【摘要】：一次屏蔽計(jì)算對(duì)于評(píng)估工作人員的輻射劑量、確保反應(yīng)堆壓力容器(RPV)及堆內(nèi)構(gòu)件在整個(gè)反應(yīng)堆壽期內(nèi)的安全性、防止混凝土屏蔽體及其外部部件和結(jié)構(gòu)被過(guò)度活化具有重要意義。本文推導(dǎo)了TORT程序三維源分布計(jì)算公式和源幾何轉(zhuǎn)換方法,編寫(xiě)了相應(yīng)的程序模塊,并在秦山一期、CAP1400和CAP1700計(jì)算模型上進(jìn)行了驗(yàn)證和應(yīng)用。結(jié)果表明,本文推導(dǎo)的理論模型和開(kāi)發(fā)的程序是正確的,為后續(xù)提高一次屏蔽設(shè)計(jì)精度提供了基礎(chǔ)。
[Abstract]:A shielding calculation is used to evaluate the radiation dose of the workers to ensure the safety of the reactor pressure vessel (RPV) and the reactor components throughout the reactor lifetime. It is important to prevent concrete shield and its exterior parts and structures from being overactivated. In this paper, the calculation formula of 3D source distribution and the method of source geometric transformation for TORT program are derived, and the corresponding program modules are compiled, and verified and applied on the calculation model of CAP1400 and CAP1700 in the first phase of Qinshan. The results show that the theoretical model and the program developed in this paper are correct and provide a basis for improving the precision of primary shielding design.
【作者單位】： 上海核工程研究設(shè)計(jì)院;
【分類(lèi)號(hào)】：TL328
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本文編號(hào)：2243943