uranyl oxalate urea | 46140-70-9

• 分子结构分类: 有机化合物 - 有机酸及其衍生物 - 羧酸及其衍生物
• 英文名称: uranyl oxalate urea
• CAS: 46140-70-9
• 化学式: CH₄N₂O*C₂O₄*O₂U
• 分子量: 418.103
• InChiKey: BUNFRLBGAZXPII-UHFFFAOYSA-L

计算性质

• 辛醇/水分配系数(LogP)：
  -4.73
• 重原子数：
  13.0
• 可旋转键数：
  0.0
• 环数：
  0.0
• sp3杂化的碳原子比例：
  0.0
• 拓扑面积：
  183.51
• 氢给体数：
  2.0
• 氢受体数：
  7.0

反应信息

• 作为反应物：
  描述：

  uranyl oxalate urea 以 neat (no solvent, solid phase) 为溶剂， 生成 uranium dioxide
  参考文献：
  名称：

  Processes for preparing mixed oxides, as applied to conditions of spent nuclear fuel reprocessing without complete separation of U and Pu

  摘要：

  Technologies for spent nuclear fuel reprocessing and fabrication of new fuel without complete separation of Pu from U meet the requirements of nonproliferation of nuclear weapons and allow the number of process operations to be reduced. Three types of known processes for converting a joint solution to mixed plutonium and uranium oxides are considered in a brief literature review: "direct" thermal denitration without isolation of intermediates, thermal denitration with conversion of nitrates to oxides in several steps, and isolation of intermediates with their separation from solution in the first step, followed by their heat treatment. It is advisable to combine processes for preparation of single-phase mixed U-Pu oxides with their purification. Additional experimental data on coprecipitation of uranyl and plutonyl oxalates in oxidizing medium are presented.

  DOI：

  10.1134/s1066362210020025
• 作为产物：
  描述：

  uranyl nitrate*2DMF 、 草酸 、 尿素 以 水 为溶剂， 生成 uranyl oxalate urea
  参考文献：
  名称：

  Processes for preparing mixed oxides, as applied to conditions of spent nuclear fuel reprocessing without complete separation of U and Pu

  摘要：

  Technologies for spent nuclear fuel reprocessing and fabrication of new fuel without complete separation of Pu from U meet the requirements of nonproliferation of nuclear weapons and allow the number of process operations to be reduced. Three types of known processes for converting a joint solution to mixed plutonium and uranium oxides are considered in a brief literature review: "direct" thermal denitration without isolation of intermediates, thermal denitration with conversion of nitrates to oxides in several steps, and isolation of intermediates with their separation from solution in the first step, followed by their heat treatment. It is advisable to combine processes for preparation of single-phase mixed U-Pu oxides with their purification. Additional experimental data on coprecipitation of uranyl and plutonyl oxalates in oxidizing medium are presented.

  DOI：

  10.1134/s1066362210020025