Abstract
New kinds of fuel for fast reactors are being developed. Uranium-plutonium nitride fuel has good neutronphysical indices, but there are peculiarities to handling it after irradiation in a reactor. At the stage of dissolution of the irradiated uranium-plutonium nitride fuel in nitric acid, a significant quantity of volatile radioactive fission products, including ruthenium, is released into the gas phase. In the present work, the possibility of catching ruthenium tetroxide on sorbents was evaluated experimentally. The catching of ruthenium tetroxide by granules of pyrolusite, γ-Al2O3, and γ-Al2O3 permeated by a 10% solution of carbamide or nitric acid was investigated. The results can be used in the development of a technology and apparatus for catching volatile product of ruthenium fission.
Sign-in/Register to access full text options 
Free) 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a call
