Irradiation behavior of ground U(Mo) fuel with and without Si added to the matrix

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Irradiation behavior of ground U(Mo) fuel with and without Si added to the matrix. / Leenaers, Ann; Van den Berghe, Sven; Van Renterghem, Wouter; Charollais, Francois; Lemoine, Patrick; Jarousse, Christophe; Rohrmoser, Anton; Petry, Winfried.

In: Journal of Nuclear Materials, Vol. 412, No. 1, 04.2011, p. 41-52.

Research output: Contribution to journalArticlepeer-review

Harvard

Leenaers, A, Van den Berghe, S, Van Renterghem, W, Charollais, F, Lemoine, P, Jarousse, C, Rohrmoser, A & Petry, W 2011, 'Irradiation behavior of ground U(Mo) fuel with and without Si added to the matrix', Journal of Nuclear Materials, vol. 412, no. 1, pp. 41-52. https://doi.org/10.1016/j.jnucmat.2011.02.002

APA

Leenaers, A., Van den Berghe, S., Van Renterghem, W., Charollais, F., Lemoine, P., Jarousse, C., Rohrmoser, A., & Petry, W. (2011). Irradiation behavior of ground U(Mo) fuel with and without Si added to the matrix. Journal of Nuclear Materials, 412(1), 41-52. https://doi.org/10.1016/j.jnucmat.2011.02.002

Author

Leenaers, Ann ; Van den Berghe, Sven ; Van Renterghem, Wouter ; Charollais, Francois ; Lemoine, Patrick ; Jarousse, Christophe ; Rohrmoser, Anton ; Petry, Winfried. / Irradiation behavior of ground U(Mo) fuel with and without Si added to the matrix. In: Journal of Nuclear Materials. 2011 ; Vol. 412, No. 1. pp. 41-52.

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@article{3efb0ab1bece4babb4bd1bec9f0bd876,
title = "Irradiation behavior of ground U(Mo) fuel with and without Si added to the matrix",
abstract = "In the framework of the IRIS-TUM irradiation program, several full size, flat dispersion fuel plates containingground U(Mo) fuel kernels in an aluminum matrix, with and without addition of silicon (2.1 wt.%), have been irradiated in the OSIRIS reactor. The highest irradiated fuel plate (with an Al–Si matrix) reached a local maximum burnup of 88.3% 235U LEU-equivalent and showed a maximum thickness increase of 323 lm (66%) but remained intact. This paper reports the post irradiation examination results obtained on four IRIS-TUM plates. The evolution of the fission gas behavior in this fuel type from homogeneously dispersed nanobubbles to the eventual formation of large but apparently stable fission gas bubbles at the interface of the interaction layer and the fuel kernel is illustrated. It is also shown that the observed moderate, but positive effect of Si as inhibitor for the U(Mo)–Al interaction is related to the dispersion of this element in the interaction layer, although its concentration is very inhomogeneous and appears to be too low to fully inhibit interaction layer growth.",
keywords = "Ground MTR fuel, U(Mo), microstructure",
author = "Ann Leenaers and {Van den Berghe}, Sven and {Van Renterghem}, Wouter and Francois Charollais and Patrick Lemoine and Christophe Jarousse and Anton Rohrmoser and Winfried Petry",
note = "Score = 10",
year = "2011",
month = apr,
doi = "10.1016/j.jnucmat.2011.02.002",
language = "English",
volume = "412",
pages = "41--52",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",
number = "1",

}

RIS - Download

TY - JOUR

T1 - Irradiation behavior of ground U(Mo) fuel with and without Si added to the matrix

AU - Leenaers, Ann

AU - Van den Berghe, Sven

AU - Van Renterghem, Wouter

AU - Charollais, Francois

AU - Lemoine, Patrick

AU - Jarousse, Christophe

AU - Rohrmoser, Anton

AU - Petry, Winfried

N1 - Score = 10

PY - 2011/4

Y1 - 2011/4

N2 - In the framework of the IRIS-TUM irradiation program, several full size, flat dispersion fuel plates containingground U(Mo) fuel kernels in an aluminum matrix, with and without addition of silicon (2.1 wt.%), have been irradiated in the OSIRIS reactor. The highest irradiated fuel plate (with an Al–Si matrix) reached a local maximum burnup of 88.3% 235U LEU-equivalent and showed a maximum thickness increase of 323 lm (66%) but remained intact. This paper reports the post irradiation examination results obtained on four IRIS-TUM plates. The evolution of the fission gas behavior in this fuel type from homogeneously dispersed nanobubbles to the eventual formation of large but apparently stable fission gas bubbles at the interface of the interaction layer and the fuel kernel is illustrated. It is also shown that the observed moderate, but positive effect of Si as inhibitor for the U(Mo)–Al interaction is related to the dispersion of this element in the interaction layer, although its concentration is very inhomogeneous and appears to be too low to fully inhibit interaction layer growth.

AB - In the framework of the IRIS-TUM irradiation program, several full size, flat dispersion fuel plates containingground U(Mo) fuel kernels in an aluminum matrix, with and without addition of silicon (2.1 wt.%), have been irradiated in the OSIRIS reactor. The highest irradiated fuel plate (with an Al–Si matrix) reached a local maximum burnup of 88.3% 235U LEU-equivalent and showed a maximum thickness increase of 323 lm (66%) but remained intact. This paper reports the post irradiation examination results obtained on four IRIS-TUM plates. The evolution of the fission gas behavior in this fuel type from homogeneously dispersed nanobubbles to the eventual formation of large but apparently stable fission gas bubbles at the interface of the interaction layer and the fuel kernel is illustrated. It is also shown that the observed moderate, but positive effect of Si as inhibitor for the U(Mo)–Al interaction is related to the dispersion of this element in the interaction layer, although its concentration is very inhomogeneous and appears to be too low to fully inhibit interaction layer growth.

KW - Ground MTR fuel

KW - U(Mo)

KW - microstructure

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_113123

UR - http://knowledgecentre.sckcen.be/so2/bibref/7959

U2 - 10.1016/j.jnucmat.2011.02.002

DO - 10.1016/j.jnucmat.2011.02.002

M3 - Article

VL - 412

SP - 41

EP - 52

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

IS - 1

ER -

ID: 163282