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IMPLICATIONS OF PLUTONIUM ISOTOPIC SEPARATION ON CLOSED FUEL CYCLES AND REPOSITORY DESIGN

机译:ISO同位素分离对封闭燃料循环的影响及储库设计

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摘要

Advances in laser enrichment may enable relatively low-cost plutonium isotopic separation creating a new unexplored dimension in fuel cycle options. This may have large impacts on light water reactor (LWR) closed fuel cycles and waste management. If~(240)Pu is removed before recycling plutonium as mixed-oxide (MOX) fuel, it would dramatically reduce the buildup of higher plutonium isotopes, americium, and curium. Plutonium-240 is a fertile material and thus can be replaced by ~(238)U. Eliminating the higher plutonium isotopes in MOX fuel increases the Doppler feedback, simplifies reactor control, and allows infinite recycle of MOX plutonium in LWRs. Reducing production of ~(241)Pu by removal of ~(240)Pu reduces production of~(241) Am-the primary heat generator in spent nuclear fuel after several decades. Reducing heat-generating ~(241)Am would reduce repository size, cost, and waste toxicity. Avoiding ~(241)Am avoids its decay product ~(237)Np, a nuclide that partly controls long-term oxidizing repository performance. The ~(240)Pu could be added to the high-level waste for disposal. Some of these benefits also apply to plutonium recycled into fast reactors. However, the benefits are fewer because in a fast neutron spectrum, ~(240)Pu is both a fissile material and a fertile material. There would be incentives to separate ~(242)Pu and dispose of it as a waste.
机译:激光浓缩技术的进步可以实现相对低成本的p同位素分离,从而在燃料循环选择中创造出一个新的未开发的规模。这可能对轻水堆(LWR)的封闭燃料循环和废物管理产生重大影响。如果在循环使用as作为混合氧化物(MOX)燃料之前先除去〜(240)Pu,它将大大减少高of同位素,a和cur的积累。 240 240是一种肥沃的材料,因此可以用〜(238)U代替。消除MOX燃料中较高的p同位素可增加多普勒反馈,简化反应堆控制,并允许在轻水堆中无限循环使用MOX lu。通过去除〜(240)Pu减少〜(241)Pu的产生,将减少几十年后〜(241)Am(乏核燃料中的主要热发生器)的产生。减少发热量〜(241)Am将减少存储库的大小,成本和废物毒性。避免〜(241)Am可避免其衰变产物〜(237)Np,这是部分控制长期氧化存储库性能的核素。可以将〜(240)Pu添加到高放废物中进行处理。其中一些好处还适用于循环到快速反应器中的p。但是,其好处较少,因为在快速中子谱中,〜(240)Pu既是易裂变材料又是可育材料。有动力将〜(242)Pu分离并将其作为废物处置。

著录项

  • 来源
    《Nuclear Technology》 |2015年第1期|63-70|共8页
  • 作者

    CHARLES FORSBERG;

  • 作者单位

    Massachusetts Institute of Technology, 77 Massachusetts Avenue Cambridge, Massachusetts 20139-4307;

  • 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

    plutonium separation; repository; recycle;

    机译:separation分离仓库回收;

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