INSTITUTO DE PESQUISAS ENERGÉTICAS E NUCLEARES
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Nome : DELVONEI ALVES DE ANDRADE

INSTITUTO DE PESQUISAS ENERGÉTICAS E NUCLEARES
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Variações do nome do autor constantes no Repositório Digital/IPEN
ANDRADE, DELVONEI A. DE
ANDRADE, D.A.
ANDRADE, DELVONEI A.
ANDRADE, DELVONEI A. de
ANDRADE, DELVONEI
ANDRADE, D.A. DE

 

Veja também, abaixo da lista, o quadro resumo por ano e tipo de publicação

 
Publicações do autor depositadas no Repositório Digital/IPEN - Total : 139
Seq Ano Ipen_doc Tipo Circ. Título
1 2018 24364 Artigo de peri贸dico I Perfil epidemiol贸gico e cl铆nico dos casos de tuberculose em Ipatinga, Minas Gerais
2 2018 24733 Artigo de peri贸dico I Constructal law of institutions within social organizations
3 2018 24758 Artigo de peri贸dico I Classification of natural circulation two-phase flow image patterns based on self-organizing maps of full frame DCT coefficients
4 2018 24764 Artigo de peri贸dico I Studies on capacity expansion of fuel plants for nuclear research reactors
5 2018 24772 Artigo de peri贸dico I Technological perspectives for propulsion on nuclear attack submarines
6 2018 24789 Artigo de peri贸dico I Proposal of a methodology for the assessment of security levels of IoT wireless sensor networks in nuclear environments
7 2018 24790 Artigo de peri贸dico I A CFD analysis of the flow dynamics of a directly-operated safety relief valve
8 2018 24791 Texto completo de evento I Transient cfd analysis of the flow inversion of the nuclear research reactor IEA-R1
9 2018 24804 Artigo de peri贸dico I Thermal hydraulic analysis improvement for the IEA-R1 research reactor and fuel assembly design modification
10 2018 25071 Artigo de peri贸dico I Two-phase flow bubble detection method applied to natural circulation system using fuzzy image processing
11 2018 25094 Artigo de peri贸dico I A system status definition to improve behavior description in specifications based on constructal law
12 2017 23036 Texto completo de evento I Numerical simulation of isothermal upward two-phase flow in a vertical tube of annular section
13 2017 23045 Artigo de peri贸dico I The role of nuclear power from a system engineering standpoint
14 2017 23123 Artigo de peri贸dico I In vitro assessment of the composition and microhardness of the hard tissues of oral cavity submitted to gamma irradiation
15 2017 23186 Artigo de peri贸dico I ATR-FTIR assessment of the biochemical composition and micro hardness of the hard tissues of oral cavity submitted to gamma irradiation
16 2017 23205 Artigo de peri贸dico I Commitment as a strategy for the adoption of an environmental management system: the case of a public research institution
17 2017 23235 Resumo de eventos cient铆ficos N Comunica莽茫o dos riscos e o plano de emerg锚ncia externo 鈥 um estudo de caso em Angra dos Reis, Rio de Janeiro
18 2017 23513 Artigo de peri贸dico I Psychometric model for safety culture assessment in nuclear research facilities
19 2017 23541 Livro
20 2017 23737 Artigo de peri贸dico I An experimental validation of Feynman-Alpha Method鈥檚 Bunching Technique in the IPEN/MB-01 Nuclear Reator
21 2017 24017 Texto completo de evento I Studies on capacity management for factories of nuclear fuel for research reactors
22 2017 24029 Texto completo de evento I Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly
23 2017 24030 Texto completo de evento I CFD analysis of blockage length on a partially blocked fuel rod
24 2017 24581 Resumo de eventos cient铆ficos I CFD analysis of blockage length on a partially blocked fuel rod
25 2017 24582 Resumo de eventos cient铆ficos I The dissemination of information about nuclear energy and the external emergency plan of the State of Rio de Janeiro, in Angra dos Reis, Brazil
26 2017 24584 Resumo de eventos cient铆ficos I A MTR fuel element flow distribution measurement preliminary results
27 2017 24585 Resumo de eventos cient铆ficos I Increasing the effectiveness of the security system on a nuclear facility
28 2017 24591 Resumo de eventos cient铆ficos I Nuclear forensics
29 2017 24599 Resumo de eventos cient铆ficos I Proposed methodology for evaluating safety levels in WSN on IOT devices in nuclear environments
30 2017 24602 Resumo de eventos cient铆ficos I "Airplane accident involving radiological facility" 鈥 What would happen if you see a newspaper headline like this? The importance of information management in crisis
31 2017 24611 Resumo de eventos cient铆ficos I Instrumented fuel assembly
32 2017 24614 Resumo de eventos cient铆ficos I A CFD numerical model for the flow distribution in a MTR fuel element
33 2017 24841 Resumo de eventos cient铆ficos I Experimental study of radiation influence on thermophysical properties of Al2O3 and ZrO2 nanofluids
34 2016 22778 Texto completo de evento I In vitro study of the composition and microhardness of the hard tissues from oral cavity submitted to gamma irradiation
35 2016 22780 Texto completo de evento N Estudo in vitro da composi莽茫o e microdureza dos tecidos duros da cavidade bucal submetidos 脿 irradia莽茫o gama
36 2016 22781 Texto completo de evento N Estudo in vitro da composi莽茫o e microdureza de tecidos duros da cavidade bucal submetidos 脿 irradiac茫o gama com a dose programada no tratamento de pacientes acometidos com c芒ncer de cabe莽a e pesco莽o
37 2016 22782 Texto completo de evento I Estudio in vitro de la composici贸n y la microdureza de los tejidos duros de la cavidad bucal sometidos a la irradiaci贸n gamma con la dosis usada en el tratamiento de los pacientes con c谩ncer de cabeza y cuello
38 2016 22826 Artigo de peri贸dico I Risk communication and external emergency plan in Angra dos Reis, Brazil
39 2016 22828 Artigo de peri贸dico I Technological perspectives for propulsion on nuclear attack submarines
40 2016 22836 Artigo de peri贸dico I Studies on production planning of dispersion type U3Si2-Al fuel in plate-type fuel elements for nuclear research reactors
41 2016 22940 Inicia莽茫o Cient铆fica N Bancada de testes de vibra莽玫es induzidas por escoamento em elementos combust铆veis de reatores nucleares de pesquisa tipo placas paralelas
42 2016 23151 Texto completo de evento I Estudo num茅rico da inclus茫o de geradores de turbul锚ncia em canal com transfer锚ncia de calor
43 2015 20797 Texto completo de evento I Thermophysical characterization of Alsub(2)Osub(3) and ZrOsub(2) nanofluids as emergency cooling fluids of future generations of nuclear reactors
44 2015 20970 Texto completo de evento I Analysis of experimental routine of high enthalpy steam discharge in subcooled water
45 2015 20971 Texto completo de evento I Preliminary calculation of tornado risk in the site of Iper贸
46 2015 20972 Texto completo de evento I Ant colony optimization and neural networks applied to nuclear power plant monitoring
47 2015 20980 Texto completo de evento I A CFD numerical model for the flow distribution in a MTR fuel element
48 2015 20988 Texto completo de evento I Development of a computational database for probabilistic safety assessment of nuclear research reactors
49 2015 21023 Texto completo de evento I A concept of PWR using plate and shell heat exchangers
50 2015 21041 Texto completo de evento I Gamma stability and powder formation of UMo alloys
51 2015 21073 Texto completo de evento I Self-organizing maps applied to two-phase flow on natural circulation loop studies
52 2015 21082 Texto completo de evento I Simulation of the first step of the coupling of the PARCS/RELAP5 codes to ANGRA 2 facility
53 2015 21137 Texto completo de evento I Characterization of physical properties of Alsub(2)Osub(3) and ZrOsub(2) nanofluids for heat transfer applications
54 2015 21153 Texto completo de evento I Casos de cancer fatal e n茫o fatal ocorridos nas diferentes regi玫es do municipio de S茫o Paulo
55 2015 21261 Artigo de peri贸dico I Historic survey on nuclear merchant ships
56 2015 21267 Artigo de peri贸dico I Evaluation tools for scientific research professionals: A contribution to the strategic planning of R&D institutions
57 2015 21290 Artigo de peri贸dico I Numerical study of the influence of elements inside the wheelhouse on the passenger vehicle aerodynamic
58 2015 21750 Cap铆tulo de livro I IEA-R1 Nuclear Reactor: Facility specification and experimental results
59 2014 20181 Artigo de peri贸dico I Relation between gamma decomposition and powder formation of 'gamma'-U8Mo nuclear fuel alloys via hydrogen embrittlement and thermal shock
60 2014 20279 Artigo de peri贸dico I The future role of the nuclear energy in Brazil in a transition energy scenario
61 2014 20396 Texto completo de evento I Levantamento bibliogr谩fico sobre metodologias para elebora莽茫o de um banco de dados da sa煤de da popula莽茫o em casos de ocorr锚ncias de c芒ncer
62 2014 20703 Artigo de peri贸dico I On applicability of plate and shell heat exchangers for steam generation in naval PWR
63 2014 22008 Inicia莽茫o Cient铆fica N Estudos do escoamento em n煤cleos de reator com elementos combust铆veis tipo placas paralelas
64 2014 22344 Artigo de peri贸dico N Introduction to the integrated environmental management: a case study at the Federal Office of Brazilian Research
65 2013 18765 Cap铆tulo de livro I Stability of 'gamma'UMo nuclear fuel alloys by thermal analysis
66 2013 19332 Texto completo de evento I The process of filing patent applications in the view of ICT inventors
67 2013 19453 Texto completo de evento I Perspectives of heat transfer enhancements in nuclear reactors toward nanofluids applications
68 2013 19461 Texto completo de evento I Risk communication importance
69 2013 19812 Texto completo de evento I The behavior of ANGRA 2 nuclear power plant core for a small break LOCA simulated with RELAP5 code
70 2013 21880 Inicia莽茫o Cient铆fica N Moderniza莽茫o da Bancada experimental Apolo para estudos de elementos combust铆veis do tipo paralelas
71 2013 23885 Resumo de eventos cient铆ficos N Heat transfer mode in the core of the Angra 2 nuclear power plant during small break loca obtained with RELAP5 code
72 2012 18039 Artigo de peri贸dico I A mathematical model for metastable condition determination of highly flashing liquid flows through expansion devices
73 2012 18093 Artigo de peri贸dico I A numerical and three-dimensional analysis of steady state rectangular natural circulation loop
74 2012 18189 Artigo de peri贸dico I Classification of natural circulation two-phase flow patterns using fuzzy inference on image analysis
75 2012 18190 Artigo de peri贸dico I Web-based post-processor for RELAP5: a development based on LabVIEW
76 2012 18200 Texto completo de evento N Flow regime identification in natural circulation phenomenon using RELAP5 code
77 2012 18201 Texto completo de evento N The behaviour of ANGRA 2 nuclear power plant core for a small break LOCA simulated with RELAP5 code
78 2012 18514 Texto completo de evento N ANGRA 2 samll break loca flow regime identification through RELAP5 code
79 2012 19896 Artigo de peri贸dico N Study of stress in nuclear area workers: silent enemy
80 2011 16846 Texto completo de evento I Thermal hydraulics special theme for CFD codes thermal stratification experiments
81 2011 16852 Texto completo de evento I Simulation of a refill/reflood experiment using the RELAP5 thermal-hydraulic code
82 2011 16868 Texto completo de evento I Development of a labview web-based simulator for RELAP5
83 2011 16908 Texto completo de evento I Study of stress in nuclear area workers: silent enemy
84 2011 16918 Texto completo de evento I A RELAP5 study to identify flow regime in natural circulation phenomenon
85 2011 16968 Texto completo de evento I A CFD model for the IEA-R1 reactor heat exchanger inlet nozzle flow
86 2011 17021 Texto completo de evento I Uranium density reduction on fuel element side plates assessment
87 2011 17037 Texto completo de evento I Frequency analysis for the thermal hydraulic characterization of a natural circulation circuit
88 2011 17206 Texto completo de evento I Development of a VBA macro-based spreadsheet application for RELAP5 data post-processing
89 2011 17556 Artigo de peri贸dico I Comparison between experimental data and numerical modeling for the natural circulation phenomenon
90 2011 17845 Artigo de peri贸dico I A three-dimensional thermal and fluid dynamics analysis of a gas cooled subcritical fast reactor driven by a D-T fusion neutron source
91 2011 21621 Inicia莽茫o Cient铆fica N Capacita莽茫o e desenvolvimento de geometrias utilizando modelador s贸lido para an谩lise num茅rica em mec芒nica dos fluidos computacional aplicado a reatores nucleares
92 2010 16126 Texto completo de evento N Analise teorico/experimental do fenomeno de circulacao natural
93 2010 16127 Texto completo de evento N Thermal hydraulic phenomenology in a natural circulation circuit
94 2010 16134 Texto completo de evento I Assessmnet of a heat exchanger inlet nozzle flow using ANSYS-CFX
95 2010 16135 Texto completo de evento N Study of the natural circulation phenomenon for nuclear reactors
96 2010 16860 Texto completo de evento I Study of the natural circulation phenomenon for nuclear reactors
97 2009 14303 Inicia莽茫o Cient铆fica N Modernizacao do circuito de circulacao natural do IPEN/CNEN-SP
98 2009 15274 Texto completo de evento I The decision-making process during accidents or incidents in the operational nuclear data
99 2009 15276 Texto completo de evento I Comparison between experimental data and numerical modeling for the natural circulation phenomenon
100 2009 15277 Texto completo de evento I Thermal hydraulic phenomenology for the heating process in a natural circulation facility
101 2009 15303 Texto completo de evento I Nuclear research reactor IEA-R1 heat exchanger inlet nozzle flow - a preliminary study
102 2009 15394 Texto completo de evento I Two-phase flow patterns recognition and parameters estimation through natural circulation test loop image analysis
103 2008 12256 Artigo de peri贸dico I Multivariate analysis with covariance matrix applied to separative power modeling of a gas centrifuge
104 2008 13460 Texto completo de evento N Analise teorico e experimental do fenomeno de circulacao natural
105 2008 13822 Artigo de peri贸dico N Study of human factors and its basic aspects, focusing the operators of IEA-R1 research reactor
106 2008 13824 Texto completo de evento I Irradiacao de miniplacas de elementos combustiveis tipo dispersao de reatores de pesquisa
107 2007 12165 Texto completo de evento I RELAP5 simulation for one and two phase natural circulation phenomenon
108 2007 12166 Texto completo de evento I Study of human factors and its basec aspects focusing the operators of IEA-R1 research reactor
109 2007 12195 Texto completo de evento I Falcao - a relational database to storaging the variables monitored in the research reactor IEA-R1
110 2006 11567 Texto completo de evento N Analise experimental do fenomeno de circulacao natural
111 2006 11574 Artigo de peri贸dico N Multivariate regression applied to the performance otimization of a countercurrent ultracentrifuge - a preliminary study
112 2005 10640 Texto completo de evento I Simulacao e analise do fenomeno de circulacao natural monofasica e bifasica no circuito experimental instalado na engenharia quimica POLI-USP, com o codigo RELAP5
113 2005 10651 Texto completo de evento I Simulacao de acidentes tipo LOCA em Angra 2 com o codigo RELAP5/MOD3.2
114 2005 10666 Texto completo de evento I Modelagem do poder de separacao de ultracentrifugas por regressao multivariada com matriz de covariancia
115 2005 10697 Texto completo de evento I Modelagem do nucleo do reator IEA-R1 com o codigo RELAP5
116 2004 08437 Inicia莽茫o Cient铆fica N Estudo e an谩lise do fen么meno de circula莽茫o natural mono e bi-f谩sico no circuito experimental instalado na Engenharia Qu铆mica/POLI-USP
117 2004 10902 Texto completo de evento N Regressao multivariada aplicada na otimizacao de performance de ultracentrifugas a contracorrente - um caso preliminar
118 2004 10903 Texto completo de evento N Simulacao de um acidente de perda de refrigerante por grande ruptura na perna quente de usina Angra-2 com o codigo RELAP5/MOD3.2.2G
119 2004 10905 Texto completo de evento I Preliminary transient analysis for the IRIS reactor pressurizer with RELAP5/Mod3.3 code
120 2004 10910 Texto completo de evento N Analise termo-hidraulica das placas externas de um elemento combustivel tipo placa utilizado no reator de pesquisa IEA-R1
121 2003 09552 Texto completo de evento I A MTR fuel element flow distribution measurement preliminary results
122 2003 09553 Texto completo de evento I Thermal-hydraulic design of a fuel mini-plate irradiator for the IEA-R1 research reactor
123 2003 09555 Texto completo de evento I Fuel performance during in LBLOCA in Angra 1 Nuclear Power Plant
124 2003 09886 Texto completo de evento I Simulacao de um acidente de perda de refrigerante primario por grande ruptura para Angra 2 com o codigo RELAP3/Mod3.2.2g
125 2002 08669 Texto completo de evento I Simulacao de um acidente postulado de perda de refrigerante primario por pequena ruptura na Usina Angra-2 com o codigo RELAP 5/MOD3.2.2g
126 2002 08676 Texto completo de evento I Dimensionamento termo-hidraulico de um dispositivo de irradiacao de mini-placas combustiveis para o reator IEA-R1
127 2002 09275 Texto completo de evento I CNEN in the IRIS Project
128 2002 09298 Texto completo de evento I Simulacao de Angra 2 com o codigo RELAP5/MOD3.2.2G gamma version
129 2002 09327 Artigo de peri贸dico N Simulacao de um acidente postulado de perda de refrigerante primario por pequena ruptura na Usina Angra-2 com o codigo RELAP 5/MOD3.2.2g
130 2002 09333 Artigo de peri贸dico N Dimensionamento termo-hidraulico de um dispositivo de irradiacao de mini-placas combustiveis para o reator IEA-R1
131 2001 07046 Texto completo de evento I Simulacao do acidente postulado de parada das bombas do circuito primario de Angra 2 com o codigo RELAP5/MOD3.2
132 2001 07047 Texto completo de evento I Modelagem do circuito primario de Angra 2 com o codigo RELAP5/MOD3.2.2G
133 2001 07112 Texto completo de evento N Analise do resfriamento de canais entre elementos combustiveis de reatores de pesquisa
134 2000 07912 Texto completo de evento I Two-phase flow instabilities in a natural circulation rectangular loop
135 2000 08441 Texto completo de evento N Simulacao de Angra 2 com o codigo RELAP5/MOD3.2.2 gamma version
136 1999 06481 Tese N Analise termo hidrodinamica de uma centrifuga a contracorrente
137 1998 06191 Artigo de peri贸dico I Thermal hydrodynamical analysis of a countercurrent gas centrifuge
138 1997 04989 Texto completo de evento N Analise termica de uma centrifuga a gas para separacao de isotopos)
139 1996 04749 Texto completo de evento N Thermal analysis of a gas centrifuge

Quadro resumo por ano e tipo de publicação gerada em tempo real a partir do registro dos dados do autor no Repositório Digital/IPEN
13/12/2018 11:50:28
Ano Periódicos Periódicos Resumos Eventos Eventos Resumos Teses / Dissertações Livros Capítulos de Livros Relatório
Técnico
Iniciação
Científica
Total
Inter. Nac. Inter. Nac. Inter. Nac. Inter. Nac. Mest. Dout. Mplo. Inter. Nac. Inter. Nac.
Total 33 6 61 17 10 2 1 1 2 139
2018 10 1 11
2017 6 4 10 1 1 22
2016 3 3 2 9
2015 3 12 1 16
2014 3 1 1 6
2013 4 1 1 7
2012 4 1 3 8
2011 2 9 12
2010 2 3 5
2009 5 6
2008 1 1 1 1 4
2007 3 3
2006 1 1 2
2005 4 4
2004 1 3 5
2003 4 4
2002 2 4 6
2001 2 1 3
2000 1 1 2
1999 1 1
1998 1 1
1997 1 1
1996 1 1