本文選題：余熱排出系統(tǒng) + 自然循環(huán)　； 參考：《原子能科學(xué)技術(shù)》2015年05期

【摘要】：池式鈉冷快堆事故余熱排出系統(tǒng)采用了非能動工作原理,依靠液態(tài)鈉及空氣的自然對流排出堆芯余熱。為研究事故工況下余熱排出系統(tǒng)一回路的換熱能力,基于FORTRAN語言,建立堆芯單通道及盒間流模型,采用全隱二階迎風(fēng)差分格式及改進(jìn)的歐拉法離散求解,對事故余熱排出系統(tǒng)一回路系統(tǒng)進(jìn)行數(shù)值模擬,并對全廠斷電事故進(jìn)行仿真計算驗證。結(jié)果表明:該程序能較好地反映事故余熱排出系統(tǒng)瞬態(tài)變化過程,并可達(dá)到超實時仿真。
[Abstract]:The reactor core residual heat is discharged by natural convection of liquid sodium and air. In order to study the heat transfer capacity of the residual heat discharge system under accident conditions, based on FORTRAN language, the single-channel and inter-box flow models of reactor core are established, and the fully hidden second-order upwind difference scheme and the improved Euler method are used to solve the problem. The primary circuit system of the accident residual heat discharge system is numerically simulated, and the power failure accident of the whole plant is simulated and verified. The results show that the program can well reflect the transient process of the accident residual heat discharge system, and can achieve super real time simulation.
【作者單位】： 哈爾濱工程大學(xué)核安全與仿真技術(shù)國防重點學(xué)科實驗室;
【基金】：國家自然科學(xué)基金資助項目(51476040,11105034) 核能開發(fā)項目資助 第46批教育部留學(xué)回國人員科研啟動基金資助項目
【分類號】：TL433;TL364.4

【參考文獻(xiàn)】

相關(guān)期刊論文 前3條

1 王武軍,單建強,朱繼洲;全隱二階迎風(fēng)差分格式在快堆模擬中的應(yīng)用，

本文編號：2013884