1-12 Prediction of Unplanned MONJU Shutdown Frequency

-Reactor Trip Frequency Prediction Using Fault Tree Analysis Method -

Fig.1-29 Reactor trip on primary system

Fig.1-29 Reactor trip on primary system

Fault Tree development through clarification of causes of system component failures leading to reactor trip

 

Table1-3 Actual case of mechanical sodium pump failure (19 cases)

Table1-3 Actual case of mechanical sodium pump failure (19 cases)

Fig.1-30 FTA result

Fig.1-30 FTA result

Failures contributing to reactor trip, broken down by component

Fig.1-31 Countermeasures of mechanical sodium pump

Fig.1-31 Countermeasures of mechanical sodium pump

Countermeasures against the pump failures shown in Table1-3: Thermal convection restrainer prevents thermal deformation of the shaft. Argon gas blower prevents sodium oxide accumulation.

Since safe and stable operation is required for nuclear power plants, including the fast breeder prototype reactor "MONJU", it is important to reduce occurrence of unplanned shutdowns of power operation as much as possible.

To improve operational reliability, we have performed fault tree analysis (FTA) to identify the important component failures leading to reactor trip, and to estimate the reactor trip frequency.

The fast breeder reactor component reliability database "CORDS" and Japanese LWR component failure database were used in the FTA of "MONJU". As the result of FTA, the reactor trip frequency was estimated as 1.2/reactor year, and the primary and secondary main circulation pumps were identified as the important components.

The failure cases of sodium circulation pumps recorded in "CORDS" database were refereed to in designing countermeasures in similar mechanical sodium pumps of "MONJU". Therefore high operational reliability has been kept and the actual reactor trip frequency is expected to be smaller than the FTA prediction.

Through this study,

(1) The components crucial to "MONJU" operational reliability have been identified.

(2) Frequency of unplanned reactor shutdown based on the current component failure rate has been estimated to be slightly higher than domestic LWRs, but the actual value is seen to be significantly smaller, due to the countermeasures against pump failures.

(3) If there are modifications to "MONJU" new prediction of unplanned reactor shutdown frequency has been enabled, through appropriate amendment of the fault tree.

Reference
Sotsu, M. et al., Unplanned Shutdown Frequency Prediction of FBR MONJU using Fault Tree Analysis Method, Proceedings of 13th International Conference on Nuclear Engineering (ICONE 13), 2005.

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