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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：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.
Katsurai, Kiyomichi; Kondo, Yoshikazu; Washiya, Tadahiro; Myochin, Munetaka; Kuroda, Kazuhiko*; Nishikawa, Hideaki*; Takizawa, Takeyuki*; Yamashita, Kazuhiko*
no journal, ,
This report presents a knowledge getting from endurance test of the bearing for rotary dram type continuous dissolver which is under development as one of the Fast Reactor Cycle technology Development Project in JAEA. Non lubricant type bearing is preferable to endure heavy radiation environment but abrasion of the bearing is concerned due to heavy weigh and low swing motion. Small scale of the endurance test of the bearing using 4 types of candidates including all-ceramics and hybrid ceramics roll bearing, carbon slide bearing and air bearing was implemented. This report demonstrates the test results of the screening and a way of the improvement for select one.
Shimada, Takashi*; Kitagaki, Toru; Tasaka, Masayuki*; Washiya, Tadahiro; Tsubota, Shuho*; Kohata, Yukifumi*; Nishikawa, Hideaki*; Kuroda, Kazuhiko*
no journal, ,
no abstracts in English
Kuroda, Kazuhiko*; Kitagaki, Toru; Higuchi, Hidetoshi; Tasaka, Masayuki*; Washiya, Tadahiro; Toya, Yuichi*; Nishikawa, Hideaki*; Karatsu, Fumiaki*
no journal, ,
no abstracts in English
Katsurai, Kiyomichi; Washiya, Tadahiro; Onishi, Hiroyuki*; Kuroda, Kazuhiko*; Nishikawa, Hideaki*; Nakatani, Tatsuya*; Yamashita, Kazuhiko*; Yoshimine, Chihiro*
no journal, ,
This report presents the knowledge acquired by the endurance test of the bearing used for the rotary drum type continuation dissolver under development as part of Fast Breeder Reactor Cycle technology Development Project (FaCT project). The bearing used for a dissolver is used on high radiation environment and the severe conditions of high load low swing motion operation. In order to check the endurance of the bearing in such conditions, the endurance test of the small scale of hybrid roll bearing using the lubricant which imitated carbon slide bearing as a-less lubricous type, and imitated radiation and heat degradation as a lubricous type was carried out, and the applicability to dissolver bearing was evaluated.
Yasumoto, Takashi*; Matsuura, Hideaki*; Shimakawa, Satoshi; Nakao, Yasuyuki*; Kochi, Shohei*; Nakaya, Hiroyuki*; Goto, Minoru; Nakagawa, Shigeaki; Nishikawa, Masabumi*
no journal, ,
no abstracts in English
Matsuura, Hideaki*; Yasumoto, Takashi*; Shimakawa, Satoshi; Kochi, Shohei*; Nakaya, Hiroyuki*; Nakao, Yasuyuki*; Goto, Minoru; Nakagawa, Shigeaki; Nishikawa, Masabumi*
no journal, ,
no abstracts in English
Matsuura, Hideaki*; Kochi, Shohei*; Nakaya, Hiroyuki*; Yasumoto, Takashi*; Nakao, Yasuyuki*; Shimakawa, Satoshi; Goto, Minoru; Nakagawa, Shigeaki; Nishikawa, Masabumi*
no journal, ,
The performance of a high-temperature gas-cooled reactor as a tritium production device for fusion reactors was examined by performing a core burn-up calculation with the continuous-energy Monte Carlo code MVP-BURN. It was shown that the high-temperature gas cooled reactor can contribute to the tritium production for fusion reactors.
Kochi, Shohei*; Matsuura, Hideaki*; Nakaya, Hiroyuki*; Nakao, Yasuyuki*; Shimakawa, Satoshi; Goto, Minoru; Nakagawa, Shigeaki; Nishikawa, Masabumi*
no journal, ,
Changes in a control rod value and a production amount of tritium with burnup were examined with a continuous energy Monte Carlo code MVP-BURN for a high temperature gas cooled reactor in which B
C control rods were replaced with Li control rods. It was shown that the amount of tritium production was increased about 20% from the previous study and the excess reactivity was properly controlled by installing the Li control rods into the outer region of the core.
Goto, Minoru; Nakagawa, Shigeaki; Shimakawa, Satoshi; Matsuura, Hideaki*; Nakao, Yasuyuki*; Nishikawa, Masabumi*; Nakaya, Hiroyuki*
no journal, ,
A High Temperature Gas-cooled Reactor (HTGR) with lithium particle, which can produce a large amount of tritium without the change of the original reactor design, is proposed as a tritium production device for an initial fusion reactor. However, the tritium production using High Temperature Engineering Test Reactor (HTGR) is not carried out so far and the investigation of the problem about its system is not carried out so far, too. Therefore we extracted a problem from an engineering viewpoint and investigated the feasibility. The problems are expected to be solved by using the HTTR technologies, which are manufacturing the coated fuel particle and handling of the fuel, and the system is feasible from an engineering viewpoint.
Nakaya, Hiroyuki*; Matsuura, Hideaki*; Nakao, Yasuyuki*; Nishikawa, Masabumi*; Goto, Minoru; Shimakawa, Satoshi; Nakagawa, Shigeaki
no journal, ,
111The performance of the tritium production by High Temperature Gas-cooled Reactor (HTGR) was evaluated in case of using GTHTR300 as a HTGR. In the evaluation, parametric study was performed for the fuel exchange period and the operation period for one batch. The amount of tritium production was calculated by whole core burnup calculation using the continuous-energy Monte Carlo transport code MVP-BURN. As a result, 23 kg of tritium, which is required for a fusion reactor as fuel, is produced for 1.7 year with the condition in which the fuel exchange period and the operation period are set to 30 days and 240 days, respectively.
