PPGENE PÓS-GRADUAÇÃO EM ENERGIA FUNDAÇÃO UNIVERSIDADE FEDERAL DO ABC Phone: Not available http://propg.ufabc.edu.br/ppgene

Banca de QUALIFICAÇÃO: PEDRO HENRIQUE SILVA RODRIGUES

Uma banca de QUALIFICAÇÃO de DOUTORADO foi cadastrada pelo programa.
DISCENTE : PEDRO HENRIQUE SILVA RODRIGUES
DATA : 05/02/2020
HORA: 14:00
LOCAL: sala 301, 3º andar, Bloco B, Campus SA da Fundação Universidade Federal do ABC, localizada na Avenida dos Estados, 5001, Santa Terezinha, Santo André, SP
TÍTULO:

INTELIGENT FUEL CORE MANAGMENT FOR PWR REACTORS


PÁGINAS: 100
GRANDE ÁREA: Engenharias
ÁREA: Engenharia Nuclear
SUBÁREA: Tecnologia dos Reatores
ESPECIALIDADE: Núcleo do Reator
RESUMO:

This work presents a methodology applied to perform an in-core fuel management (ICFM) in PWR-type reactors using genetic algorithms (AG's). ICFM consists of defining a recharge pattern during the operational cycles of the reactor, that is, finding the best arrangement of new and partially burned fuel elements (EC's), which optimizes the performance of the reactor according to its safety criteria. For this, the proposed methodology is based on developing an interface in which the GA can interact with the simulation code of reactor physics, which holds the neutron characteristics of each EC and which must be reliable and fast. Therefore, it was necessary to develop, through a technique already consolidated in the Literature, a thick mesh node code that numerically solves the multigroup diffusion equation for 2 groups of energy, fast and thermal neutrons, in two dimensions. In this type of code, it is necessary for each EC, represented by a node, to be homogenized and represented by its multigroup constants, for each burnup of the reactor. For this, the SCALE system, developed by the Reactor and Nuclear Systems Division (RNSD) of the Oak Ridge National Laboratory (ORNL) was used. All the qualification and validation of the results obtained from the homogenization of the EC’s by the SCALE together with the nodal code were performed comparing them with the Benmarmark of the Almaraz Nuclear Power Plant provided by the IAEA and other benchmarks found in the literature.


MEMBROS DA BANCA:
Presidente - Interno ao Programa - 670232 - JOSE RUBENS MAIORINO
Membro Titular - Examinador(a) Interno ao Programa - 6670680 - JOAO MANOEL LOSADA MOREIRA
Membro Titular - Examinador(a) Externo ao Programa - 2263681 - PEDRO CARLOS RUSSO ROSSI
Membro Suplente - Examinador(a) Interno ao Programa - 1545354 - RICARDO CANELOI DOS SANTOS
Membro Suplente - Examinador(a) Externo ao Programa - 1544363 - ALFREDO DEL SOLE LORDELO
Notícia cadastrada em: 10/01/2020 18:05
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