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**Harvard**

Demazière, C. (2004) *Development of a 2-D 2-group neutron noise simulator*. : External organization

** BibTeX **

@article{

Demazière2004,

author={Demazière, Christophe},

title={Development of a 2-D 2-group neutron noise simulator},

journal={Annals of Nuclear Energy},

issn={0306-4549},

volume={31},

issue={6},

pages={647-680},

abstract={In this paper, the development of a so-called neutron noise simulator is reported. This simulator calculates both the direct and the adjoint reactor transfer function between a stationary noise source and its induced neutron noise for any 2-dimensional heterogeneous critical system. The main advantage of this neutron noise simulator is that any realistic core can be modelled, since the simulator is designed to rely on a set of material constants corresponding to the actual reactor operating conditions. The calculations are performed in the 2-group diffusion approximation and in the frequency domain. The spatial discretisation is carried out with respect to the finite difference scheme. The noise source, expressed as an "absorber of variable strength" type, is defined directly from the fluctuations of the macroscopic cross-sections and can be spatially distributed over the core or concentrated in a few discrete nodes. If the noise source is a point-source, the simulator actually estimates the 2-dimensional 2-group discretised Green's function of the system. From the calculated Green's function, the neutron noise induced by a "vibrating absorber" type of noise source can also be determined. Different benchmark cases show that this neutron noise simulator works satisfactorily.},

publisher={External organization},

year={2004},

keywords={nuclear reactor, noise analysis, core calculations, dynamic reactor transfer function, benchmarking},

}

** RefWorks **

RT Journal Article

SR Electronic

ID 1666

A1 Demazière, Christophe

T1 Development of a 2-D 2-group neutron noise simulator

YR 2004

JF Annals of Nuclear Energy

SN 0306-4549

VO 31

IS 6

SP 647

OP 680

AB In this paper, the development of a so-called neutron noise simulator is reported. This simulator calculates both the direct and the adjoint reactor transfer function between a stationary noise source and its induced neutron noise for any 2-dimensional heterogeneous critical system. The main advantage of this neutron noise simulator is that any realistic core can be modelled, since the simulator is designed to rely on a set of material constants corresponding to the actual reactor operating conditions. The calculations are performed in the 2-group diffusion approximation and in the frequency domain. The spatial discretisation is carried out with respect to the finite difference scheme. The noise source, expressed as an "absorber of variable strength" type, is defined directly from the fluctuations of the macroscopic cross-sections and can be spatially distributed over the core or concentrated in a few discrete nodes. If the noise source is a point-source, the simulator actually estimates the 2-dimensional 2-group discretised Green's function of the system. From the calculated Green's function, the neutron noise induced by a "vibrating absorber" type of noise source can also be determined. Different benchmark cases show that this neutron noise simulator works satisfactorily.

PB External organization

LA eng

DO 10.1016/j.anucene.2003.08.007

LK http://dx.doi.org/10.1016/j.anucene.2003.08.007

OL 30