Hostname: page-component-77c89778f8-fv566 Total loading time: 0 Render date: 2024-07-20T23:11:20.777Z Has data issue: false hasContentIssue false
  • English
  • Français

Further Developments of the Reductive Capacity Model for Spent Fuel Stability: Application to Minor Radionuclides

Published online by Cambridge University Press:  10 February 2011

J. Bruno ,
E. Cera ,
L. Duro ,
K. Spahiu ,
T. Eriksen ,
U-B. Eklund  and
L.O. Werme
J. Bruno
Affiliation:
QuantiSci, Parc Tecnològic del Vallés, 08290 Cerdanyola (Spain). jbruno@quantisci.es
E. Cera
Affiliation:
QuantiSci, Parc Tecnològic del Vallés, 08290 Cerdanyola (Spain)
L. Duro
Affiliation:
QuantiSci, Parc Tecnològic del Vallés, 08290 Cerdanyola (Spain)
K. Spahiu
Affiliation:
Swedish Nuclear Fuel and Waste Management (SKB), Box 5864, S 102 48, Stockholm (Sweden)
T. Eriksen
Affiliation:
Dept. of Nuclear Chemistry, Royal Institute of Technology, S 100 44, Stockholm (Sweden)
U-B. Eklund
Affiliation:
Studsvik Nuclear AB S-611 82 Nykcping (Sweden)
L.O. Werme
Affiliation:
Swedish Nuclear Fuel and Waste Management (SKB), Box 5864, S 102 48, Stockholm (Sweden)
Get access

Abstract

A reductive capacity (RDC) kinetic model previously developed for the radiolitically induced oxidative dissolution of the spent fuel matrix has been applied to critical minor radionuclides present in spent fuel [1]. The model has been tested in front of experimental results from spent fuel corrosion obtained within the SKB programme. The experimental procedure is detailed in a previous publication [2]. The RDC model considers

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 506: Symposium – Scientific Basis for Nuclear Waste Management XXI , 1997 , 1021
Copyright
Copyright © Materials Research Society 1998

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 Bruno, J., Cera, E., Duro, L., Eriksen, T.E. and Werme, L.O.. J. Nucl. Mater. 238, 1 (1996)Google Scholar
2 Forsyth, R.S. and Werme, L.O.. J. Nucl. Mater. 189, 3 (1992)Google Scholar