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Journal Articles

Low-temperature thermochronology of active arc-arc collision zone, South Fossa Magna region, central Japan

Sueoka, Shigeru; Kobayashi, Yumi*; Fukuda, Shoma; Kohn, B. P.*; Yokoyama, Tatsunori; Sano, Naomi*; Hasebe, Noriko*; Tamura, Akihiro*; Morishita, Tomoaki*; Tagami, Takahiro*

Tectonophysics, 828, p.229231_1 - 229231_17, 2022/04

 Times Cited Count:1 Percentile:24.42(Geochemistry & Geophysics)

The South Fossa Magna zone, central Japan, has been an active collision zone between the Honshu Arc and the Izu-Bonin Arc since the middle Miocene and provides an excellent setting for reconstructing the earliest stages of continent formation. Multi-system geo-thermochronometry was applied to different domains of the South Fossa Magna zone, together with some previously published data, to reveal mountain formation processes, i.e., vertical crustal movements. Nine granitic samples yielded zircon U-Pb ages of 10.2-5.8 Ma ($$n$$ = 2), apatite (U-Th)/He (AHe) ages of 42.8-2.6 Ma ($$n$$ = 7), and apatite fission-track (AFT) ages of 44.1-3.0 Ma ($$n$$ = 9). Thermal history inversion modeling based on the AHe and AFT data suggested rapid cooling events confined within the study region at $$sim$$6-2 Ma. The Kanto Mountains may have undergone a domal uplift in association with their collision with the Tanzawa Block at $$sim$$5 Ma. However, this uplift may have slowed down following the migration of the plate boundary and late Pliocene termination of the Tanzawa collision. The Minobu Mountains and possibly adjacent mountains may have been uplifted by the motional change of the Philippine Sea plate at $$sim$$3 Ma. Therefore, the mountain formation in the South Fossa Magna zone was mainly controlled by collisions of the Tanzawa and Izu Blocks and motional change of the Philippine Sea plate. Earlier collisions of the Kushigatayama Block at $$sim$$13 Ma and Misaka Block at $$sim$$10 Ma appeared to have had little effect on mountain formation. Together with a $$sim$$90 deg. clockwise rotation of the Kanto Mountains at 12-6 Ma, these observations suggest that horizontal deformation predominated during the earlier stage of arc-arc collision, and vertical movements due to buoyancy resulting from crustal shortening and thickening developed at a later stage.

JAEA Reports

Annual report on the activities in Safety Administration Department; Report of the fiscal year 2009

Hayashi, Naomi

JAEA-Review 2010-062, 399 Pages, 2011/01

JAEA-Review-2010-062.pdf:18.79MB

The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of the occupational safety and health, the crisis management, the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since April, 2009 until March, 2010.

JAEA Reports

Annual report on the activities in Safety Administration Department; Report of the fiscal year 2008

Hayashi, Naomi

JAEA-Review 2010-002, 269 Pages, 2010/03

JAEA-Review-2010-002.pdf:25.87MB

The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of a safety and health, the crisis management and the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since April, 2008 until March 2009.

JAEA Reports

A Semi annual report on the activities in Safety Administration Department; Report of the second half of 2007

Hayashi, Naomi

JAEA-Review 2009-034, 208 Pages, 2009/11

JAEA-Review-2009-034.pdf:20.59MB

The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of a safety and health, the crisis management and the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since October, 2007 until March, 2008.

JAEA Reports

A Semi annual report on the activities in Safety Administration Department; Report of the first half of 2007

Hayashi, Naomi

JAEA-Review 2008-046, 182 Pages, 2008/10

JAEA-Review-2008-046.pdf:10.21MB

This report is the summary of the activities of Safety Administration Department since April, 2007 until September, 2007.

JAEA Reports

A Semi annual report on the activities in Safety Administration Department; Report of the second half of 2006

Hayashi, Naomi

JAEA-Review 2007-048, 182 Pages, 2008/01

JAEA-Review-2007-048.pdf:6.17MB

The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of a safety and health, the crisis management and the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since October, 2006 until March, 2007.

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.

Journal Articles

The Trend of the MOX fuel use in the world

Hayashi, Naomi

Genshiryoku Nenkan 2007, p.61 - 66, 2006/10

no abstracts in English

JAEA Reports

The report of the fuel fabrication record for Experimental Fast Reactor "JOYO"

Yanagibashi, Katsumi; Hayashi, Naomi

JNC TN8450 2004-009, 6 Pages, 2005/01

JNC-TN8450-2004-009.pdf:0.19MB

Japan Nuclear Cycle Development Institute (the old name; Power Reactor and Nuclear fuel Development Cooperation) has fabricated the MOX fuel assemblies for Experimental Fast Reactor "JOYO" since 1972. This report summarizes the fabrication record.

Journal Articles

EARLY FECAL EXCRETION OF INHALED PLUTONIUM

Kurihara, Osamu; Tasaki, Takashi; Momose, Takumaro; Hayashi, Naomi; Shinohara, Kunihiko

Radiation Protection Dosimetry, 102(2), p.137 - 141, 2002/00

 Times Cited Count:7 Percentile:44.37(Environmental Sciences)

None

JAEA Reports

Study on Evaluation of Internal Exposure Dose

Miyahara, H.*; Narita, N.*; Ikeda, Keiichi*; Kato, Y.*; Fujiki, K.*; Momose, Takumaro; Tasaki, Takashi; Kurihara, Osamu; Hayashi, Naomi

JNC TY8400 2001-002, 81 Pages, 2001/07

JNC-TY8400-2001-002.pdf:2.35MB

no abstracts in English

Journal Articles

Application of the Neutron Dose Equivalent Monitor with TLDs to Calibration of Personal Neutron Dosemeters

Tsujimura, Norio; ; Momose, Takumaro; Hayashi, Naomi

Hoken Butsuri, 36(2), p.137 - 140, 2001/06

None

Journal Articles

None

Tsujimura, Norio; ; Hayashi, Naomi

Saikuru Kiko Giho, (11), p.1 - 5, 2001/06

None

JAEA Reports

Preliminary characterization of the passive neutron dose equivalent monitor with TLDs

Tsujimura, Norio; ; Momose, Takumaro; Hayashi, Naomi

JNC TN8400 2001-004, 13 Pages, 2001/02

JNC-TN8400-2001-004.pdf:1.25MB

The passive neutron dose equivalent monitor with TLDs is composed of a cubic polyethylene moderator and TLDs at the center of moderator. This monitor was originally designed for measurements of neutron doses over long-term period of time around the nuclear facilities. In this study, the energy response of this monitor was calculated by Monte Carlo methods and experimentally obtained under $$^{241}$$Am-Be, $$^{252}$$Cf and moderated $$^{252}$$Cf neutron irradiation. Additionally, the responses of two types of conventional neutron dose equivalent meters (rem counters) were also investigated as comparison. The authors concluded that this passive neutron monitor with TLDs had a good energy response similar to conventional rem counters and could evaluate neutron doses within 10 % of accuracy to the moderated fission spectra.

Journal Articles

None

Tsujimura, Norio; Momose, Takumaro; Hayashi, Naomi

Saikuru Kiko Giho, (7), p.11 - 18, 2000/06

None

Journal Articles

None

Hayashi, Naomi

Hoeikyo Nyusu, (25), p.0 - 0, 2000/00

None

JAEA Reports

None

Oshima, Hirofumi; Hayashi, Naomi; ; Muto, Shigeo; ; ;

JNC TN8420 99-003, 46 Pages, 1998/11

JNC-TN8420-99-003.pdf:8.16MB

None

JAEA Reports

Investigation of operating condition; The report for investigation of bituminization demonstration facility incident(4/7)

; ; Kurosawa, A.; Hayashi, Naomi; Kobayashi, Kentaro; Kitajima, Takafumi; Sato, Yoshihiko

PNC TN8410 98-047, 278 Pages, 1998/02

PNC-TN8410-98-047.pdf:19.5MB

The fire and explosion incident occurred at the Bituminization Demonstration Facility of the Tokai Reprocessing Plant on march 11th, 1997. For investigation of Bituminization Demonstration Facility Incident and prevention relapse, Investigation Group for Bituminization Demonstration Facility incident was set up. It has been investigated the situation at the time of incident was occurred. The result of investigated was presented for Science and Technology Agency. This report is arranged the result of investigated the situation for investigation and prevention relapse.

JAEA Reports

Feasibility study on transmutation of long lived fission products in a fast reactor

Higano, Naomi; Wakabayashi, Toshio

PNC TN9410 96-248, 69 Pages, 1996/11

PNC-TN9410-96-248.pdf:2.32MB

In spent fuel there are many kinds of long-lived fission products. $$^{99}$$Tc and $$^{129}$$I are contained as fission products in HLW: they have comparatively long half lives and their toxicity remains for more than 1000 years, when the efficacy of the engineered barrier is uncertain. Fortunately, these two nuclides have large capture cross-sections in the thermal-resonance neutron energy region, so they have a good potential to be changed to stable nuclides in such a neutron flux. We tried to reduce the amount of these nuclides using a fast reactor. The neutron spectrum of a FR is too hard for effective transmutation of these nuclides, but the flux of a FR is much higher than in other commercial reactors, and the hard spectrum of a FR can be changed locally into a moderated spectrum by the addition of some moderator materials. We tried to make a good neutron flux for transmutation of these long lived fission products and to get high transmutation rates. In this survey, 60 moderated target subassemblies were modeled on the core periphery of a 600MWe fast reactor. Using a continuous energy Monte-Carlo code (MVP), some parametric surveys have been done, examining the effects on transmutation performances of : moderator fraction ; pin and subassembly arrangements ; moderating materials. The code system allowed us to investigate the effects of self-shielding. For $$^{99}$$Tc, the best transmutation rate is about 10%/y in the case of Duplex pin -the FP region is surrounded by moderator material-. With the best arrangement to maximize the amount transmuted, we can transmute 40kg $$^{99}$$Tc in a year. With the present case, the transmutation rate and transmuted amount of $$^{129}$$I are inferior to those of $$^{99}$$Tc. In the most effective case, the $$^{129}$$I transmutation rate is 5.2% and the transmuted amount is 18kg in a year. But the produced amount of $$^{129}$$I from a PWR is small - about 5kg from a 100MWe PWR in a year-, so the transmuted amount of $$^{129}$$I is ...

JAEA Reports

The fundamental data book for the actinide recycle system; Nuclear data

;

PNC TN9450 95-005, 332 Pages, 1995/03

PNC-TN9450-95-005.pdf:22.73MB

Studies on actinide (Pu, Np, Am, Cm) transmutation and on making extra gains from the actinides have been enhanced recently. The fundamental data of these nuclides are very important in the studies. However, they are not sufficient and have larger uncertainty comparing to uranium and major isotopes of Pu, since the actinides were considered to play minor roles in fuel cycle. Both difficulties in handling and higher cost make it troublesome to improve nuclear data of the actinides. To facilitate the related studies on actinides, nuclear data of actinides, which are usable, are described in this report. Data items and nuclides are selected from the view point of thier importance in researching Actinide Recycle System. Thirteen items shown below are selected, (1)Cross Section (2)Uncertainty of Cross Section data (3)Chain (4)Decay Constant (5)Fission Yield (6)Mass Yield (7)Decay Heat (8)Energy Lever Schema of Gamma Ray (9)Specific Activity (10)Toxicity (11)Neutron Yields (12)Calorific Value (13)Group Constant

35 (Records 1-20 displayed on this page)