium on Fusion Engineering, p.204 - 207, 1993/00

no abstracts in English

Journal Articles

Application of sidestream recycle to the separation of hydrogen isotopes by cryogenic distillation

Sherman, R. H.*; Taylor, D. J.*; Barnes, J. W.*; Yamanishi, Toshihiko; Enoeda, Mikio; Konishi, Satoshi; Okuno, Kenji

Proceedings of 15th IEEE/NPSS Symposium on Fusion Engineering, p.77 - 79, 1993/00

no abstracts in English

26 (Records 1-20 displayed on this page)