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The core design of ALFRED, a demonstrator for the European lead-cooled reactors

机译:欧洲铅冷反应堆演示器ALFRED的核心设计

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摘要

The European Union has recently co-funded the LEADER (Lead-cooled European Advanced DEmonstration Reactor) project, in the frame of which the preliminary designs of an industrial size lead-cooled reactor (1500MW_(th)) and of its demonstrator reactor (300MW_(th)) were developed. The latter is called ALFRED (Advanced Lead-cooled Fast Reactor European Demonstrator) and its core, as designed and characterized in the project, is presented here. The core parameters have been fixed in a comprehensive approach taking into account the main technological constraints and goals of the system from the very beginning: the limiting temperature of the clad and of the fuel, the Pu enrichment, the achievement of a burn-up of 100 GWd/t, the respect of the integrity of the system even in design extension conditions (DEC). After the general core design has been fixed, it has been characterized from the neutronic point of view by two independent codes (MCNPX and ERANOS), whose results are compared. The power deposition and the reactivity coefficient calculations have been used respectively as input for the thermal-hydraulic analysis (TRACE, CFD and ANTEO codes) and for some preliminary transient calculations (RELAP, CATHARE and SIM-LFR codes). The results of the lead activation analysis are also presented (FISPACT code). Some issues of the core design are to be reviewed and improved, uncertainties are still to be evaluated, but the verifications performed so far confirm the promising safety features of the lead-cooled fast reactors.
机译:欧盟最近共同资助了LEADER(欧洲先进的铅冷却示范反应堆)项目,该项目的框架是工业规模的铅冷却反应堆(1500MW_th)和示范反应堆(300MW_)的初步设计。 (th))被开发。后者称为ALFRED(高级铅冷却快堆欧洲演示器),在项目中进行了设计和表征,其核心如图所示。从一开始就考虑到系统的主要技术限制和目标,已采用综合方法确定了核心参数:包层和燃料的极限温度,Pu富集,燃料的燃尽。 100 GWd / t,即使在设计扩展条件(DEC)下也要尊重系统的完整性。固定了通用堆芯设计后,已从中子学角度通过两个独立的代码(MCNPX和ERANOS)对其进行了表征,并对其结果进行了比较。功率沉积和反应系数的计算已分别用作热工水力分析(TRACE,CFD和ANTEO代码)和一些初步暂态计算(RELAP,CATHARE和SIM-LFR代码)的输入。还显示了铅激活分析的结果(FISPACT代码)。堆芯设计的一些问题有待审查和改进,不确定性仍有待评估,但迄今为止进行的验证证实了铅冷快堆的安全性能很有希望。

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  • 来源
    《Nuclear Engineering and Design》 |2014年第10期|287-301|共15页
  • 作者单位

    ENEA (Italian National Agency for New Technologies, Energy and Sustainable Economic Development), via Martin di Monte Sole, 4,40129 Bologna, Italy;

    ENEA (Italian National Agency for New Technologies, Energy and Sustainable Economic Development), via Martin di Monte Sole, 4,40129 Bologna, Italy;

    ENEA (Italian National Agency for New Technologies, Energy and Sustainable Economic Development), via Martin di Monte Sole, 4,40129 Bologna, Italy;

    ENEA (Italian National Agency for New Technologies, Energy and Sustainable Economic Development), via Martin di Monte Sole, 4,40129 Bologna, Italy;

    CEA (Alternative Energies and Atomic Energy Commission), DEN, DER, 13108 St Paul lez Durance, France;

    RATEN-ICN (Institute for Nuclear Research), Cod 115400 Mioveni, Str. Campului, 1,Jud. Arges, Romania;

    ENEA (Italian National Agency for New Technologies, Energy and Sustainable Economic Development), via Martin di Monte Sole, 4,40129 Bologna, Italy;

    KIT (Karlsruhe Institute of Technology), Institute for Neutron Physics and Reactor Technology, Hermann-von-Helmholtz-Platz 1,76344 Eggenstein-Leopoldshafen, Germany;

    PSI (Paul Scherrer Institute), OHSA/D11,5232 Villigen PSI, Switzerland;

  • 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
  • 中图分类
  • 关键词

  • 入库时间 2022-08-18 00:43:09

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