MOX fuel enrichment prediction in PWR using polynomial models

作者：Mouginot B^*; Leniau B; Thiolliere N; Bidaud A; Courtin F; Doligez X; Ernoult M

来源：Annals of Nuclear Energy, 2015, 85: 812-819.

DOI：10.1016/j.anucene.2015.06.038

• PWR MOX
• Nuclear fuel fabrication
• Model
• Fuel cycle

A dynamic fuel cycle simulation code models all the ingoing and outgoing material flow in all facilities of a nuclear reactor's fleet as well as their evolutions through the different nuclear processes (irradiation, decay, chemical separation, etc.). One of the main difficulties encountered when performing such calculation comes from the fuel fabrication of reprocessed fuel such as MOX fuel. Indeed, the MOX fuel is fabricated using a plutonium base completed with depleted uranium. The amount of plutonium in the fuel will directly impact the neutron multiplication factor and its evolution through irradiation, so the duration to keep the fuel in the reactor. The present paper presents the study of different PWR MOX fuel fabrication polynomial models. Those models will allow the prediction of the amount of plutonium needed to reach a wanted burnup from the plutonium isotopics. After defining a method to generate a training sample, that is to say the set of fuel depletion calculations used to fit the polynomial models, this papers will discuss their performances on 3 different applications. On the two tested models, one linear and one quadratic, while the linear model fail to properly describe the amount of plutonium needed, the fuel fabricated, using the quadratic one, reaches the wanted burnup with a discrepancy below 2%.

• 出版日期2015-11