Published 1990 | Version v1
Miscellaneous Open

CONDOR: neutronic code for fuel elements calculation with rods

Description

CONDOR neutronic code is used for the calculation of fuel elements formed by fuel rods. The method employed to obtain the neutronic flux is that of collision probabilities in a multigroup scheme on two-dimensional geometry. This code utilizes new calculation algorithms and normalization of such collision probabilities. Burn-up calculations can be made before the alternative of applying variational methods for response flux calculations or those corresponding to collision normalization. (Author)

Availability note (English)

MF available from INIS under the Report Number.

Abstract (Spanish)

El codigo neutronico CONDOR es empleado para el calculo de elementos combustibles formado por barras combustibles. El metodo aplicado para obtener el flujo neutronico es el de probabilidades de colision PC en un esquema multigrupo en geometria bidimensional. Este codigo emplea nuevos algoritmos de calculo y normalizacion de las PC. Se pueden realizar calculos de quemado con la alternativa de aplicar metodos variacionales en el calculo de los flujos de respuesta o de las PC. (Autor)

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Additional details

Additional titles

Original title (Spanish)
CONDOR: codigo neutronico para el calculo de elementos combustibles con barras

Publishing Information

Imprint Pagination
7 p.
Report number
INIS-mf--13265

Conference

Title
18. Annual meeting of the Argentine Association of Nuclear Technology.
Original Conference Title
18. Reunion anual de la Asociacion Argentina de Tecnologia Nuclear
Dates
22-26 Oct 1990.
Place
Buenos Aires (Argentina).

INIS

Country of Publication
Argentina
Country of Input or Organization
Argentina
INIS RN
23055041
Subject category
S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
ALGORITHMS; BURNUP; C CODES; COLLISIONS; EXPERIMENTAL DATA; FUEL RODS; NEUTRON FLUX; PROBABILITY; TWO-DIMENSIONAL CALCULATIONS
Descriptors DEC
COMPUTER CODES; DATA; FUEL ELEMENTS; INFORMATION; NUMERICAL DATA; RADIATION FLUX; REACTOR COMPONENTS

Optional Information

Notes
Pre-conference paper.