Thermal and photo-oxidation of a potential extractant in nuclear fuel reprocessing

机译：核燃料后处理中潜在萃取剂的热氧化和光氧化

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Malonamides have been investigated by the C.E.A. (Commissariat a l'Energie Atomique) to extract actinides (III) and lanthanides (III) from acidic nitrate nuclear waste solutions. The destructin of these potentially incinerable molecules has been tested in relatively soft conditions: thermal oxidation at temperatures below 250 deg C and photo-oxidation at short wavelengths (185-254 nm). qualitative and quantitative analysis of main degradation products allows the comparison between these methods. Thermal oxidation leads to a rapid destruction of the initial modecule but numerous by-products and some black insoluble material appear, whereas photo-oxidation is slower but doensn't give so many by-products and any insoluble residues.

机译：丙二酰胺已由C.E.A. （Commerariat a l'Energie Atomique）从酸性硝酸盐核废液中提取act系元素（III）和镧系元素（III）。已经在相对较软的条件下测试了这些可能被焚化的分子的破坏素：在低于250摄氏度的温度下进行热氧化，在短波长（185-254 nm）下进行光氧化。通过对主要降解产物进行定性和定量分析，可以对这些方法进行比较。热氧化导致初始分子的快速破坏，但出现了许多副产物和一些黑色的不溶物，而光氧化反应则较慢，但不会产生这么多副产物和任何不溶性残留物。

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《Environmental engineering and management》|1998年|p.189-198|共10页
会议地点 Barcelona(ES)
作者
F. Delavente; J. -M. Guillot; O. Thomas; L. Berthon; M. -C. Charbonnel;
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1. Photo-oxidation of two malonamides, extractant models for minor actinides in nuclear fuel reprocessing [J] . Franck Delavente, Jean-Michel Guillot, Olivier Thomas, Journal of Photochemistry and Photobiology, A. Chemistry . 2003,第1期

机译：两种丙二酰胺的光氧化，核燃料后处理中次act系元素的萃取剂模型
2. Power/energy: Rebirth for nuclear fuel: Reprocessing is `inÂ¿ again; if so, the debate will center on conserving nuclear fuels and the question of nuclear proliferation [J] . Miller M.M. Spectrum, IEEE . 1981,第11期

机译：功率/能源：核燃料的重生：后处理又在进行中；如果是这样，辩论将集中在节约核燃料和核扩散问题上
3. NEW TECHNOLOGY AND HARDWARE FOR REPROCESSING SPENT NUCLEAR FUEL FROM THERMAL REACTORS [J] . Volk V. I., Veselov S. N., Dvoeglazov K. N., Atomic Energy . 2016,第5期

机译：从热反应器中处理核燃料的新技术和新硬件
4. Nuclear waste reprocessing: study of the separation of radioactive cations 137{sup left}Cs{sup}+ and 90{sup left}Sr{sup}2+ from the high level activity radioactive waste (HLW) by extractants derivatives of the hydroborates B{sub}10H{sub}10{sup}(2-) [C] . D. Naoufal, B. Gruner, P. Selucky, Mediterranean Conference for Environment and Solar . 2001

机译：核废料再加工：通过萃取剂衍生物的衍生物的衍生物，对放射性阳离子137 {sup左} cs {sup} cs {sup} +和90×sup} 2+的分离的研究 b {sub} 10h {sub} 10 {sup}（2-）
5. COMPARATIVE EVALUATION OF NUCLEAR FUEL REPROCESSING TECHNIQUES FOR ADVANCED FUEL CYCLE CONCEPTS. [D] . SELVADURAY, GUNA SEELAN -1

机译：先进燃料循环概念的核燃料后处理技术的比较评估。
6. Thermally-Conductive and Mechanically-Robust Graphene Nanoplatelet Reinforced UO2 Composite Nuclear Fuels [O] . Tiankai Yao, Guoqing Xin, Spencer Michael Scott, -1

机译：导热和机械稳健的石墨烯纳米片增强UO2复合核燃料
7. Demonstration of the Potential for Designing Extractants with Preselected Extraction Properties: Possible Application to Reactor Fuel Reprocessing [O] . G. W. MASON, H. E. GRIFFIN 1980

机译：用预选的提取性能设计萃取剂的潜力：可能的应用于反应堆燃料再处理
8. Di-N-Amyl-N-Amylphosphonate and Tricaprylmethylammonium Nitrate as Potential Extractants for Reprocessing Th-U Fuels [R] . Diamond, H., Sabau, C. S., Horwitz, E. P., 1979

机译：二-N-戊基-N-戊基膦酸盐和三癸基甲基硝酸铵作为Th-U燃料再处理的潜在萃取剂

Thermal and photo-oxidation of a potential extractant in nuclear fuel reprocessing

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