Hostname: page-component-848d4c4894-tn8tq Total loading time: 0 Render date: 2024-06-19T16:19:20.438Z Has data issue: false hasContentIssue false

RN Fractional Release of High Burn-Up Fuel: Effect of HBS and Estimation of Accessible Grain Boundary

Published online by Cambridge University Press:  01 February 2011

F. Clarens
Affiliation:
CTM Centre Tecnològic, Av Bases de Manresa 1, 08242, 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
A. Martínez-Esparza
Affiliation:
ENRESA, Emilio Vargas 7, Madrid, Spain.
D. Wegen
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:
Chemical Engineering Department, Universitat Politècnica de Catalunya UPC, Av Diagonal 647, 08028, Barcelona, Spain
J. de Pablo
Affiliation:
CTM Centre Tecnològic, Av Bases de Manresa 1, 08242, Spain Chemical Engineering Department, Universitat Politècnica de Catalunya UPC, Av Diagonal 647, 08028, Barcelona, Spain
I Casas
Affiliation:
Chemical Engineering Department, Universitat Politècnica de Catalunya UPC, Av Diagonal 647, 08028, Barcelona, Spain
J. Giménez
Affiliation:
Chemical Engineering Department, Universitat Politècnica 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
Get access

Abstract

The so-called Instant Release Fraction (IRF) is considered to govern the dose released from Spent Fuel repositories. Often, IRF calculations are based on estimations of fractions of inventory release based in fission gas release [1]. The IRF definition includes the inventory located within the Gap although a conservative approach also includes both the Grain Boundary (GB) and the pores of restructured HBS inventories.

A correction factor to estimate the fraction of Grain Boundary accessible for leaching has been determined and applied to spent fuel static leaching experiments carried out in the ITU Hot Cell facilities [2]. Experimental work focuses especially on the different properties of both the external rim area (containing the High Burn-up Structure (HBS)) and the internal area, to which we will refer as Out and Core sample, respectively. Maximal release will correspond to an extrapolation to simulate that all grain boundaries or pores are open and in contact with solution.

The correction factor has been determined from SEM studies taking into account the number of particles with HBS in Out sample, the porosity of HBS particles, and the amount of transgranular fractures during sample preparation.

Type
Research Article
Copyright
Copyright © Materials Research Society 2008

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

1 Poinssot, C et al. . Final Report of the European Project Spent Fuel Stability under Repository Conditions. CEA-R-6093. ISSN 0429-3460. 2005, pp 103.Google Scholar
2 Final Report of the European Project Near Field Processes (NF-PRO). In preparation.Google Scholar
3 Spino, J., Vennix, K. and Coquerelle, M.. Journal of Nuclear Materials. Vol. 231, 1996, pp 179190.Google Scholar
4 Walker, T., Staicu, D., Sheindlin, M., Papaioannou, D., Goll, W., Sontheimer, F.. Journal of Nuclear Materials, Vol. 350, 2006, pp 1939.Google Scholar
5 Fernéndez, A. M.. PreparaciÓn de una agua intersticial sintética bentonítica a diferentes salinidades (Preparation of a synthetic bentonitic interstitial water at different salinities). CIEMAT DMA/M214213/05, Madrid, 2005.Google Scholar
6 UTHSCSA Image Tool 3. University of Texas Health Science Center at San Antonio, Texas and available from the Internet by anonymous FTP from maxrad6.uthscsa.edu.Google Scholar
7 Johnson, L.. Journal of Nuclear Materials, Vol. 346, 2005, pp 5665.Google Scholar
8 Coble, L.. Journal of Applied Physics, Vol. 32 (5), 1961, pp. 787792.Google Scholar
9 Döbrich, K.M., Rau, C., Krill, C.E.. Metallurgical and Materials Transaction A. Vol. 35A, 2004, pp. 19531961.Google Scholar
10 Hosford, W.F., www.cambridge.org. ISBN=13:9780511258336. 18/04/07.Google Scholar
11 Gray, W.J.; Wilson, C.N. Spent Fuel Dissolution Studies FY 1991 to 1994. PNL- 10540.Google Scholar