Published 1984
| Version v1
Report
Open
UNICIN - an one-dimensional computer code for reactor kinetics
Description
A program for the solution of the time- and space-dependent multigroup diffusion equations and the delayed-neutron precursors concentration equations in one dimensional geometries by the weighted residual method is described. The discretized equations are solved through an iterative procedure with convergence accelerated by the over-relaxation method. The system is perturbed through the variation of the nuclide concentrations in specified regions. Two feedback effects are included, namely, the temperature and the burnup. (Author)
Availability note (English)
MF available from INIS under the Report Number.Abstract (Portuguese)
Um programa para solucao das equacoes de difusao de neutrons em multigrupo e das equacoes de concentracao de precursores de neutrons atrasados, dependentes de espaco e tempo em geometrias unidimensionais, pelo metodo de rediduos ponderados e descrito. As equacoes discretizadas sao resolvidas por um metodo iterativo, com aceleracao da convergencia pelo metodo 'over-relaxation'. O sistema e perturbado atraves da variacao da concentracao de nuclideos em regioes especificadas. Dois efeitos de realimentacao sao considerados: o efeito de temperatura e o efeito do consumo de combustivel. (Autor)Files
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Additional details
Additional titles
- Original title (Portuguese)
- UNICIN - um programa unidimensional de cinetica de reatores
Publishing Information
- Imprint Pagination
- 87 p.
- Report number
- CTA-IEAV-NT--024/84
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 16078024
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- COMPUTER CALCULATIONS; DELAYED NEUTRON PRECURSORS; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; ONE-DIMENSIONAL CALCULATIONS; U CODES
- Descriptors DEC
- COMPUTER CODES; RADIATION FLUX