Abstract The gradual corrosion and activation of the cooling loop with time in water-cooled reactor is one of the safety and environmental issues. Activated corrosion products (ACPs) are the dominant radiation hazard in water-cooled reactor under normal operation conditions, and directly determine Occupational Radiological Exposure (ORE) during operation and maintenance. ACPs have different phases: ions, particles, oxides layer, deposits layer. Among them, particles are an important movable source item in coolant due to their unique behavioral characteristics and they can deposit on pipe surface to form deposits layer. In this paper, code CATE is upgraded to V3.0 based on CATE V2.1 and a four-phase three-node model is proposed for calculating radioactivity of multi-phase ACPs. For code testing, the blanket cooling loop of International Thermonuclear Experimental Reactor (ITER) is simulated, and the results obtained by CATE V3.0 agree reasonably well with published data calculated by other international codes PACTITER and TRACT, which means CATE V3.0 is available and credible on ACPs analysis of water-cooled reactor. Then ACPs in the primary loop of a typical PWR is analyzed using CATE V3.0 and the sensitivity of some important parameters on ACPs is analyzed. The results showed that ions play an important role in corrosion products mass of coolant and oxides layer plays a decisive role in corrosion products mass of pipe surface. The main contributors to radioactivity of coolant, in-flux pipe, out-flux pipe are separately ions, oxides layer and deposits layer. Long-lived nuclides such as Co-58 and Co-60 are major contributors to total radioactivity after shutdown. From the sensitivity analysis, it can be seen that using low-cobalt materials and controlling pH of coolant rationally can help reduce source term of ACPs.

中文翻译：

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为典型 PWR 中的多相 ACP 分析开发 CATE V3.0 代码

摘要 水冷堆冷却回路随时间逐渐腐蚀和活化是安全和环境问题之一。活性腐蚀产物（ACPs）是正常运行条件下水冷堆的主要辐射危害，直接决定运行和维护过程中的职业辐射暴露（ORE）。ACP 具有不同的相：离子、颗粒、氧化物层、沉积层。其中，颗粒由于其独特的行为特性是冷却剂中重要的可移动源项，它们可以沉积在管道表面形成沉积层。本文在CATE V2.1的基础上将代码CATE升级到V3.0，提出了一种四相三节点模型来计算多相ACP的放射性。对于代码测试，模拟了国际热核实验反应堆（ITER）的毯式冷却回路，CATE V3.0 获得的结果与其他国际代码 PACTITER 和 TRACT 计算的公布数据相当吻合，这意味着 CATE V3.0 在水冷反应堆的ACPs分析。然后使用CATE V3.0对典型压水堆主回路中的ACP进行分析，并分析了一些重要参数对ACP的敏感性。结果表明，离子对冷却液腐蚀产物质量起重要作用，氧化层对管道表面腐蚀产物质量起决定性作用。冷却剂、流入管、流出管的放射性的主要贡献者分别是离子、氧化物层和沉积层。Co-58 和 Co-60 等长寿命核素是关闭后总放射性的主要贡献者。从敏感性分析可以看出，使用低钴材料和合理控制冷却液的pH值有助于降低ACPs的源项。