2017
DOI: 10.1016/j.anucene.2017.01.012
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Testing the new stochastic neutronic code ANET in simulating safety important parameters

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Cited by 3 publications
(3 citation statements)
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“…Regarding the simulation of neutron flux and reaction rates, the collision and the track-length estimators are implemented in ANET following the standard MC procedure. In addition, the ANET code has been successfully validated for its capability to reliably predict basic parameters of critical and subcritical reactor systems, namely the multiplication factor, neutron fluxes as well as neutron reaction rates, using international benchmarks and data from various installations [12].…”
Section: The Anet Codementioning
confidence: 99%
See 1 more Smart Citation
“…Regarding the simulation of neutron flux and reaction rates, the collision and the track-length estimators are implemented in ANET following the standard MC procedure. In addition, the ANET code has been successfully validated for its capability to reliably predict basic parameters of critical and subcritical reactor systems, namely the multiplication factor, neutron fluxes as well as neutron reaction rates, using international benchmarks and data from various installations [12].…”
Section: The Anet Codementioning
confidence: 99%
“…At a first stage, the GEANT3.21 capability to be applied on nuclear reactor analysis was sought through the expansion of the treated energy spectrum to lower energies, so as to include the part involved in neutronics analysis and also through the incorporation of fission reactions [10] [11]. In the current ANET version, a bulk of subroutines has been incorporated so that the computation of the neutron multiplication factor, the neutron flux and the reaction rates are treated strictly with the stochastic approach using the standard MC estimators [12]. ANET code is continuously developing targeting at an enhanced MC code which will be also capable of performing core isotopic evolution calculations for conventional and innovative reactors, being at the same time prepared to be coupled with thermal-hydraulic solvers.…”
Section: Introductionmentioning
confidence: 99%
“…The neutronics interactions included currently in ANET are elastic collision, capture and fission while pointwise cross-section data from JEFF li- The standard Monte Carlo approach is followed for all the estimators concerning the neutron multiplication factor (k eff ) calculation, the neutron flux and the reaction rates. During ANET's development, several tests using international benchmarks and data from various installations have been performed in order to validate its capability for reliable calculations of basic parameters of critical and subcritical reactor systems including ADSs, such as the multiplication factor, neutron fluxes as well as neutron reaction rates [14]. In addition, ANET code is continuously developing targeting at an enhanced Monte Carlo code which will be also capable of performing core isotopic evolution calculations for conventional and innovative reactors, being at the same time prepared to be coupled with thermal-hydraulic solvers.…”
Section: Introductionmentioning
confidence: 99%