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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.

JAEA Reports

JOYO MK-III Performance Test; Criticality Test, Excess Reactivity Measurement and Burn-up Coefficient Measurement

Maeda, Shigetaka; Sekine, Takashi; Kitano, Akihiro; Nagasaki, Hideaki*

JNC TN9400 2005-022, 31 Pages, 2005/03

JNC-TN9400-2005-022.pdf:2.41MB

The MK-III performance test began in June 2003 to fully characterize the upgraded core and heat transfer system. This paper describes the results of the approach to criticality, excess reactivity evaluation and burn-up coefficient measurement. In the approach to criticality test, the MK-III core achieved the initial criticality at control rod bank position of 412.8 mm on 14:03 July 2nd, 2003. Because the replacement of the outer two rows of reflector subassemblies with shielding subassemblies reduced source range monitor signals by a factor of 3 at the same reactor power, we measured the change of detector response and decide the count rate to define zero power criticality as 2$$times$$ 10$$^{4}$$ cps. In the excess reactivity evaluation, Based on the measured critical rod bank position and the measured control rod worths, the zero power excess reactivity at 250$$^{circ}$$C was 2.99$$pm$$0.10%$$Delta$$k/kk'. The prediction by JOYO core management code system HESTIA, which is 3.13$$pm$$0.16% $$Delta$$k/kk', agree with the measured value well. On the other hand, the measured excess reactivity was within a safety requirement limit. In the burn-up coefficient measurement, the reactivity change against the reactor burn-up. The measurement method was adopted to measure control rod position at rated power operation. Finally, -2.12$$times$$10$$^{-4}$$ $$Delta$$k/kk'/Mwd was obtained as a measured of burn-up coefficient. The calculated value by HESTIA became -2.12$$times$$10$$^{-4}$$ $$Delta$$k/kk'/Mwd and it agree with the measured value well. The measurements are emphasized but comparisons with calculated predictions are included. The design predictions are consistent with the performance test results, and all technical safety specifications are satisfied.

JAEA Reports

Joyo MK-II core characteristics database -Update to JFS-3-J3.2R-

Okawachi, Yasushi; Maeda, Shigetaka; Nagasaki, Hideaki*; Sekine, Takashi

JNC TN9400 2003-029, 96 Pages, 2003/04

JNC-TN9400-2003-029.pdf:5.2MB

The (JOYO) MK-II core characteristics database was compiled and published in 1998. Comments and requests from many users led to the creation of a revised edition in 2001. The revisions include changes to the MAGI calculation code system to use the 70 group JFS-3-J3.2 constant set processed from the JENDL-3.2 library. However, after the database was published, it was recently found that there were errors in the process of making the group constant set JFS-3-J3.2, and lt was revised at JFS-3-J3.2R. Then, the group constant set was updated at JFS-3-J3.2R in this database. The MK-II core management data and core characteristics data were recorded on CD-ROM for user convenience. The structure of the database is the same as in the first edition. The (configuration Data) include the core arrangement and refueling record for each operational cycle. The (Subassembly Library Data) include the atomic number density, neutron fluence, burn-up, integral power of 362 driver fuel subassemblies and 69 irradiation test subassemblies. The (Output Data) contain the calculated neutron flux, gamma flux, power density, linear heat rate, coolant and fuel temperature distribution of all the fuel subassemblies at the beginning and end of each operational cycle. The (Core Characteristics Data) include the measured excess reactivity, control rod worth calibration curve, and reactivity coefficients of temperature, power and burn-up. The effect of updating the group constant set, the calculation results excess reactivity decreased by about 0.15 delta-k/kk' , and the effects to other core characteristics were negligible.

JAEA Reports

Development of JOYO MK-III core management code system "HESTIA"

Okawachi, Yasushi; Maeda, Shigetaka; Sekine, Takashi; Nagasaki, Hideaki*

JNC TN9400 2002-070, 49 Pages, 2003/01

JNC-TN9400-2002-070.pdf:1.78MB

As part of the JOYO upgrading program (MK-III program), the JOYO MK-III core management code system "HESTIA" was developed in order to improve the calculation accuracy concerning the core and fuel management and irradiation condition evaluation in the MK-III core. The neutronic calculation of HESTIA was modified to improve the power and neutron flux distribution. The calculation geometry was changed to Tri-Z geometry from Hex-Z geometry which was used in the MK-II core management code system "MAGI". The number of calculation mesh per subassembly was increased to 24 meshes in the radial direction, and the fuel region was divided into 20 meshes in the axial direction. The number of neutron energy group was increased from 7 to 18, and that of gamma energy group was increased from 3 to 7 groups respectively. As a result, HESTIA can accurately calculate the local neutron flux distribution and spectrum change within the fuel subassembly at the boundary between the fuel and reflector regions, which can not be fully simulated by MAGI. It was also confirmed that HESTIA can improve the power distribution in the driver fuel subassembly adjacent to radial reflector. As to thermo-hydraulic calculation, the porous body model was adopted to improve the calculation accuracy of coolant temperature. This model can take into account the detailed power distribution and the turbulent heat transfer in a fuel subassembly. It was found that the calculated value by HESTIA agreed well with that of the subchannel model. In order to verify the calculation accuracy of HESTIA, JOYO MK-II core characteristics calculation was conducted using HESTIA, and calculation results were compared with those of MAGI. The MAGI calculation results were already confirmed by the core performance test and post irradiation examination data. The comparison of both calculation code systems showed that the excess reactivity agreed within 0.01 % $$Delta$$ k/kk', the maximum neutron flux agreed within 3%, the ...

JAEA Reports

Measurement and evaluation of decay heat on the "JOYO" spent fuel; Decay heat of short term cooled spent fuel

Torimaru, Tadahiko; Yoshida, Akihiro; Nagasaki, Hideaki*; Suzuki, Soju

PNC TN9410 98-034, 31 Pages, 1998/03

PNC-TN9410-98-034.pdf:0.58MB

Decay heat measurement system for the JOYO spent fuels was developed to obtain the decay heat data of the fuel assemblies as a non-destructive examination method. Since then, decay heat of the JOYO Mk-II fuels, which were cooled for more than 70 days, was measured in the spent fuel storage pond. The measurement of the short term cooled spent fuels, which were discharged without cooling in the reactor vessel, was performed in order to obtain the higher decay heat of the spent fuels. The burn-up of the measured fuels was about 60GWd/t, and the shortest cooling time was 24 days. The experimental data were compared with calculated values of ORIGEN2 using new libraries based on latest nuclear data library "JENDL-3.2". The main results are as follows; (1) The measured decay heat at 24 days after the reactor shut down was approximately 1.25$$pm$$0.3 kW. (2) The ratio between calculated and experimental values, C/E, was approximately 0.9 and indicated a cool down time dependence. (3) The heat generated by $$^{238}$$Pu and $$^{241}$$Am, which amount to 1% of initial composition of fresh fuel, reached 7 - 19% of decay heat at 24-160 days after the reactor shut down.

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