Steam Drum Level Dynamics in a Multiple Loop Natural Circulation System of a Pressure-Tube Type Boiling Water Reactor
NURETH-14 - 2011 September 25-30

Presented at:
2011 September 25-30
Toronto, Canada
Session Title:
G3-1 Advanced PWRs, Advanced BWRs, Advanced CANDU Reactors

Vikas Jain (Bhabha Atomic Research Centre)
Parimal Kulkarni (Bhabha Atomic Research Centre)
Arun Kumar Nayak (Bhabha Atomic Research Centre)
Pallipattu Krishnan Vijayan (Bhabha Atomic Research Centre)
Dilip Saha (Bhabha Atomic Research Centre)
R. K. Sinha (Bhabha Atomic Research Centre)


Advanced Heavy Water Reactor (AHWR) is a pressure tube type boiling water reactor employing natural circulation as the mode of heat removal under all the operating conditions. Main Heat Transport System (MHTS) of AHWR is essentially a multi-loop natural circulation system with all the loops connected to each other. Each loop of MHTS has a steam drum that provides for gravity based steam-water separation. Steam drum level is a very critical parameter especially in multi-loop natural circulation systems as large departures from the set point may lead to ineffective separation of steam-water or may affect the driving head. However, such a system is susceptible to steam drum level anomalies under postulated asymmetrical operating conditions among the different quadrants of the core like feedwater flow distribution anomaly among the steam drums or power anomaly among the core quadrants. Analyses were carried out to probe such scenarios and unravel the underlying dynamics of steam drum level using system code RELAP5/Mod3.2. In addition, a scheme to obviate such problem in a passive manner without dependence on level controller was examined. It was concluded that steam drums need to be connected in the liquid as well as steam space to make the system tolerant to asymmetrical operating conditions.

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