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Title: Swelling of U(Mo)–Al(Si) dispersion fuel under irradiation – Non-destructive analyses of the LEONIDAS E-FUTURE plates

Abstract

In the framework of the elimination of High-Enriched Uranium (HEU) from the civil circuit, the search for an appropriate fuel to replace the high-enriched research reactor fuel in those reactors that currently still require it for their operation has led to the development of a U–7 wt.%Mo alloy based dispersion fuel with an Al–Si matrix. The European LEONIDAS program, joining SCK-CEN, ILL, CEA and AREVA-CERCA, is aimed at the qualification of such a fuel for the use in high power conditions. The first experiment of the program, designated E-FUTURE, was performed to select the appropriate matrix Si concentration and fuel plate post-production heat treatment parameters for further qualification. It consisted of the irradiation of four distinct (4% and 6% Si, 3 different heat treatments) full size, flat fuel plates in the BR2 reactor. The irradiation conditions were relatively severe: 470 W/cm2 peak BOL power, with an approximate 70% 235U peak burnup.

Authors:
; ; ; ; ; ; ; ; ; ; ; ; ; ;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
USDOE
OSTI Identifier:
1062187
Report Number(s):
INL/JOU-13-28287
Journal ID: ISSN 0022-3115
DOE Contract Number:  
DE-AC07-05ID14517
Resource Type:
Journal Article
Resource Relation:
Journal Name: Journal of Nuclear Materials; Journal Volume: 430; Journal Issue: 1-3
Country of Publication:
United States
Language:
English
Subject:
99 GENERAL AND MISCELLANEOUS; disperson fuel; LEONIDAS E-FUTURE Plates

Citation Formats

S. Van den Berghe, Y. Parthoens, F. Charollais, Y. S. Kim, A. Leenaers, E. Koonen, V. Kuzminov, P. Lemoine, C. Jarousse, H. Guyon, D. Wachs, D. Keiser, Jr., A. Robinson, J. Stevens, and G. Hofman. Swelling of U(Mo)–Al(Si) dispersion fuel under irradiation – Non-destructive analyses of the LEONIDAS E-FUTURE plates. United States: N. p., 2012. Web. doi:10.1016/j.jnucmat.2012.06.045.
S. Van den Berghe, Y. Parthoens, F. Charollais, Y. S. Kim, A. Leenaers, E. Koonen, V. Kuzminov, P. Lemoine, C. Jarousse, H. Guyon, D. Wachs, D. Keiser, Jr., A. Robinson, J. Stevens, & G. Hofman. Swelling of U(Mo)–Al(Si) dispersion fuel under irradiation – Non-destructive analyses of the LEONIDAS E-FUTURE plates. United States. doi:10.1016/j.jnucmat.2012.06.045.
S. Van den Berghe, Y. Parthoens, F. Charollais, Y. S. Kim, A. Leenaers, E. Koonen, V. Kuzminov, P. Lemoine, C. Jarousse, H. Guyon, D. Wachs, D. Keiser, Jr., A. Robinson, J. Stevens, and G. Hofman. Thu . "Swelling of U(Mo)–Al(Si) dispersion fuel under irradiation – Non-destructive analyses of the LEONIDAS E-FUTURE plates". United States. doi:10.1016/j.jnucmat.2012.06.045.
@article{osti_1062187,
title = {Swelling of U(Mo)–Al(Si) dispersion fuel under irradiation – Non-destructive analyses of the LEONIDAS E-FUTURE plates},
author = {S. Van den Berghe and Y. Parthoens and F. Charollais and Y. S. Kim and A. Leenaers and E. Koonen and V. Kuzminov and P. Lemoine and C. Jarousse and H. Guyon and D. Wachs and D. Keiser, Jr. and A. Robinson and J. Stevens and G. Hofman},
abstractNote = {In the framework of the elimination of High-Enriched Uranium (HEU) from the civil circuit, the search for an appropriate fuel to replace the high-enriched research reactor fuel in those reactors that currently still require it for their operation has led to the development of a U–7 wt.%Mo alloy based dispersion fuel with an Al–Si matrix. The European LEONIDAS program, joining SCK-CEN, ILL, CEA and AREVA-CERCA, is aimed at the qualification of such a fuel for the use in high power conditions. The first experiment of the program, designated E-FUTURE, was performed to select the appropriate matrix Si concentration and fuel plate post-production heat treatment parameters for further qualification. It consisted of the irradiation of four distinct (4% and 6% Si, 3 different heat treatments) full size, flat fuel plates in the BR2 reactor. The irradiation conditions were relatively severe: 470 W/cm2 peak BOL power, with an approximate 70% 235U peak burnup.},
doi = {10.1016/j.jnucmat.2012.06.045},
journal = {Journal of Nuclear Materials},
number = 1-3,
volume = 430,
place = {United States},
year = {Thu Nov 01 00:00:00 EDT 2012},
month = {Thu Nov 01 00:00:00 EDT 2012}
}