INSTITUTO DE PESQUISAS ENERGÉTICAS E NUCLEARES
Repositório Digital da Produção Técnico Científica
Biblioteca Terezine Arantes Ferraz
   

 
Voltar
Nome : DELVONEI ALVES DE ANDRADE

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

 

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

 
Publicações do autor   DELVONEI ALVES DE ANDRADE    depositadas no Repositório Digital/IPEN - Total : 171
Seq Ano Ipen_doc Tipo Circ. Título
1 2021 27846 Artigo de peri贸dico N A simulation model for capacity planning of nuclear fuel plants for research reactors
2 2021 27927 Artigo de peri贸dico N Entering new markets
3 2021 27928 Artigo de peri贸dico N Potential advantages of molten salt reactor for merchant ship propulsion
4 2020 25565 Artigo de peri贸dico I Two-phase flow void fraction estimation based on bubble image segmentation using Randomized Hough Transform with Neural Network (RHTN)
5 2020 27185 Livro N IPEN e a nanotecnologia
6 2020 27372 Artigo de peri贸dico N Computer simulator for the research reactor IPEN/MB-01
7 2020 27565 Artigo de peri贸dico I Nutritional evaluation of Brachiaria brizantha cv. marandu using convolutional neural networks
8 2020 27581 Artigo de peri贸dico N Fundamentos de prote莽茫o radiol贸gica para condu莽茫o de submarinos nucleares
9 2020 27651 Resumo de eventos cient铆ficos I Investigation on the improvement of thermal properties of TiO2 nanofluids
10 2020 27678 Texto completo de evento I CFD simulation of isothermal upward two-phase flow in a vertical tube of annular section
11 2020 27692 Cap铆tulo de livro I Economic evaluation of a mobile nuclear power plant using uranium over 5% enrichment
12 2020 27722 Artigo de peri贸dico N Modeling dynamic scenarios for safety, reliability, availability, and maintainability analysis
13 2019 25205 Artigo de peri贸dico I Economically feasible mobile nuclear power plant for merchant ships and remote clients
14 2019 25802 Artigo de peri贸dico I New formulation for semi-empirical correlations for penetration jets
15 2019 25814 Artigo de peri贸dico I Procedures for manufacturing an instrumented nuclear fuel element
16 2019 25917 Texto completo de evento I Subcritical boron experiments in the IPEN/MB-01 reactor
17 2019 25933 Artigo de peri贸dico I A reliability-based strategy for the analysis of single proton exchange membrane fuel cells
18 2019 26330 Texto completo de evento I Entering new markets
19 2019 26332 Texto completo de evento I Methodology proposal for assessing safety in WSN and IoT devices in nuclear research laboratory
20 2019 26334 Texto completo de evento I Potential advantages of molten salt reactor for merchant ship propulsion
21 2019 26335 Texto completo de evento I Adherence of the IPEN post-graduation program dissertations to the ABNT norms
22 2019 26346 Texto completo de evento I Status of the development of a fuel assembly decay heat calorimeter for the IEA-R1 nuclear research reactor
23 2019 26376 Texto completo de evento I Modeling dynamic scenarios for safety, reliability, availability and maintainability analysis
24 2019 26385 Texto completo de evento I Preliminary numerical analysis of the flow distribution in the core of a research reactor
25 2019 26386 Texto completo de evento I Proposal for a nuclear power-plant ship decomissioning
26 2019 26394 Artigo de peri贸dico N A CFD analysis of blockage length on a partially blocked fuel rod
27 2019 26714 Livro N O IPEN e a sa煤de
28 2019 26777 Resumo de eventos cient铆ficos I The four functions of elementary pipe design from constructal law
29 2018 24364 Artigo de peri贸dico I Perfil epidemiol贸gico e cl铆nico dos casos de tuberculose em Ipatinga, Minas Gerais
30 2018 24733 Artigo de peri贸dico I Constructal law of institutions within social organizations
31 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
32 2018 24764 Artigo de peri贸dico I Studies on capacity expansion of fuel plants for nuclear research reactors
33 2018 24772 Artigo de peri贸dico I Technological perspectives for propulsion on nuclear attack submarines
34 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
35 2018 24790 Artigo de peri贸dico I A CFD analysis of the flow dynamics of a directly-operated safety relief valve
36 2018 24791 Texto completo de evento I Transient cfd analysis of the flow inversion of the nuclear research reactor IEA-R1
37 2018 24804 Artigo de peri贸dico I Thermal hydraulic analysis improvement for the IEA-R1 research reactor and fuel assembly design modification
38 2018 25071 Artigo de peri贸dico I Two-phase flow bubble detection method applied to natural circulation system using fuzzy image processing
39 2018 25094 Artigo de peri贸dico I A system status definition to improve behavior description in specifications based on constructal law
40 2018 25523 Texto completo de evento I Experimental investigation of critical velocity in fuel element for the RMB reactor
41 2018 25543 Texto completo de evento I A proposal for WSN cybersecurity levels for IoT devices in nuclear research facilities
42 2018 25868 Artigo de peri贸dico I Perfil de pacientes oncol贸gicos tratados con l谩ser de baja intensidad
43 2017 23036 Texto completo de evento I Numerical simulation of isothermal upward two-phase flow in a vertical tube of annular section
44 2017 23045 Artigo de peri贸dico I The role of nuclear power from a system engineering standpoint
45 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
46 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
47 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
48 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
49 2017 23513 Artigo de peri贸dico I Psychometric model for safety culture assessment in nuclear research facilities
50 2017 23541 Livro I Radioterapia Oncol贸gica: efectos y repercusi贸n en la cavidad bucal
51 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
52 2017 24017 Texto completo de evento I Studies on capacity management for factories of nuclear fuel for research reactors
53 2017 24029 Texto completo de evento I Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly
54 2017 24030 Texto completo de evento I CFD analysis of blockage length on a partially blocked fuel rod
55 2017 24581 Resumo de eventos cient铆ficos I CFD analysis of blockage length on a partially blocked fuel rod
56 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
57 2017 24584 Resumo de eventos cient铆ficos I A MTR fuel element flow distribution measurement preliminary results
58 2017 24585 Resumo de eventos cient铆ficos I Increasing the effectiveness of the security system on a nuclear facility
59 2017 24591 Resumo de eventos cient铆ficos I Nuclear forensics
60 2017 24599 Resumo de eventos cient铆ficos I Proposed methodology for evaluating safety levels in WSN on IOT devices in nuclear environments
61 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
62 2017 24611 Resumo de eventos cient铆ficos I Instrumented fuel assembly
63 2017 24614 Resumo de eventos cient铆ficos I A CFD numerical model for the flow distribution in a MTR fuel element
64 2017 24841 Resumo de eventos cient铆ficos I Experimental study of radiation influence on thermophysical properties of Al2O3 and ZrO2 nanofluids
65 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
66 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
67 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
68 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
69 2016 22826 Artigo de peri贸dico I Risk communication and external emergency plan in Angra dos Reis, Brazil
70 2016 22828 Artigo de peri贸dico I Technological perspectives for propulsion on nuclear attack submarines
71 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
72 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
73 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
74 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
75 2015 20970 Texto completo de evento I Analysis of experimental routine of high enthalpy steam discharge in subcooled water
76 2015 20971 Texto completo de evento I Preliminary calculation of tornado risk in the site of Iper贸
77 2015 20972 Texto completo de evento I Ant colony optimization and neural networks applied to nuclear power plant monitoring
78 2015 20980 Texto completo de evento I A CFD numerical model for the flow distribution in a MTR fuel element
79 2015 20988 Texto completo de evento I Development of a computational database for probabilistic safety assessment of nuclear research reactors
80 2015 21023 Texto completo de evento I A concept of PWR using plate and shell heat exchangers
81 2015 21041 Texto completo de evento I Gamma stability and powder formation of UMo alloys
82 2015 21073 Texto completo de evento I Self-organizing maps applied to two-phase flow on natural circulation loop studies
83 2015 21082 Texto completo de evento I Simulation of the first step of the coupling of the PARCS/RELAP5 codes to ANGRA 2 facility
84 2015 21137 Texto completo de evento I Characterization of physical properties of Alsub(2)Osub(3) and ZrOsub(2) nanofluids for heat transfer applications
85 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
86 2015 21261 Artigo de peri贸dico I Historic survey on nuclear merchant ships
87 2015 21267 Artigo de peri贸dico I Evaluation tools for scientific research professionals: A contribution to the strategic planning of R&D institutions
88 2015 21290 Artigo de peri贸dico I Numerical study of the influence of elements inside the wheelhouse on the passenger vehicle aerodynamic
89 2015 21750 Cap铆tulo de livro I IEA-R1 Nuclear Reactor: Facility specification and experimental results
90 2015 26920 Artigo de peri贸dico N Levantamento bibliogr谩fico sobre metodologias para elabora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
91 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
92 2014 20279 Artigo de peri贸dico I The future role of the nuclear energy in Brazil in a transition energy scenario
93 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
94 2014 20703 Artigo de peri贸dico I On applicability of plate and shell heat exchangers for steam generation in naval PWR
95 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
96 2014 22344 Artigo de peri贸dico N Introduction to the integrated environmental management: a case study at the Federal Office of Brazilian Research
97 2013 18765 Cap铆tulo de livro I Stability of 'gamma'UMo nuclear fuel alloys by thermal analysis
98 2013 19332 Texto completo de evento I The process of filing patent applications in the view of ICT inventors
99 2013 19453 Texto completo de evento I Perspectives of heat transfer enhancements in nuclear reactors toward nanofluids applications
100 2013 19461 Texto completo de evento I Risk communication importance
101 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
102 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
103 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
104 2012 18039 Artigo de peri贸dico I A mathematical model for metastable condition determination of highly flashing liquid flows through expansion devices
105 2012 18093 Artigo de peri贸dico I A numerical and three-dimensional analysis of steady state rectangular natural circulation loop
106 2012 18189 Artigo de peri贸dico I Classification of natural circulation two-phase flow patterns using fuzzy inference on image analysis
107 2012 18190 Artigo de peri贸dico I Web-based post-processor for RELAP5: a development based on LabVIEW
108 2012 18200 Texto completo de evento N Flow regime identification in natural circulation phenomenon using RELAP5 code
109 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
110 2012 18514 Texto completo de evento N ANGRA 2 samll break loca flow regime identification through RELAP5 code
111 2012 19896 Artigo de peri贸dico N Study of stress in nuclear area workers: silent enemy
112 2011 16846 Texto completo de evento I Thermal hydraulics special theme for CFD codes thermal stratification experiments
113 2011 16852 Texto completo de evento I Simulation of a refill/reflood experiment using the RELAP5 thermal-hydraulic code
114 2011 16868 Texto completo de evento I Development of a labview web-based simulator for RELAP5
115 2011 16908 Texto completo de evento I Study of stress in nuclear area workers: silent enemy
116 2011 16918 Texto completo de evento I A RELAP5 study to identify flow regime in natural circulation phenomenon
117 2011 16968 Texto completo de evento I A CFD model for the IEA-R1 reactor heat exchanger inlet nozzle flow
118 2011 17021 Texto completo de evento I Uranium density reduction on fuel element side plates assessment
119 2011 17037 Texto completo de evento I Frequency analysis for the thermal hydraulic characterization of a natural circulation circuit
120 2011 17206 Texto completo de evento I Development of a VBA macro-based spreadsheet application for RELAP5 data post-processing
121 2011 17556 Artigo de peri贸dico I Comparison between experimental data and numerical modeling for the natural circulation phenomenon
122 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
123 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
124 2010 16126 Texto completo de evento N Analise teorico/experimental do fenomeno de circulacao natural
125 2010 16127 Texto completo de evento N Thermal hydraulic phenomenology in a natural circulation circuit
126 2010 16134 Texto completo de evento I Assessmnet of a heat exchanger inlet nozzle flow using ANSYS-CFX
127 2010 16135 Texto completo de evento N Study of the natural circulation phenomenon for nuclear reactors
128 2010 16860 Texto completo de evento I Study of the natural circulation phenomenon for nuclear reactors
129 2009 14303 Inicia莽茫o Cient铆fica N Modernizacao do circuito de circulacao natural do IPEN/CNEN-SP
130 2009 15274 Texto completo de evento I The decision-making process during accidents or incidents in the operational nuclear data
131 2009 15276 Texto completo de evento I Comparison between experimental data and numerical modeling for the natural circulation phenomenon
132 2009 15277 Texto completo de evento I Thermal hydraulic phenomenology for the heating process in a natural circulation facility
133 2009 15303 Texto completo de evento I Nuclear research reactor IEA-R1 heat exchanger inlet nozzle flow - a preliminary study
134 2009 15394 Texto completo de evento I Two-phase flow patterns recognition and parameters estimation through natural circulation test loop image analysis
135 2008 12256 Artigo de peri贸dico I Multivariate analysis with covariance matrix applied to separative power modeling of a gas centrifuge
136 2008 13460 Texto completo de evento N Analise teorico e experimental do fenomeno de circulacao natural
137 2008 13822 Artigo de peri贸dico N Study of human factors and its basic aspects, focusing the operators of IEA-R1 research reactor
138 2008 13824 Texto completo de evento I Irradiacao de miniplacas de elementos combustiveis tipo dispersao de reatores de pesquisa
139 2007 12165 Texto completo de evento I RELAP5 simulation for one and two phase natural circulation phenomenon
140 2007 12166 Texto completo de evento I Study of human factors and its basec aspects focusing the operators of IEA-R1 research reactor
141 2007 12195 Texto completo de evento I Falcao - a relational database to storaging the variables monitored in the research reactor IEA-R1
142 2006 11567 Texto completo de evento N Analise experimental do fenomeno de circulacao natural
143 2006 11574 Artigo de peri贸dico N Multivariate regression applied to the performance otimization of a countercurrent ultracentrifuge - a preliminary study
144 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
145 2005 10651 Texto completo de evento I Simulacao de acidentes tipo LOCA em Angra 2 com o codigo RELAP5/MOD3.2
146 2005 10666 Texto completo de evento I Modelagem do poder de separacao de ultracentrifugas por regressao multivariada com matriz de covariancia
147 2005 10697 Texto completo de evento I Modelagem do nucleo do reator IEA-R1 com o codigo RELAP5
148 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
149 2004 10902 Texto completo de evento N Regressao multivariada aplicada na otimizacao de performance de ultracentrifugas a contracorrente - um caso preliminar
150 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
151 2004 10905 Texto completo de evento I Preliminary transient analysis for the IRIS reactor pressurizer with RELAP5/Mod3.3 code
152 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
153 2003 09552 Texto completo de evento I A MTR fuel element flow distribution measurement preliminary results
154 2003 09553 Texto completo de evento I Thermal-hydraulic design of a fuel mini-plate irradiator for the IEA-R1 research reactor
155 2003 09555 Texto completo de evento I Fuel performance during in LBLOCA in Angra 1 Nuclear Power Plant
156 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
157 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
158 2002 08676 Texto completo de evento I Dimensionamento termo-hidraulico de um dispositivo de irradiacao de mini-placas combustiveis para o reator IEA-R1
159 2002 09275 Texto completo de evento I CNEN in the IRIS Project
160 2002 09298 Texto completo de evento I Simula莽茫o de Angra 2 com o c贸digo RELAP5/MOD3.2.2G gamma version
161 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
162 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
163 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
164 2001 07047 Texto completo de evento I Modelagem do circuito primario de Angra 2 com o codigo RELAP5/MOD3.2.2G
165 2001 07112 Texto completo de evento N Analise do resfriamento de canais entre elementos combustiveis de reatores de pesquisa
166 2000 07912 Texto completo de evento I Two-phase flow instabilities in a natural circulation rectangular loop
167 2000 08441 Texto completo de evento N Simulacao de Angra 2 com o codigo RELAP5/MOD3.2.2 gamma version
168 1999 06481 Tese N Analise termo hidrodinamica de uma centrifuga a contracorrente
169 1998 06191 Artigo de peri贸dico I Thermal hydrodynamical analysis of a countercurrent gas centrifuge
170 1997 04989 Texto completo de evento N Analise termica de uma centrifuga a gas para separacao de isotopos)
171 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   DELVONEI ALVES DE ANDRADE    no Repositório Digital/IPEN
28/09/2021 10:14:52
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 40 14 73 17 12 2 1 1 2 3 171
2021 3 3
2020 2 3 1 1 1 1 9
2019 4 1 9 1 1 16
2018 11 3 14
2017 6 4 10 1 1 22
2016 3 3 2 9
2015 3 1 12 1 17
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