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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)
Publication Information
Journal of Energy Engineering / v.12, no.4, 2003 , pp. 281-288 More about this Journal
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.
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