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Simulation of hot-channel transients for PHWR reactors; Simulacion del canal caliente durante transitorios en reactores PHWR

Abstract

For the simulation of transients a whole-plant code is needed. These codes model the core in a very simplified way. When local variables have to be calculated a different kind of code is needed: a subchannel-code. This report studies the use of the cobra code as a subchannel-code, for the simulation of a PHWR fuel channel, considering that this code was developed for PWR cores calculation. A special effort is made to obtain optimized models for different calculations: steady state, soft transients and severe transients. These models differ in number of subchannels, axial nodes, and the choice of the most important variables. (Author). [Espanol] En la simulacion de transitorios es necesario modelar toda la planta, por lo que los programas que realizan este calculo representan el nucleo muy elementalmente. Para estimar variables locales en canales refrigerantes durante transitorios se usan programas que toman como entrada el calculo de un codigo de planta y modelan a nivel de subcanales. En este trabajo se analizara el uso del programa `cobra` realizando esta segunda funcion. Se estudian las particularidades que implica modelar el canal combustible de un reactor PHWR usando un programa desarrollado para el calculo de nucleos PWR. Se profundiza en la  More>>
Authors:
Publication Date:
Dec 31, 1988
Product Type:
Conference
Report Number:
INIS-mf-13203; CONF-8811356-
Reference Number:
SCA: 220100; 210400; PA: AIX-23:048770; SN: 92000771686
Resource Relation:
Conference: 16. scientific meeting of the Argentine Association of Nuclear Technology,16. Reunion cientifica de la Asociacion Argentina de Tecnologia Nuclear,Mendoza (Argentina),7-11 Nov 1988; Other Information: DN: Pre-conference paper.; PBD: 1988
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HOT CHANNEL; COMPUTERIZED SIMULATION; C CODES; FUEL CHANNELS; PHWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR SIMULATORS; STEADY-STATE CONDITIONS; TRANSIENTS; 220100; 210400; THEORY AND CALCULATION; POWER REACTORS, NONBREEDING, OTHERWISE MODERATED OR UNMODERATED
OSTI ID:
10156211
Research Organizations:
Empresa Nuclear Argentina de Centrales Electricas SA (ENACE), Buenos Aires (Argentina)
Country of Origin:
Argentina
Language:
Spanish
Other Identifying Numbers:
Other: ON: DE92634336; TRN: AR9100163048770
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
7 p.
Announcement Date:
Jul 06, 2005

Citation Formats

Masriera, N A. Simulation of hot-channel transients for PHWR reactors; Simulacion del canal caliente durante transitorios en reactores PHWR. Argentina: N. p., 1988. Web.
Masriera, N A. Simulation of hot-channel transients for PHWR reactors; Simulacion del canal caliente durante transitorios en reactores PHWR. Argentina.
Masriera, N A. 1988. "Simulation of hot-channel transients for PHWR reactors; Simulacion del canal caliente durante transitorios en reactores PHWR." Argentina.
@misc{etde_10156211,
title = {Simulation of hot-channel transients for PHWR reactors; Simulacion del canal caliente durante transitorios en reactores PHWR}
author = {Masriera, N A}
abstractNote = {For the simulation of transients a whole-plant code is needed. These codes model the core in a very simplified way. When local variables have to be calculated a different kind of code is needed: a subchannel-code. This report studies the use of the cobra code as a subchannel-code, for the simulation of a PHWR fuel channel, considering that this code was developed for PWR cores calculation. A special effort is made to obtain optimized models for different calculations: steady state, soft transients and severe transients. These models differ in number of subchannels, axial nodes, and the choice of the most important variables. (Author). [Espanol] En la simulacion de transitorios es necesario modelar toda la planta, por lo que los programas que realizan este calculo representan el nucleo muy elementalmente. Para estimar variables locales en canales refrigerantes durante transitorios se usan programas que toman como entrada el calculo de un codigo de planta y modelan a nivel de subcanales. En este trabajo se analizara el uso del programa `cobra` realizando esta segunda funcion. Se estudian las particularidades que implica modelar el canal combustible de un reactor PHWR usando un programa desarrollado para el calculo de nucleos PWR. Se profundiza en la obtencion de modelos optimizados para el calculo de: estados estacionarios, transitorios suaves y transitorios severos, en cuanto a numero de subcanales transversales, nodos axiales y definicion de las variables de mayor interes. (Autor).}
place = {Argentina}
year = {1988}
month = {Dec}
}