<p>Nuclear reactor power for a heat to desalinate the seawater has been deeply considered in Saudi Arabia. For this purpose, the steam temperature shall be required with the relative low temperature around <InlineEquation ID="IEq1"> <InlineMediaObject> <ImageObject Color="BlackWhite" FileRef="13369_2025_9973_Article_IEq1.gif" Format="GIF" Height="14" Rendition="HTML" Resolution="72" Type="Linedraw" Width="46" /> </InlineMediaObject> <EquationSource Format="TEX">\(100\,^{\circ }\hbox {C}\)</EquationSource> <EquationSource Format="MATHML"><math> <mrow> <mn>100</mn> <mmultiscripts> <mspace width="0.166667em" /> <mrow /> <mo>∘</mo> </mmultiscripts> <mtext>C</mtext> </mrow> </math></EquationSource> </InlineEquation>. The 400MWth nuclear heating reactor (NDP-400) dedicated to supplying heat for desalination is developed with cooperation of Saudi Arabia and South Korea. In order to improve the safety and to achieve the economics goal, the advanced features, in-vessel control rod drive mechanism (IV-CRDM), printed circuit heat intermediate exchanger (PCIHX), and canned motor type reactor coolant pump (RCP) are harmonized with the design of SMART, which is an integral-type SMR developed by KAERI. This paper will describe the main design features and safety analysis results for representative accidents for the NDP-400</p>

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Preliminary Design of NDP-400: Economical Heat Generation for Efficient Desalination

  • H. J. Jeong,
  • J. S. Song,
  • G. M. Lee,
  • H. Cho,
  • S. S. Lim,
  • Y. Alessi,
  • M. Albooq,
  • J. J. Choi,
  • Y. H. Jeong,
  • H. Kwon

摘要

Nuclear reactor power for a heat to desalinate the seawater has been deeply considered in Saudi Arabia. For this purpose, the steam temperature shall be required with the relative low temperature around \(100\,^{\circ }\hbox {C}\) 100 C . The 400MWth nuclear heating reactor (NDP-400) dedicated to supplying heat for desalination is developed with cooperation of Saudi Arabia and South Korea. In order to improve the safety and to achieve the economics goal, the advanced features, in-vessel control rod drive mechanism (IV-CRDM), printed circuit heat intermediate exchanger (PCIHX), and canned motor type reactor coolant pump (RCP) are harmonized with the design of SMART, which is an integral-type SMR developed by KAERI. This paper will describe the main design features and safety analysis results for representative accidents for the NDP-400