Title of article :
Swelling of U(Mo) dispersion fuel under irradiation – Non-destructive analyses of the SELENIUM plates
Author/Authors :
Van den Berghe، نويسنده , , S. and Parthoens، نويسنده , , Y. and Cornelis، نويسنده , , G. and Leenaers، نويسنده , , A. and Koonen، نويسنده , , E. and Kuzminov، نويسنده , , V. and Detavernier، نويسنده , , C.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2013
Abstract :
Extensive fuel-matrix interactions leading to plate pillowing have caused a severe impediment on the development of a suitable high density low-enriched uranium dispersion fuel for high power applications in research reactors. Surface engineering of the U(Mo) kernel surfaces, where the interaction occurs, is put forward by SCK⋅CEN as a possible solution in the Surface Engineering of Low ENrIched Uranium Molybdenum fuel (SELENIUM) program. The project involved the construction of a sputter coater, the coating of U(Mo) kernels, the production of fuel plates, the irradiation and post-irradiation examination of 2 plates. The irradiation of 2 distinct (600 nm Si and 1000 nm ZrN coated) full size, flat fuel plates was performed in the BR2 reactor in 2012. The irradiation conditions were: 470 W/cm2 peak Beginning Of Life (BOL) power, with a ∼70% 235U peak burnup. The plates were successfully irradiated and did not show any pillowing at the end of the irradiation.
aper reports the results and interpretation of the non-destructive post-irradiation examinations that were performed on these fuel plates and derives a law for the fuel swelling evolution with burnup for this fuel type. It further reports additional PIE results obtained on fuel plates irradiated in campaigns in the past in order to allow a complete comparison with all results obtained under similar conditions. The fuel swelling is shown to evolve linearly with the fission density, with an increase in swelling rate around 2.5 × 1021 f/cm3, which is associated with the restructuring of the fuel. A further increase in swelling rate is observed at the highest burnups, which is discussed in this article.
Journal title :
Journal of Nuclear Materials
Journal title :
Journal of Nuclear Materials