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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：52 Percentile：71.76(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.
Sugawara, Satoru; ;
Proceedings of 1st Korea-Japan Symposium on Nuclear Thermal Hydrqulics and Safety (NTHAS 98), p.335 - 341, 1998/00
None
; ; ; ; Kobayashi, Tetsuro*; ; Sugawara, Satoru; Matsumoto, Mitsuo
Donen Giho, (94), p.36 - 52, 1995/06
None
plug region of higher-pressure turbine outlet piping for ATR FUGEN; Sugawara, Satoru
PNC TN9410 93-031, 53 Pages, 1993/01
A small steam leakage was discovered at a plug region of the higher-pressure turbine outlet piping of the FUGEN reactor on october 18, 1992. It was concluded that the cause of the leakage is due to the erosion process by wetted steam flows from the higher-pressure turbine outlet piping. In this study, multi-dimensional hydraulic characteristics at the plug region have been investigated using a multi-purpose thermohydraulics analysis code AQUA. From the analysis, the following results have been obtained: (1)Decreasing of maximum velocity components in the plug was 84 % in the case that a mean steam velocity in the higher-pressure turbine outlet piping decreases to 31.3 m/s (75.8 %) from 41.3 m/s. (2)Maximum velocity components in an improved plug was reduced to 0.44 % compared with the original plug condition. It was concluded that the improved plug can be prevent effectively the growth of the erosion process.
; ; Yamaguchi, Akira; ; ; Sugawara, Satoru
PNC TN9410 92-352, 62 Pages, 1992/11
In-vessel thermohydraulic analysis with multi-dimensional code AQUA was conducted to investigate efficiency of a baffle ring and of a porous-type UIS (upper instrumentation structure) for preventation of gas entrainment to coolant from gas plenum of reactor vessel. Through the analysis using the AQUA code and the discussion based on their results, the following results have been obtained: [Baffle Ring Equipment] (1)In order to reduce maximum surface verocity, the effect with the width 40 cm of the baffle ring equipment better than the width 20 cm. (2)Maximum surface velocity is 
40 cm/s using the baffle ring equipment of width 40 cm. [Porous-type UIS] (1)Effective mass flow ratio of the UIS porous to the UIS skirt is 50 % to decrease maximum surface velocity. (2)Maximum surface velocity is 52 cm/s using the porous-type UIS with the above mass flow distribution. Furthermore analysis with the AQUA code were carried out for the conbined condition of the baffle rings with 40 cm width and the porous-type UIS with the condition of the effective mass flow ratio 50 %. Maximum surface velocity 0.33 m/s closer to the MONJU condition (0.3 m/s) was obtained from the analysis.
Hayafune, Hiroki; ; Sugawara, Satoru
PNC TN9410 92-062, 20 Pages, 1992/05
LOF (Loss of flow) transient tests were carried out simulating a LOPI (Loss of Piping Integrity) event in the prototype LMFBR "MONJU" using the PLANDTL (PLANt Dynamics Test Loop) facility in order to accumulate experimental data on thermo-hydraulics in subassemblies with and without sodium boiling under higher heat flux and LOF conditions. In parallel with the experiments, thermo-hydraulic analysis codes of SSC (Super System Code) and SABENA (Subassembly Boiling Evolution Analysis) have been validated through the analysis of above-mentioned LOPI transient experiments. The LOPI transient in prototype LMFBR "MONJU" was analyzed by using validated SSC and SABENA codes. This leads a eonclusion that the previous analysis in the licensing document is conservative from the view point of core cooling.
Muramatsu, Toshiharu; Murata, Masayuki*; Ieda, Yoshiaki; Yamaguchi, Akira; Nagata, Takashi; Sugawara, Satoru
PNC TN9410 91-318, 48 Pages, 1991/10
In-vessel thermohydraulic analysis with multi-purpose three-dimensional code AQUA as conducted for transient simulating a pump coast down and reactor scram (manual reactor trip event) to confirm efficiency of partially dip plate equipments in a large-scale fast breeder reactor. Throught the analysis using the AQUA code and the discussion based on their results, the following results have been obtained: [Sodium Surface Velocity] Maximum surface velocity is 0.33m/s in the condition of D=0.75m and W=1.905m. The velocity is the same as that or the MONJU reactor. [Thermal Stratification] Maximum axial temperature gradient 445
C/m was calculated. The gradient is nearly equal to the results in the MONJU reactor. [Main Loop Temperature Transient] Maximum temperature transients at the outlet nozzle of reactor vessel was -0.51C/s. [Circumferential Temperature Gradient] Maximum circumferential temperature gradient at the neighborhood of reactor vessel was 67C/m. The gradient is equivalent to five times of that when a partially dip plate is not adopted.
; *; ; Yamaguchi, Akira; ; Sugawara, Satoru
PNC TN9410 91-089, 130 Pages, 1991/03
In-vessel thermohydraulic analysis with multi-dimensional code AQUA was conducted for transient simulating a pump coast down and reactor scram (manual reactor trip event) to confirm efficiency of outer barrel equipments on a large-scale fast breeder reactor. Through the analysis using the AQUA code and the discussion based on their results, the following results have been obtained: [Main Loop Temperature Transient] The transient rate with the outer barrel equipments are approximately equal to the result when an inner barrel was adopted. [Thermal stratification] Axial temperature distributions are approximately equal to the result in the case without an inner barrel. Therefore appearance of an axial temperature distribution can be neglected from a structural design. [Circumferential Temperature Distribution] Maximum temperature gradient 104C/m was confirmed. The value is equivalent to three times of that when an inner barrel was not adopted. Further investigation on a thermal stress at reactor vessel is necessary. [Sodium Surface Velocity] Maximum velocity is the same as that described for the case without an inner barrel. From the above results, it is concluded that the outer barrel considered here is an efficient equipment to relax the main loop temperature transient.
Sugawara, Satoru; Beattie, D. R. H.*
International Journal of Multiphase Flow, 12(4), p.641 - 653, 1986/07
Times Cited Count：22 Percentile：73.06(Mechanics)None
Yonezawa, Minoru; Sugawara, Satoru
no journal, ,
It is necessary to make the most of accumulated nuclear knowledge and information resources for sustainable nuclear research and development (R&D). While importance of Nuclear Knowledge Management (NKM) has been recognized, introduced and applied in nuclear communities, there still remain some issues. The authors extract issues from the standpoint of sharing nuclear knowledge and information resources more efficiently, such as promotion of open access to R&D results, enhancement of International Nuclear Information System (INIS) and transfer of tacit knowledge. Concerning promotion of open access to R&D results, R&D results should be open as much as possible through institutional repository, INIS, etc. Promotion of INIS database and libraries network is required for better nuclear knowledge and information resources sharing. Socialization of tacit knowledge is required and externalization of tacit knowledge to become explicit knowledge is important for transfer of tacit knowledge.
