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ASTRID-like Fast Reactor Cores for Burning Plutonium and Minor Actinides

机译:类似于燃烧钚和轻微散光的Astrid的快速反应器核心

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A reduction of nuclear waste by transmutation of trans-uranium elements (TRUs), such as Pu and Minor Actinides (MAs) contained in Spent Nuclear Fuel (SNF), is a goal for future reactors. In general, countries with on-going nuclear scenarios would profit from MA mass stabilization, while transmutation of Pu and MAs from SNF could be desired in countries in nuclear phase-out. Both missions can be accomplished by employing fast reactors loaded with fuels containing different amounts of Pu and MAs in a closed (or partially closed) fuel cycle. In this paper, two 1200 MWth sodium-cooled fast reactor cores, based on the French ASTRID design, are proposed for burning TRUs (phase-out option) or only MAs (on-going option). Main attention is focused on the safety and on the transmutation performance. The coolant void effect, in the region including the core and the plenum above and the Doppler constant of both systems are negative also with irradiated fuel. The conversion ratios (CR) of the Pu and MA burners are in the ranges from 0.6 to 0.7 and from 0.5 to 0.6, respectively. These results show a large safety and transmutation potential of ASTRID type reactors.
机译:通过核燃料(SNF)中包含的官铀元素(TRU)(TRUS)的嬗变减少了官方元素(TRU)的核废料,这是未来反应堆的目标。一般而言,具有持续核情景的国家将从MA质量稳定下利润,而核淘汰的国家可能需要来自SNF的PU和MAS的嬗变。两者都可以通过采用装载的快速反应器来实现,该燃料在闭合(或部分封闭的)燃料循环中含有不同量的PU和MAS。在本文中,基于法国Astrid设计的两种1200 MWTH冷却的快速反应器核心被燃烧TRU(淘汰选项)或仅用于MAS(正在进行的选项)。主要关注专注于安全性和嬗变性能。在包括核心和上述内部的区域的冷却剂空隙效应和两个系统的多普勒常数也具有照射燃料。 PU和MA燃烧器的转化比(Cr)分别为0.6至0.7和0.5至0.6的范围。这些结果显示了Astrid型反应堆的大安全性和嬗变电位。

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