Journal of computational fluids engineering (한국전산유체공학회지)

Korean Society of Computational Fluids Engineering (한국전산유체공학회)
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VALIDATION OF A DESIGN CODE FOR SODIUM-TO-SODIUM HEAT EXCHANGERS BY UTILIZING COMPUTATIONAL FLUID DYNAMICS

전산유체역학을 이용한 소듐-소듐 열교환기 설계코드의 검증

  • Kim, D. (Div. of SFR NSSS Design, Korea Atomic Energy Research Institute) ;
  • Eoh, J.H. (Div. of SFR NSSS Design, Korea Atomic Energy Research Institute) ;
  • Lee, T.H. (Div. of SFR NSSS Design, Korea Atomic Energy Research Institute)
  • 김대희 (한국원자력연구원 SFR계통설계부) ;
  • 어재혁 (한국원자력연구원 SFR계통설계부) ;
  • 이태호 (한국원자력연구원 SFR계통설계부)
  • Received : 2016.02.01
  • Accepted : 2016.03.15
  • Published : 2016.03.31
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Abstract

A Prototype Gen-IV Sodium-cooled Fast Reactor which is one of the $4^{th}$ generation nuclear reactors is in development by Korea Atomic Energy Research Institute. The reactor is composed of four main fluid systems which are categorized by its functions, i.e., Primary Heat Transport System, Intermediate Heat Transport System, Decay Heat Removal System and Sodium-Water Reaction Pressure Relief System. The coolant of the reactor is liquid sodium and sodium-to-sodium heat exchangers are installed at the interfaces between two fluid systems, Intermediate Heat Exchangers between the Primary Heat Transport System and the Intermediate Heat Transport System and Decay Heat Exchangers between the Primary Heat Transport System and the Decay Heat Removal System. For the design and performance analysis of the Intermediate Heat Exchanger and the Decay Heat Exchanger, a computer code was written during previous step of research. In this work, the computer code named "SHXSA" has been validated preliminarily by computational fluid dynamics simulations.

Keywords

Acknowledgement

Supported by : National Research Foundation of Korea(NRF)

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