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The boundary conditions for the reconstruction of the Boron clouds, injected in the moderator tank by the shut-down emergency system, were derived by previously executed Computational Fluid-dynamics CFD analyses by the CFX code [ 2 ]. Further development of these models consider 10 levels of axial discretization to take into account the axial differences in temperature and density. The last two applications were relevant for performing successive three dimensional neutron kinetic analyses since it was necessary to correctly evaluate the effect of each oblique control rod in each cell discretizing the reactor. This is an open access article distributed under the Creative Commons Attribution License , which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited. After the definition of a relevant core status with fuel at the burnup equilibrium, a set of neutron cross section libraries were calculated by the lattice physics code HELIOS.

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All these data were used as a boundary and initial conditions BICs for the steady state and transients calculations. The geometrical complexity and the peculiarities of Atucha-2 PHWR require the adoption of advanced Monte Carlo codes for performing realistic neutronic simulations. These model were successfully used for CZP criticality calculation. Finally, further applications of these models are envisaged in the near future e.

The effects of initial source distribution and of different continuous energy e. Placzek, Introduction to the Theory of Neutron Diffusionvol. Power control is achieved by changing the moderator temperature by an external cooling circuit, and by the use of 12 of the 18 oblique control rods. Results with low variance were obtained running about million of active neutron histories.

Cmnp5 the definition of a relevant core status with fuel at the burnup equilibrium, a set of neutron cross section libraries were calculated by the lattice physics code HELIOS. Subscribe to Table of Contents Alerts.

The complex Atucha-2 geometrical design required the adoption of advanced 3D Monte Carlo calculations. The results obtained by the Monte Carlo codes i.

Development and Application of MCNP5 and KENO-VI Monte Carlo Models for the Atucha-2 PHWR Analysis

The 3D effects seem negligible when considering the fast absorption cross section for the gray CRs. To receive news and publication updates for Science and Technology of Nuclear Installations, enter your email address in the box below.

In order to get a low variance on each flux i.

Moreover, million of neutron histories were employed to minimize statistical fluctuations. Thus, the effects of possible insertion modes of the CR on the macroscopic cross sections were evaluated. Therefore, in order to calculate appropriate CR weighting factors, several cases of intersection had to be identified and the relative cell CR volumes calculated. The CR volume to be measured was enclosed in a sphere, and an inward spherical distribution of neutron particles was employed for flooding the objects, that is, the CR and the intersected hexagonal mfnp5.

Abstract The geometrical complexity and the peculiarities of Atucha-2 PHWR require the adoption of advanced Monte Carlo codes for performing realistic neutronic simulations.

The mcbp5 conditions for the reconstruction of the Boron clouds, injected in the moderator tank by the shut-down emergency system, were derived by previously executed Computational Fluid-dynamics CFD analyses by the CFX code [ 2 ]. A flux tally got the resulting volume calculation see Figure 8.

MCNP5 for proton radiography.

Reactor power W and void fraction in central and hot channel. In Table 1 is reported the results of sensitivity of Boron concentration in the case of all rod inserted ARIthen in Figures 5 and 6 the flux distribution is given. These corrective factors were then applied to the mfnp5 cross sections calculated by the two-dimensional deterministic lattice physics code HELIOS.

The transient is initiated by the instantaneous opening i. Atucha-2 has two types of CR, differing by the absorber material hafnium and stainless steel. Science and Mmcnp5 of Nuclear Installations. Instead, during some accidental conditions, a fully independent shut-down system the JDJ allows the fast injection of a highly concentrated Boron solution in the moderator tank [ 1 ]. This is an open access article distributed under the Creative Commons Attribution Licensewhich permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

The mcno5 of the emergency Boron injection system and CRs insert enough negative reactivity see Figure 12 to quench the mcn5 excursion. The last two applications were relevant for performing successive three dimensional neutron kinetic analyses since it was necessary to correctly evaluate the effect of each oblique control rod in each cell discretizing the reactor. The geometrical complexity of this design e.

Several cases were simulated to investigate the effects of control rod insertion, different Boron concentration, flux distribution, and beta delayed factors. Further development of these models consider 10 levels of axial discretization to take into account the axial differences in temperature and density.