Most two-phase heat exchangers consist of multiple parallel boiling channels, and studies concerning multi-channel instabilities in boiling systems are of significant interest. The natural circulation boiling water reactor (NCBWR) considered in the present work is a pressure tube type boiling light water cooled and heavy water moderated reactor. The primary heat transport loop, comprising a number of parallel channels, is modeled by RELAP5/MOD3.4. The effects of on-power refueling on the flow rate and stability of the system are investigated. The conditions under which a sustainable flow rate can be maintained during on-power refueling are explored. It is observed that during on-power refueling, a near-stagnation condition or low-velocity reverse flow can occur, the possibility of reverse flow being higher at low pressures and low powers.
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16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4816-7
PROCEEDINGS PAPER
Numerical Investigation of On-Power Refueling in a Natural Circulation Boiling Water Reactor
G. V. Durga Prasad,
G. V. Durga Prasad
Indian Institute of Technology-Guwahati, Guwahati, Assam, India
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Manmohan Pandey,
Manmohan Pandey
Indian Institute of Technology-Guwahati, Guwahati, Assam, India
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S. K. Pradhan,
S. K. Pradhan
Atomic Energy Regulatory Board, Mumbai, Maharashtra, India
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S. K. Gupta
S. K. Gupta
Atomic Energy Regulatory Board, Mumbai, Maharashtra, India
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G. V. Durga Prasad
Indian Institute of Technology-Guwahati, Guwahati, Assam, India
Manmohan Pandey
Indian Institute of Technology-Guwahati, Guwahati, Assam, India
S. K. Pradhan
Atomic Energy Regulatory Board, Mumbai, Maharashtra, India
S. K. Gupta
Atomic Energy Regulatory Board, Mumbai, Maharashtra, India
Paper No:
ICONE16-48396, pp. 389-395; 7 pages
Published Online:
June 24, 2009
Citation
Durga Prasad, GV, Pandey, M, Pradhan, SK, & Gupta, SK. "Numerical Investigation of On-Power Refueling in a Natural Circulation Boiling Water Reactor." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Instrumentation and Controls. Orlando, Florida, USA. May 11–15, 2008. pp. 389-395. ASME. https://doi.org/10.1115/ICONE16-48396
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