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Possibility of Burning Americium in Fast Reactors
Atomic Energy ( IF 0.4 ) Pub Date : 2020-06-01 , DOI: 10.1007/s10512-020-00656-w
A. V. Gulevich , V. A. Eliseev , D. A. Klinov , L. V. Korobeinikova , M. V. Kryachko , V. A. Pershukov , V. M. Troyanov

The possibilities of burning americium from spent nuclear fuel of thermal reactors in the operating BN-800 are examined. It is shown that because of the small fission cross-section in the neutron spectrum of a fast reactor all of the americium cannot be directly converted into fission products. This can be done only by transmutation of americium into plutonium, which must be separated and directed into fuel, where it will burn. In a reactor only 15–20% of the americium is transmuted, and the remaining americium must be returned into the reactor for transmutation. The volume of the recycled americium can be significantly reduced by burning in facilities possessing a moderator (zirconium hydride) and the need for burning it can be eliminated by using plutonium with a high content of the isotope 241Pu as the fuel of fast reactors, where this isotope fissions efficiently.

中文翻译:

在快堆中燃烧镅的可能性

研究了在运行的 BN-800 中从热反应堆的乏核燃料中燃烧镅的可能性。结果表明,由于快堆中子谱中的裂变截面很小,所有的镅不能直接转化为裂变产物。这只能通过镅转化为钚来实现,钚必须被分离并转化为燃料,然后在那里燃烧。在反应器中,只有 15-20% 的镅发生嬗变,其余的镅必须返回反应器进行嬗变。通过在具有减速剂(氢化锆)的设施中燃烧可以显着减少回收镅的体积,并且可以通过使用同位素 241Pu 含量高的钚作为快堆燃料来消除燃烧它的需要,
更新日期:2020-06-01
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