Assessment of leak-tightness for nuclear reactor containment under overpressure conditions considering aging effects
Author:
Funder
National Natural Science Foundation of China
National Key Research and Development Program of China
Publisher
Elsevier BV
Reference44 articles.
1. Study on failure mechanism of prestressed concrete containments following a loss of coolant accident;Wang;Eng. Struct.,2020
2. Investigation on damage assessment of fiber-reinforced prestressed concrete containment under temperature and subsequent internal pressure;Zheng;Nucl. Eng. Technol.,2023
3. Report on Ageing of Nuclear Power Plant Reinforced Concrete Structures;Naus,1996
4. Nuclear power plant life extension:How aging affects performance of containments & other structures;Dameron;Eng. Sci.,2013
5. Long-term aging of light water reactor concrete containments;Shah;Nucl. Eng. Des.,1998
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