## Abstract

Many processes in reactor physics are described by the energy dependent neutron diffusion equations which for many practical purposes can often be reduced to one-dimensional two-group equations. Though such two-group models are satisfactory from the standpoint of accuracy, they require rather extensive computations which are usually iterative and involve the use of digital computers. In many applications, however, and particularly in dynamic analyses, where the studies are performed on analogue computers, it is preferable to avoid iterative calculations. The usual practice in such situations is to resort to one group models, which allow the solution to be expressed analytically. However, the loss in accuracy is rather great particularly when several media of different properties are involved. This paper describes a procedure by which the solution of the two-group neutron diffusion. equations can be expressed analytically in the form which, from the computational standpoint, is as simple as the one-group model, but retains the accuracy of the two-group treatment. In describing the procedure, the case of a multi-region nuclear reactor of cylindrical geometry is treated, but the method applied and the results obtained are of more general application. Another approach in approximate solution of diffusion equations, suggested by Galanin is applicable
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Bingulac, S;
Radanovic, L;
Lazarevic, B;
Matausek, M;
Pop-Jordanov, J

^{[1] }- Boris Kidric Institute of Nuclear Sciences, Vinca, Belgrade (Yugoslavia)

## Citation Formats

Bingulac, S, Radanovic, L, Lazarevic, B, Matausek, M, and Pop-Jordanov, J.
One-velocity neutron diffusion calculations based on a two-group reactor model.
Serbia: N. p.,
1965.
Web.

Bingulac, S, Radanovic, L, Lazarevic, B, Matausek, M, & Pop-Jordanov, J.
One-velocity neutron diffusion calculations based on a two-group reactor model.
Serbia.

Bingulac, S, Radanovic, L, Lazarevic, B, Matausek, M, and Pop-Jordanov, J.
1965.
"One-velocity neutron diffusion calculations based on a two-group reactor model."
Serbia.

@misc{etde_21095389,

title = {One-velocity neutron diffusion calculations based on a two-group reactor model}

author = {Bingulac, S, Radanovic, L, Lazarevic, B, Matausek, M, and Pop-Jordanov, J}

abstractNote = {Many processes in reactor physics are described by the energy dependent neutron diffusion equations which for many practical purposes can often be reduced to one-dimensional two-group equations. Though such two-group models are satisfactory from the standpoint of accuracy, they require rather extensive computations which are usually iterative and involve the use of digital computers. In many applications, however, and particularly in dynamic analyses, where the studies are performed on analogue computers, it is preferable to avoid iterative calculations. The usual practice in such situations is to resort to one group models, which allow the solution to be expressed analytically. However, the loss in accuracy is rather great particularly when several media of different properties are involved. This paper describes a procedure by which the solution of the two-group neutron diffusion. equations can be expressed analytically in the form which, from the computational standpoint, is as simple as the one-group model, but retains the accuracy of the two-group treatment. In describing the procedure, the case of a multi-region nuclear reactor of cylindrical geometry is treated, but the method applied and the results obtained are of more general application. Another approach in approximate solution of diffusion equations, suggested by Galanin is applicable only in special ideal cases.}

place = {Serbia}

year = {1965}

month = {Jul}

}

title = {One-velocity neutron diffusion calculations based on a two-group reactor model}

author = {Bingulac, S, Radanovic, L, Lazarevic, B, Matausek, M, and Pop-Jordanov, J}

abstractNote = {Many processes in reactor physics are described by the energy dependent neutron diffusion equations which for many practical purposes can often be reduced to one-dimensional two-group equations. Though such two-group models are satisfactory from the standpoint of accuracy, they require rather extensive computations which are usually iterative and involve the use of digital computers. In many applications, however, and particularly in dynamic analyses, where the studies are performed on analogue computers, it is preferable to avoid iterative calculations. The usual practice in such situations is to resort to one group models, which allow the solution to be expressed analytically. However, the loss in accuracy is rather great particularly when several media of different properties are involved. This paper describes a procedure by which the solution of the two-group neutron diffusion. equations can be expressed analytically in the form which, from the computational standpoint, is as simple as the one-group model, but retains the accuracy of the two-group treatment. In describing the procedure, the case of a multi-region nuclear reactor of cylindrical geometry is treated, but the method applied and the results obtained are of more general application. Another approach in approximate solution of diffusion equations, suggested by Galanin is applicable only in special ideal cases.}

place = {Serbia}

year = {1965}

month = {Jul}

}