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ATHLET-SC程序的开发及适用性分析 被引量：6

Development and Applicability Analysis of ATHLET-SC Code
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摘要 由于超临界水堆(SCWR)在系统简化、降低成本和提高热效率上的优势,SCWR的研究在全球范围内得到广泛关注。在众多有关超临界水堆的研发工作中,开发适用于SCWR的系统分析程序是进行SCWR系统设计和安全评估的关键技术难题之一。本工作基于最佳估算系统分析程序ATHLET2.1A,增加了超临界热物性参数,开发出适用于SCWR的系统分析程序ATHLET-SC,将现有的ATH-LET程序扩展到超临界压力状态。为评估修改后的程序的适用性,建立了混合能谱超临界水堆堆芯模型,并对该模型进行了功率瞬态计算。此外,对1个简化的超临界水冷却回路进行了稳定性分析。计算结果表明:修改过的ATHLET程序(ATHLET-SC)对SCWR系统的模拟具有良好的适用性。 Research activities of supercritical water reactor （SCWR） have been carried out worldwide, aiming at cost reduction by system simplification and higher thermal efficiency. One of the most important tasks for the design and assessment of SCWR performance is to develop system analysis codes which are applicable under supercritical conditions. The paper presents the development of new system analysis code ATHLETSC based on ATHLET 2.1A. Thermo-physical properties package valid for supercritical conditions are implemented into the existing ATHLET code to extend its application to safety analysis of SCWR. In to evaluate the applicability of the modified code, a core calculation model of mixed SCWR （SCWR-M） was proposed and analyzed, and transients of core power were simulated. Moreover, a simplified supercritical water cooled loop was proposed and its stability behaviors were analyzed. The results achieved up to now indicate a good applicability of the modified ATHLET code （ATHLET-SC） in simulation of SCWR.
作者 周翀 刘晓晶 杨燕华 程旭
机构地区 上海交通大学核科学与工程学院
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2009年第6期556-560,共5页 Atomic Energy Science and Technology
基金 国家重点基础研究发展计划资助项目(2007CB209804)
关键词 超临界水堆 安全分析 ATHLET-SC程序 supercritical water reactor safety analysis ATHLET-SC code
分类号 TL4 [核科学技术—核技术及应用]
  • 相关文献

参考文献6

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二级参考文献11

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共引文献45

同被引文献31

  • 1许志红,傅晟威,刘晓晶,杨燕华,程旭.混合能谱超临界水堆失流事故缓解措施研究[J].原子能科学技术,2012,46(9):1097-1106. 被引量：1
  • 2Yi T T, lshiwatari Y, Koshizuka S, et al. Startup Ther- mal Analysis of a High-Temperature Supercritical- Pressure Light Water Reactor[J]. Journal of Nuclear Science and Technology, 2004, 41:790-801.
  • 3Cheng X, Liu X J, Yang Y H. A Mixed Core for Super- critical Water-Cooled Reactors[J]. Nuclear Engineering and Technology, 2008, 40:117-126.
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  • 6Fu S W, Zhou C, Xu Z H, et al. Modification and Ap- plication of the ATHLET-SC Code to Trans-Critical Simulations[C]. Vancouver: The 5th International Sym- posium on Supercritical Water-Cooled Reactors, 2011.
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引证文献6

二级引证文献6

原子能科学技术
2009年 第6期

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