UO2, NpO2 and PuO2 preparation in aqueous nitrate solutions in the presence of hydrazine hydrate
It was established that heating to 90 °C of nitrate solutions of U, Np and Pu in the presence of hydrazine hydrate results in the formation of hydrated dioxides of these elements. On ignition under inert or reducing conditions in the temperature range of 280–800 °C hydrated uranium dioxide transmogrify into crystalline UO2. On ignition in air atmosphere UO2·nH2O turns into UO3 at 440 °C and into U3O8 at 570–800 °C. It was shown that thermolysis of the solution containing a mixture of uranium, neptunium and plutonium nitrates at 90 °C in the presence of hydrazine hydrate allows one to prepare hydrated dioxides (U, Np, Pu)O2·nH2O which on heating to ~300 °C transmogrify into crystalline product of UO2, NpO2 and PuO2 solid solution. The technique of preparation of solid solutions of U and Pu dioxides is very promising as simple and effective method of production of MOX-fuel for.
KeywordsUranium Plutonium Neptunium Hydrazine hydrate Denitration
The project was supported by the Ministry of Education and Science of the Russian Federation (Grant 8438), by RFBR (12-03-00661-a, 12-08-00559-a) and by the State Atomic Energy Corporation ROSATOM.
- 1.Nuclear power technologies of new generation for the period of 2010–2015 years and in perspective to 2020. Passport of the Federal objective programGoogle Scholar
- 2.Adamov EO, Orlov VV (1999) Nuclear power development based on new concepts of nuclear reactors and fuel cycle. Proc Heavy Liquid Metal Coolants Nuclear Technol 1:25–32Google Scholar
- 5.Zilberman BY (2000) Development PUREX process for processing highly burnt out fuel for nuclear power plants in the closed nuclear fuel cycle in terms of localization of long-lived radionuclides. Radiochemistry 42(1):3–15Google Scholar
- 6.Gavrilov PM, Kudryavtsev EG, Revenko YA et al (2009) Experimental demonstration center on MCC as a prototype of the 3rd generation plant for thermal reactor SNF reprocessing. Proceedings of international conference on global 2009, paper 9075Google Scholar
- 7.Volk VI (2011) Combined (Pyro + Hydro) Technology of FNR SNF Reprocessing. Proceedings of international conference on global 2011, paper 386756Google Scholar
- 8.Samoilov AG (1985) Fuel elements of nuclear reactors. Energoatomizdat, Moskva (in Russian)Google Scholar
- 9.Lerch RE, Norman RE (1984) Nuclear fuel conversion and fabrication chemistry. Radiochim Acta 36(1/2):75–88Google Scholar
- 10.Vandergrift GF (2000) Transformation of UREX effluents to solid oxides by concentration, denitration, and calcination, ANL-00/25, 20Google Scholar
- 11.Haas PA (1973) Conversion of fuel-metal nitrate solutions to oxides. US Patent 3.725.293Google Scholar
- 13.JCPDS-International Centre for Diffraction Data (1999) PCPDFWIN v. 2.02Google Scholar
- 15.Il’in EG, Beirakhov AG, Kulyako YM et al (2010) A new procedure for preparing mixed uranium–plutonium dioxide. Radiochemistry 52(4):297–299Google Scholar
- 16.Aliyev RI, Guseinov MI, Klyuchnikov II (1967) Complex compounds of copper and zinc with hydrazine. Russ J Inorg Chem 12:1219Google Scholar