대한기계학회:학술대회논문집 (Proceedings of the KSME Conference)
- 대한기계학회 2001년도 추계학술대회논문집B
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- Pages.3-8
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- 2001
핵연료 집합체에서의 열유동 특성에 관한 연구
A Study on Thermal-hydraulic Characteristics for Nuclear Fuel Rod Bundle
초록
For the successful design of nuclear reactor, it is very important to investigate thermal-hydraulic characteristics of fuel rod bundle. Fluid flow and heat transfer in the non-circular cross-section of nuclear fuel rod bundle are different from those found in common circular tube. And complex three dimensional flow including secondary and vortex flow, is formed around the bundles. The purpose of this research is to examine how geometries and flow conditions affect heat transfer in fuel rod bundle. Design data for nuclear fuel rod bundle and structure are surveyed, and
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