• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.242-242
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.487-494
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• 1997

비등이 발생하는 경사유로에서 이상유동 구조 파악을 위해 국부적 이상유동 변수의 측정이 이루어졌다. 국부 기포율, 국부 기포빈도, 국부기포속도 그리고 국부 기포크기와 같은 기상 관련 이상유동변수는 이중 전기전도도 탐침으로, 액상속도 분포는 Pilot tuba로 측정하였다. 유로의 경사도가 이상유동 구조에 미치는 영향을 파악하기 위해 실험은 수직, 수직으로부터 30도 경사도 및 60도 경사도에서 유량과 열유속을 변화시켜가며 수행하였으며 유동변수의 측정은 경사진 경우에 측면 방향으로의 대칭성을 고려하여 유로 반 단면내 총 91개 지점에서, 수직인 경우에는 13개 지점에서 이루어졌다. 유동조건은 1.4m/s 이하의 평균 액상 겉보기 속도에 제한되었고 유로내 압력은 대기압이며 유동양식은 미포화 비등에 국한되었다. 측정된 이상유동 변수의 분포를 이용하여 경사유로에 적용할 수 있는 distribution parameter와 drift velocity 같은 dirft flux parameter에 대한 상관식이 개발되었다.

• Nuclear Engineering and Technology
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• v.27 no.4
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• pp.503-517
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• 1995

A mechanistic model for forced convective transition boiling has been developed to predict transition boiling heat flux realistically. This model is based on a postulated multi­stage boiling process occurring during the passage time of an elongated vapor blanket specified at a critical heat flux condition. Between the departure from nucleate boiling (DNB) and the departure from film boiling (DFB) points, the boiling heat transfer is established through three boiling stages, namely, the macrolayer evaporation and dryout governed by nucleate boiling in a thin liquid film and the unstable film boiling. The total heat transfer rate during the transition boiling is the sum of the heat transfer rates after the DNB weighted by the time fractions of each stage, which are defined as the ratio of each stage duration to the vapor blanket passage time. The model predictions are compared with some available experimental transition boiling data. From these comparisons, it can be seen that the transition boiling heat fluxes including the maximum heat flux and the minimum film boiling heat flux are nil predicted at low qualities/high pressures near 10 bar.

• Proceedings of the KSME Conference
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• 2007.05b
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• pp.2696-2701
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• 2007

For the analysis of a two-phase flow, the interaction between two phases such as the interfacial momentum or heat transfer is proportional to the interfacial area. So the interfacial area concentration (IAC) is one of the most important parameters governing the behavior of each phase. This study focuses on the development of a computational fluid dynamics (CFD) code for investigating a boiling flow with a one-group IAC transport equation. It was based on the two-fluid model and governing equations were calculated by SMAC algorithm. For checking the robustness of the developed code, the experiment of a subcooled boiling in a vertical annulus channel was analyzed to validate the capability of the IAC transport equation. As the results, the developed code was confirmed to have the capability in predicting multi-dimensional phenomena of vapor generation and propagation in a subcooled boiling.