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One-velocity neutron diffusion calculations based on a two-group reactor model

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  More>>
Authors:
Bingulac, S; Radanovic, L; Lazarevic, B; Matausek, M; Pop-Jordanov, J [1] 
  1. Boris Kidric Institute of Nuclear Sciences, Vinca, Belgrade (Yugoslavia)
Publication Date:
Jul 01, 1965
Product Type:
Conference
Report Number:
INIS-RS-1465
Resource Relation:
Conference: 3. International Conference on the peaceful uses of atomic energy, Geneva (Switzerland), 31 Aug - 9 Sep 1964; Other Information: 6 refs., 4 figs., 5 tabs
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; ENERGY DEPENDENCE; FAST NEUTRONS; MULTIGROUP THEORY; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; ONE-DIMENSIONAL CALCULATIONS; ONE-GROUP THEORY; RICCATI EQUATION; SPATIAL DISTRIBUTION; THERMAL NEUTRONS
OSTI ID:
21095389
Country of Origin:
Serbia
Language:
English
Other Identifying Numbers:
TRN: RS08RB273105999
Availability:
Available from INIS in electronic form; Also available from the Institute of nuclear sciences Vinca
Submitting Site:
INIS
Size:
8 pages
Announcement Date:
Dec 05, 2008

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}
}