Removal of Irradiated UO2 Fuel from the Cladding by Controlled Oxidation
Author : L. A. Hanson
Publisher :
Page : 30 pages
File Size : 27,8 MB
Release : 1959
Category : Nuclear fuel claddings
ISBN :
Author : L. A. Hanson
Publisher :
Page : 30 pages
File Size : 27,8 MB
Release : 1959
Category : Nuclear fuel claddings
ISBN :
Author : J. Guon
Publisher :
Page : 44 pages
File Size : 22,71 MB
Release : 1962
Category : Reactor fuel reprocessing
ISBN :
Author : J. E. Bodine
Publisher :
Page : 22 pages
File Size : 22,64 MB
Release : 1962
Category : Carbides
ISBN :
Author :
Publisher :
Page : 212 pages
File Size : 26,77 MB
Release : 1964
Category : Nuclear fuels
ISBN :
Author : W. G. Smiley
Publisher :
Page : 30 pages
File Size : 22,23 MB
Release : 1962
Category : Nuclear fuels
ISBN :
Author :
Publisher :
Page : 726 pages
File Size : 46,47 MB
Release : 1963
Category : Nuclear engineering
ISBN :
Author :
Publisher :
Page : 640 pages
File Size : 37,78 MB
Release : 1975
Category : Nuclear energy
ISBN :
Author : D. G. Cummings
Publisher :
Page : pages
File Size : 14,81 MB
Release : 2006
Category :
ISBN :
The development of a head-end processing step for spent oxide fuel that applies to both aqueous and pyrometallurgical technologies is being performed by the Idaho National Laboratory, the Oak Ridge National Laboratory, and the Korean Atomic Energy Research Institute through a joint International Nuclear Energy Research Initiative. The processing step employs high temperatures and oxidative gases to promote the oxidation of UO2 to U3O8. Potential benefits of the head-end step include the removal or reduction of fission products as well as separation of the fuel from cladding. The effects of temperature, pressure, oxidative gas, and cladding have been studied with irradiated spent oxide fuel to determine the optimum conditions for process control. Experiments with temperatures ranging from 500oC to 1250oC have been performed on spent fuel using either air or oxygen gas for the oxidative reaction. Various flowrates and applications have been tested with the oxidative gases to discern the effects on the process. Tests have also been performed under vacuum conditions, following the oxidation cycle, at high temperatures to improve the removal of fission products. The effects of cladding on fission product removal have also been investigated with released fuel under vacuum and high temperature conditions. Results from these experiments will be presented as well as operating conditions based on particle size and decladding characteristics.
Author : T. F. Connolly
Publisher :
Page : 170 pages
File Size : 43,31 MB
Release : 1960
Category : Chemistry
ISBN :
Author : G. E. Brand
Publisher :
Page : 68 pages
File Size : 37,78 MB
Release : 1965
Category : Reactor fuel reprocessing
ISBN :
This report summarizes the work carried out at Atomics International on the AIROX process. This process is based on the oxidation of UO2 to U3O and reconversion to UO2 by reduction with hydrogen. Repeated oxidation-reduction effectively pulverizes the UO2.