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http://dx.doi.org/10.1016/j.net.2021.11.016

Comparative study of constitutive relations implemented in RELAP5 and TRACE - Part II: Wall boiling heat transfer  

Shin, Sung Gil (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology (KAIST))
Lee, Jeong Ik (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology (KAIST))
Publication Information
Nuclear Engineering and Technology / v.54, no.5, 2022 , pp. 1860-1873 More about this Journal
Abstract
Nuclear thermal-hydraulic system analysis codes have been developed to comprehensively model nuclear reactor systems to evaluate the safety of a nuclear reactor system. For analyzing complex systems with finite computational resources, system codes usually solve simplified fluid equations for coarsely discretized control volumes with one-dimensional assumptions and replace source terms in the governing equations with constitutive relations. Wall boiling heat transfer models are regarded as essential models in nuclear safety evaluation among many constitutive relations. The wall boiling heat transfer models of two widely used nuclear system codes, RELAP5 and TRACE, are analyzed in this study. It is first described how wall heat transfer models are composed in the two codes. By utilizing the same method described in Part 1 paper, heat fluxes from the two codes are compared under the same thermal-hydraulic conditions. The significant factors for the differences are identified as well as at which conditions the non-negligible difference occurs. Steady-state simulations with both codes are also conducted to confirm how the difference in wall heat transfer models impacts the simulation results.
Keywords
Thermal-hydraulic analysis code; Constitutive relation; Closure model; Boiling wall; Heat transfer; RELAP5; TRACE;
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Times Cited By KSCI : 4  (Citation Analysis)
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