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Calculation of the CAREM reactor with the HUEMUL-PUMA-THERMIT chain of codes; Calculo del reactor CAREM con la cadena de codigos HUEMUL-PUMA-THERMIT

Abstract

The purpose of the work was the evaluation of the the CAREM 25 reactor core, using a chain of codes (HUEMUL-PUMA-THERMIT) different to the one used in the original design (CONDOR-CITVAP-THERMIT). First, we performed a partial validation of the our codes in lattices similar to CAREM and reproduced a benchmark for simulation of gadolinium burnup. The results were considered satisfactory for this stage of the project. Then, we calculated the core along the normal operating equilibrium cycle and in hot and cold shut-down conditions. The main outcome of our evaluation confirms the general behaviour of the reference calculations except in one important point referring to the cold shut down. In this condition, the failure of one single rod of bank number 13 of the shut down system, leaves the core in a supercritical state at the beginning of the cycle and this anomaly persists during almost a third of the overall cycle. A new design of the core is proposed with minor modifications of the reference one, without introducing new types of fuel elements and keeping the same fuel management scheme. This new core fulfills all the design requirements. (author)
Authors:
Notari, Carla; Grant, Carlos R [1] 
  1. Comision Nacional de Energia Atomica, General San Martin (Argentina)
Publication Date:
Jul 01, 2000
Product Type:
Conference
Report Number:
INIS-AR-C-083
Reference Number:
EDB-01:093228
Resource Relation:
Conference: AATN 2000: 27. Annual meeting of the Argentine Association of Nuclear Technology (AANT), AATN 2000: 27. Reunion anual de la Asociacion Argentina de Tecnologia Nuclear (AATN), Buenos Aires (Argentina), 22-24 Nov 2000; Other Information: 4 refs., 3 figs; PBD: 2000
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BENCHMARKS; BURNABLE POISONS; BURNUP; GADOLINIUM; H CODES; P CODES; PWR TYPE REACTORS; REACTOR CORES; SHUTDOWN; SIMULATION; T CODES
OSTI ID:
20198995
Country of Origin:
Argentina
Language:
Spanish
Other Identifying Numbers:
TRN: AR01C0111048922
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
8 pages
Announcement Date:
Nov 01, 2001

Citation Formats

Notari, Carla, and Grant, Carlos R. Calculation of the CAREM reactor with the HUEMUL-PUMA-THERMIT chain of codes; Calculo del reactor CAREM con la cadena de codigos HUEMUL-PUMA-THERMIT. Argentina: N. p., 2000. Web.
Notari, Carla, & Grant, Carlos R. Calculation of the CAREM reactor with the HUEMUL-PUMA-THERMIT chain of codes; Calculo del reactor CAREM con la cadena de codigos HUEMUL-PUMA-THERMIT. Argentina.
Notari, Carla, and Grant, Carlos R. 2000. "Calculation of the CAREM reactor with the HUEMUL-PUMA-THERMIT chain of codes; Calculo del reactor CAREM con la cadena de codigos HUEMUL-PUMA-THERMIT." Argentina.
@misc{etde_20198995,
title = {Calculation of the CAREM reactor with the HUEMUL-PUMA-THERMIT chain of codes; Calculo del reactor CAREM con la cadena de codigos HUEMUL-PUMA-THERMIT}
author = {Notari, Carla, and Grant, Carlos R}
abstractNote = {The purpose of the work was the evaluation of the the CAREM 25 reactor core, using a chain of codes (HUEMUL-PUMA-THERMIT) different to the one used in the original design (CONDOR-CITVAP-THERMIT). First, we performed a partial validation of the our codes in lattices similar to CAREM and reproduced a benchmark for simulation of gadolinium burnup. The results were considered satisfactory for this stage of the project. Then, we calculated the core along the normal operating equilibrium cycle and in hot and cold shut-down conditions. The main outcome of our evaluation confirms the general behaviour of the reference calculations except in one important point referring to the cold shut down. In this condition, the failure of one single rod of bank number 13 of the shut down system, leaves the core in a supercritical state at the beginning of the cycle and this anomaly persists during almost a third of the overall cycle. A new design of the core is proposed with minor modifications of the reference one, without introducing new types of fuel elements and keeping the same fuel management scheme. This new core fulfills all the design requirements. (author)}
place = {Argentina}
year = {2000}
month = {Jul}
}