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KMID : 0371819960280060542
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Nuclear Engineering and Technology
1996 Volume.28 No. 6 p.542 ~ p.550
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Development of RETRAN-03/MOV Code for Thermal-Hydraulic Analysis of Nuclear Reactor under Moving Conditions
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Jae Hak Kim and Goon Cherl Park
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Abstract
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Nuclear ship reactors have several features different from land-based PWR's. Especially, effects of ship motions on reactor thermal-hydraulics and good load following capability for abrupt load changes are essential characteristics of nuclear ship reactors. This study modified the RETRAN-03 to analyze the thermal-hydraulic transients under three-dimensional ship motions, named RETRAN-03/MOV in order to apply to future marine reactors. First Japanese nuclear ship MUTSU reactor have been analyzed under various ship motions to verify this code. Calculations have been peformed under rolling, heaving and stationary inclination conditions during normal operation. Also, the natural circulation has been analyzed, which can provide the decay heat removal to ensure the passive safety of marine reactors. As results, typical thermal-hydraulic characteristics of marine reactors such as flow rate oscillations and S/G water level oscillations have been successfully simulated at various conditions.
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