You need JavaScript to view this

Application of perturbation theory to sensitivity calculations of PWR type reactor cores using the two-channel model; Aplicacao da teoria de perturbacao para calculos de sensibilidade em nucleos de reatores PWR, usando um modelo de dois canais

Abstract

Sensitivity calculations are very important in design and safety of nuclear reactor cores. Large codes with a great number of physical considerations have been used to perform sensitivity studies. However, these codes need long computation time involving high costs. The perturbation theory has constituted an efficient and economical method to perform sensitivity analysis. The present work is an application of the perturbation theory (matricial formalism) to a simplified model of DNB (Departure from Nucleate Boiling) analysis to perform sensitivity calculations in PWR cores. Expressions to calculate the sensitivity coefficients of enthalpy and coolant velocity with respect to coolant density and hot channel area were developed from the proposed model. The CASNUR.FOR code to evaluate these sensitivity coefficients was written in Fortran. The comparison between results obtained from the matricial formalism of perturbation theory with those obtained directly from the proposed model makes evident the efficiency and potentiality of this perturbation method for nuclear reactor cores sensitivity calculations (author). 23 refs, 4 figs, 7 tabs.
Publication Date:
Dec 01, 1988
Product Type:
Thesis/Dissertation
Report Number:
INIS-BR-3505/A
Reference Number:
SCA: 210200; PA: AIX-26:053100; EDB-95:089940; ERA-20:018272; NTS-96:002996; SN: 95001414111
Resource Relation:
Other Information: DN: PRONUCLEAR. Tese de Mestrado, 45.; TH: Tese (M.Sc.).; PBD: Dec 1988
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; HOT CHANNEL; SENSITIVITY ANALYSIS; COMPUTERIZED SIMULATION; DEPARTURE NUCLEATE BOILING; ENTHALPY; PERTURBATION THEORY; PWR TYPE REACTORS
OSTI ID:
65446
Research Organizations:
Pernambuco Univ., Recife, PE (Brazil). Dept. de Energia Nuclear
Country of Origin:
Brazil
Language:
Portuguese
Other Identifying Numbers:
Other: ON: DE95631413; TRN: BR9533225053100
Availability:
INIS; OSTI as DE95631413
Submitting Site:
INIS
Size:
183 p.
Announcement Date:

Citation Formats

Oliveira, A.C.J.G. de. Application of perturbation theory to sensitivity calculations of PWR type reactor cores using the two-channel model; Aplicacao da teoria de perturbacao para calculos de sensibilidade em nucleos de reatores PWR, usando um modelo de dois canais. Brazil: N. p., 1988. Web.
Oliveira, A.C.J.G. de. Application of perturbation theory to sensitivity calculations of PWR type reactor cores using the two-channel model; Aplicacao da teoria de perturbacao para calculos de sensibilidade em nucleos de reatores PWR, usando um modelo de dois canais. Brazil.
Oliveira, A.C.J.G. de. 1988. "Application of perturbation theory to sensitivity calculations of PWR type reactor cores using the two-channel model; Aplicacao da teoria de perturbacao para calculos de sensibilidade em nucleos de reatores PWR, usando um modelo de dois canais." Brazil.
@misc{etde_65446,
title = {Application of perturbation theory to sensitivity calculations of PWR type reactor cores using the two-channel model; Aplicacao da teoria de perturbacao para calculos de sensibilidade em nucleos de reatores PWR, usando um modelo de dois canais}
author = {Oliveira, A.C.J.G. de}
abstractNote = {Sensitivity calculations are very important in design and safety of nuclear reactor cores. Large codes with a great number of physical considerations have been used to perform sensitivity studies. However, these codes need long computation time involving high costs. The perturbation theory has constituted an efficient and economical method to perform sensitivity analysis. The present work is an application of the perturbation theory (matricial formalism) to a simplified model of DNB (Departure from Nucleate Boiling) analysis to perform sensitivity calculations in PWR cores. Expressions to calculate the sensitivity coefficients of enthalpy and coolant velocity with respect to coolant density and hot channel area were developed from the proposed model. The CASNUR.FOR code to evaluate these sensitivity coefficients was written in Fortran. The comparison between results obtained from the matricial formalism of perturbation theory with those obtained directly from the proposed model makes evident the efficiency and potentiality of this perturbation method for nuclear reactor cores sensitivity calculations (author). 23 refs, 4 figs, 7 tabs.}
place = {Brazil}
year = {1988}
month = {Dec}
}