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Structural integrity of hydrided nuclear fuel cladding

Published online by Cambridge University Press:  27 March 2012

Jesús Ruiz-Hervías ,
F. Javier Gomez ,
Miguel A. Martín-Rengel  and
Elena Torres
Jesús Ruiz-Hervías
Affiliation:
Departamento de Ciencia de Materiales, UPM, E.T.S.I. Caminos, Canales y Puertos. Profesor Aranguren s/n, E-28040 Madrid, Spain
F. Javier Gomez
Affiliation:
Advanced Material Simulation, S.L. Isabel Collbrand, 6. E-28050 Madrid, Spain
Miguel A. Martín-Rengel
Affiliation:
Departamento de Ciencia de Materiales, UPM, E.T.S.I. Caminos, Canales y Puertos. Profesor Aranguren s/n, E-28040 Madrid, Spain
Elena Torres
Affiliation:
Consejo de Seguridad Nuclear (CSN). Justo Dorado 11, E-28040 Madrid, Spain
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Abstract

The structural integrity of nuclear fuel cladding is affected by the precipitation of hydrides during operation, which may embrittle the cladding. The aim of this work is to obtain the mechanical and fracture properties of the cladding as a function of the hydrogen content and testing temperature. To this end, the embrittlement caused by circumferential hydrides was simulated on unirradiated fuel cladding samples in the laboratory. The structural integrity of the cladding was assessed at different temperatures (20, 135 and 300ºC), by using the ring compression test. The mechanical properties and the fracture energy were calculated from the experimental load vs. displacement curves, by means of a finite element model which incorporates the cohesive crack model.

Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1475: Symposium NW – Scientific Basis for Nuclear Waste Management XXXV , 2012 , imrc11-1475-nw35-o56
Copyright
Copyright © Materials Research Society 2012

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References

REFERENCES

1. Grange, M., Fragilisation du zircaloy-4 par l’hydrogen: Comportament, mécanismes déndommagement, interaction avec la couche d’oxide, simulation numérique, École des Mines de Paris, Paris, 1998.Google Scholar
2. Sabol, G.P., ZIRLOTM- An Alloy Development Success, J. ASTM Intern. 2 (2005) Paper ID JAI12942.Google Scholar
3. Ruiz-Hervias, J., Martin-Rengel, M.A., Gomez, F.J., Caballero, L., Valiente, A., Mechanical behaviour of hydrogen-charged PWR cladding samples: experimental and numerical characterization, 2008 Water Reactor Fuel Performance Meeting, Seoul, Korea, 2008, Paper 8092 Google Scholar
4. Martin-Rengel, M.A., Gómez, F.J., Ruiz-Hervias, J., Caballero, L., Valiente, A., Obtention of fracture properties of unirradiated hydrogen-charged fuel cladding from ring compression tests, Top Fuel 2009, Paris, France, 2009, p. Paper 2112.Google Scholar
5. Martín-Rengel, M.A., Gómez, F.J., Ruiz-Hervias, J., Valiente, A., New method to calculate the mechanical properties of unirradiated hydrogen-charged fuel cladding from ring tensile tests, Water Reactor Fuel Performance Meeting, Paris, France, 2009, p. Paper n. 2111.Google Scholar
6. ADJUSTSE. Numerical code. F.J. Gómez, Advanced Material Simulation, S.L. 2011.Google Scholar
7. Gómez, F.J., Martin-Rengel, M.A. and Ruiz-Hervias, J.. A new procedure to determine the stress strain curve from ring compression tests. In press 2012 Google Scholar
8. BUCLECD Numerical code. F.J. Gómez, Advanced Material Simulation, S.L. 2011.Google Scholar
9. Gómez, F.J., Martin-Rengel, M.A. and Ruiz-Hervias, J.. A non linear optimization procedure to obtained fracture parameters from a ring compression tests. In press 2012 Google Scholar