(T-4)-二氟二氧代-铀 | 13536-84-0

• 分子结构分类: 无机化合物 - 混合金属/非金属化合物 - 锕系盐类
• 中文名称: (T-4)-二氟二氧代-铀
• 英文名称: uranyl difluoride
• 英文别名: uranyl fluoride；dioxouranium(2+);difluoride
• CAS: 13536-84-0
• 化学式: F₂O₂U
• 分子量: 308.025
• InChiKey: KCKICANVXIVOLK-UHFFFAOYSA-L

物化性质

• 熔点：
  300 °C (decomp)
• 密度：
  6.37 g/cm3
• 溶解度：
  不溶于苯

计算性质

• 辛醇/水分配系数(LogP)：
  -6.23
• 重原子数：
  5
• 可旋转键数：
  0
• 环数：
  0.0
• sp3杂化的碳原子比例：
  0.0
• 拓扑面积：
  34.1
• 氢给体数：
  0
• 氢受体数：
  4

安全信息

• 危险等级：
  7

反应信息

• 作为反应物：
  描述：

  (T-4)-二氟二氧代-铀 生成 uranium;tetraperoxide
  参考文献：
  名称：

  TANAKA, HIROSHI;UMEMURA, AKIO

  摘要：

  DOI：
• 作为产物：
  描述：

  铀(VI)氟化物 生成 (T-4)-二氟二氧代-铀
  参考文献：
  名称：

  YATO, TADAO;TANAKA, HIROSHI;KIKUCHI, TOSHIAKI;ONOSHITA, TOSHIO

  摘要：

  DOI：

文献信息

• Process for manufacturing uranium dioxide powder
  申请人：Mitsubishi Nuclear Fuel Co., Ltd.

  公开号：US04505882A1

  公开（公告）日：1985-03-19

  A process for manufacturing uranium dioxide powder which comprises forming fine uranium dioxide powder having a high sinterability and coarse uranium dioxide powder having a low sinterability continuously in one process by changing periodically the precipitation condition of the ammonium diuranate under the same condition of calcining and reducing of the ammonium diuranate. The thus obtained mixture of these uranium dioxide powders is suitable for uranium dioxide pellet which is a fuel of nuclear power reactor.

  制造二氧化铀粉末的工艺包括在同一过程中连续形成具有高烧结性能的细二氧化铀粉末和具有低烧结性能的粗二氧化铀粉末，通过周期性改变铵二铀酸的沉淀条件，在铵二铀酸的煅烧和还原条件相同的情况下。因此获得的这些二氧化铀粉末的混合物适用于核功率反应堆的燃料-二氧化铀颗粒。
• Recovery of anhydrous hydrogen fluoride from depleted uranium
  申请人：Sequoyah Fuels Corporation

  公开号：US05346684A1

  公开（公告）日：1994-09-13

  A method is provided for recovering an anhydrous hydrogen fluoride product from uranium hexafluoride gas by initially reacting the uranium hexafluoride in a primary reactor with steam to produce a uranyl fluoride intermediate and a gaseous mixture of hydrogen fluoride and water. The uranyl fluoride intermediate is fed to a secondary reactor and reacted with water to produce a triuranium octoxide product for disposal, and a gaseous mixture of water, hydrogen fluoride and oxygen. The two mixtures from the primary and secondary reactors are combined and subsequently separated in a distillation column to obtain an anhydrous hydrogen fluoride product stream and an aqueous azeotropic recycle stream containing water and hydrogen fluoride which is vaporized and returned to the primary reactor as the steam feed.

  本方法提供了一种从六氟化铀气体中回收无水氢氟酸产品的方法。首先，在主反应器中将六氟化铀与蒸汽反应，生成尿铀氟中间体和氢氟酸和水的混合气体。尿铀氟中间体被送入次级反应器，并与水反应，生成可处置的三铀八氧化物产品和水、氢氟酸和氧的混合气体。来自主反应器和次级反应器的两种混合物被结合，随后在蒸馏柱中分离，以获得无水氢氟酸产品流和含水和氢氟酸的水性共沸再循环流，该流体被汽化并返回主反应器作为蒸汽进料。
• Radiation shielding materials and containers incorporating same
  申请人：Mirsky Steven M.

  公开号：US06960311B1

  公开（公告）日：2005-11-01

  An improved radiation shielding material and storage systems for radioactive materials incorporating the same. The PYRolytic Uranium Compound (“PYRUC”) shielding material is preferably formed by heat and/or pressure treatment of a precursor material comprising microspheres of a uranium compound, such as uranium dioxide or uranium carbide, and a suitable binder. The PYRUC shielding material provides improved radiation shielding, thermal characteristic, cost and ease of use in comparison with other shielding materials. The shielding material can be used to form containment systems, container vessels, shielding structures, and containment storage areas, all of which can be used to house radioactive waste. The preferred shielding system is in the form of a container for storage, transportation, and disposal of radioactive waste. In addition, improved methods for preparing uranium dioxide and uranium carbide microspheres for use in the radiation shielding materials are also provided.

  一种改进的辐射屏蔽材料和储存系统，其中包括PYRolytic铀化合物（“PYRUC”）屏蔽材料。该PYRUC屏蔽材料最好是通过热和/或压力处理前体材料形成的，该前体材料包括微球形铀化合物，例如二氧化铀或碳化铀，以及适当的粘合剂。与其他屏蔽材料相比，PYRUC屏蔽材料提供了改进的辐射屏蔽、热特性、成本和易用性。该屏蔽材料可用于形成封闭系统、容器、屏蔽结构和封闭储存区，这些都可用于存放放射性废物。首选的屏蔽系统是用于存储、运输和处理放射性废物的容器。此外，还提供了用于制备用于辐射屏蔽材料的二氧化铀和碳化铀微球的改进方法。
• Process for making uranium carbide
  申请人：The United States of America as represented by the United States Department of Energy

  公开号：US06599490B1

  公开（公告）日：2003-07-29

  An improved radiation shielding material and storage systems for radioactive materials incorporating the same. The PYRolytic Uranium Compound (“PYRUC”) shielding material is preferably formed by heat and/or pressure treatment of a precursor material comprising microspheres of a uranium compound, such as uranium dioxide or uranium carbide, and a suitable binder. The PYRUC shielding material provides improved radiation shielding, thermal characteristic, cost and ease of use in comparison with other shielding materials. The shielding material can be used to form containment systems, container vessels, shielding structures, and containment storage areas, all of which can be used to house radioactive waste. The preferred shielding system is in the form of a container for storage, transportation, and disposal of radioactive waste. In addition, improved methods for preparing uranium dioxide and uranium carbide microspheres for use in the radiation shielding materials are also provided.

  改进的辐射屏蔽材料及储存系统，其中包括该材料。PYRolytic铀化合物（“PYRUC”）屏蔽材料最好是通过热和/或压力处理前体材料形成的，该前体材料包括微球形铀化合物，例如二氧化铀或碳化铀，以及适当的粘合剂。与其他屏蔽材料相比，PYRUC屏蔽材料提供了改进的辐射屏蔽、热特性、成本和易于使用性。该屏蔽材料可用于形成包含系统、容器、屏蔽结构和容纳储存区，所有这些都可以用于存放放射性废物。首选的屏蔽系统是用于存储、运输和处置放射性废物的容器。此外，还提供了改进的制备二氧化铀和碳化铀微球形颗粒用于辐射屏蔽材料的方法。
• Holz, K.; Mattes, R., Zeitschrift fur Anorganische und Allgemeine Chemie
  作者：Holz, K.、Mattes, R.

  DOI：——

  日期：——