Neutronic core calculations of Bushehr VVER-1000 reactor and investigating the control rod worth using MCNPX code

Authors

10.22052/4.2.45

Abstract

In this research, required information to simulate and perform neutronic calculations for Bushehr nuclear power plant using the MCNPX code was provided. The results of the code were verified with at least one of the operational data from the reactor. In this work, by writing and implementing a comprehensive program to solve the equations of statistical distribution, neutron flux was obtained and then various parameters including the infinite multiplication factor in terms of fluence were calculated and the control rod worth for Groups 9 and 10 were calculated at Hot Zero Power (HZP) state.

Keywords

References

[1] M. Rafiei Karahroudi, et al., Optimization of designing the core fuel loading pattern in a VVER-1000 nuclear power reactor using the genetic algorithm. Annals of Nuclear Energy 57 (2013) 142–150. [2] Preliminary Safety Analysis Report, (PSAR) of Nuclear Power Plant, Iran 1 and 2, Vol. 1 and 2, KWU (1976). [3] E.K. Lee, etal., New dynamic method to measure rod worth in zero power physics test at PWR startup. Annals of Nuclear Energy 32 (2005) 1457–1475. [4] F. Faghihi, et al., Reactivity coefficients simulation of the Iranian VVER-1000 nuclear reactor using WIMS and CITATION codes. Progress in Nuclear Energy 49 (2007) 68-78. [5] A.H. Fadaei, et al., Control rod worth calculation for VVER-1000 nuclear reactor using WIMS and CITATION codes. Progress in Nuclear Energy 51(1) (2009) 184-191. [6] Los Alamos National Laboratory, Monte Carlo N-Particle Transport Code. MCNPX User’s Manual. Version 2.4.0, LA-CP-02-408 (2002). [7] M.N. Nasrabadi, et al., Analysis of Self-Sustained Nuclear Fission Wave Evolution in a Fast Critical Reactor. Journal of computational methods in engineering, 33(1) (2014) 101-111. [8] Bushehr Nuclear Power Plant, Final Safety Analysis Report (FSAR), Technical Report, Chapter 4 (2003). [9] N. Taheranpour, et al., Development of practical method using a Monte Carlo code for evaluation of optimum fuel pitch in a typical VVER-1000 core. Annals of Nuclear Energy 54 (2013)129–133.

Files

Share

How to cite

Statistics