ROSA-III Base Test Series for a Large Break Loss-of-Coolant Accident in a Boiling Water Reactor
Author:
Affiliation:
1. Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, 319-11, Japan
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT82-A26280
Cited by 17 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
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;J NUCL SCI TECHNOL;1987
3. Investigation of Effect of Pressure Control System on BWR LOCA Phenomena Using ROSA-III Test Facility;Journal of Nuclear Science and Technology;1987-10
4. BWR small break LOCA counterpart tests at ROSA-III and FIST test facilities;Nuclear Engineering and Design;1987-06
5. EFFECT OF HEAT-GENERATION DIFFERENCE AMONG FUEL BUNDLES ON CORE THERMAL-HYDRAULICS DURING 200-PERCENT AND 5-PERCENT LOSS-OF-COOLANT ACCIDENT EXPERIMENTS AT ROSA-III;J NUCL SCI TECHNOL;1987
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