Vol. XXIII, No. 1, Pp. 1-62
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Authors: Foudil Zeggar, Amrane Halilou, Brahim Meftah, Mohamed Y. Mokeddem, Fathi Letaim, Anis Bousbia-Salah
In this article, we present the results of a few energy groups calculations for the NUR reactor fuel depletion analysis up to 45 000 MWd/tU taken as the maximum fuel burn up. The WIMSD-4 cell code has been employed as a calculation tool. In this study, we are interested in actinides such as the uranium and plutonium isotopes, as well as fission products Xe-135, Sm-149, Sm-151, Eu-155, and Gd-157.
Calculation results regarding the five energy groups are in a good agreement with those obtained with only two energy groups which can, therefore, be used in all subsequent calculations. Calculation results presented in this article can be used as a microscopic data base for estimating the amount of radioactive sources randomly dispersed in the environment. They can also be used to monitor the fuel assemblies inventory at the core level.
Key words: MTR-LEU fuel, burn up, NUR reactor, WIMSD-4
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