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Core Design of a Small Pressurized Water Reactor with AP1000 Fuel Assembly Using SRAC and COBRA-EN Codes
Science and Technology of Nuclear Installations ( IF 1.0 ) Pub Date : 2020-11-11 , DOI: 10.1155/2020/8847897
Van Khanh Hoang 1
Affiliation  

This paper presents the core design and performance characteristics of a 300 MWt small modular reactor (SMR) with fuel assemblies of the AP1000 reactor. Numerical calculations have been performed to evaluate a proper active core size and core loading pattern using the SRAC code system with the JENDL-4.0 data library and the CORBRA-EN code. The calculated temperature coefficients including fuel temperature, coolant temperature, and isothermal temperature coefficient provide adequate negative reactivity feedbacks. The thermal-hydraulic analysis reveals acceptable radial and axial fuel element temperature profiles with significant safety margin of fuel and clad surface temperature. A safety analysis using the CORBRA-EN code shows that the core will remain covered during the entire transient procedure of the fast transient of remarkably increasing power that would be caused by the ejection of control rod. The analysis results indicate that the core with a cycle length of 2.22 years is achievable while satisfying the operation and safety-related design criteria with sufficient margins.

中文翻译:

使用SRAC和COBRA-EN代码的带有AP1000燃料组件的小型压水堆的核心设计

本文介绍了带有AP1000反应堆燃料组件的300 MWt小型模块化反应堆(SMR)的核心设计和性能特征。使用带有JENDL-4.0数据库和CORBRA-EN代码的SRAC代码系统,已经进行了数值计算,以评估合适的有效堆芯尺寸和堆芯装载方式。计算得出的温度系数(包括燃料温度,冷却液温度和等温温度系数)提供了足够的负反应性反馈。热工液压分析揭示了可接受的径向和轴向燃料元件温度曲线,并具有明显的燃料安全裕度和复合表面温度。使用CORBRA-EN代码进行的安全分析表明,在因控制杆弹出而导致功率急剧增加的快速瞬变过程中,磁芯将保持覆盖状态。分析结果表明,可以达到周期长度为2.22年的堆芯,同时以足够的余量满足运行和安全相关的设计标准。
更新日期:2020-11-12
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