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Master's Dissertation
DOI
https://doi.org/10.11606/D.3.2015.tde-12082020-091116
Document
Author
Full name
Matheus Araujo Tunes
E-mail
Institute/School/College
Knowledge Area
Date of Defense
Published
São Paulo, 2015
Supervisor
Committee
Schön, Claudio Geraldo (President)
Carluccio, Thiago
Silva, Antonio Teixeira e
Title in Portuguese
Desenvolvimento de um modelo computacional de reator nuclear para estudos de optimização da blindagem primária em submarinos nucleares.
Keywords in Portuguese
Blindagem de radiação
Física de reatores
Método de Monte Carlo
Métodos de optimização
Reatores nucleares
Abstract in Portuguese
A presente pesquisa apresenta o desenvolvimento de um modelo computacional de um reator nuclear térmico e compacto para estudos em optimização e avaliação de materiais inovadores para uma melhor efetividade da blindagem primária. Utilizou-se dois códigos de transporte nêutron-gama, o estatístico MCNP5 e o determinístico gem/EVENT: o primeiro para o design do PWR e o segundo para simular um modelo 1D do reator para estudar o comportamento de blindagem gama e de nêutrons para diversos materiais. Adicionalmente o MATLAB Optimization Toolbox foi utilizado para fornecer novas configurações geométricas optimizadas do modelo unidimensional do reator visando reduzir o volume e o peso das cascas da blindagem por meio de uma função custo/objetiva. Foi demonstrado no MCNP5 que a dose após a blindagem primária reduziu uma ordem de magnitude para o modelo optimizado utilizando-se um novo material compósito e o volume e o peso das cascas de blindagem foram reduzidos por um fator de 13%. Os resultados confirmam que os códigos nucleares podem ser executados paralelamente ao MATLAB com a intenção de se testar novos materiais para o propósito de optimização da blindagem da radiação em um reator PWR compacto e que materiais compósitos podem substituir os materiais de blindagem tradicionais sem o comprometimento da segurança da instalação nuclear.
Title in English
Modelling a compact nuclear reactor for optimization studies in biological shielding in nuclear submarines.
Keywords in English
Nuclear reactors
Optimization methods
Radiation shielding
Reactor physics
The Monte Carlo Method
Abstract in English
This research was focused to develop a computational model of a compact PWR to study optimization methods and evaluate innovative materials to enhance the biological shielding effectiveness. We used two radiation transport codes MCNP5 and GEM/EVENT: the first for the PWR design and the second one to simulate (in a 1D slab) several materials and shielding thickness behavior under gamma and neutron penetration. Additionally MATLAB Optimization Toolbox was used to provide new geometric configurations of the slab aiming to reduce the volume and weight of the walls by means of a cost/objective function. It is demonstrated in the MCNP5 that the dose rate after biological shielding has reduced by one order of magnitude for the optimized model with a new composite material (Ecomass) and the volume and weight of the shielding walls were reduced by 13% when we compare both sets. The results confirm that we can couple a deterministic and stochastic transport codes with MATLAB to test new materials in a very fast way for the purpose of radiation shielding optimization in common compact PWR. All this states that composite materials can replace (with advantages) traditional shielding materials without jeopardizing the nuclear power plant safety assurance.
 
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Publishing Date
2020-08-12
 
WARNING: The material described below relates to works resulting from this thesis or dissertation. The contents of these works are the author's responsibility.
  • TUNES, MATHEUS A., et al. Pulse-to-pulse stability analysis in a frequency-doubled, q-switched Nd:YAG rod-laser [doi:10.1117/12.2025847]. In SPIE NanoScience + Engineering, San Diego. , 2013.
  • TUNES, MATHEUS A., SCHÖN, CLÁUDIO G., and WETTER, NIKLAUS URSUS. Viability study of using the Laser-Induced Breakdown Spectroscopy technique for radioactive waste detection at IPEN-CNEN/SP. In XI Encontro Nacional de Aplicações Nucleares - International Nuclear Atlantic Conference, Recife, 2013. XI ENAM - INAC 2013.Recife : Associação Brasileira de Energia Nuclear, 2013. Available from: http://www.inac2013.com.br/admin/_m2brupload/arquivos_trabalhos_arquivos/455/LIBS-tritio-INAC.pdf.
All rights of the thesis/dissertation are from the authors
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