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RRFM 2009 Transactions - European Nuclear Society

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It has been proposed that the efficiency of the “thermal rods” along the fission fragment<br />

tracks is greatly reduced in high conductivity fuels [8]. The thermal-mechanical effect of the<br />

“thermal rods” on the defect structure that controls creep is therefore more pronounced in<br />

UO 2 .<br />

The most important conclusion of the present study is that the fission enhanced creep rate of<br />

U-10Mo provides for a crucial stress relaxation mechanism. Without this, the isotropic<br />

swelling of the fuel would result in large lateral stresses in the thin fuel plates, and could lead<br />

to buckling of the plates when restrained in a fuel element.<br />

Another outcome of the present analysis is a revision of the U-Mo swelling correlation. Many<br />

of the high fission density data were obtained from fuel plate thickness measurements taken<br />

in areas of the plates where fuel relocation by creep had occurred. A new correlation shown<br />

in Fig. 8 was developed by selecting swelling data from areas in the plates that were not<br />

affected by lateral creep.<br />

(ΔV/ V 0 ) f<br />

(%)<br />

100<br />

80<br />

60<br />

40<br />

Open symbols: literature data<br />

RERTR-6 (monolithic)<br />

RERTR-7 (monolithic)<br />

RERTR-9 (monolithic)<br />

2002 model-dispersion plate data [10]<br />

2007 model-high BU monolithic plate data [11]<br />

<strong>2009</strong> model-monolithic plate center on metallographs<br />

Recrystalization<br />

begins<br />

20<br />

SFP=3.5%/10 21 f/cm 3<br />

0<br />

0 2 4 6 8<br />

Fission density (10 21 f/cm 3 )<br />

Fig. 8 Comparison of fuel swelling correlations with measured data.<br />

4. References<br />

[1] S.T. Konobeevsky, N.E. Pravdyuk, V.I. Kutaitsev, UN Int’l Conf. Peaceful Use of<br />

Atomic Energy, Geneva, Switzerland, Paper no. 681, 1955.<br />

[2] A.C. Roberts, A.H. Cottrell, Phil. Mag., 1, 711, 1956.<br />

[3] A.S. Zaimovsky, UN Int’l Conf. Peaceful Use of Atomic Energy, 1958.<br />

[4] M. Hesketh, Discussion in paper: M. Englander, C. T. Montpreville, 11th Colloque de<br />

Metallurgie, Creep, June 1967, p.28, Centre D’Etudes Nucleaires de Saclay, 1968.<br />

[5] W. Dienst, J. Nucl. Mater., 65, 1, 1977.<br />

[6] A.A. Solomon, J. Am. Ceram. Soc., 56, 164, 1973.<br />

[7] D.J. Clough, J. Nucl. Mater., 65, 24, 1977.<br />

[8] D. Brucklacher, W. Dienst, Am. Ceram. Soc., Anaheim, California, USA, Nov. 1971.<br />

[9] P. Zeisser, G. Maraniello, P. Combette, J. Nucl. Mater., 65, 48, 1977.<br />

[10] S.L. Hayes, G.L. Hofman, M.K. Meyer, J. Rest, J.L. Snelgrove, RERTR Meeting,<br />

2002.<br />

[11] Y.S. Kim, G.L. Hofman, P. Medvedev, G. Shevlyakov, A.B. Robinson, H.J. Ryu,<br />

RERTR Meeting, 2007.<br />

165 of 455

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