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Volumen II - SAM

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element and/or impurities) for the calculation of equilibrium composition to anticipate oxygen profile<br />

evolution in the Zy-4 cladding tube.<br />

a) b)<br />

Fig. 7. Simulation of O diffusion profiles in αZr and βZr at 1200°C: a) α and β phases, b) blow-up of the β<br />

phase region<br />

Diffusion time prediction at 1200°C for ductile-brittle transition in Zy-4<br />

Experiments show that the brittle behaviour of Zr-alloys can be better correlated to the parameters of the<br />

ductile metallic phase (i.e. O-profile in phases, H- hydrides content) [1].<br />

In [1] the ductile-to-brittle temperature transition and the mechanical constitutive laws as a function of the<br />

oxygen content were described. Different experimental tests showed the existence of a ductile-to-brittle<br />

failure mode transition at 20°C for a critical oxygen concentration (around 0.4 wt. %~2.2 at.%).<br />

Simulations at 1200°C were performed in order to predict the diffusion time where the β-prior phase is<br />

completely brittle (and consequently the cladding tube). In Table 4 calculated information for Zy-4 at<br />

1200°C is presented. The thermodynamic and kinetic values used for the simulation are from this work.<br />

For temperatures T16.5 brittle<br />

4. CONCLUSIONS<br />

The coupling of the diffusion code “EKINOX” and the thermodynamics database “ZIRCOBASE was made<br />

via TQ interface.<br />

The simulation of the oxygen diffusion and the phase transformation β→α in a LOCA temperature-time<br />

range was performed.<br />

Diffusion parameters in [1100-1250]°C temperature range were obtained.<br />

Experimental oxygen diffusion information corroborated the diffusion simulations in [1100-1250]°C for<br />

different times.<br />

For Zy-4 steam oxidation at 1200°C the diffusion time for the ductile-brittle transition was predicted.<br />

REFERENCES<br />

1. J.C. Brachet et al., Journal of ASTM International, Vol. 5, No. 5, 2008, Paper ID JAI101116.<br />

2. X. Ma, C. Toffolon-Masclet, T. Guilbert, D. Hamon, J.C. Brachet, J.of Nuclear Mat. 377 (2008) 359–369.<br />

3. N. Bertrand et al., Materials Science Forum, 595-598, 2008, pp 463-472.<br />

4. J. Debuigne, PhD thesis, Paris University (1966), in French.<br />

5. C. Desgranges, PhD Thesis, Université Paris XI Orsay (1998).<br />

6. J.O. Andersson, T. Helander, L.H. Hoglund, P.F. Shi, B. Sundman, CALPHAD 26 (2002) 273.<br />

7. N. Dupin et al. J. Nucl. Mater. 275 (1999) 287.<br />

8. H.M. Chung, T.F. Kassner, J. Nucl. Mater. 84 (1979) 327.<br />

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