Study of the fuel combustion of MTR-22MW reactor using the GETERA and MCNP5 Codes

In this study, a simulation of the MTR-22MW reactor and a study of standard and mixed fuel combustion using the Codes GETERA and MCNP5. The Results of the simulation showed that the operation time of the reactor in the case of standard fuel is 274 days and if the use of mixed fuel is 135 days.

Calculation of the effective multiplication factor, neutron flux and power distribution for ETRR-2 Egyptian Second research reactor using MCNP4C2 code

The MCNP4C2 Monte Carlo code was used to model the Egyptian Second research reactor in this paper, to calculate the effective multiplication factor keff, distribution of the thermal and fast neutron fluxes and power in reactor core with two type of fuels: standard and mixed. The values of the keff were 1.21842 and 1.05272, the maximum thermal flux were 2.975x10+14 and 3.352x10+14 n/cm2s, and the maximum fast flux was 2.950x10+14 and 2.389x10+14 n/cm2s for standard and mixed fuels respectively. The results showed good agreements with previous results available in the literature.

Calculation of the effective multiplication factor of the highly safe new generation VVER- 640 type reactor

Nuclear reactors depend on nuclear fission phenomenon in their work. The effective multiplication factor depends on the number of neutrons in two successive generations and it usually controled in the reactor by using control rods. In this paper، calculations of the effective multiplication factor for the highly safe new generation VVER- 640 type reactor is conducted in two methods: analytic method using the Mathcad program and the GETERA code. The effective multiplication factor for the first method was 1.3430 and it was 1.3477 using the GETERA cod. Good agreement was noticed between the two methods.