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

 

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 periódico	N	A simulation model for capacity planning of nuclear fuel plants for research reactors
2	2021	27927	Artigo de periódico	N	Entering new markets
3	2021	27928	Artigo de periódico	N	Potential advantages of molten salt reactor for merchant ship propulsion
4	2020	25565	Artigo de periódico	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 periódico	N	Computer simulator for the research reactor IPEN/MB-01
7	2020	27565	Artigo de periódico	I	Nutritional evaluation of Brachiaria brizantha cv. marandu using convolutional neural networks
8	2020	27581	Artigo de periódico	N	Fundamentos de proteção radiológica para condução de submarinos nucleares
9	2020	27651	Resumo de eventos científicos	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	Capítulo de livro	I	Economic evaluation of a mobile nuclear power plant using uranium over 5% enrichment
12	2020	27722	Artigo de periódico	N	Modeling dynamic scenarios for safety, reliability, availability, and maintainability analysis
13	2019	25205	Artigo de periódico	I	Economically feasible mobile nuclear power plant for merchant ships and remote clients
14	2019	25802	Artigo de periódico	I	New formulation for semi-empirical correlations for penetration jets
15	2019	25814	Artigo de periódico	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 periódico	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 periódico	N	A CFD analysis of blockage length on a partially blocked fuel rod
27	2019	26714	Livro	N	O IPEN e a saúde
28	2019	26777	Resumo de eventos científicos	I	The four functions of elementary pipe design from constructal law
29	2018	24364	Artigo de periódico	I	Perfil epidemiológico e clínico dos casos de tuberculose em Ipatinga, Minas Gerais
30	2018	24733	Artigo de periódico	I	Constructal law of institutions within social organizations
31	2018	24758	Artigo de periódico	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 periódico	I	Studies on capacity expansion of fuel plants for nuclear research reactors
33	2018	24772	Artigo de periódico	I	Technological perspectives for propulsion on nuclear attack submarines
34	2018	24789	Artigo de periódico	I	Proposal of a methodology for the assessment of security levels of IoT wireless sensor networks in nuclear environments
35	2018	24790	Artigo de periódico	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 periódico	I	Thermal hydraulic analysis improvement for the IEA-R1 research reactor and fuel assembly design modification
38	2018	25071	Artigo de periódico	I	Two-phase flow bubble detection method applied to natural circulation system using fuzzy image processing
39	2018	25094	Artigo de periódico	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 periódico	I	Perfil de pacientes oncológicos tratados con láser 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 periódico	I	The role of nuclear power from a system engineering standpoint
45	2017	23123	Artigo de periódico	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 periódico	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 periódico	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 científicos	N	Comunicação dos riscos e o plano de emergência externo – um estudo de caso em Angra dos Reis, Rio de Janeiro
49	2017	23513	Artigo de periódico	I	Psychometric model for safety culture assessment in nuclear research facilities
50	2017	23541	Livro	I	Radioterapia Oncológica: efectos y repercusión en la cavidad bucal
51	2017	23737	Artigo de periódico	I	An experimental validation of Feynman-Alpha Method’s 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 científicos	I	CFD analysis of blockage length on a partially blocked fuel rod
56	2017	24582	Resumo de eventos científicos	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 científicos	I	A MTR fuel element flow distribution measurement preliminary results
58	2017	24585	Resumo de eventos científicos	I	Increasing the effectiveness of the security system on a nuclear facility
59	2017	24591	Resumo de eventos científicos	I	Nuclear forensics
60	2017	24599	Resumo de eventos científicos	I	Proposed methodology for evaluating safety levels in WSN on IOT devices in nuclear environments
61	2017	24602	Resumo de eventos científicos	I	"Airplane accident involving radiological facility" – What would happen if you see a newspaper headline like this? The importance of information management in crisis
62	2017	24611	Resumo de eventos científicos	I	Instrumented fuel assembly
63	2017	24614	Resumo de eventos científicos	I	A CFD numerical model for the flow distribution in a MTR fuel element
64	2017	24841	Resumo de eventos científicos	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 composição e microdureza dos tecidos duros da cavidade bucal submetidos à irradiação gama
67	2016	22781	Texto completo de evento	N	Estudo in vitro da composição e microdureza de tecidos duros da cavidade bucal submetidos à irradiacão gama com a dose programada no tratamento de pacientes acometidos com câncer de cabeça e pescoço
68	2016	22782	Texto completo de evento	I	Estudio in vitro de la composición y la microdureza de los tejidos duros de la cavidad bucal sometidos a la irradiación gamma con la dosis usada en el tratamiento de los pacientes con cáncer de cabeza y cuello
69	2016	22826	Artigo de periódico	I	Risk communication and external emergency plan in Angra dos Reis, Brazil
70	2016	22828	Artigo de periódico	I	Technological perspectives for propulsion on nuclear attack submarines
71	2016	22836	Artigo de periódico	I	Studies on production planning of dispersion type U3Si2-Al fuel in plate-type fuel elements for nuclear research reactors
72	2016	22940	Iniciação Científica	N	Bancada de testes de vibrações induzidas por escoamento em elementos combustíveis de reatores nucleares de pesquisa tipo placas paralelas
73	2016	23151	Texto completo de evento	I	Estudo numérico da inclusão de geradores de turbulência em canal com transferência 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 Iperó
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 não fatal ocorridos nas diferentes regiões do municipio de São Paulo
86	2015	21261	Artigo de periódico	I	Historic survey on nuclear merchant ships
87	2015	21267	Artigo de periódico	I	Evaluation tools for scientific research professionals: A contribution to the strategic planning of R&D institutions
88	2015	21290	Artigo de periódico	I	Numerical study of the influence of elements inside the wheelhouse on the passenger vehicle aerodynamic
89	2015	21750	Capítulo de livro	I	IEA-R1 Nuclear Reactor: Facility specification and experimental results
90	2015	26920	Artigo de periódico	N	Levantamento bibliográfico sobre metodologias para elaboração de um banco de dados da saúde da população em casos de ocorrências de câncer
91	2014	20181	Artigo de periódico	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 periódico	I	The future role of the nuclear energy in Brazil in a transition energy scenario
93	2014	20396	Texto completo de evento	I	Levantamento bibliográfico sobre metodologias para eleboração de um banco de dados da saúde da população em casos de ocorrências de câncer
94	2014	20703	Artigo de periódico	I	On applicability of plate and shell heat exchangers for steam generation in naval PWR
95	2014	22008	Iniciação Científica	N	Estudos do escoamento em núcleos de reator com elementos combustíveis tipo placas paralelas
96	2014	22344	Artigo de periódico	N	Introduction to the integrated environmental management: a case study at the Federal Office of Brazilian Research
97	2013	18765	Capítulo 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	Iniciação Científica	N	Modernização da Bancada experimental Apolo para estudos de elementos combustíveis do tipo paralelas
103	2013	23885	Resumo de eventos científicos	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 periódico	I	A mathematical model for metastable condition determination of highly flashing liquid flows through expansion devices
105	2012	18093	Artigo de periódico	I	A numerical and three-dimensional analysis of steady state rectangular natural circulation loop
106	2012	18189	Artigo de periódico	I	Classification of natural circulation two-phase flow patterns using fuzzy inference on image analysis
107	2012	18190	Artigo de periódico	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 periódico	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 periódico	I	Comparison between experimental data and numerical modeling for the natural circulation phenomenon
122	2011	17845	Artigo de periódico	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	Iniciação Científica	N	Capacitação e desenvolvimento de geometrias utilizando modelador sólido para análise numérica em mecânica 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	Iniciação Científica	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 periódico	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 periódico	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 periódico	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	Iniciação Científica	N	Estudo e análise do fenômeno de circulação natural mono e bi-fásico no circuito experimental instalado na Engenharia Química/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	Simulação de Angra 2 com o código RELAP5/MOD3.2.2G gamma version
161	2002	09327	Artigo de periódico	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 periódico	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 periódico	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