کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
8069342 | 1521132 | 2014 | 10 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Depressurization study of supercritical fluid blowdown from simple vessel
ترجمه فارسی عنوان
مطالعه کاهش فشار از انفجار مایع فوق بحرانی از کشتی ساده
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موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
چکیده انگلیسی
The loss of coolant accident (LOCA), particularly the depressurization process, is one of the difficulties in safety analysis of supercritical water-cooled reactor (SCWR). In this study, a comprehensive mathematic-physical model was established and a transient analysis code was developed to simulate the blowdown behaviors of SCWR in a large container. Three alternative phase separation models were adopted to calculate the stagnation enthalpy of the two-phase fluid in the container. Break flow rate models were established for different thermodynamic regions, including the supercritical region, the subcooled region, the overheating region and the two-phase region. The code was verified by comparison with blowdown experiment of supercritical CO2 which shows a good agreement. Then the blowdown of supercritical water from simple vessel was investigated in detail with the code. The effect of initial conditions on pressure transitions was discussed for different regions divided by the relationship between the initial temperature and the corresponding pseudo-critical temperature. Furthermore, both the depressurization speed and the void fraction increase with the increase of initial temperature and the decrease of the initial pressure, yet the fluid inventory has an opposite trend. Discharge speed varies directly with break area, and the pressure transition which turns up earlier remains a constant value. These investigations may lay a theoretical foundation for the accident analysis of SCWR.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 66, April 2014, Pages 94-103
Journal: Annals of Nuclear Energy - Volume 66, April 2014, Pages 94-103
نویسندگان
Jing Zhang, Dahuan Zhu, Wenxi Tian, Suizheng Qiu, Guanghui Su, Dalin Zhang,