Boiling Water Reactor Loss of Coolant Tests Single Failure Tests with ROSA-III
Author:
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://www.tandfonline.com/doi/pdf/10.1080/18811248.1983.9733432
Reference12 articles.
1. Nuclear Safety Commission. 1978. Safety evaluation criteria for a light water nuclear power plant, (in Japanese
2. Soda, K., Tasaka, K. and Shiba, M. 1980.Boiling water reactor LOCA/ECCS integral tests at ROSA-III facility of JAERI1–5. Yugoslavia: Dubrovnik. Presented at Int. Seminar on Nuclear Reactor Safety Heat Transfer, Sep
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1. Overview of SAFER03 Assessment Studies;Journal of Nuclear Science and Technology;1988-03
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. Analyses of ROSA-III Break Area Spectrum Experiments on a Boiling Water Reactor Loss-of-Coolant Accident;Nuclear Technology;1985-12
4. Recirculation Pump Discharge Line Break Tests at ROSA-III for a Boiling Water Reactor;Nuclear Technology;1985-08
5. BWR Recirculation Line Break Simulation Tests at Two Bundle Loop;Journal of Nuclear Science and Technology;1985-04
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