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Preparation and characterization of UO2-based AGR SIMFuel

Published online by Cambridge University Press:  30 June 2014

Zoltan Hiezl ,
David Hambley  and
William E. Lee
Zoltan Hiezl
Affiliation:
Imperial College London, Centre for Nuclear Engineering, London, SW7 2AZ, UK
David Hambley
Affiliation:
Spent Fuel Management and Disposal, UK National Nuclear Laboratory (NNL), Springfields, PR4 0XJ, UK
William E. Lee
Affiliation:
Imperial College London, Centre for Nuclear Engineering, London, SW7 2AZ, UK
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Abstract

Preparation and characterization of a Simulated Spent Nuclear Fuel (SIMFuel), which replicates the chemical state and microstructure of Spent Nuclear Fuel (SNF) discharged from UK Advanced Gas-cooled Reactor (AGR) after a cooling time of 100 years is described. Thirteen stable elements were added to depleted UO2 and sintered to simulate the composition of fuel pellets after burn-ups of 25 and 43 GWd/tU and, as a reference, pure UO2 pellets were also investigated. The fission product distribution was calculated using the Fispin code provided by NNL. SIMFuel pellets exhibit a microstructure up to 92% TD. During the sintering process in H2 atmosphere Mo-Ru-Rh-Pd metallic precipitates and grey-phase ((Ba, Sr)(Zr, RE)O3 oxide precipitates) formed within the UO2 matrix. These secondary phases are present in real PWR and AGR SNF, although they are smaller in size than those examined in this study. The grain size of the produced SIMFuel is in good agreement with literature references.

Keywords

USEMsintering
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1665: Symposium NW – Scientific Basis for Nuclear Waste Management XXXVII , 2014 , pp. 245 - 251
Copyright
Copyright © Materials Research Society 2014 

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References

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