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首页> 外文期刊>International Journal of Nuclear Energy Science and Technology >Numerical simulations of corrosion product activity in the purification system of a typical PWR under nonlinearly rising corrosion and flow rate perturbations
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Numerical simulations of corrosion product activity in the purification system of a typical PWR under nonlinearly rising corrosion and flow rate perturbations

机译：非线性上升腐蚀和流量扰动下典型压水堆净化系统中腐蚀产物活性的数值模拟

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摘要

Numerical simulations of corrosion product activity in the purification system of a Pressurised Water Reactor (PWR) are presented. The computer programme code Collision Product Activity in Reactors (CPAIR-RC), developed by the authors, has been used to find corrosion product activity in the ion exchanger and filters of PWR under nonlinearly rising corrosion rates and flow rate perturbations. For nonlinearly rising corrosion rates, a typical value of removal rate 750 cm~3 s~(-1) is taken, for which the saturation value of the activity has been found sufficiently low (0.27 μCi cm~(-3)). The simulation results shows that for the constant refuelling and purification process, the activity, due to ~(59)Fe, ~(99)Mo and ~(56)Mn, reaches saturation values within about 1000 h of reactor operation. However, two major contributors to radioactive buildup, ~(58)Co and ~(60)Co, keep on accumulating and do not saturate within this period. When the flow rate is decreased by 10% of the rated flow rate after 500 h of reactor operation, a dip in the activity is seen (which reaches the value of 0.0182 μCi cm~(-3)), then it begins to rise again and reaches a saturation value of 0.271 μCi cm~(-3). The computed values of corrosion product activity from CPAIR-RC have been compared with some of the experimental data that are available in the literature and a fair agreement between them has been found.
机译：提出了压水反应堆（PWR）净化系统中腐蚀产物活性的数值模拟。作者开发的计算机程序代码“反应堆中的碰撞产物活性”（CPAIR-RC）已用于在非线性上升的腐蚀速率和流速扰动下，找到PWR离子交换器和过滤器中的腐蚀产物活性。对于非线性上升的腐蚀速率，采用去除速率的典型值750 cm〜3 s〜（-1），对于该值，已发现其活性的饱和值足够低（0.27μCicm〜（-3））。仿真结果表明，对于恒定的加油和提纯过程，由于〜（59）Fe，〜（99）Mo和〜（56）Mn导致的活性在反应堆运行约1000小时内达到饱和值。但是，放射性堆积的两个主要贡献者〜（58）Co和〜（60）Co在此期间不断积累并且没有饱和。当反应器运行500小时后，流量降低到额定流量的10％时，可以看到活性下降（达到0.0182μCicm〜（-3）的值），然后又开始上升饱和度达到0.271μCicm〜（-3）。已将CPAIR-RC的腐蚀产物活性的计算值与文献中提供的一些实验数据进行了比较，并且发现它们之间存在公平的协议。

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