PODESY program for flux mapping of CNA II reactor:
- 1. ENACE S.A., Buenos Aires (Argentina)
Description
The PODESY program, developed by KWU, calculates the spatial flux distribution of CNA II reactor through a three-dimensional expansion of 90 incore detector measurements. The calculation is made in three steps: a) short-term calculation which considers the control rod positions and it has to be done each time the flux mapping is calculated; b) medium-term calculation which includes local burn-up dependent calculation made by diffusion methods in macro-cell configurations (seven channels in hexagonal distribution), and c) long-term calculation, or macroscopic flux determination, that is a fitting and expansion of measured fluxes, previously corrected by local effects, using the eigen functions of the modified diffusion equation. The paper outlines development of step (c) of the calculation. The incore detectors have been located in the central zone of the core. In order to obtain low errors in the expansion procedure it is necessary to include additional points, whose flux values are assumed to be equivalent to detector measurements. These flux values are calculated with detector measurements and a spatial flux distribution calculated by a PUMA code. This PUMA calculation employs a smooth burn-up distribution (local burn-up variations are considered in step (b) of the whole calculation) representing the state of core evolution at the calculation time. The core evolution referred to ends when the equilibrium core condition is reached. Additionally, a calculation method to be employed in the plant in case of incore detector failures, is proposed. (Author)
Availability note (English)
Also available from Comision Nacional de Energia Atomica, Buenos Aires (AR). Library.Abstract (Spanish)
El programa PODESY, desarrollado por KWU, calcula la distribucion espacial de flujo del reactor de CNA II a partir de las mediciones de sus 90 detectores incore. Este calculo se realiza en tres etapas: a) calculo de corto plazo que considera la incidencia de la posicion de las barras de control y se realiza cada vez que se calcula un mapa de flujo; b) calculo de mediano plazo que considera la distribucion local de quemado mediante un calculo de difusion de celda y macrocelda (siete canales) y c) calculo de largo plazo (o del flujo macroscopico) que realiza una interpolacion de las mediciones corregidas usando las funciones propias de la ecuacion de difusion modificada. El presente trabajo se desarrolla sobre la etapa (c). Los detectores incore han sido ubicados en la zona central del nucleo. Para obtener errores aceptables en la interpolacion es necesario definir puntos adicionales, cuyos flujos se consideran como si fuesen lecturas de detector. Se calculan en base a dos elementos: las lecturas de los detectores y una distribucion espacial de flujo calculada por PUMA. Este calculo se realiza tomando una distribucion global de quemado (las fluctuaciones locales se consideran en la etapa de (b) del calculo) correspondiente al momento de la evolucion del reactor en que se realiza el calculo. Esta evolucion culmina cuando se alcanza el nucleo de equilibrio. Por ultimo, se sugiere una metodologia de calculo, a inplementar en planta, para dos casos de rotura o funcionamento erroneo de alguna de los detectores incore. (Autor)Additional details
Additional titles
- Subtitle (English)
- Scheme applied in the macroscopic flux determination
- Original title (Spanish)
- Programa PODESY para mapeo de flujo del reactor de CNA II:
- Original subtitle (Spanish)
- Esquema para la determinacion del flujo macroscopico.
Publishing Information
- Imprint Pagination
- 5 p.
Conference
- Title
- 16. Scientific meeting of the Argentine Association of Nuclear Technology.
- Original Conference Title
- 16. Reunion cientifica de la Asociacion Argentina de Tecnologia Nuclear
- Dates
- 7-11 Nov 1988.
- Place
- Mendoza (Argentina).
INIS
- Country of Publication
- Argentina
- Country of Input or Organization
- Argentina
- INIS RN
- 22012666
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ARGENTINA; ATUCHA-2 REACTOR; ENERGY SPECTRA; NEUTRON DETECTION; NEUTRON FLUX; NUCLEAR POWER PLANTS; P CODES; PROGRAMMING; REACTOR CORES; SPATIAL DISTRIBUTION; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- COMPUTER CODES; DETECTION; DEVELOPING COUNTRIES; DISTRIBUTION; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; LATIN AMERICA; NATURAL URANIUM REACTORS; NUCLEAR FACILITIES; PHWR TYPE REACTORS; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION DETECTION; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; SOUTH AMERICA; SPECTRA; THERMAL POWER PLANTS; THERMAL REACTORS
Optional Information
- Notes
- Pre-conference paper.