Core Catcher is provided as an in-vessel core debris retention device to collect, support, cool and maintain in sub-critical configuration, the generated core debris from fuel melting due to certain postulated Beyond Design Basis Events (BDBE) for Fast Breeder Reactor (FBR). This also acts as a barrier to prevent settling of debris on main vessel and keeps its maximum temperature within acceptable creep range. Heat transfer by natural convection in the core catcher assembly has been assessed numerically and through water experiments using geometrically similar configuration. Resistive heating elements are used in experiment as heat source to simulate debris decay heat on core catcher. Series of experiments were carried out for two configurations referred as geometry A and geometry B. The later configuration showed enhanced natural convective heat transfer from the lower plenum of the vessel. Temperatures were monitored at critical positions and compared with numerical evaluation. Numerically evaluated flow fields and isotherms are compared with experimental data for specific steady state temperatures on heat source plate. Numerical results are found to be in good agreement with that obtained from experiments. The combined efforts of numerical and experimental work conclude core catcher assembly with geometry B to be more suitable.
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14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4246-0
PROCEEDINGS PAPER
Numerical and Experimental Model Studies on Thermal Hydraulic Behavior of FBR Internal Core Catcher Assembly
Sanjay Kumar Das,
Sanjay Kumar Das
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
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Anil Kumar Sharma,
Anil Kumar Sharma
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
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A. Jasmin Sudha,
A. Jasmin Sudha
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
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G. Punitha,
G. Punitha
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
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G. Lydia,
G. Lydia
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
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P. A. Somayajulu,
P. A. Somayajulu
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
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S. S. Murthy,
S. S. Murthy
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
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B. Malarvizhi,
B. Malarvizhi
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
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V. Gopalakrishnan,
V. Gopalakrishnan
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
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J. Harvey,
J. Harvey
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
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N. Kasinathan,
N. Kasinathan
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
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M. Rajan
M. Rajan
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
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Sanjay Kumar Das
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
Anil Kumar Sharma
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
A. Jasmin Sudha
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
G. Punitha
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
G. Lydia
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
P. A. Somayajulu
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
S. S. Murthy
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
B. Malarvizhi
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
V. Gopalakrishnan
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
J. Harvey
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
N. Kasinathan
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
M. Rajan
Indira Gandhi Centre for Atomic Research, Kalpakkam, TN, India
Paper No:
ICONE14-89406, pp. 197-203; 7 pages
Published Online:
September 17, 2008
Citation
Das, SK, Sharma, AK, Jasmin Sudha, A, Punitha, G, Lydia, G, Somayajulu, PA, Murthy, SS, Malarvizhi, B, Gopalakrishnan, V, Harvey, J, Kasinathan, N, & Rajan, M. "Numerical and Experimental Model Studies on Thermal Hydraulic Behavior of FBR Internal Core Catcher Assembly." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum. Miami, Florida, USA. July 17–20, 2006. pp. 197-203. ASME. https://doi.org/10.1115/ICONE14-89406
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