Uranium oxide (UO2)

Base Information

• Chemical Name: Uranium oxide (UO2)
• CAS No.: 1344-57-6
• Deprecated CAS: 1293289-56-1
• Molecular Formula: O2U
• Molecular Weight: 270.028
• European Community (EC) Number: 215-700-3
• ICSC Number: 1251
• Wikipedia: Uranium dioxide,Uranium(IV) oxide,Uranium_dioxide
• Wikidata: Q378379
• Mol file: 1344-57-6.mol

Synonyms:uranium dioxide;uranium dioxide, (233)U-labeled;uranium dioxide, (235)U-labeled

Chemical Property of Uranium oxide (UO2)

Chemical Property:

• Melting Point: 2500oC
• Boiling Point: °Cat760mmHg
• Flash Point: °C
• PSA: 34.14000
• Density: g/cm³
• LogP: -0.23760
• Hydrogen Bond Donor Count: 0
• Hydrogen Bond Acceptor Count: 2
• Rotatable Bond Count: 0
• Exact Mass: 270.04062
• Heavy Atom Count: 3
• Complexity: 18.3

Purity/Quality:

99%, ^*data from raw suppliers

Safty Information:

• Pictogram(s): High radiation risk. Ignites spontaneously in finely divided form.
• Hazard Codes: High radiation risk. Ignites spontaneously in finely divided form.

MSDS Files:

SDS file from LookChem

Useful:

• Chemical Classes: Physical/Radiation -> Radioactive Compounds
• Canonical SMILES: O=[U]=O
• Inhalation Risk: A harmful concentration of airborne particles can be reached quickly when dispersed, especially if powdered.
• Effects of Short Term Exposure: The substance is irritating to the eyes.
• Effects of Long Term Exposure: Repeated or prolonged inhalation of dust particles may cause effects on the lungs.
• Use Description: Uranyl(VI) chloride, a specific chemical compound, serves distinct roles in various fields. In the realm of nuclear energy and nuclear chemistry, it plays a crucial role as a precursor or reagent in the production and purification of uranium compounds used in nuclear reactors, fuel production, and nuclear research. In analytical chemistry, it serves as a reference material for the calibration of instruments used in the detection and measurement of radiation, aiding in the accurate assessment of radioactive samples. Additionally, in scientific research, uranyl(VI) chloride may be employed in studies related to the behavior of uranium and its compounds, contributing to our understanding of nuclear chemistry and radiochemistry. Its applications in nuclear energy, analytical chemistry, and scientific research underscore its significance in advancing nuclear technology, ensuring accurate radiation measurements, and supporting scientific investigations within these distinct domains.

Technology Process of Uranium oxide (UO2)

There total 17 articles about Uranium oxide (UO2) which guide to synthetic route it. The literature collected by LookChem mainly comes from the sharing of users and the free literature resources found by Internet computing technology. We keep the original model of the professional version of literature to make it easier and faster for users to retrieve and use. At the same time, we analyze and calculate the most feasible synthesis route with the highest yield for your reference as below:

synthetic route:

Reference yield:

C61H77N6P3Si3U + 9-anthracene aldehyde (642-31-9) → uranium dioxide (1344-57-6) + C46H48N2P2Si2 (1282040-50-9) + C31H29PSi

Guidance literature:

In benzene-d6; at 20 ℃; for 16h; Inert atmosphere;

DOI:10.1002/anie.201802080

Reference yield:

uranium oxide → uranium dioxide (1344-57-6)

Guidance literature:

at 650 ℃; for 18h; Inert atmosphere;

DOI:10.1021/acs.inorgchem.8b01284

Reference yield:

uranium(IV) aspartate + water (7732-18-5) → uranium dioxide (1344-57-6)

Guidance literature:

at 160 ℃; for 30h; Time; Autoclave; High pressure;

DOI:10.1039/c8ce01352g

upstream raw materials:

carbon monoxide

carbon dioxide

benzaldehyde

9-anthracene aldehyde

Downstream raw materials:

uranium hexafluoride

uranyl fluoride

Refernces

• 1、 Trillaud,Maynadié,Manaud,Hidalgo,Meyer,Podor,Dacheux,Clavier. "Synthesis of size-controlled UO2 microspheres from the hydrothermal conversion of U(iv) aspartate". . p. 7749 - 7760. Retrieved 2018.
• 2、 Chatelain, Lucile,Faizova, Radmila,Fadaei-Tirani, Farzaneh,Pécaut, Jacques,Mazzanti, Marinella. "Structural Snapshots of Cluster Growth from {U6} to {U38} During the Hydrolysis of UCl4". . p. 3021 - 3026. Retrieved 2019.
• 3、 Kulyako, Yu. M.,Myasoedov, B. F.,Perevalov, S. A.,Pilyushenko, K. S.,Savel’ev, B. V.,Trofimov, T. I.,Vinokurov, S. E.. "Use of Microwave Radiation for Denitration of Uranyl Nitrate Solution and Subsequent Sintering of Uranium Dioxide Fuel Pellets". . p. 317 - 322. Retrieved 2021/06/02.