Published 2018 | Version v1
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Reduction of U3O8 and (U,Pu)3O8-x powders in flowing (N2+7% H2) gas mixture by microwave heating

  • 1. Advanced Fuel Fabrication Facility, Nuclear Recycle Board, Bhabha Atomic Research Centre, Tarapur (India)

Description

The reduction of U3O8 and (U,Pu)3O8-x is reported at temperatures in the range 300-900 °C using several reductants like H2, NH3, CO, C, CH4, etc. The reduction of U3O8 to UO2 by H2 is a surface controlled gas-solid reaction which proceeds according to contracting-sphere model involving desorption of water as the rate-limiting step. The stoichiometric reduction of U3O8 and (U,Pu)3O8-x is time consuming process which initially is fast and becomes slow at the end. The conversion of U3O8 to UO2 proceeds via formation of reaction intermediates (U3O7/U4O9) which are unstable at temperature > 300 °C. The efficient reduction of U3O8 and (U,Pu)3O8-x to MO2-x (M: U or U+Pu) using microwave heating is being reported using flowing (N2+7% H2) gas mixture in the present article. The method is fast and advantageous in comparison to the more traditional method of reduction in the electrical resistance furnaces. The reduction of U3O8 or the oxidized mixed oxide (U,Pu)3O8-x powders is a vital step in the feed preparation for oxide and MOX fuel fabrication

Part of:
Proceedings of the second DAE-BRNS symposium on recent advances in nuclear fuel cycle activities

Additional details

Publishing Information

Publisher
Indian Association of Nuclear Chemists and Allied Scientists
Imprint Place
Tarapur (India)
Imprint Title
Proceedings of the second DAE-BRNS symposium on recent advances in nuclear fuel cycle activities
Imprint Pagination
178 p.
Journal Page Range
p. 150-151

Conference

Title
2. DAE-BRNS symposium on recent advances in nuclear fuel cycle activities
Acronym
NUFUC-2018
Dates
26-27 Oct 2018
Place
Tarapur (India)

Optional Information