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JAEA Reports

Probabilistic safety assessment on experimental fast reactor Joyo; Level1 PSA for internal events

Ishikawa, Koki; Takamatsu, Misao; Kawahara, Hirotaka; Mihara, Takatsugu; Kurisaka, Kenichi; Terano, Toshihiro; Murakami, Takanori; Noritsugi, Akihiro; Iseki, Atsushi; Saito, Takakazu; et al.

JAEA-Technology 2009-004, 140 Pages, 2009/05

JAEA-Technology-2009-004.pdf:2.0MB

Probabilistic safety assessment (PSA) has been applied to nuclear plants as a method to achieve effective safety regulation and safety management. In order to establish the PSA standard for fast breeder reactor (FBR), the FBR-PSA for internal events in rated power operation is studied by Japan Atomic Energy Agency (JAEA). The level1 PSA on the experimental fast reactor Joyo was conducted to investigate core damage probability for internal events with taking human factors effect and dependent failures into account. The result of this study shows that the core damage probability of Joyo is 5.0$$times$$10$$^{-6}$$ per reactor year (/ry) and that the core damage probability is smaller than the safety goal for existed plants (10 ry) and future plants (10$$^{-5}$$/ry) in the IAEA INSAG-12 (International Nuclear Safety Advisory Group) basic safety principle.

Journal Articles

Development of operation technology JOYO MK-III function tests and results

Ito, Hideaki; Noritsugi, Hiroaki; Suzuki, Toshiaki; Yamazaki, Manabu; Okawa, Toshikatsu

Saikuru Kiko Giho, (21), p.77 - 97, 2004/00

Focusing on the cover layer materials (as the Radon Barrier Materials), which could have the effect to restrain the radon from scattering into the air and the effect of the radiation shielding, we produced the radon barrier materials with crude bentonite on an experimental basis, using the rotary type comprehensive unit for grinding and mixing, through which we carried out the evaluation of the characteristics thereof.

JAEA Reports

None

; ; ; ; ; ;

PNC TN9410 95-270, 414 Pages, 1995/10

PNC-TN9410-95-270.pdf:9.47MB

None

JAEA Reports

None

; ; ; Yasu, Tetsunori; ; Terano, Toshihiro;

PNC TN9410 95-269, 458 Pages, 1995/10

PNC-TN9410-95-269.pdf:10.14MB

None

JAEA Reports

None

; ; ; ; ; ; Terunuma, Seiichi

PNC TN9410 91-042, 500 Pages, 1991/02

PNC-TN9410-91-042.pdf:11.22MB

None

JAEA Reports

None

; ; Kotaka, Yoshinori; ; ; ;

PNC TN9520 89-024, 208 Pages, 1989/03

PNC-TN9520-89-024.pdf:4.1MB

None

JAEA Reports

Operation experience report of experimental fast reactor JOYO operation experience of electric power supply system

; Kotaka, Yoshinori; ; ; ; ;

PNC TN9410 89-038, 75 Pages, 1989/03

PNC-TN9410-89-038.pdf:2.93MB

JOYO has been operated smoothly since the initial criticality in 1977. This report describes the actual operation experience of JOYO electric power supply system till Dec. 1988. Major results obtained from operation experience are as follows. (1)Accumulated electric power: 371,290,600 kWh (Oct. 1973-Dec. 1988) (2)The average electric power consumption of several reactor conditions. (a)Operation : about 4,460kW (b)Shut Down : about 3,350kW (c)Periodic Inspection : about 3,000kW (3)Number of loss of external electric power : total 10 times in the following items. (a)Operation : 8 times (b)Shut Down and Periodic Inspection : 2 times

JAEA Reports

None

; ; Kawai, Masashi; ; ;

PNC TN9410 88-197, 60 Pages, 1988/02

PNC-TN9410-88-197.pdf:3.52MB

None

JAEA Reports

Operation and maintenance experience report of experimental fast reactor "Joyo"; Operation and maintenance history of nuclear instrumentation system

; ; ; ; ; ;

PNC TN9410 88-023, 41 Pages, 1988/02

PNC-TN9410-88-023.pdf:2.63MB

JOYO has been operated smoothly since the initial criticality in 1977. This report describes the actual operation and maintenance experience of JOYO nuclear instrumentation system till 1986. Major results obtained from operation and maintenance experience are as follows; (1)Maximum neutron fluence of neutron detector. (a)5.30$$times$$10$$^{17}$$ nvt (fission counter) (b)9.30 $$times$$10$$^{16}$$ nvt ($$gamma$$-ray compensated ionization chamber) (2)Imported four fission counters, using one source range monitor (SRM) and three intermediate range monitors (IRM), have been changed for home made ones. They have been kept in good operating conditions. (3)The overlaps in the monitoring ranges between SRM and IRM, IRM and power range monitor (PRM), were confirmed to be more than one decade.

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