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Assessment of SFR reactor safety issues: Part II: Analysis results of ULOF transients imposed on a variety of different innovative core designs with SAS-SFR

机译:SFR反应堆安全问题的评估:第二部分:使用SAS-SFR施加于多种不同创新堆芯设计的ULOF瞬态分析结果

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摘要

In the framework of cooperation agreements between KIT-INR and AREVA SAS NP as well as between KIT-INR and EDF R&D in the years 2008-2013, the evaluation of severe transient behavior in sodium-cooled fast reactors (SFRs) was investigated. In Part I of this contribution, the efficiency of newly conceived prevention and mitigation measures was investigated for unprotected loss-of-flow (ULOF), unprotected loss-of-heat-sink (ULOHS) and the unprotected transient-overpower (UTOP) transients. In this second part, consequence analyses were performed for the initiation phase of different unprotected loss-of-flow (ULOF) scenarios imposed on a variety of different core design options of SFRs. The code system SAS-SFR was used for this purpose. Results of analyses for cases postulating unavailability of prevention measures as shut-down systems, passive and/or active additional devices show that entering into an energetic power excursion as a consequence of the initiation phase of a ULOF cannot be avoided for those core designs with a cumulative void reactivity feedback larger than zero. However, even for core designs aiming at values of the void reactivity less than zero it is difficult to find system design characteristics which prevent the transient entering into partial core destruction. Further studies of the transient core and system behavior would require codes dedicated to specific aspects of transition phase analyses and of in-vessel material relocation analyses. (C) 2015 Elsevier B.V. All rights reserved.
机译:在KIT-INR与AREVA SAS NP之间以及KIT-INR与EDF R&D在2008-2013年之间的合作协议框架内,对钠冷快堆(SFR)的严重瞬态行为进行了评估。在此贡献的第一部分中,针对未保护的流量损失(ULOF),未保护的散热片(ULOHS)和未保护的瞬态过功率(UTOP)瞬变,研究了新构思的预防和缓解措施的效率。 。在第二部分中,针对不同的无保护流量损失(ULOF)场景的启动阶段进行了后果分析,这些场景适用于SFR的各种不同核心设计方案。为此,使用了代码系统SAS-SFR。假设无法使用预防措施作为关闭系统,无源和/或有源附加设备的案例的分析结果表明,对于那些具有ULOF核心设计的核心设计,无法避免由于ULOF的启动阶段而进入能量消耗大的情况。累积空隙反应性反馈大于零。然而,即使对于旨在空隙反应性值小于零的芯设计,也难以找到防止瞬态进入部分芯破坏的系统设计特征。对瞬态核心和系统行为的进一步研究将需要专用于过渡阶段分析和容器内材料迁移分析的特定方面的代码。 (C)2015 Elsevier B.V.保留所有权利。

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  • 来源
    《Nuclear Engineering and Design》 |2015年第4期|263-283|共21页
  • 作者单位

    Karlsruhe Inst Technol, Inst Neutron Phys & Reactor Technol INR, D-76344 Eggenstein Leopoldshafen, Germany;

    Karlsruhe Inst Technol, Inst Neutron Phys & Reactor Technol INR, D-76344 Eggenstein Leopoldshafen, Germany;

    Karlsruhe Inst Technol, Inst Neutron Phys & Reactor Technol INR, D-76344 Eggenstein Leopoldshafen, Germany;

    Karlsruhe Inst Technol, Inst Neutron Phys & Reactor Technol INR, D-76344 Eggenstein Leopoldshafen, Germany;

    AREVA, F-69456 Lyon 06, France;

    AREVA, F-69456 Lyon 06, France;

    EDF R&D, F-92140 Clamart, France;

    EDF R&D, F-92140 Clamart, France;

  • 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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