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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 ( = 2), apatite (U-Th)/He (AHe) ages of 42.8-2.6 Ma ( = 7), and apatite fission-track (AFT) ages of 44.1-3.0 Ma ( = 9). Thermal history inversion modeling based on the AHe and AFT data suggested rapid cooling events confined within the study region at 6-2 Ma. The Kanto Mountains may have undergone a domal uplift in association with their collision with the Tanzawa Block at 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 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 13 Ma and Misaka Block at 10 Ma appeared to have had little effect on mountain formation. Together with a 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.
Hayashi, Naomi
JAEA-Review 2010-062, 399 Pages, 2011/01
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.
Hayashi, Naomi
JAEA-Review 2010-002, 269 Pages, 2010/03
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.
Hayashi, Naomi
JAEA-Review 2009-034, 208 Pages, 2009/11
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.
Hayashi, Naomi
JAEA-Review 2008-046, 182 Pages, 2008/10
This report is the summary of the activities of Safety Administration Department since April, 2007 until September, 2007.
Hayashi, Naomi
JAEA-Review 2007-048, 182 Pages, 2008/01
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.
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.
Hayashi, Naomi
Genshiryoku Nenkan 2007, p.61 - 66, 2006/10
no abstracts in English
Yanagibashi, Katsumi; Hayashi, Naomi
JNC TN8450 2004-009, 6 Pages, 2005/01
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.
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
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
no abstracts in English
Tsujimura, Norio; ; Momose, Takumaro; Hayashi, Naomi
Hoken Butsuri, 36(2), p.137 - 140, 2001/06
None
Tsujimura, Norio; ; Momose, Takumaro; Hayashi, Naomi
JNC TN8400 2001-004, 13 Pages, 2001/02
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 Am-Be, Cf and moderated 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.
Tsujimura, Norio; Momose, Takumaro; Hayashi, Naomi
Saikuru Kiko Giho, (7), p.11 - 18, 2000/06
None
Oshima, Hirofumi; Hayashi, Naomi; ; Muto, Shigeo; ; ;
JNC TN8420 99-003, 46 Pages, 1998/11
None
; ; Kurosawa, A.; Hayashi, Naomi; Kobayashi, Kentaro; Kitajima, Takafumi; Sato, Yoshihiko
PNC TN8410 98-047, 278 Pages, 1998/02
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.
Higano, Naomi; Wakabayashi, Toshio
PNC TN9410 96-248, 69 Pages, 1996/11
In spent fuel there are many kinds of long-lived fission products. Tc and 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 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 Tc in a year. With the present case, the transmutation rate and transmuted amount of I are inferior to those of Tc. In the most effective case, the I transmutation rate is 5.2% and the transmuted amount is 18kg in a year. But the produced amount of I from a PWR is small - about 5kg from a 100MWe PWR in a year-, so the transmuted amount of I is ...
;
PNC TN9450 95-005, 332 Pages, 1995/03
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