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Journal Articles

A Modelling study on water radiolysis for primary coolant in PWR

Mukai, Satoru*; Umehara, Ryuji*; Hanawa, Satoshi; Kasahara, Shigeki; Nishiyama, Yutaka

Proceedings of 20th International Conference on Water Chemistry of Nuclear Reactor Systems (NPC 2016) (USB Flash Drive), 9 Pages, 2016/10

In Japanese PWR, the concentration of dissolved hydrogen in the primary coolant is controlled in the range from 25 cc/kg-H$$_{2}$$O to 35 cc/kg-H$$_{2}$$O for suppression of water decomposition. However this concentration is desired to reduce for the purpose of radiation source reduction in Japan. So, the concentration due to water radiolysis in primary coolant was evaluated at lower hydrogen concentration by the water radiolysis model in consideration of $$gamma$$ ray, fast neutron and alpha ray due to the reaction $$^{10}$$B(n,$$alpha$$)$$^{7}$$Li. The results of evaluation showed that the water radiolysis was suppressed even if the hydrogen concentration was decreased to 5 cc/kg-H$$_{2}$$O. The effects of the different G-value and the rate constants of major reaction on the concentration of H$$_{2}$$O$$_{2}$$ and O$$_{2}$$ were studied under hydrogen addition. We also focused on the effect of the alpha radiolysis in boron acid water.

JAEA Reports

Study on the evaluation method to determine the radioactivity concentration waste generated from post-irradiation examination facilities

Hoshino, Yuzuru; Sakamoto, Yoshiaki; Muroi, Masayuki*; Mukai, Satoru*

JAEA-Technology 2015-015, 96 Pages, 2015/07

JAEA-Technology-2015-015.pdf:20.34MB

In order to dispose of the radioactive waste which generates from post-irradiation examination (PIE) facilities, the common evaluation method of radioactivity in wastes from PIE should be established by the actual data such as radioactivity values and the theoretical calculation. In this study, the radioactivity concentrations of 17 nuclides (H-3, C-14, Co-60, Ni-63, Sr-90, Tc-99, Cs-137, Eu-154, U-234, U-235, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Am-241, Cm-244) in combustible wastes stored in NUCLEAR DEVELOPMENT CORPORATION were measured from 3 samples and the radioactivity was calculated by ORIGEN-2 based on initial contents and operation record of the spent fuel. From the comparison of the obtained data by the radiological measurement with the calculated values, the subject to be solved for establishment of the radioactivity evaluation method for PIE was extracted.

Journal Articles

Restart of protype FBR "Monju" after long-term shut-down

Nakai, Satoru; Kaneko, Yoshihisa; Mukai, Kazuo

Hozengaku, 9(4), p.44 - 49, 2011/01

The sodium leak accident in a secondary main cooling system of prototype fast breeder reactor Monju on December 8th in 1995, and the Monju has shut down for 14 and half years since that. JAEA improved the safety by investigating the sodium leakage accident, taking countermeasures such as better understanding by the local's, improvement of operation. In the maintenance field, the confirmation of Monju systems and components integrity, systems improvement as sodium leak countermeasures, introduction of the maintenance program to resolve maintenance problems. Monju restarted on May 6th 2010 after the confirmation of restart readiness by safety authorities and the core confirmation test which is first test after restart was continued to July 22nd as planned.

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:50 Percentile:24.62(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

Study on diffusion depth of matrix in granitic rock

Tochigi, Yoshikatsu; Kogawa, Noritaka*; Mukai, Satoru*; Jintoku, Takashi*; Sasamoto, Hiroshi; Shibata, Masahiro; Yui, Mikazu

JAEA-Research 2007-024, 27 Pages, 2007/03

JAEA-Research-2007-024.pdf:1.83MB

In the safety assessment of high-level radioactive waste (HLW) geological disposal, it is important to understand diffusion behavior of radionuclides for evaluation of retardation capacity in the host rock. In this study, non steady state diffusion experiments with non-sorbing ion ware carried out using several granitic rock samples of different length and the matrix diffusion depth was evaluated. As the results of experiment, it is confirmed that the non-sorbing ion can diffuse into the unaltered zone of granitic rock at least about 200 mm in depth and almost same diffusion coefficient is estimated for all rock samples independent of length. Based on these results, it is expected that matrix diffusion of nuclides is acting on a scale of several dozens of centimeters in the granitic rock.

Journal Articles

Outline of fast reactor cycle technology development; Launch of FaCT project

Mukai, Kazuo; Sagayama, Yutaka; Kondo, Satoru; Iwamura, Takamichi; Sugiyama, Toshihide

Genshiryoku eye, 53(3), p.24 - 33, 2007/03

no abstracts in English

JAEA Reports

Study on the nuclide behavior in the engineered barrier for TRU waste (V)

Yanagisawa, Ichiro*; Katsurai, Kiyomichi*; Mukai, Satoru*; *

JNC-TJ8400 2000-028, 224 Pages, 2000/02

JNC-TJ8400-2000-028.pdf:4.06MB

In this study, in-diffusion experiment was conducted under reducing condition to measure apparent diffusion coefficients and distribution coefficients of Uranium and Neptunium for bentonite materials as engineered barrier. The summary of this study is as follows: (1)Apparent diffusion coefficients of U and Np under reducing condition were one or two orders magnitude lower than those of the results obtained in the previous studies. From this result, the valence of U and Np was estimated to be +4 charge during diffusion experiment. (2)Distribution coefficients of U and Np for the system of equilibriated water with bentonite at density of 1.6 g/cm$$^{3}$$ were a little lower than those for the other synthetic groundwater system. (3)Distribution coefficients of Cs and Sr decreased as ion strength of pore water in bentonite increased. Distribution coefficient of Sr increased for alternation of bentonite. (4)Distribution coefficients of Ni, Sn, Zr and Nb were little difference for any type of bentonite or synthetic groundwater. (5)Distribution coefficients or Am for Na-type of bentonite was higher than that of Ca-type of bentonite. But the difference of distribution coefficients for any synthetic groundwater was small. (6)Data base of apparent diffusion coefficients and distribution coefficients was renewed.

JAEA Reports

Study on the nuclide behavior in the engineered barrier for TRU waste(V)

Yanagisawa, Ichiro*; Katsurai, Kiyomichi*; Mukai, Satoru*; *

JNC-TJ8400 2000-027, 28 Pages, 2000/02

JNC-TJ8400-2000-027.pdf:0.76MB

no abstracts in English

JAEA Reports

Study on the nuclide behavior in the engineered barrier for TRU wasete, IV

Yanagisawa, Ichiro*; Naito, Taisei*; Kitao, Hideo*; Mukai, Satoru*; Doi, Hideo*

JNC-TJ8400 99-020, 25 Pages, 1999/02

JNC-TJ8400-99-020.pdf:0.64MB

In this study, apparent diffusion coefficients and distribution coefficient of some nuclides were measured for bentonite materials as engineered barrier. The summary of this study is as follows: (1)Apparent diffusion coefficients of nuclides in compacted bentonite were measured. The data so far were summarized as database of apparent diffusion coefficients and distribution coefficients. (2)In diffusion tests for mixture of Ca-type altered bentonite and analcime, apparent diffusion coefficient of Sr was a little smaller than that for Ca-type altered bentonite. (3)In diffusion tests for Ca-type altered bentonite, apparent diffusion coefficients and distribution coefficients of nuclides showed no significant difference between bentonite-water system and bentonite-cementitious solution systems. (4)In Na-type bentonite-solution with nitrate system, apparent diffusion coefficients of Cs and Sr were smaller than that for other bentonite-solution systems. (5)Apparent diffusion coefficients of tritium showed no significant difference between Ca-type altered bentonite and Na-type bentonite in any solution systems.

JAEA Reports

None

Iriya, Keishiro*; Kubo, Hiroshi*; *; Mukai, Satoru*; Kitao, Hideo*; Ishihara, Yoshinao*; Neyama, Atsushi*

PNC-TJ1449 96-002, 71 Pages, 1996/03

PNC-TJ1449-96-002.pdf:2.13MB

None

JAEA Reports

None

Iriya, Keishiro*; Kubo, Hiroshi*; *; Mukai, Satoru*; Kitao, Hideo*; Ishihara, Yoshinao*; Neyama, Atsushi*

PNC-TJ1449 96-001, 379 Pages, 1996/03

PNC-TJ1449-96-001.pdf:12.36MB

None

JAEA Reports

None

Mukai, Satoru*; Kitao, Hideo*; Tachikawa, Hirokazu*; Fusaeda, Shigeki*; Yanagisawa, Ichiro*; *; *

PNC-TJ1216 96-003, 106 Pages, 1996/03

PNC-TJ1216-96-003.pdf:2.44MB

None

JAEA Reports

None

Mukai, Satoru*; *; *

PNC-TJ1214 95-006, 34 Pages, 1995/03

PNC-TJ1214-95-006.pdf:0.53MB

None

JAEA Reports

None

Mukai, Satoru*; *; *

PNC-TJ1214 94-009, 25 Pages, 1994/03

PNC-TJ1214-94-009.pdf:0.45MB

None

JAEA Reports

None

Mukai, Satoru*; *; *

PNC-TJ1214 94-008, 137 Pages, 1994/03

PNC-TJ1214-94-008.pdf:1.9MB

None

JAEA Reports

None

Mukai, Satoru*; *

PNC-TJ1214 93-005, 64 Pages, 1993/03

PNC-TJ1214-93-005.pdf:0.89MB

None

JAEA Reports

Integration study (IV) for performance assessment system of geological disposal

Yanagisawa, Ichiro*; Ezaki, Masahiro*; Ishihara, Yoshinao*; Fusaeda, Shigeki*; Mukai, Satoru*; Doi, Hideo*; Maeda, Kazuto*; Nakahara, Yutaka*

PNC-TJ1214 93-001, 544 Pages, 1993/03

PNC-TJ1214-93-001.pdf:16.47MB

None

JAEA Reports

None

Ikeda, Yasuhiro*; Ishihara, Yoshinao*; *; *; *; Mukai, Satoru*; *

PNC-TJ1214 92-002, 1340 Pages, 1992/02

PNC-TJ1214-92-002.pdf:31.34MB

None

Journal Articles

None

Mukai, Satoru*; Kataoka, Shinichi*

Proceedings of Migration '97, 28 Pages, 

None

Oral presentation

Study of the radiolysis for ITER cooling water at 14MeV neutron

Sato, Kazuyoshi; Neyatani, Yuzuru; Maruo, Takeshi; Mukai, Satoru*; Uchida, Shoji*; Soman, Yoshindo*

no journal, , 

no abstracts in English

Oral presentation

Confirmation of Monju systems and components integrity and maintenance program toward Monju restart

Nakai, Satoru; Mukai, Kazuo

no journal, , 

no abstracts in English

21 (Records 1-20 displayed on this page)