CUPID 코드를 이용한 연구로 사이펀 차단 현상 해석

다국어 초록 (Multilingual Abstract)

A pipe rupture of a primary cooling system in a open-pool type research reactor could lead to drainage of the coolant in a reactor pool though this pipe by siphon effect. As a consequence, the core could be exposed to the air. Therefore, this type of research reactor is equipped with a siphon breaking system to maintain reactor pool water level above the required height during a loss of coolant accident. In this study, numerical simulations are performed to assess the effect of interfacial drag on siphon break phenomena using CUPID code. The CUPID results indicate that siphonage break flow rate and initiation of siphon break are significantly affected by the interfacial drag. The calculated break flow rate and final water level in the pool using CUPID code with relevant interfacial drag are a good agreement with experimental data.

참고문헌 (Reference)

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