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CFD analysis on a three by three nuclear fuel bundle with five spacer grid assemblies
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  • CFD analysis on a three by three nuclear fuel bundle with five spacer grid assemblies
  • CFD analysis on a three by three nuclear fuel bundle with five spacer grid assemblies
저자명
Jin. Hailan,Lee. Youngshin,Park. Namgyu
간행물명
Journal of mechanical science and technology
권/호정보
2012년|26권 12호|pp.3965-3972 (8 pages)
발행정보
대한기계학회
파일정보
정기간행물|ENG|
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이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
서지반출

기타언어초록

This study has been conducted to investigate the flow characteristics for SMART $3{ imes}3$ rod bundle with various turbulence models, namely, ${kappa}-{varepsilon}$ model, ${kappa}-{omega}$ shear stress transport (SST) model and Baseline (BSL) Reynolds stress model. Commercial code CFX 12.0 was used for the simulation, and pressure drop, second flow intensity, flow velocity and temperature fields were predicted. For the development of an adequate computational model to simulate such a complex geometry, a grid sensitivity study was first examined. In addition, a pressure drop test for SMART rod bundle was shortly introduced, which test was done at Korea Atomic Energy Research Institute and compared with simulation results. From the comparison, with the SST model and BSL model similar pressure drop values were obtained. Maximum surface temperatures in the cross-section increase with the increase in the steps of the span (spacer grid assembly) and the temperature immediately decreases just after the mixing vane and then the temperature slowly rises. Compared with experimental results, the SST model had a similar maximum temperature pattern along rod axis. Also, it was interesting to find that the turbulence model did not affect the secondary flow intensity while affecting the flow velocity values. As a result, the most appropriate turbulence model and the grids were able to be determined.