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Application of CATE 2.0 Code on Evaluating Activated Corrosion Products in a PWR Cooling Loop

机译:CATE 2.0代码在压水堆冷却回路中活化腐蚀产物评估中的应用

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摘要

In PWR plants, most Occupational Radiation Exposure (ORE) for personnel results from Activated Corrosion Products (ACPs) in the cooling loop. In order to evaluate the ACPs in the cooling loop, a three-region transport model is built up based on the theory of driving force from the concentration difference in CATE 2.0 code. In order to analyze the nuclide composition of ACPs, the EAF-2007 nuclear database is embedded in CATE 2.0. The case of MIT PCCL test loop is simulated to test the availability of CATE 2.0 on PWR ACPs evaluation, and the activity of Co-58 and Co-60 after operation for 42 days calculated by CATE 2.0 is consistent with that from the code CRUDSIM adopted by MIT. Then, the nuclide composition of ACPs is analyzed in detail respectively for operation of 42 days and 12 months using CATE 2.0. The results show that the short-lived nuclides contribute a majority of the activity in the regions of in-flux wall and coolant, while the long-lived nuclides contribute most of the activity in the region of out-flux wall.
机译:在压水堆工厂中,大多数人员的职业辐射暴露(ORE)来自冷却回路中的活性腐蚀产物(ACP)。为了评估冷却回路中的ACP,基于驱动力理论,根据CATE 2.0代码中的浓度差,建立了一个三区域运输模型。为了分析ACP的核素组成,将EAF-2007核数据库嵌入CATE 2.0中。模拟了MIT PCCL测试循环的情况,以测试PATE ACP评估中CATE 2.0的可用性,并且CATE 2.0计算出的Co-58和Co-60在运行42天后的活动与所采用的代码CRUDSIM一致由麻省理工学院。然后,使用CATE 2.0对42天和12个月的运行分别详细分析了ACP的核素组成。结果表明,短寿命的核素在流入壁和冷却液区域中贡献了大部分活性,而长寿命的核素在流出壁中发挥了大部分活性。

著录项

  • 来源
    《ATW》 |2017年第3期|181-185152|共6页
  • 作者

    Zhang Jingyu; Li Lu; Chen Yixue;

  • 作者单位

    North China Elect Power Univ, Sch Nucl Sci & Engn, 2 Beinong Rd, Beijing, Peoples R China;

    North China Elect Power Univ, Sch Nucl Sci & Engn, 2 Beinong Rd, Beijing, Peoples R China;

    North China Elect Power Univ, Sch Nucl Sci & Engn, 2 Beinong Rd, Beijing, Peoples R China;

  • 收录信息 美国《科学引文索引》(SCI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

  • 入库时间 2022-08-18 00:38:49

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