In pool type Fast Breeder Reactors (FBR) a passive Safety Grade Decay Heat Removal (SGDHR) system removes decay heat produced in the core when normal heat removal path through steam water system is not available. This is essential to maintain the core temperatures within limits. A Decay Heat Exchanger (DHX) picks the heat from the pool and transfers the heat to atmosphere through sodium to Air Heat Exchanger (AHX) situated at high elevation. Due to the temperature differences existent in the system density differences are generated causing a buoyant convective heat transfer. The system is completely passive as primary sodium, secondary sodium and air flows under natural convection. DHX is a sodium to sodium counter flow heat exchanger with primary sodium on shell side and secondary sodium on tube side. AHX is a cross flow heat exchanger with sodium on tube side and air flows in cross flow across the finned tubes. Capacity of a single loop of SGDHR is 8MW. Four such loops are available for the decay heat removal. It has been seen that the decay heat removal to a large extent depends on the AHX performance. AHX tested have shown reduced heat removal capacity much as 30 to 40%, essentially due to the bypassing of the finned tubes by the air. It was felt that a geometrically similar AHX be tested in sodium. Towards this a 2MW Sodium to air heat exchanger (AHX) was tested in the Steam Generator Test Facility (SGTF) constructed at Indira Gandhi Center for Atomic Research (IGCAR), Kalpakkam. The casing arrangement of the AHX was designed to minimise bypassing of air.
Skip Nav Destination
14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4243-6
PROCEEDINGS PAPER
Performance Assessment of Sodium to Air Finned Heat Exchanger for FBR
V. Vinod,
V. Vinod
Indira Gandhi Center for Atomic Research, Kalpakkam, India
Search for other works by this author on:
V. A. Suresh Kumar,
V. A. Suresh Kumar
Indira Gandhi Center for Atomic Research, Kalpakkam, India
Search for other works by this author on:
I. B. Noushad,
I. B. Noushad
Indira Gandhi Center for Atomic Research, Kalpakkam, India
Search for other works by this author on:
T. R. Ellappan,
T. R. Ellappan
Indira Gandhi Center for Atomic Research, Kalpakkam, India
Search for other works by this author on:
K. K. Rajan,
K. K. Rajan
Indira Gandhi Center for Atomic Research, Kalpakkam, India
Search for other works by this author on:
M. Rajan,
M. Rajan
Indira Gandhi Center for Atomic Research, Kalpakkam, India
Search for other works by this author on:
G. Vaidyanathan
G. Vaidyanathan
Indira Gandhi Center for Atomic Research, Kalpakkam, India
Search for other works by this author on:
V. Vinod
Indira Gandhi Center for Atomic Research, Kalpakkam, India
V. A. Suresh Kumar
Indira Gandhi Center for Atomic Research, Kalpakkam, India
I. B. Noushad
Indira Gandhi Center for Atomic Research, Kalpakkam, India
T. R. Ellappan
Indira Gandhi Center for Atomic Research, Kalpakkam, India
K. K. Rajan
Indira Gandhi Center for Atomic Research, Kalpakkam, India
M. Rajan
Indira Gandhi Center for Atomic Research, Kalpakkam, India
G. Vaidyanathan
Indira Gandhi Center for Atomic Research, Kalpakkam, India
Paper No:
ICONE14-89118, pp. 115-118; 4 pages
Published Online:
September 17, 2008
Citation
Vinod, V, Suresh Kumar, VA, Noushad, IB, Ellappan, TR, Rajan, KK, Rajan, M, & Vaidyanathan, G. "Performance Assessment of Sodium to Air Finned Heat Exchanger for FBR." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 2: Thermal Hydraulics. Miami, Florida, USA. July 17–20, 2006. pp. 115-118. ASME. https://doi.org/10.1115/ICONE14-89118
Download citation file:
12
Views
Related Proceedings Papers
Related Articles
Thermal-Hydraulic Performance of a 2 MW t Sodium-Heated, Forced Recirculation Steam Generator Model
J. Eng. Power (January,1974)
Dual Receiver Concept for Solar Towers up to 100 MW
J. Sol. Energy Eng (August,2006)
Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor
J. Pressure Vessel Technol (April,2012)
Related Chapters
Studies Performed
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
Scope of Section I, Organization, and Service Limits
Power Boilers: A Guide to the Section I of the ASME Boiler and Pressure Vessel Code, Second Edition
Random Turbulence Excitation in Single-Phase Flow
Flow-Induced Vibration Handbook for Nuclear and Process Equipment