Improving safety margin of LWRs by rethinking the emergency core cooling system criteria and safety system capacity-Reference-Cited by-同舟云学术

Improving safety margin of LWRs by rethinking the emergency core cooling system criteria and safety system capacity

Published:2016-10 Issue: Volume:307 Page:402-410
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Lee Youho,Kim Bokyung,NO Hee Cheon

Funder

Korea Institute of Energy Technology and Planning

Korea government ministry of Trade, Industry and Energy

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference32 articles.

1. Studies of Metal-Water Reactions at High Temperatures; III. Experimental and Theoretical Studies of the Zirconium-Water Reaction;Baker,1962

2. Report to the American Physical Society by the study group on light-water reactor safety;Bethe;Rev. Mod. Phys.,1975

3. Zirconium Metal-Water Oxidation Kinetics IV. Reaction Rate Studies;Cathcart,1977

4. Fuel behavior under loss-of-coolant accident situations;Chung;Nucl. Eng. Technol.,2005

5. Chung, H.M., Kassner, T.F., 1980. Embrittlement Criteria for Zircaloy Fuel Cladding Applicable to Accident Situations in Light-Water Reactors: Summary Report. Argonne National Laboratory. NUREG/CR-1344. ANL-79-48.

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