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exotic nuclei structure and reaction noyaux exotiques ... - IPN - IN2P3

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measurements. We can also control the density<br />

ranging from 3.5 g.cm -3 to 13.2 g.cm -3 (25% to 97%<br />

of the theoretical density of UC, determined by<br />

helium pycnometry).<br />

Work in progress <strong>and</strong> perspectives<br />

The control of the grain size ranging from 1 to 30<br />

µm (measured by Scanning Electron Microscope)<br />

<strong>and</strong> also the control of the size <strong>and</strong> the distribution<br />

of the pore size (measured by mercury porosimetry)<br />

are in progress. The temperature <strong>and</strong><br />

the duration of the plateau are the parameters to<br />

be studied. The kinetic of the closing of the pores<br />

<strong>and</strong> the evolution of the mechanical strength of the<br />

pellet during long term operation will also be studied.<br />

The identification of the irradiation damages<br />

will be undertaken. In the case of the use as a target,<br />

measurement of diffusion/effusion of the fission<br />

products by irradiation <strong>and</strong> gamma-ray measurements<br />

will be performed in order to qualify the<br />

target. A 3D modelling will be developed to define<br />

the best structural characteristics for an “ideal” material<br />

for radioactive isotopes beam production.<br />

The material must have the maximum density for<br />

fission production yield <strong>and</strong> also a maximum release<br />

of fission products through the porous network.<br />

These two requirements are antagonist. But<br />

an optimum does exist for porosity, pore diameter<br />

<strong>and</strong> length <strong>and</strong> pore distribution in the matrix.<br />

We will also take back our reprocessing studies in<br />

order to determine the kinetic of dissolution in corrosive<br />

media.<br />

References<br />

[1] A vision report Towards a European Strategic<br />

Energy Technology Plan, COM, 847 (2006)<br />

[2] OAK RIDGE NATIONAL LABORATORY, The<br />

Gas Fast Reactor (GFR) Survey of Materials Experience<br />

<strong>and</strong> R&D Needs to Assess Viability, rapport<br />

ORNL/TM-2004/99, (april 2004)<br />

[3] The Sustainable Nuclear EnergyTechnology<br />

Platform - SPECIAL REPO RT (2007)<br />

www.snetp.eu<br />

[4] Sladkov V. <strong>and</strong> Fourest B., Journal of Chromatography<br />

A, 1216 (2009) 2605–2608<br />

[5] J.F.A. Hennecke et al., J. Nucl. Mater., 38, 285<br />

(1971)<br />

[6] S.K. Mukerjee et al., J. Nucl. Mater. 210, 107<br />

(1994)<br />

[7] T.W. Knights et al., J. Nucl. Mater. 306, 54<br />

(2002)<br />

[8] S. Gossé et al., J. Nucl. Mater. 352, 13 (2006)<br />

[9] C.A. Utton et al., J. Nucl. Mater. 385, 443<br />

(2009)<br />

[10] D.J. Clough, J. Nucl. Mater. 56, 279 (1975)<br />

[11] J.P. Green et al., NIMB 241, 986 (2005)<br />

[12] V.N. Panteleev et al., NIMB 240, 888 (2005)<br />

[13] J.W. Harrison, J. Nucl. Mater. 30, 319 (1969)<br />

[14] T. Iwai et al., J. Nucl. Sc. <strong>and</strong> Tech. 25, 456<br />

(1988)<br />

[15] G. Bart et al., J. Nucl. Mater. 376, 47 (2008)<br />

125

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