首页> 外文期刊>Nuclear Engineering and Design >The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)
【24h】

The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)

机译:MYRRHA-FASTEF核心设计用于关键和次关键操作模式(欧盟FP7中央设计团队项目)

获取原文
获取原文并翻译 | 示例
           

摘要

On April 2009, a three-year-project was launched within the 7th Framework Programme (FP) of the European Commission: the Central Design Team (CDT) for a FAst Spectrum Transmutation Experimental Facility (FASTEF). The main goal was to achieve an advanced level of design for an irradiation facility, cooled by lead-bismuth, operating in both critical and sub-critical modes. In continuity with the research studies on fast nuclear systems carried out in the 5-6th FPs, the CDT had the further ambitious objective to define a preliminary design of the MYRRHA reactor, planned to be built at the SCK·CEN research centre in Mol (Belgium). In addition to being a multi-purpose irradiation facility, MYRRHA should be able to demonstrate the Acceleration Driven System concept at ~100MW power level and an efficient transmutation of minor actinides, as main contributors to high-level long-lived radioactive wastes. This paper describes the design of cores able to operate the MYRRHA-FASTEF plant in both critical and sub-critical modes. The design studies were performed by detailed neutronic analyses (with deterministic and Monte Carlo methods) and by accurate thermal-hydraulic evaluations (at the fuel assembly and pin sub-channel level), by taking also into account thermo-mechanical and safety constraints. Among the most significant core features, the fast flux level (Φ_(>0.75Mev) ~ 10~(15) cm~(-2) s~(-1)), the high flexibility for irradiation purposes and the limited overall dimension (impacting on the cost of the plant) can be noticed. The transmutation of minor actinides, enhanced by the high fast flux, reaches values of about 32 kg_(HM) TWT~(-1) in both operational modes.
机译:2009年4月,在欧盟委员会的第七框架计划(FP)中启动了一个为期三年的项目:用于FAst光谱Trans变实验设施(FASTEF)的中央设计团队(CDT)。主要目标是实现在临界和次临界模式下运行的,由铅铋冷却的辐照设施的高级设计。与在第5-6个FP中进行的快速核系统研究相继,CDT的进一步雄心勃勃的目标是确定MYRRHA反应堆的初步设计,该反应堆计划在Mol的SCK·CEN研究中心建造(比利时)。除作为多功能辐射设施外,MYRRHA还应能够证明功率约为100MW的加速驱动系统概念以及次minor系元素的高效转化,这是高水平长寿命放射性废物的主要贡献者。本文介绍了能够在关键和亚关键模式下运行MYRRHA-FASTEF工厂的核的设计。设计研究是通过详细的中子学分析(采用确定性和蒙特卡洛方法)和精确的热工液压评估(在燃料组件和销子通道水平)进行的,同时还要考虑热机械和安全约束。在最显着的核心特征中,快速的通量水平(Φ_(> 0.75Mev)〜10〜(15)cm〜(-2)s〜(-1)),用于辐照目的的高柔韧性和有限的整体尺寸(对工厂成本的影响)。在两种操作模式下,次act系元素的trans变均通过高快速通量增强,达到约32 kg_(HM)TWT〜(-1)的值。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2013年第12期|184-200|共17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;

    SCK·CEN, Belgian Nuclear Research Centre, Boeretang 200,2400 Mol, Belgium;

    SCK·CEN, Belgian Nuclear Research Centre, Boeretang 200,2400 Mol, Belgium;

    SCK·CEN, Belgian Nuclear Research Centre, Boeretang 200,2400 Mol, Belgium;

    SCK·CEN, Belgian Nuclear Research Centre, Boeretang 200,2400 Mol, Belgium;

    SCK·CEN, Belgian Nuclear Research Centre, Boeretang 200,2400 Mol, Belgium;

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

    ANSALDO NUCLEARE S.p.A., Corso Perrone25, 16152 Cenova, Italy;

    CIEMAT, Spanish National Research Centre for Energy, Environment and Technology, Avenida Complutense 40,28040 Madrid, Spain;

    AREVA-NP, Rue Juliette Recamier 10, 69456 Lyon Cedex 06, France;

    ANSALDO NUCLEARE S.p.A., Corso Perrone25, 16152 Cenova, Italy;

    SCK·CEN, Belgian Nuclear Research Centre, Boeretang 200,2400 Mol, Belgium;

  • 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

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号