Portal de Programas de Pós-Graduação (UFSJ)

SIGAA - Sistema Integrado de Gestão de Atividades Acadêmicas

PPGEQ PROGRAMA DE PÓS-GRADUAÇÃO EM ENGENHARIA QUÍMICA PRÓ-REITORIA DE PESQUISA E PÓS-GRADUAÇÃO Phone: Not available E-mail: renataczlofrano@ufsj.edu.br

Banca de QUALIFICAÇÃO: CARLA CRISTINA ARAÚJO PARREIRA

Uma banca de QUALIFICAÇÃO de MESTRADO foi cadastrada pelo programa.
STUDENT : CARLA CRISTINA ARAÚJO PARREIRA
DATE: 10/12/2021
TIME: 19:00
LOCAL: https://meet.google.com/rbh-wrnz-ygw
TITLE:

DEVELOPMENT OF A NEW EQUATION FOR FORECAST PARAMETERS OF NUCLEAR FISSION REACTORS FROM DYNAMIC MODELING AND SIMULATION

KEY WORDS:

dynamic modeling, simulation, nuclear reactor, neutron density, systems of nonlinear equations

PAGES: 82
BIG AREA: Engenharias
AREA: Engenharia Química
SUBÁREA: Processos Industriais de Engenharia Química
SPECIALTY: Processos Inorgânicos
SUMMARY:

The viability of nuclear reactors depends on an efficient safety system in the operation of nuclear processing units. Much of the safety of nuclear fission reactors is related to the neutron density that requires a well-balanced balance between the emitted neutrons and the lost neutrons (via neutron absorption or leakage), in order to avoid major damage such as overheating and possible explosions. In the present work, a literature review on nuclear energy, dynamic modeling and simulation of a nuclear reactor and the development of a new equation (system of non-linear differential equations) for prediction of neutron density, power and fractions was carried out. delayed neutron precursor groups in a nuclear fission reactor and application of fuzzy logic. According to the literature, the system of nonlinear differential equations proposed by Duderstadt and Hamilton is one of the most representative for the prediction of neutron density, but it has a deficiency in the result of neutron density in moderate systems. In this work, the Duderstadt and Hamilton equation was modified with the insertion of new terms in the neutron density, power and concentration equations of the delayed neutron generator groups, generating a system of seven nonlinear differential equations that were solved by the Runge Kutta method. fourth order in the OCTAVE free software. From the proposed model, dynamic simulations of fission nuclear reactors were performed. The simulations resulted in the neutron density, the reactor power estimation and the estimation of the mass fractions of the late neutron precursor groups. The validation of the new proposed model was performed by superimposing the plotting of simulation results on the plotting of experimental data from the literature for the PWR TRIGA reactor at CDTN/UFMG. Through Fuzzy Logic, it was possible to perform a numerical estimate in relation to the percentages of neutrons in the Reactor. With this analysis, we obtained a value of approximately 60% of neutrons that must be emitted by the primary source in the Reactor and 41% of neutrons that must be absorbed by the moderators. The new equation proposed by the author resulted in an adequate compatibility between the proposed model and the experimental data. This new equation is an important tool for the design of control systems for nuclear fission reactors, representing an interesting suggestion for future work.

BANKING MEMBERS:
Presidente - 1742695 - JUAN CANELLAS BOSCH NETO
Interno - 1811284 - EDSON ROMANO NUCCI
Externo à Instituição - PEDRO PRATES VALÉRIO - UNA
Externo à Instituição - MARCELO CARDOSO - UFMG

Notícia cadastrada em: 01/12/2021 17:13