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 : 188
Seq	Ano	Ipen_doc	Tipo	Circ.	Título
1	2022	28697	Artigo de periódico	I	Análises de amostras ambientais para fins de salvaguardas nucleares no Brasil
2	2022	28705	Capítulo de livro	N	Medida de distribuição de vazão no núcleo do reator IEA-R1 usando o elemento DMPV-01
3	2022	28706	Capítulo de livro	N	Estudos e ações corretivas para aumentar a vazão do núcleo ativo do reator IEA-R1
4	2022	28707	Capítulo de livro	N	Comparação entre a queda de pressão no DMPV-01 e queda de pressão no núcleo do reator IEA-R1 medida pelo instrumento do sistema
5	2022	28708	Capítulo de livro	N	Distribuição de vazão entre os canais de resfriamento do elemento combustível do IEA-R1
6	2021	27846	Artigo de periódico	N	A simulation model for capacity planning of nuclear fuel plants for research reactors
7	2021	27927	Artigo de periódico	N	Entering new markets
8	2021	27928	Artigo de periódico	N	Potential advantages of molten salt reactor for merchant ship propulsion
9	2021	28138	Artigo de periódico	I	Novel aspects of constructal law
10	2021	28148	Artigo de periódico	I	Characterization of polyacrylonitrile thermal stabilization process for carbon fiber production using intelligent algorithms
11	2021	28167	Artigo de periódico	I	Novel technological developments with impacts on perspectives for mobile nuclear power plants
12	2021	28224	Texto completo de evento	I	Functional analysis, diversity and defense-in-depth principle applied for instrumentation and control architecture in accordance with U.S.NRC
13	2021	28252	Texto completo de evento	I	On the commercial feasibility of decommissioning a nuclear power plant ship
14	2021	28304	Texto completo de evento	I	Very High Temperature Reactor (VHTR)
15	2021	28510	Artigo de periódico	I	Preliminary survey on cold fusion
16	2021	28529	Artigo de periódico	I	RANS-based CFD calculation for pressure drop and mass flow rate distribution in an MTR fuel assembly
17	2021	28576	Resumo de eventos científicos	I	A hypothesis of kinetics and dynamic control of nuclear reactions in solids
18	2021	28577	Resumo de eventos científicos	I	A survey on the evolution of yearly works on Pd-D, Ti-D and Ni-H systems within cold fusion field
19	2021	28578	Resumo de eventos científicos	I	Some facts about nuclear forces and evidence of their range being longer than people believe
20	2021	28627	Texto completo de evento	I	Clean and safe nuclear power
21	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)
22	2020	27185	Livro	N	IPEN e a nanotecnologia
23	2020	27372	Artigo de periódico	N	Computer simulator for the research reactor IPEN/MB-01
24	2020	27565	Artigo de periódico	I	Nutritional evaluation of Brachiaria brizantha cv. marandu using convolutional neural networks
25	2020	27581	Artigo de periódico	N	Fundamentos de proteção radiológica para condução de submarinos nucleares
26	2020	27651	Resumo de eventos científicos	I	Investigation on the improvement of thermal properties of TiO2 nanofluids
27	2020	27678	Texto completo de evento	I	CFD simulation of isothermal upward two-phase flow in a vertical tube of annular section
28	2020	27692	Capítulo de livro	I	Economic evaluation of a mobile nuclear power plant using uranium over 5% enrichment
29	2020	27722	Artigo de periódico	N	Modeling dynamic scenarios for safety, reliability, availability, and maintainability analysis
30	2019	25205	Artigo de periódico	I	Economically feasible mobile nuclear power plant for merchant ships and remote clients
31	2019	25802	Artigo de periódico	I	New formulation for semi-empirical correlations for penetration jets
32	2019	25814	Artigo de periódico	I	Procedures for manufacturing an instrumented nuclear fuel element
33	2019	25917	Texto completo de evento	I	Subcritical boron experiments in the IPEN/MB-01 reactor
34	2019	25933	Artigo de periódico	I	A reliability-based strategy for the analysis of single proton exchange membrane fuel cells
35	2019	26330	Texto completo de evento	I	Entering new markets
36	2019	26332	Texto completo de evento	I	Methodology proposal for assessing safety in WSN and IoT devices in nuclear research laboratory
37	2019	26334	Texto completo de evento	I	Potential advantages of molten salt reactor for merchant ship propulsion
38	2019	26335	Texto completo de evento	I	Adherence of the IPEN post-graduation program dissertations to the ABNT norms
39	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
40	2019	26376	Texto completo de evento	I	Modeling dynamic scenarios for safety, reliability, availability and maintainability analysis
41	2019	26385	Texto completo de evento	I	Preliminary numerical analysis of the flow distribution in the core of a research reactor
42	2019	26386	Texto completo de evento	I	Proposal for a nuclear power-plant ship decomissioning
43	2019	26394	Artigo de periódico	N	A CFD analysis of blockage length on a partially blocked fuel rod
44	2019	26714	Livro	N	O IPEN e a saúde
45	2019	26777	Resumo de eventos científicos	I	The four functions of elementary pipe design from constructal law
46	2018	24364	Artigo de periódico	I	Perfil epidemiológico e clínico dos casos de tuberculose em Ipatinga, Minas Gerais
47	2018	24733	Artigo de periódico	I	Constructal law of institutions within social organizations
48	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
49	2018	24764	Artigo de periódico	I	Studies on capacity expansion of fuel plants for nuclear research reactors
50	2018	24772	Artigo de periódico	I	Technological perspectives for propulsion on nuclear attack submarines
51	2018	24789	Artigo de periódico	I	Proposal of a methodology for the assessment of security levels of IoT wireless sensor networks in nuclear environments
52	2018	24790	Artigo de periódico	I	A CFD analysis of the flow dynamics of a directly-operated safety relief valve
53	2018	24791	Texto completo de evento	I	Transient cfd analysis of the flow inversion of the nuclear research reactor IEA-R1
54	2018	24804	Artigo de periódico	I	Thermal hydraulic analysis improvement for the IEA-R1 research reactor and fuel assembly design modification
55	2018	25071	Artigo de periódico	I	Two-phase flow bubble detection method applied to natural circulation system using fuzzy image processing
56	2018	25094	Artigo de periódico	I	A system status definition to improve behavior description in specifications based on constructal law
57	2018	25523	Texto completo de evento	I	Experimental investigation of critical velocity in fuel element for the RMB reactor
58	2018	25543	Texto completo de evento	I	A proposal for WSN cybersecurity levels for IoT devices in nuclear research facilities
59	2018	25868	Artigo de periódico	I	Perfil de pacientes oncológicos tratados con láser de baja intensidad
60	2017	23036	Texto completo de evento	I	Numerical simulation of isothermal upward two-phase flow in a vertical tube of annular section
61	2017	23045	Artigo de periódico	I	The role of nuclear power from a system engineering standpoint
62	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
63	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
64	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
65	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
66	2017	23513	Artigo de periódico	I	Psychometric model for safety culture assessment in nuclear research facilities
67	2017	23541	Livro	I	Radioterapia Oncológica: efectos y repercusión en la cavidad bucal
68	2017	23737	Artigo de periódico	I	An experimental validation of Feynman-Alpha Method’s Bunching Technique in the IPEN/MB-01 Nuclear Reator
69	2017	24017	Texto completo de evento	I	Studies on capacity management for factories of nuclear fuel for research reactors
70	2017	24029	Texto completo de evento	I	Experimental investigation of critical velocity in a parallel plate research reactor fuel assembly
71	2017	24030	Texto completo de evento	I	CFD analysis of blockage length on a partially blocked fuel rod
72	2017	24581	Resumo de eventos científicos	I	CFD analysis of blockage length on a partially blocked fuel rod
73	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
74	2017	24584	Resumo de eventos científicos	I	A MTR fuel element flow distribution measurement preliminary results
75	2017	24585	Resumo de eventos científicos	I	Increasing the effectiveness of the security system on a nuclear facility
76	2017	24591	Resumo de eventos científicos	I	Nuclear forensics
77	2017	24599	Resumo de eventos científicos	I	Proposed methodology for evaluating safety levels in WSN on IOT devices in nuclear environments
78	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
79	2017	24611	Resumo de eventos científicos	I	Instrumented fuel assembly
80	2017	24614	Resumo de eventos científicos	I	A CFD numerical model for the flow distribution in a MTR fuel element
81	2017	24841	Resumo de eventos científicos	I	Experimental study of radiation influence on thermophysical properties of Al2O3 and ZrO2 nanofluids
82	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
83	2016	22780	Texto completo de evento	N	Estudo in vitro da composição e microdureza dos tecidos duros da cavidade bucal submetidos à irradiação gama
84	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
85	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
86	2016	22826	Artigo de periódico	I	Risk communication and external emergency plan in Angra dos Reis, Brazil
87	2016	22828	Artigo de periódico	I	Technological perspectives for propulsion on nuclear attack submarines
88	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
89	2016	22940	Iniciação Científica	N	Bancada de testes de vibrações induzidas por escoamento em elementos combustíveis de reatores nucleares de pesquisa tipo placas paralelas
90	2016	23151	Texto completo de evento	I	Estudo numérico da inclusão de geradores de turbulência em canal com transferência de calor
91	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
92	2015	20970	Texto completo de evento	I	Analysis of experimental routine of high enthalpy steam discharge in subcooled water
93	2015	20971	Texto completo de evento	I	Preliminary calculation of tornado risk in the site of Iperó
94	2015	20972	Texto completo de evento	I	Ant colony optimization and neural networks applied to nuclear power plant monitoring
95	2015	20980	Texto completo de evento	I	A CFD numerical model for the flow distribution in a MTR fuel element
96	2015	20988	Texto completo de evento	I	Development of a computational database for probabilistic safety assessment of nuclear research reactors
97	2015	21023	Texto completo de evento	I	A concept of PWR using plate and shell heat exchangers
98	2015	21041	Texto completo de evento	I	Gamma stability and powder formation of UMo alloys
99	2015	21073	Texto completo de evento	I	Self-organizing maps applied to two-phase flow on natural circulation loop studies
100	2015	21082	Texto completo de evento	I	Simulation of the first step of the coupling of the PARCS/RELAP5 codes to ANGRA 2 facility
101	2015	21137	Texto completo de evento	I	Characterization of physical properties of Alsub(2)Osub(3) and ZrOsub(2) nanofluids for heat transfer applications
102	2015	21153	Texto completo de evento	I	Casos de cancer fatal e não fatal ocorridos nas diferentes regiões do municipio de São Paulo
103	2015	21261	Artigo de periódico	I	Historic survey on nuclear merchant ships
104	2015	21267	Artigo de periódico	I	Evaluation tools for scientific research professionals: A contribution to the strategic planning of R&D institutions
105	2015	21290	Artigo de periódico	I	Numerical study of the influence of elements inside the wheelhouse on the passenger vehicle aerodynamic
106	2015	21750	Capítulo de livro	I	IEA-R1 Nuclear Reactor: Facility specification and experimental results
107	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
108	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
109	2014	20279	Artigo de periódico	I	The future role of the nuclear energy in Brazil in a transition energy scenario
110	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
111	2014	20703	Artigo de periódico	I	On applicability of plate and shell heat exchangers for steam generation in naval PWR
112	2014	22008	Iniciação Científica	N	Estudos do escoamento em núcleos de reator com elementos combustíveis tipo placas paralelas
113	2014	22344	Artigo de periódico	N	Introduction to the integrated environmental management: a case study at the Federal Office of Brazilian Research
114	2013	18765	Capítulo de livro	I	Stability of 'gamma'UMo nuclear fuel alloys by thermal analysis
115	2013	19332	Texto completo de evento	I	The process of filing patent applications in the view of ICT inventors
116	2013	19453	Texto completo de evento	I	Perspectives of heat transfer enhancements in nuclear reactors toward nanofluids applications
117	2013	19461	Texto completo de evento	I	Risk communication importance
118	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
119	2013	21880	Iniciação Científica	N	Modernização da Bancada experimental Apolo para estudos de elementos combustíveis do tipo paralelas
120	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
121	2012	18039	Artigo de periódico	I	A mathematical model for metastable condition determination of highly flashing liquid flows through expansion devices
122	2012	18093	Artigo de periódico	I	A numerical and three-dimensional analysis of steady state rectangular natural circulation loop
123	2012	18189	Artigo de periódico	I	Classification of natural circulation two-phase flow patterns using fuzzy inference on image analysis
124	2012	18190	Artigo de periódico	I	Web-based post-processor for RELAP5: a development based on LabVIEW
125	2012	18200	Texto completo de evento	N	Flow regime identification in natural circulation phenomenon using RELAP5 code
126	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
127	2012	18514	Texto completo de evento	N	ANGRA 2 samll break loca flow regime identification through RELAP5 code
128	2012	19896	Artigo de periódico	N	Study of stress in nuclear area workers: silent enemy
129	2011	16846	Texto completo de evento	I	Thermal hydraulics special theme for CFD codes thermal stratification experiments
130	2011	16852	Texto completo de evento	I	Simulation of a refill/reflood experiment using the RELAP5 thermal-hydraulic code
131	2011	16868	Texto completo de evento	I	Development of a labview web-based simulator for RELAP5
132	2011	16908	Texto completo de evento	I	Study of stress in nuclear area workers: silent enemy
133	2011	16918	Texto completo de evento	I	A RELAP5 study to identify flow regime in natural circulation phenomenon
134	2011	16968	Texto completo de evento	I	A CFD model for the IEA-R1 reactor heat exchanger inlet nozzle flow
135	2011	17021	Texto completo de evento	I	Uranium density reduction on fuel element side plates assessment
136	2011	17037	Texto completo de evento	I	Frequency analysis for the thermal hydraulic characterization of a natural circulation circuit
137	2011	17206	Texto completo de evento	I	Development of a VBA macro-based spreadsheet application for RELAP5 data post-processing
138	2011	17556	Artigo de periódico	I	Comparison between experimental data and numerical modeling for the natural circulation phenomenon
139	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
140	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
141	2010	16126	Texto completo de evento	N	Analise teorico/experimental do fenomeno de circulacao natural
142	2010	16127	Texto completo de evento	N	Thermal hydraulic phenomenology in a natural circulation circuit
143	2010	16134	Texto completo de evento	I	Assessmnet of a heat exchanger inlet nozzle flow using ANSYS-CFX
144	2010	16135	Texto completo de evento	N	Study of the natural circulation phenomenon for nuclear reactors
145	2010	16860	Texto completo de evento	I	Study of the natural circulation phenomenon for nuclear reactors
146	2009	14303	Iniciação Científica	N	Modernizacao do circuito de circulacao natural do IPEN/CNEN-SP
147	2009	15274	Texto completo de evento	I	The decision-making process during accidents or incidents in the operational nuclear data
148	2009	15276	Texto completo de evento	I	Comparison between experimental data and numerical modeling for the natural circulation phenomenon
149	2009	15277	Texto completo de evento	I	Thermal hydraulic phenomenology for the heating process in a natural circulation facility
150	2009	15303	Texto completo de evento	I	Nuclear research reactor IEA-R1 heat exchanger inlet nozzle flow - a preliminary study
151	2009	15394	Texto completo de evento	I	Two-phase flow patterns recognition and parameters estimation through natural circulation test loop image analysis
152	2008	12256	Artigo de periódico	I	Multivariate analysis with covariance matrix applied to separative power modeling of a gas centrifuge
153	2008	13460	Texto completo de evento	N	Analise teorico e experimental do fenomeno de circulacao natural
154	2008	13822	Artigo de periódico	N	Study of human factors and its basic aspects, focusing the operators of IEA-R1 research reactor
155	2008	13824	Texto completo de evento	I	Irradiacao de miniplacas de elementos combustiveis tipo dispersao de reatores de pesquisa
156	2007	12165	Texto completo de evento	I	RELAP5 simulation for one and two phase natural circulation phenomenon
157	2007	12166	Texto completo de evento	I	Study of human factors and its basec aspects focusing the operators of IEA-R1 research reactor
158	2007	12195	Texto completo de evento	I	Falcao - a relational database to storaging the variables monitored in the research reactor IEA-R1
159	2006	11567	Texto completo de evento	N	Analise experimental do fenomeno de circulacao natural
160	2006	11574	Artigo de periódico	N	Multivariate regression applied to the performance otimization of a countercurrent ultracentrifuge - a preliminary study
161	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
162	2005	10651	Texto completo de evento	I	Simulacao de acidentes tipo LOCA em Angra 2 com o codigo RELAP5/MOD3.2
163	2005	10666	Texto completo de evento	I	Modelagem do poder de separacao de ultracentrifugas por regressao multivariada com matriz de covariancia
164	2005	10697	Texto completo de evento	I	Modelagem do nucleo do reator IEA-R1 com o codigo RELAP5
165	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
166	2004	10902	Texto completo de evento	N	Regressao multivariada aplicada na otimizacao de performance de ultracentrifugas a contracorrente - um caso preliminar
167	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
168	2004	10905	Texto completo de evento	I	Preliminary transient analysis for the IRIS reactor pressurizer with RELAP5/Mod3.3 code
169	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
170	2003	09552	Texto completo de evento	I	A MTR fuel element flow distribution measurement preliminary results
171	2003	09553	Texto completo de evento	I	Thermal-hydraulic design of a fuel mini-plate irradiator for the IEA-R1 research reactor
172	2003	09555	Texto completo de evento	I	Fuel performance during in LBLOCA in Angra 1 Nuclear Power Plant
173	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
174	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
175	2002	08676	Texto completo de evento	I	Dimensionamento termo-hidraulico de um dispositivo de irradiacao de mini-placas combustiveis para o reator IEA-R1
176	2002	09275	Texto completo de evento	I	CNEN in the IRIS Project
177	2002	09298	Texto completo de evento	I	Simulação de Angra 2 com o código RELAP5/MOD3.2.2G gamma version
178	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
179	2002	09333	Artigo de periódico	N	Dimensionamento termo-hidraulico de um dispositivo de irradiacao de mini-placas combustiveis para o reator IEA-R1
180	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
181	2001	07047	Texto completo de evento	I	Modelagem do circuito primario de Angra 2 com o codigo RELAP5/MOD3.2.2G
182	2001	07112	Texto completo de evento	N	Analise do resfriamento de canais entre elementos combustiveis de reatores de pesquisa
183	2000	07912	Texto completo de evento	I	Two-phase flow instabilities in a natural circulation rectangular loop
184	2000	08441	Texto completo de evento	N	Simulacao de Angra 2 com o codigo RELAP5/MOD3.2.2 gamma version
185	1999	06481	Tese	N	Analise termo hidrodinamica de uma centrifuga a contracorrente
186	1998	06191	Artigo de periódico	I	Thermal hydrodynamical analysis of a countercurrent gas centrifuge
187	1997	04989	Texto completo de evento	N	Analise termica de uma centrifuga a gas para separacao de isotopos)
188	1996	04749	Texto completo de evento	N	Thermal analysis of a gas centrifuge