Title: Thermal coupling system analysis of a nuclear desalination plant

Authors: A.K. Adak, V.K. Srivastava, P.K. Tewari

Addresses: Desalination Division, Bhabha Atomic Research Centre, Trombay, Mumbai-400085, India. ' Desalination Division, Bhabha Atomic Research Centre, Trombay, Mumbai-400085, India. ' Desalination Division, Bhabha Atomic Research Centre, Trombay, Mumbai-400085, India

Abstract: When a nuclear reactor is used to supply steam for a desalination plant, the method of coupling has a significant technical and economic impact. The exact method of coupling depends on the type of reactor and the type of desalination plant. As a part of Nuclear Desalination Demonstration Project (NDDP), BARC has successfully commissioned a 4500 m³/day multi-stage flash desalination plant coupled to Madras Atomic Power Station at Kalpakkam. A desalination plant coupled to nuclear reactor of pressurised heavy water reactor type is a good example of dual-purpose nuclear desalination plant. This paper presents the thermal coupling system analysis of this plant along with technical and safety aspects.

Keywords: nuclear desalination; PHWR; pressurised heavy water reactors; nuclear desalination demonstration plant; MSF; multi-stage flash; IHX; isolation heat exchangers; coupling loop; nuclear safety; reactor safety; nuclear energy; nuclear power; dual-purpose plants; thermal coupling.

DOI: 10.1504/IJND.2010.035170

International Journal of Nuclear Desalination, 2010 Vol.4 No.2, pp.123 - 133

Published online: 10 Sep 2010 *

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