Journal of Energy Engineering (에너지공학)

The Korean Society for Energy (한국에너지학회)
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A Subchannel Analysis Code for LMR Core Subassembly Thermal Hydraulic Analysis: The MATRA-LMR

  • Lim, Hyun-Jin (Ajou University, Korea Atomic Energy Research Institute) ;
  • Kim, Young-Gyun (Ajou University, Korea Atomic Energy Research Institute) ;
  • Kim, Yeong-Il (Ajou University, Korea Atomic Energy Research Institute) ;
  • Oh, Se-Kee (Ajou University, Korea Atomic Energy Research Institute)
  • Published : 2003.11.01
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Abstract

The MATRA-LMR code has been developed based on a subchannel analysis method for LMR (Liquid Metal Reactor) core subassembly thermal hydraulic design and analysis. The code was improved to allow a seven assembly calculation and can account for inter-assembly heat transfer based on a lumped parameter model. This paper describes the main modifications and improvements of the code and shows reference calculation results which compared single assembly calculation with seven assembly calculation cased for driver and blanket subassemblies of the KALIMER 150 MWe breakeven conceptual design core. KAL- IMER is a pool-type sodium cooled reactor with a thermal output of 392.0 MWth, which have inherently safe, environmentally friendly, proliferation-resistant and economically viable reactor concepts.

Keywords

References

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