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Reduced Basis Approaches in Time-Dependent Non-Coercive Settings for Modelling the Movement of Nuclear Reactor Control Rods

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Communications in Computational Physics 2016年第6期20卷 23-59页

作者： Alberto Sartori Antonio Cammi Lelio Luzzi Gianluigi Rozza Politecnico di Milano–Department of Energy CeSNEFEnrico Fermi Center for Nuclear Studiesvia La Masa 3420156MilanoItaly SISSA International School for Advanced StudiesMathematics Area–mathLabVia Bonomea 26534136 TriesteItaly.

In this work,two approaches,based on the certified Reduced Basis method,have been developed for simulating the movement of nuclear reactor control rods,in time-dependent non-coercive settings featuring a 3D geometrical *** particular,in a first approach,a piece-wise affine transformation based on subdomains division has been implemented for modelling the movement of one control *** the second approach,a“staircase”strategy has been adopted for simulating themovement of all the three rods featured by the nuclear reactor chosen as case *** neutron kinetics has been modelled according to the so-called multi-group neutron diffusion,which,in the present case,is a set of ten coupled parametrized parabolic equations(two energy groups for the neutron flux,and eight for the precursors).Both the reduced order models,developed according to the two approaches,provided a very good accuracy comparedwith high-fidelity results,assumed as“truth”*** the same time,the computational speed-up in the Online phase,with respect to the fine“truth”finite element discretization,achievable by both the proposed approaches is at least of three orders of magnitude,allowing a real-time simulation of the rod movement and control.

关键词： Reduced basis method control rod movement spatial kinetics parametrized geometry multi-group neutron diffusion non-coercive operators

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Numerical Analysis for Transients in External Source Driven Reactors

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World Journal of Nuclear Science and Technology 2017年第2期7卷 103-120页

作者： Willian Vieira de Abreu Alessandro da Cruz Goncalves Zelmo Rodrigues de Lima Nuclear Engineering Institute National Commission for Nuclear EnergyRio de JaneiroBrazil Nuclear Engineering Program COPPEFederal University of Rio de Janeiro/UFRJRio de JaneiroBrazil

The main purpose of this paper is to perform a numerical analysis of the Neutron spatial Kinetic Equations, subject to transients of the External Neutron Source, by applying the Implicit Euler Method as well as the Runge-Kutta Method in order to check which methods are best applicable in transients caused by External Neutron Source. For this purpose, a one-dimensional ADS reactor with a constant external source was simulated based on the geometry of ANL-BSS-6 reactor for benchmark effects.

关键词： ADS Transients spatial kinetics

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