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Effect of HBS Structure in Fast Release Fraction of 48 GWd/tU PWR Fuel

Published online by Cambridge University Press:  15 February 2011

J. de Pablo ,
D. Serrano-Purroy ,
E. Gonzalez-Robles ,
F. Clarens ,
A. Martinez-Esparza ,
D.H. Wegen ,
I. Casas ,
B. Christiansen ,
J.-P. Glatz  and
J. Gimenez
J. de Pablo
Affiliation:
CTM Centre Tecnologic, Av Bases de Manresa 1, 08242, Spain Chemical Engineering Department, Universitat Politecnica de Catalunya UPC, Av Diagonal 647, 08028, Barcelona, Spain
D. Serrano-Purroy
Affiliation:
JRC-ITU, European Commission Joint Research Centre-Institute of Transuranium Elements, Hermann-von-Helmholtz-Platz 1, Eggenstein-Leopoldshafen, 76344, Germany
E. Gonzalez-Robles
Affiliation:
CTM Centre Tecnologic, Av Bases de Manresa 1, 08242, Spain
F. Clarens
Affiliation:
CTM Centre Tecnologic, Av Bases de Manresa 1, 08242, Spain
A. Martinez-Esparza
Affiliation:
ENRESA, Emilio Vargas 7, Madrid, Spain
D.H. Wegen
Affiliation:
JRC-ITU, European Commission Joint Research Centre-Institute of Transuranium Elements, Hermann-von-Helmholtz-Platz 1, Eggenstein-Leopoldshafen, 76344, Germany
I. Casas
Affiliation:
Chemical Engineering Department, Universitat Politecnica de Catalunya UPC, Av Diagonal 647, 08028, Barcelona, Spain
B. Christiansen
Affiliation:
JRC-ITU, European Commission Joint Research Centre-Institute of Transuranium Elements, Hermann-von-Helmholtz-Platz 1, Eggenstein-Leopoldshafen, 76344, Germany
J.-P. Glatz
Affiliation:
JRC-ITU, European Commission Joint Research Centre-Institute of Transuranium Elements, Hermann-von-Helmholtz-Platz 1, Eggenstein-Leopoldshafen, 76344, Germany
J. Gimenez
Affiliation:
Chemical Engineering Department, Universitat Politecnica de Catalunya UPC, Av Diagonal 647, 08028, Barcelona, Spain
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Abstract

Two important issues in Performance Assessment exercises regarding the alteration of Spent Nuclear Fuel (SNF) are the contribution of Instant or better called Fast release Fraction (FRF) and the effect of High Burn-Up Structure (HBS). Therefore this paper focuses on the effect of HBS in FRF of a PWR irradiated in a commercial reactor with a mean Burn-Up (BU) of 48 GWd/tU. Additionally, determined FRF are compared with previous experiments performed with PWR with a mean BU of 60 GWd/tU, in order to evaluate the effect of BU on FRF.

In order to study the HBS contribution, static leaching experiments are performed with two samples prepared from different radial positions, labeled Core, central region and Out, enriched with HBS. Two synthetic leaching solutions, bicarbonate and bentonitic granitic groundwater are used under oxic conditions.

The estimated FRF are calculated from the determined Fraction of Inventory in Aqueous Phase (FIAP) taking into account the inventory determined experimentally for each fraction.

Higher release is observed for Core sample, which can be an indicative that HBS does not increase the RN release. With the exception of Rb and Cs, which release is higher at lower BU, no clear effect of BU is observed within the studied range.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1193: Scientific Basis for Nuclear Waste Management XXXIII , 2009 , 613
Copyright
Copyright © Materials Research Society 2009

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References

1 Johnson, L., Ferry, C., Poinssot, C., Lovera, P.. “Spent Fuel radionuclide source-term model for assessing spent fuel performance in geological disposal. Part I: Assessment of the instant release fraction”. J. Nuclear Materials 346, 56 (2005).Google Scholar
2 Walker, C.T., Staicu, D., Sheindlin, M., Papaioannou, D., Goll, W., Sontheimer, F.. “On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100 MWd/kgHM”. Journal of Nuclear Materials, 350, 19 (2006).Google Scholar
3 Pablo, J. de, Casas, I., Gimenez, J., Clarens, F., Gonzalez-Robles, E., Serrano-Purroy, D., Glatz, J.-P., Wegen, D., Christiansen, B., Martinez-Esparza, A.. “Contribution to leaching studies of high-burnup spent nuclear fuel”. “Proceedings of the 12th Internacional High-Level Radioactive Waste Management Conference (IHLRWM),”Steps toward Reality for Safe Disposal”. September 7-11,2008. Las Vegas (Nevada).Google Scholar
4 Clarens, F., Serrano-Purroy, D., Martinez-Esparza, A., Wegen, D., Gonzalez-Robles, E., Pablo, J. de, Casas, I., Christiansen, B. and Glatz, J.P.. “RN fractional release of High Burn-Up fuel: effect of HBS and estimation of accessible Grain Boundary.” XXXI Materials Research Symposia in Scientific Basis for Nuclear Waste Management. Held on Sheefield, England, September 2007.Google Scholar
5 Fernandez, A. M.. “Preparacion de una agua intersticial sintetica bentonitica a diferentes salinidades (Preparation of a synthetic bentonitic interstitial water at different salinities).” CIEMAT DMA/M214213/05, Madrid, 2005.Google Scholar
6 Forsyth, R.S. and Werme, L.O.. Spent fuel corrosion and dissolution J. Nucl. Mater. 190 (1992), p. 3. Forsyth R, 1995. Spent nuclear fuel. A review of properties of possible relevance to corrosion processes. SKB TR 95-23Google Scholar
7 Hanson, , Mat. Res. Soc. Symp. Proc. 824, 89, (2004).Google Scholar
8 Martinez-Esparza, A., Gago, J.A., Quinones, J., Iglesias, E., Andres, S. Perez de.: “Review of Influence of burn-up and irradiation history on spent fuel instant release”. Contract number: FI6W-CT-2003-02389) NF-PRO (D1.4.2)Google Scholar