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Heat Transfer Analysis of CANDU 6 Nuclear Reactor using Supercritical Carbon-Dioxide Considering Brayton Cycle
Authors(3) :-Lakshmana Kishore T, Dr. Kiran Chaudhari, Dr. G. Ranga Janardhana
Currently available CANDU 6 nuclear reactor uses heavy water as working fluid and contains two circuits â€“ Primary and Secondary Circuits, one for heat input and the other for the power generation. In order to increase the heat transfer and for better performance, supercritical fluids (SCFâ€™s) are selected as the working fluid. Using supercritical fluids instead of two circuits, one circuit is sufficient for both heat input and power generation. Supercritical carbondioxide is used as the working fluid and Brayton cycle is considered for the design and analysis of the circuit. The pressure drop and the various factors affecting the heat transfer are analysed. Optimization of Pressure is carried out for the circuit. The circuit end states, thermal efficiency and number of pressure tubes are finalized for simple, Regenerative, Regeneration with intercooling and Regeneration split Brayton cycle.
Lakshmana Kishore T, Dr. Kiran Chaudhari, Dr. G. Ranga Janardhana
Nuclear Reactor, Pressure Tube, Supercritical Fluids, Brayton Cycle
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Published in : Volume 4 | Issue 2 | January-February 2018
Date of Publication : 2018-02-28
License: This work is licensed under a Creative Commons Attribution 4.0 International License.
Page(s) : 355-360
Manuscript Number : IJSRST184193
Publisher : Technoscience Academy
PRINT ISSN : 2395-6011
ONLINE ISSN : 2395-602X
Cite This Article :
Lakshmana Kishore T, Dr. Kiran Chaudhari, Dr. G. Ranga Janardhana, "Heat Transfer Analysis of CANDU 6 Nuclear Reactor using Supercritical Carbon-Dioxide Considering Brayton Cycle", International Journal of Scientific Research in Science and Technology(IJSRST), Print ISSN : 2395-6011, Online ISSN : 2395-602X, Volume 4, Issue 2, pp.355-360, January-February-2018.
Journal URL : http://ijsrst.com/IJSRST184193