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하나로 핵연료시험설비의 비상냉각수계통 성능 예측 평가모델 분석
박수기(Su-Ki Park),심봉식(Bong-Sik Sim),박국남(Kuk-Nam Park),이한희(Han-Hee Lee),이정영(Chung-Young Lee) 대한기계학회 2006 대한기계학회 춘추학술대회 Vol.2006 No.11
The performance of the emergency cooling water system of the HANARO fuel test loop has been predicted with the MARS code. Evaluation models such as the Moody model for discharge rate calculation and the Baker-Just model for water-metal reaction calculation were used. Multipliers were also introduced to the correlations of heat transfer coefficients in the MARS code in order to calculate conservative peak cladding temperatures for accidents. The maximum peak cladding temperature is calculated for the longitudinal split of the cold leg in the HANARO pool and greatly depends on the multipliers of the critical heat flux and film boiling correlations. In the analyses the issue on return-to-nucleate boiling phenomena, after critical heat flux is first predicted at an axial fuel rod location during blowdown, is not important for predicting the maximum peak cladding temperature.
3-Pin 핵연료 노내조사시험설비의 IR1 유동관 및 노내시험부 차압특성 분석
이한희(Han-Hee Lee),이종민(Jong-Min Lee),심봉식(Bong-Sik Sim),이정영(Chung-Young Lee) 대한기계학회 2006 대한기계학회 춘추학술대회 Vol.2006 No.6
The in-pile Sectio of 3-pin Fuel Test Loop shall be installed in the vertical hole call IR1 of HANARO reactor core. In order to verify the pressure drop and flow rate both the inside region of IPS at the annular region between IPS and IR1 flow tube, a pressure drop was measured by varing the flow rate on both regions. The measured pressure drop in the annular region is 209㎪ at 14.9㎏/s which meets the limiting condition of operation of 200㎪. The measured pressure drop in side the IPS becomes 260.25㎪ which is lower than the designed value of 306.65㎪. As the pressure drop is lower than the design value, it is quite conservative from the safety and operating point of view.