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Tasaka K, Suzuki M, Anoda Y, Koizumi Y, Yonomoto T, Kumamaru H, Nakamura H, Shiba M. ROSA-III Double-Ended Break Test Series for a Loss-of-Coolant Accident in a Boiling Water Reactor. NUCL TECHNOL 2017. [DOI: 10.13182/nt85-a33569] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- K. Tasaka
- Japan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
| | - M. Suzuki
- Japan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
| | - Y. Anoda
- Japan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
| | - Y. Koizumi
- Japan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
| | - T. Yonomoto
- Japan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
| | - H. Kumamaru
- Japan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
| | - H. Nakamura
- Japan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
| | - M. Shiba
- Japan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan
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NAKAMURA H, KUKITA Y, TASAKA K. BWR Loss-of-Coolant Accident Tests at ROSA-III with High Temperature Emergency Core Coolant Injection. J NUCL SCI TECHNOL 1988. [DOI: 10.1080/18811248.1988.9733573] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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KUMAMARU H, KOIZUMI Y, KUKITA Y, TASAKA K. Investigation of Effect of Pressure Control System on BWR LOCA Phenomena Using ROSA-III Test Facility. J NUCL SCI TECHNOL 1987. [DOI: 10.1080/18811248.1987.9735888] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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BWR small break LOCA counterpart tests at ROSA-III and FIST test facilities. NUCLEAR ENGINEERING AND DESIGN 1987. [DOI: 10.1016/0029-5493(87)90247-0] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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KOIZUMI Y, YONOMOTO T, TASAKA K. Effect of Heat Generation Difference among Fuel Bundles on Core Thermal-Hydraulics during 200% and 5% Loss-of-Coolant Accident Experiments at ROSA-III. J NUCL SCI TECHNOL 1987. [DOI: 10.1080/18811248.1987.9735775] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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KOIZUMI Y, TASAKA K. Investigation of Break Location Effects on Thermal-Hydraulics during Intermediate Break Loss-of-Coolant Accident Experiments at ROSA-III. J NUCL SCI TECHNOL 1986. [DOI: 10.1080/18811248.1986.9735089] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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Investigation of BWR LOCA at ROSA-III — Effect of break configuration on system transients. NUCLEAR ENGINEERING AND DESIGN 1986. [DOI: 10.1016/0029-5493(86)90246-3] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Analysis of large break LOCA experiment at ROSA-III. NUCLEAR ENGINEERING AND DESIGN 1985. [DOI: 10.1016/0029-5493(85)90301-2] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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Five percent break BWR LOCA/ECC test at ROSA-III without HPCS actuation - two-dimensional core thermal-hydraulic phenomena. NUCLEAR ENGINEERING AND DESIGN 1985. [DOI: 10.1016/0029-5493(85)90224-9] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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Koizumi Y, Iriko M, Yonomoto T, Tasaka K. Experimental analysis of the power curve sensitivity test series at ROSA-III. NUCLEAR ENGINEERING AND DESIGN 1985. [DOI: 10.1016/0029-5493(85)90227-4] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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IKEDA T, YAMANOUCHI A, SUMIDA I. Numerical Study of Depressurization Rate during Blowdown Based on Lumped Model Analysis. J NUCL SCI TECHNOL 1984. [DOI: 10.1080/18811248.1984.9731135] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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TASAKA K, KOIZUMI Y, ANODA Y, KUMAMARU H, SHIBA M. Simulation Experiment of Five Percent Small Break Loss-of-Coolant Accident of Boiling Water Reactor. J NUCL SCI TECHNOL 1983. [DOI: 10.1080/18811248.1983.9733367] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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