Simulation Experiment of Five Percent Small Break Loss-of-Coolant Accident of Boiling Water Reactor
Author:
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://www.tandfonline.com/doi/pdf/10.1080/18811248.1983.9733367
Reference20 articles.
1. Soda, K., Tasaka, K. and Shiba, M. 1980.Boiling water reactor LOCA/ECCS integral tests at ROSA-III facility of JAERI1–5. Yugoslavia: Dubrovnik. Paper presented at International Seminar on Nuclear Reactor Safety Heat Transfer, Sep
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1. BWR Loss-of-Coolant Accident Tests at ROSA-III with High Temperature Emergency Core Coolant Injection;Journal of Nuclear Science and Technology;1988-02
2. Investigation of Effect of Pressure Control System on BWR LOCA Phenomena Using ROSA-III Test Facility;Journal of Nuclear Science and Technology;1987-10
3. Effect of Heat Generation Difference among Fuel Bundles on Core Thermal-Hydraulics during 200% and 5% Loss-of-Coolant Accident Experiments at ROSA-III;Journal of Nuclear Science and Technology;1987-01
4. Investigation of Break Location Effects on Thermal-Hydraulics during Intermediate Break Loss-of-Coolant Accident Experiments at ROSA-III;Journal of Nuclear Science and Technology;1986-11
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