Zobrazeno 1 - 10
of 21
pro vyhledávání: '"C. Jarousse"'
Publikováno v:
Sciences, Eaux & Territoires, Iss Spécial Ingénieries-EAT-22 (2006)
La capacité de débit d'un géocomposite de drainage est intuitivement liée à son épaisseur, d'où l'importance de la maîtrise du fluage. Le fluage d'un géosynthétique est sa diminution d'épaisseur dans le temps, sous contrainte constante, en
Externí odkaz:
https://doaj.org/article/5fd56b87c64c42b8b8ab7864cf5380ae
Autor:
Daniel M. Wachs, Yeon Soo Kim, Y. Calzavara, P. Lemoine, D. Geslin, S. Van den Berghe, Gerard L. Hofman, H. Guyon, Dennis D. Keiser, E. Koonen, C. Jarousse, J. Van Eyken, Adam B. Robinson, F. Charollais, Ann Leenaers
Publikováno v:
Journal of Nuclear Materials. 441:439-448
Several irradiation experiments have confirmed the positive effect of adding Si to the matrix of an U(Mo) dispersion fuel plate on its in-pile irradiation behavior. E-FUTURE, the first experiment of the LEONIDAS program, was performed to select an op
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d52dae210b4168b02dc26a2a9d759b8b
https://doi.org/10.1016/j.jnucmat.2013.06.027
https://doi.org/10.1016/j.jnucmat.2013.06.027
Autor:
C. Bertrand-Drira, C. Jarousse, Hervé Palancher, Bertrand Stepnik, Xavière Iltis, Anne Bonnin, Wolfgang W. Schmahl, R. Jungwirth, Camelia N. Borca, Winfried Petry, Veijo Honkimäki, Sohyun Park
Publikováno v:
Journal of Nuclear Materials. 438:246-260
UMo-Al based fuel plates prepared with ground U8wt%Mo, ground U8wt%MoX (X = 1 wt%Pt, 1 wt%Ti, 1.5 wt%Nb or 3 wt%Nb) and atomized U7wt%Mo have been examined. The first finding is that that during the fuel plate production the metastable γ-UMo phases
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fe74c1a1cdfa8320fd124ee784db9d27
https://doi.org/10.1016/j.jnucmat.2013.03.021
https://doi.org/10.1016/j.jnucmat.2013.03.021
Autor:
Gerard L. Hofman, Daniel M. Wachs, F. Charollais, Yeon Soo Kim, J. Stevens, Adam B. Robinson, Y. Parthoens, C. Jarousse, P. Lemoine, Ann Leenaers, H. Guyon, S. Van den Berghe, V. Kuzminov, E. Koonen, Dennis D. Keiser
Publikováno v:
Journal of Nuclear Materials. 430:246-258
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::738151cf5a83d36984067ba7d55788e7
https://doi.org/10.1016/j.jnucmat.2012.06.045
https://doi.org/10.1016/j.jnucmat.2012.06.045
Autor:
W. Van Renterghem, P. Lemoine, F. Charollais, S. Van den Berghe, Winfried Petry, C. Jarousse, Ann Leenaers, A. Röhrmoser
Publikováno v:
Journal of Nuclear Materials. 412:41-52
In the framework of the IRIS-TUM irradiation program, several full size, flat dispersion fuel plates containing ground U(Mo) fuel kernels in an aluminum matrix, with and without addition of silicon (2.1 wt.%), have been irradiated in the OSIRIS react
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::092f2a56d446c37aaaf2aa46841513f2
https://doi.org/10.1016/j.jnucmat.2011.02.002
https://doi.org/10.1016/j.jnucmat.2011.02.002
Autor:
N. Wieschalla, H. Breitkreutz, L. Beck, Winfried Petry, W. Schmid, C Jarousse, J. Schneider, R.M. Hengstler, R. Jungwirth
Publikováno v:
Journal of Nuclear Materials. 402:74-80
As a possible high density fuel for research reactors, monolithic U8 wt.%–Mo (“U8Mo”) was examined with regard to its structural, thermal and electric properties. X-ray diffraction by the Bragg-Brentano method was used to reveal the tetragonal
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c9ac26f1a2890861ad8d35e085934455
https://doi.org/10.1016/j.jnucmat.2010.04.024
https://doi.org/10.1016/j.jnucmat.2010.04.024
Autor:
M. Trotabas, E. Koonen, L. Sannen, C. Jarousse, Ann Leenaers, Marc Verwerft, F. Huet, S. Guillot, M. Boyard, S. Van den Berghe
Publikováno v:
Journal of Nuclear Materials. 335:39-47
Two low-enriched uranium fuel plates consisting of U–7wt%Mo atomized powder dispersed in an aluminum matrix, have been irradiated in the FUTURE irradiation rig of the BR2 reactor at SCK•CEN. The plates were submitted to a heat flux of maximum 353
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::034f6f7b3f51de2308c443ac5757e570
https://doi.org/10.1016/j.jnucmat.2004.07.004
https://doi.org/10.1016/j.jnucmat.2004.07.004
Autor:
E. Koonen, A Ballagny, L. Sannen, B Guigon, S. Van den Berghe, P Jacquet, C. Jarousse, Ann Leenaers
Publikováno v:
Journal of Nuclear Materials. 327:121-129
In order to gain insight on the performance limits of U 3 Si 2 fuel with Al cladding, fuel plates with a fissile material density of 5.1 and 6.1 g U/cm 3 were irradiated in the BR2 reactor of SCK • CEN in Mol. The plates were intended to be subject
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6c94f9e161f30a3c4c3a04465ce0527f
https://doi.org/10.1016/j.jnucmat.2004.01.025
https://doi.org/10.1016/j.jnucmat.2004.01.025
Publikováno v:
Revue Générale Nucléaire. :36-41
Historiquement, la plupart des reacteurs experimentaux, en particulier les Reacteurs de Test et de Recherche, producteurs de hauts flux neutroniques, ont utilise du combustible metallique a haut enrichissement en U235 (>90%). La politique actuelle es
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cd5d1de3cae8f1662aa7609b5403e032
https://doi.org/10.1051/rgn/20023036
https://doi.org/10.1051/rgn/20023036
Autor:
R, Vaillant, C, Jarousse
Publikováno v:
Comptes rendus hebdomadaires des seances de l'Academie des sciences. Serie D: Sciences naturelles. 278(13)
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=pmid________::3db1dbcda4fed29568a9f9212db05ce4
https://pubmed.ncbi.nlm.nih.gov/4211388
https://pubmed.ncbi.nlm.nih.gov/4211388