EOF可居留性分析程序設(shè)計與開發(fā)
發(fā)布時間:2019-03-30 08:46
【摘要】:以先進壓水堆核電廠為對象,研究了設(shè)計基準(zhǔn)事故及嚴重事故工況下放射性遷移行為,確定了應(yīng)急指揮中心(EOF)工作人員各種受照途徑的劑量分析模型,包括進入EOF內(nèi)污染空氣吸入內(nèi)照射、EOF內(nèi)污染空氣γ淹沒外照射、EOF外污染空氣穿過混凝土屏蔽墻或鐵門γ外照射等。在此基礎(chǔ)上,利用VC++6.0語言的MFC平臺,自主研發(fā)了可視化EOF劑量計算程序VYJcode,實現(xiàn)了EOF劑量計算程序化目標(biāo),為非能動核電廠EOF可居留性設(shè)計提供了技術(shù)支持。通過一系列的對比驗證,證明了程序的有效性、正確性。
[Abstract]:Taking the advanced PWR nuclear power plant as an object, the radiation migration behavior under design reference accident and serious accident condition was studied, and the dose analysis models of all kinds of exposure paths for (EOF) staff in emergency command center were determined. These include internal exposure of polluted air in EOF, inundation of 緯 in polluted air in EOF, external exposure of polluted air in EOF through concrete shielded walls or irongate 緯, and so on. On this basis, based on the MFC platform of VC 6.0language, a visual EOF dose calculation program VYJcode, is developed independently to realize the goal of EOF dosimetry programming, which provides technical support for EOF residency design of passive nuclear power plants. Through a series of comparison, the validity and correctness of the program are proved.
【作者單位】: 上海核工程研究設(shè)計院;嘉興市環(huán)境保護監(jiān)測站;
【分類號】:TM623.91;TP311.1
本文編號:2449977
[Abstract]:Taking the advanced PWR nuclear power plant as an object, the radiation migration behavior under design reference accident and serious accident condition was studied, and the dose analysis models of all kinds of exposure paths for (EOF) staff in emergency command center were determined. These include internal exposure of polluted air in EOF, inundation of 緯 in polluted air in EOF, external exposure of polluted air in EOF through concrete shielded walls or irongate 緯, and so on. On this basis, based on the MFC platform of VC 6.0language, a visual EOF dose calculation program VYJcode, is developed independently to realize the goal of EOF dosimetry programming, which provides technical support for EOF residency design of passive nuclear power plants. Through a series of comparison, the validity and correctness of the program are proved.
【作者單位】: 上海核工程研究設(shè)計院;嘉興市環(huán)境保護監(jiān)測站;
【分類號】:TM623.91;TP311.1
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相關(guān)期刊論文 前1條
1 王駿;;核電廠應(yīng)急指揮中心設(shè)計[J];核安全;2012年04期
,本文編號:2449977
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