Experimental evidence of oxygen thermo-migration in PWR UO2 fuels during power ramps using in-situ oxido-reduction indicators

JOURNAL OF NUCLEAR MATERIALS

卷:480

Article

Riglet-Martial, Ch.¹  Sercombe, J.¹  Lamontagne, J.¹  Noirot, J.¹  Roure, I.¹  Blay, T.¹  Desgranges, L.¹ 

[1] Commissariat Energie Atom & Energies Alternat, Direct Energie Nucl, Dept Etud Combustibles, Ctr Etud Cadarache, F-13108 St Paul Les Durance, France

关键词: Uranium;    Oxide;    Fuel;    Power ramp;    Power transient;    Temperature gradient;    Chromium;    Dopant;    Additive;    Solubility;    Thermodynamics;    Oxido-reduction;    Redox indicator;    Oxygen potential;    Thermo-migration;    Oxygen re-distribution;   

DOI  :  10.1016/j.jnucmat.2016.07.056

来源: Elsevier

【 摘 要 】

The present study describes the in-situ electrochemical modifications which affect irradiated PWR UO2 fuels in the course of a power ramp, by means of in-situ oxido-reduction indicators such as chromium or neo-formed chemical phases. It is shown that irradiated fuels (of nominal stoichiometry close to 2.000) under temperature gradient such as that occurring during high power transients are submitted to strong oxido-reduction perturbations, owing to radial migration of oxygen from the hot center to the cold periphery of the pellet. The oxygen redistribution, similar to that encountered in Sodium Fast Reactors fuels, induces a massive reduction/precipitation of the fission products Mo, Ru, Tc and Cr (if present) in the high temperature pellet section and the formation of highly oxidized neo-formed grey phases of U4O9 type in its cold section, of lower temperature. The parameters governing the oxidation states of UO2 fuels under power ramps are finally debated from a cross-analysis of our results and other published information. The potential chemical benefits brought by oxido-reductive additives in UO2 fuel such as chromium oxide, in connection with their oxygen buffering properties, are discussed. (c) 2016 Elsevier B.V. All rights reserved.

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