Published 1986 | Version v1
Miscellaneous Metadata-only

Model for calculating the boron concentration in PWR type reactors

Creators

  • 1. FURNAS, Rio de Janeiro (Brazil)

Description

A PWR boron concentration model has been developed for use with RETRAN code. The concentration model calculates the boron mass balance in the primary circuit as the injected boron mixes and is transported through the same circuit. RETRAN control blocks are used to calculate the boron concentration in fluid volumes during steady-state and transient conditions. The boron reactivity worth is obtained from the core concentration and used in RETRAN point kinetics model. A FSAR type analysis of a Steam Line Break Accident in Angra I plant was selected to test the model and the results obtained indicate a sucessfull performance. (Author)

Abstract (Portuguese)

Desenvolveu-se atraves do codigo RETRAN, um modelo que determimna a distribuicao da concentracao de boro no circuito primario de um reator tipo PWR a medida que o boro injetado se dilui e e transportado atraves do mesmo. Sao utilizados blocos de controle para o calculo das concentracoes em condicoes estacionarias e transitorias. O valor da reatividade associada ao boro e calculada a partir da concentracao no nucleo e e utilizada nos calculos de cinetica puntual do RETRAN. O modelo foi testado em uma analise tipo FSAR para um acidente de Ruptura na Linha Principal de Vapor em Angra I e seu desempenho revelou-se satisfatorio. (Autor)

Additional details

Additional titles

Original title (Portuguese)
Modelo para o calculo da concentracao de boro em reatores PWR

Publishing Information

Imprint Title
Proceedings of the 1. General Congress of Nuclear Energy. v. 1
Imprint Pagination
430 p.
Journal Page Range
v. 1 p. 18-21.
Report number
INIS-BR--537(v.1)

Conference

Title
1. General Congress of Nuclear Energy.
Dates
17-20 Mar 1986.
Place
Rio de Janeiro, RJ (Brazil).

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
17069456
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANGRA-1 REACTOR; BORON; COMPUTERIZED SIMULATION; MATHEMATICAL MODELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; QUANTITY RATIO; R CODES; REACTIVITY; STEAM LINES
Descriptors DEC
COMPUTER CODES; COOLING SYSTEMS; ELEMENTS; ENRICHED URANIUM REACTORS; PIPELINES; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SEMIMETALS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:Anais do 1. Congresso Geral de Energia Nuclear. v. 1.