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首页> 美国政府科技报告 >Review of methods for immobilizing iodine-129 arising from a nuclear fuel recycle plant, with emphasis on waste-form chemistry.
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Review of methods for immobilizing iodine-129 arising from a nuclear fuel recycle plant, with emphasis on waste-form chemistry.

机译：审查固定化核燃料循环装置产生的碘-122的方法，重点是废物形式化学。

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Possible methods for the separation and immobilization of iodine (mainly iodine-129) in a fuel recycle plant are reviewed, with special emphasis placed on the evaluation of waste forms. A distinction is drawn between waste forms selected by thermodynamic (solubility) or kinetic (dissolution rate) considerations. The most promising solubility-limited waste forms appear to be AgI (or AgI + AgCl) and a combination of Bi(sub 2)O(sub 3) and Bi(sub 5)O(sub 7)I. These materials use relatively scarce metals, Ag and Bi. They also have substantial chemical limitations, such as susceptibility to reductive dissolution and anion-displacement reactions; this calls for special care in the choice of a disposal site. All other organic iodides and iodates considered here and elsewhere appear to be still more limited in this respect. The most promising kinetically limited candidate waste form appears to be iodide-sodalite, but further information is needed on both the fabrication and leaching behaviour of this material. The possibility of disposal in a more soluble but isotopically dilute waste form, employing abundant raw materials, also warrants further consideration. (Atomindex citation 23:002552)

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