Experimental studies in a single-phase parallel channel natural circulation system: preliminary results

Author:

Bodkha K.1,Pilkhwal D. S.1,Jana S. S.1,Vijayan P. K.1

Affiliation:

1. Reactor Engineering Division , Bhabha Atomic Research Centre, Mumbai , India 400085.

Abstract

Abstract Natural circulation systems find extensive applications in industrial engineering systems. One of the applications is in nuclear reactor where the decay heat is removed by natural circulation of the fluid under off-normal conditions. The upcoming reactor designs make use of natural circulation in order to remove the heat from core under normal operating conditions also. These reactors employ multiple vertical fuel channels with provision of on-power refueling/defueling. Natural circulation systems are relatively simple, safe and reliable when compared to forced circulation systems. However, natural circulation systems are prone to encounter flow instabilities which are highly undesirable for various reasons. Presence of parallel channels under natural circulation makes the system more complicated. To examine the behavior of parallel channel system, studies were carried out for single-phase natural circulation flow in a multiple vertical channel system. The objective of the present work is to study the flow behavior of the parallel heated channel system under natural circulation for different operating conditions. Steady state and transient studies have been carried out in a parallel channel natural circulation system with three heated channels. The paper brings out the details of the system considered, different cases analyzed and preliminary results of studies carried out on a single-phase parallel channel system.

Publisher

Walter de Gruyter GmbH

Subject

Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation

Reference8 articles.

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2. The onset of flows and instabilities in a thermosyphon with parallel loops;Nuclear Engineering and Design,1986

3. Natural circulation in parallel vertical channels with different heat inputs;Nuclear Engineering and Design,1987

4. Boiling thermal hydraulic analysis of multichannel low flow;Nuclear Engineering and Design,1979

5. Nuclear systems II,1990

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