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首页> 外文期刊>Nuclear Engineering and Design >Development of a coupled neutronic/thermal-hydraulic tool with multi-scale capabilities and applications to HPLWR core analysis
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Development of a coupled neutronic/thermal-hydraulic tool with multi-scale capabilities and applications to HPLWR core analysis

机译:具有多尺度功能的中子/热液耦合工具的开发及其在HPLWR岩心分析中的应用

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摘要

The High Performance Light Water Reactor (HPLWR) is a thermal spectrum nuclear reactor cooled and moderated with light water operated at supercritical pressure. It is an innovative reactor concept, which requires developing and applying advanced analysis tools as described in the paper. The relevant water density reduction associated with the heat-up, together with the multi-pass core design, results in a pronounced coupling between neutronic and thermal-hydraulic analyses, which takes into account the strong natural influence of the in-core distribution of power generation and water properties. The neutron flux gradients within the multi-pass core, together with the pronounced dependence of water properties on the temperature, require to consider a fine spatial resolution in which the individual fuel pins are resolved to provide precise evaluation of the clad temperature, currently considered as one of the crucial design criteria. These goals have been achieved considering an advanced analysis method based on the usage of existing codes which have been coupled with developed interfaces. Initially neutronic and thermal-hydraulic full core calculations have been iterated until a consistent solution is found to determine the steady state full power condition of the HPLWR core. Results of few group neutronic analyses might be less reliable in case of HPLWR 3-pass core than for conventional LWRs because of considerable changes of the neutron spectrum within the core, hence 40 groups transport theory has been preferred to the usual 2 groups diffusion theory. Successively, with the usage of a developed pin-power reconstruction technique capable to account for the innovative fuel assembly design, subchannel investigations of the individual fuel assemblies have been performed evaluating pin-wise clad temperatures. Obtained results will be discussed giving a detailed insight of the revolutionary HPLWR 3 pass core concept and understanding the physical reasons, which influence the local clad temperatures. The obtained results represent a new quality in core analyses, which takes into full consideration the coupling between neutronics and thermal-hydraulics as well as the spatial effects of the fuel assembly heterogeneity in determining the local pin-power and the associated maximum clad temperature.
机译:高性能轻水反应堆(HPLWR)是一种热谱核反应堆,用在超临界压力下运行的轻水进行冷却和调节。这是一个创新的反应堆概念,需要开发和应用本文所述的高级分析工具。与加热相关的水密度降低以及多程堆芯设计导致中子学分析与热工水力分析之间的显着耦合,这考虑到了堆芯内功率分配的强大自然影响发电和水的特性。多程堆芯内的中子通量梯度,以及水性质对温度的明显依赖性,需要考虑一个精细的空间分辨率,在该分辨率中,单个燃料销被分解以提供对包层温度的精确评估,目前被认为是关键的设计标准之一。考虑到基于使用已开发接口的现有代码的使用情况的高级分析方法,可以实现这些目标。最初,中子学和热工液压全铁心计算已经反复进行,直到找到一致的解决方案来确定HPLWR铁心的稳态全功率状态。由于堆芯内部中子谱的显着变化,在HPLWR 3通堆芯情况下,少数几组中子分析的结果可能不如常规LWR可靠,因此,与常规的2组扩散理论相比,首选40组输运理论。继而,通过使用能够解释创新燃料组件设计的发达的销钉功率重建技术,已对单个燃料组件进行了子通道研究,以评估销钉包覆温度。将讨论获得的结果,以提供对革命性的HPLWR 3通道核心概念的详细了解,并了解影响局部熔覆温度的物理原因。获得的结果代表了岩心分析的新质量,它在确定局部销钉功率和相关的最大包层温度时,充分考虑了中子学与热工液压之间的耦合以及燃料组件异质性的空间影响。

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  • 来源
    《Nuclear Engineering and Design》 |2011年第5期|p.1579-1591|共13页
  • 作者单位

    Karlsruhe Institute of Technology (KIT), Institute for Nuclear and Energy Technologies (1KET), Hermann-von-Helmholaplatz 1, 76344 Eggenstein-Leopoldshafen, Germany;

    Universitat Stuttgart, lnstitutfur Kernenergetik und Energiesysteme, Pfaffenwaldring 31, 70569 Stuttgart, Germany;

    Karlsruhe Institute of Technology (KIT), Institute for Nuclear and Energy Technologies (1KET), Hermann-von-Helmholaplatz 1, 76344 Eggenstein-Leopoldshafen, Germany;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
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