MONJU is a sodium-cooled, loop-type prototype fast breeder reactor with three primary cooling loops which can supply 280 MW of electricity. Limiting conditions of operation (LCO) defined in the safety regulations in MONJU given the allowed outage time (AOT) are evaluated using a PSA technique. The result indicates the possibility of limit extension and some prospects that we should examine.
- Nuclear Engineering Division
Evaluation of Monju Core Damage Risk With Change of AOT Using Probabilistic Method
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Sotsu, M, & Kurisaka, K. "Evaluation of Monju Core Damage Risk With Change of AOT Using Probabilistic Method." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications. Brussels, Belgium. July 12–16, 2009. pp. 445-453. ASME. https://doi.org/10.1115/ICONE17-75263
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