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Kodaira, Tsuneo; Sukegawa, T.; Amano, Hidetoshi; Kanaitsuka, Fumio;
JAERI-Conf 99-009, p.20 - 31, 1999/09
no abstracts in English
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PNC TN9410 87-185, 377 Pages, 1997/12
The objective of this study is to be contributed to quantitative estimation of R&Ds and design study for cost reduction of FBR. The assessment models for equipments and components of LWR were prepared to estimate capital costs which based on actual LWR cost data. Subsequently, these models have been applied to FBR. These models were developed at a detailed levels such as the parts of equipments and components of LWR and FBR with regard to the reactor plant equipment, turbine plant and electric plant equipment. The validity of LWR version assumed a scandard PWR plant was confirmed by the comparison with practical LWR cost. In the next step, the validity of FBR version will be confirmed and these assessment methods will be improved.
S.Navarro-Valenti*; S.H.Kim*; V.Georgevich*; R.P.Taleyarkhan*; Fuketa, Toyoshi; Soyama, Kazuhiko; Ishijima, Kiyomi; Kodaira, Tsuneo
NUREG/CP-0142 (Vol. 4), 0, p.2957 - 2976, 1996/00
no abstracts in English
Fuketa, Toyoshi; Ishijima, Kiyomi; ; Soyama, Kazuhiko; Ichikawa, Hiroki; Kodaira, Tsuneo
JAERI-Research 95-077, 28 Pages, 1995/10
JAERI-Research-95-077.pdf:2.49MB
no abstracts in English
Nishiyama, Yutaka; Fukaya, Kiyoshi; Suzuki, Masahide; Kodaira, Tsuneo; Oku, Tatsuo*
Effects of Radiation on Materials; 15th International Symposium (ASTM STP 1125), p.1287 - 1303, 1992/00
no abstracts in English
Suzuki, Masahide; Eto, Motokuni; Fukaya, Kiyoshi; Nishiyama, Yutaka; Kodaira, Tsuneo; Oku, Tatsuo; ; ; ; *; et al.
Journal of Nuclear Materials, 179-181, p.441 - 444, 1991/00
Times Cited Count：29 Percentile：92.44(Materials Science, Multidisciplinary)no abstracts in English
Oku, Tatsuo; Kodaira, Tsuneo; Fukaya, Kiyoshi; Suzuki, Masahide; *; *; *; *
Nucl. Eng. Des., 119, p.177 - 186, 1990/00
Times Cited Count：5 Percentile：52.84(Nuclear Science & Technology)no abstracts in English
*; *; *; *; *; *; Oku, Tatsuo; Kodaira, Tsuneo; Fukaya, Kiyoshi; Nishi, Hiroshi; et al.
JAERI-M 88-172, 20 Pages, 1988/09
no abstracts in English
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Nihon Gakujutsu Shinkokai Tainetsu Kinzoku Zairyo Dai-123 Iinkai Kenkyu Hokoku, 27(1), p.11 - 20, 1986/00
no abstracts in English
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JAERI-M 85-170, 36 Pages, 1985/10
no abstracts in English
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Journal of Nuclear Materials, 132, p.10 - 13, 1985/00
Times Cited Count：1 Percentile：24.17(Materials Science, Multidisciplinary)no abstracts in English
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Nihon Genshiryoku Gakkai-Shi, 27(8), p.722 - 724, 1985/00
Times Cited Count：0 Percentile：0.33(Nuclear Science & Technology)no abstracts in English
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Nucl.Eng.Des., 85, p.1 - 13, 1985/00
Times Cited Count：4 Percentile：54.56(Nuclear Science & Technology)no abstracts in English
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Nuclear Technology, 66, p.619 - 629, 1984/00
Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)no abstracts in English
*; Setoguchi, Keiichi; *; *; *; *; Miyaguchi, Kimihide
PNC TN941 82-270, 109 Pages, 1982/12
Following surveillance tests ought to be performed five times during twenty years operation of Joyo. (1)Surveillance test of reactor vessel (2)Surveillance test of safety vessel (3)Surveillance test of primary main cooling system (4)Surveillanee test of secondary cooling system The first taking-out of surveillance test pieces from the secondary dump tank was carried out from Feb. 22 to Mar. 10, 1982, based on the surveillance test, program of secondary cooling system. We had to perform the work under the conditions such as the sodium filled in the dump tank and to protect the air from coming into the tank. This report describes the details of the working processes.
Furukawa, Kiyoshi; Hirao, Kazunori; Taniyama, Hiroshi; Matsuno, Yoshiaki
PNC TG033 82-01(2), 7 Pages, 1982/02
The sturctural materials of the experimental fast reactor, "JOYO", must maintain sufficient mechanical strength during the entire reactor plant lifetime. In JOYO, the material surveillance for reactor structureal components, safety vessel, primary cooling system piping, secondary cooling system piping and tank have been planned to confirem the design integrity of these structures. The material surveillance speciments have been loaded in the reactor plant and they will be periodically taken out and examined during plant life to monitor any changes in mechanical properites. This report summarizes the material surveillance program of JOYO.
Nakano, Makoto*; Furukawa, Kiyoshi; Ito, Yoshio; Inoue, Tatsuya; Matsuno, Yoshiaki
PNC TG033 82-01(1), 26 Pages, 1982/01
The preliminary design of experimental fast reactor JOYO was started in 1965. After thid design, three steps of conceptual designs are carried out, and main parameters were fixed during these steps. This paper describes the operatin experiences which contain functional test beore criticality, initial criticality and low power testing, power ascension tests to 50 MWt operation, power ascension tests to 75 MWt and 75 MWt operation.
; ; ;
Tetsu To Hagane, 61(8), p.1032 - 1039, 1982/00
no abstracts in English
Yamamoto, Hisashi*; Sekiguchi, Yoshiyuki*; Hirose, Tadashi*; Sanda, Toshio*; Tamura, Seiji*; *; *
PNC TN941 80-179, 402 Pages, 1980/10
On April 24th, 1977, the initial criticality of JOYO was achieved and on July 5th, 1978, the reactor output reached rated power of 50 MW for the first time. The 75MW power ascension test was started in July, 1979, followed by two cycles of rated power operations, and the 100 hour nominal power continuous operation was completed in February, 1980. Through the tests for the core, plant it self, radiation shield and plant monitoring, the results proved satisfactory operation characteristics at 75MW. This report presents the summary of an the results obtained in the Test of MK-I core.
