Hostname: page-component-6bf8c574d5-2jptb Total loading time: 0 Render date: 2025-02-15T09:42:51.596Z Has data issue: false hasContentIssue false
  • English
  • Français

Leaching behaviour of non-irradiated and irradiated HTR UO2-ThO2 fuel particles under reducing conditions

Published online by Cambridge University Press:  21 March 2011

Cyrille Alliot  and
Bernd Grambow
Bernd Grambow
Affiliation:
SUBATECH Laboratory UMR 6457 BP 20722 44307 Nantes cedex 3, France
Get access

Abstract

The dissolution of irradiated HTR UO2-ThO2 fuel particle under reducing conditions was studied using a continuous flow-through reactor and compared to the dissolution of unirradiated fuel particle in the same condition. The irradiated fuel particle was leached for more than eight months. A fast 137Cs release was observed, corresponding to a labile fraction (“instant release fraction”). Then, a congruent leaching of 137Cs and 90Sr was measured corresponding to a matrix dissolution rate equal to 1.7 mg/m2/d. A slower release of 238Pu probably due to sorption phenomena is observed. Dissolution rates are 100-2000 times higher than for unirradiated material. We can conclude that alpha-radiolysis is responsible for this increase due to local oxic conditions. However we cannot exclude that due to irradiation the accessible surface area has been increased as well.

The coating of this irradiated particle was equally studied to determine the presence of different radionuclides and their leaching properties of leaching

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 932: Symposium – Scientific Basis for Nuclear Waste Management XXIX , 2006 , 70.1
Copyright
Copyright © Materials Research Society 2006

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

[1] Schenk, W., Naoumidis, A., Nickel, H., J. Nucl. Mater. 124 (1984) 25.Google Scholar
[2] Schenk, W., Pott, G., Nabielek, H., J. Nucl. Mater. 171 (1990) 19.Google Scholar
[3] Alliot, C., Grambow, B., Landesman, C., J. Nucl. Mater. (accepted).Google Scholar
[4] , Fanchinger, pers. CommunicationGoogle Scholar
[5] Nimura, H., Saito, M., Akiba, K., Onodera, Y., J. Nucl. Sci. Tech. 38 (2001) 872.Google Scholar
[6] Nimura, H., Onodera, Y., J. Nucl. Sci. Tech. 39 (2002) 282.Google Scholar
[7] Horwitz, E., Solvent Extraction and Ion Exchange 10 (1992) 313.Google Scholar
[8] Horwitz, E., Extraction Chromatography of Actinides and Selected Fission Products: Principles and Achievement of Selectivity, International Workshop on the Application of Extraction Chromatography in Radionuclide Measurement, IRMM, Geel 9-10, Belgium(1998).Google Scholar
[9] Brodda, B., Merz, E., Radiochim. Acta 44/45 (1988) 3.Google Scholar