Improvement of MARS-KS sub-channel module using CTF code

Hoang, Nam H.; Kwack, Y.K.; Bae, Sang Hyun; Kim, Y.S.; Sim, Suk Ku

doi:10.1016/j.nucengdes.2019.110431

Cited by 2 publications

(1 citation statement)

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“…The thermal-hydraulic system codes can simulate the systems of nuclear plants and are indispensable for plant safety evaluation, where full-scale experiments cannot be realistically performed. Several countries independently developed their codes, including the reactor excursion and leak analysis program 5 (RELAP5) [2], transient reactor analysis code (TRAC) [3], TRAC/RELAP advanced computational engine (TRACE) [4], code for analysis of thermalhydraulics during an accident of reactor and safety evaluation 3 (CATHARE-3) [5], analysis of thermal-hydraulics of leaks and transients (ATHLET) [6], multidimensional analysis of reactor safety KINS standard (MARS-KS) [7], and advanced multifluid analysis code for generation of thermal-hydraulic information (AMAGI) [8]. Among these codes, RELAP5 and TRACE are widely used for safety analysis and engineering design.…”

Section: Introductionmentioning

confidence: 99%

Opposing Mixed Convection Heat Transfer for Turbulent Single-Phase Flows

Motegi,

Sibamoto,

Hibiki

et al. 2024

International Journal of Energy Research

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Convection, wherein forced and natural convections are prominent, is known as mixed convection. Specifically, when a forced convection flow is downward, this flow is called opposing flow. The objectives of this study are to gain a comprehensive understanding of opposing flow mixed convection heat transfer and to establish the prediction methodology by evaluating existing correlations and models. Several heat transfer correlations have been reported related to single-phase opposing flow; however, these correlations are based on experiments conducted in various channel geometries, working fluids, and thermal flow parameter ranges. Because the definition of nondimensional parameters and their validated range confirmed by experiments differ for each correlation reported in previous studies, establishing a guideline for deciding which correlation should be selected based on its range of applicability and extrapolation performance is important. This study reviewed the existing heat transfer correlations for turbulent opposing flow mixed convection and the single-phase heat transfer correlations implemented in the thermal–hydraulic system codes. Furthermore, the authors evaluated the predictive performance of each correlation by comparing them with the experimental data obtained under various experimental conditions. The Jackson and Fewster, Churchill, and Swanson and Catton correlations can accurately predict all the experimental data. The effect of the difference in the thermal boundary conditions, i.e., uniform heat flux and uniform wall temperature, on the turbulent mixed convection heat transfer coefficient is not substantial. The authors confirmed that heat transfer correlations using the hydraulic-equivalent diameter as a characteristic length can be used for predictions regardless of channel-geometry differences. Furthermore, correlations described based on nondimensional dominant parameters can be used for predictions regardless of the differences in working fluids. The authors investigated the extrapolation performance of the mixed convection heat transfer correlations for a wide range of nondimensional parameters and observed that the Jackson and Fewster, Churchill, and Aicher and Martin correlations exhibit excellent extrapolation performance with respect to natural and forced convection flows, indicating that they can be applied beyond the parameter range validated experimentally.

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Section: Introductionmentioning

confidence: 99%