한국전산유체공학회:학술대회논문집
- 한국전산유체공학회 2008년도 춘계학술대회논문집
- /
- Pages.292-295
- /
- 2008
원형관에서 수직상향유동 초임계압 $CO_2$ 의 대류열전달 상관식 개발
Development of a correlation on the convective heat transfer of supercritical pressure $CO_2$ vertically upward flowing in a circular tube
- 발행 : 2008.03.26
초록
In a SCWR (SuperCritical pressure Water cooled Reactor), the coolant temperature initially at below the pseudo-critical temperature at the bottom of a reactor core increases as the coolant flows upward through the sub-channels of the fuel assemblies, and it finally becomes higher than the pseudo-critical temperature when it leaves the reactor core. At certain conditions, heat transfer deterioration occurs near the pseudo-critical temperature and it may cause a drastic rise of the fuel surface temperature resulting a fuel failure. Therefore, an accurate estimation of the heat transfer coefficient is very important for the thermal-hydraulic design of a reactor core. An experiment on heat transfer to the vertically upward flowing