COMPARATIVE NEUTRONIC ANALYSIS OF IRT FUELS

Ramadan M.  Kuridan; Ayman M.  Dandi

doi:10.66411/jer.v7i7.413

Authors

Ramadan M. Kuridan Nuclear Engineering Department, Al-Fateh University, Tripoli, Libya Author
Ayman M. Dandi Nuclear Engineering Department, Al-Fateh University, Tripoli, Libya Author

DOI:

https://doi.org/10.66411/jer.v7i7.413

Keywords:

reactor, flux, enriched fuel, monte carlo, core, reactivity, power

Abstract

The Monte Carlo method is used for the comparison of the neutronic analysis of the IRT fuels. The effective multiplication factor (k eff ), excess reactivity, control worth, and shutdown margin are calculated and are found to be as in the following Table:

IRT-2M

IRT-4M

IRT-MR

k eff

1.20665

1.21190

1.23271

ρex (Δk / k %)

17.1

17.5

18.9

Total worth

26.81

24.05

21.54

ρsm (%)

9.7

6.6

2.6

Also, the radial, axial, horizontal (cross sectional) thermal and fast flux distributions are obtained. When the IRT-4M fuel is used the thermal flux is reduced significantly in the core and the beryllium reflector where the irradiation channels are located. This will have an adverse effect on the irradiation of samples which may require power increase as compared to the IRT-2M fuel. The power distribution horizontally and axially in the hottest tube and hence the hottest spot are determined. The power produced in the hottest tubes in the three cores are 0.69, 0.71, 0.72 Mega watts respectively. These results are basic for further thermal hydraulic and safety calculations.

References

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