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

 

Publicações do autor   DANIEL DE SOUZA GOMES    depositadas no Repositório Digital/IPEN - Total : 47 19/04/2024 17:53:15
Seq	Ano	Ipen_doc	Tipo	Circ.	Título
1	2023	29831	Artigo de periódico	N	Overview of the physical properties of molten salt reactor using FLiBe
2	2022	29340	Texto completo de evento	N	Avaliação da liberação de gás de fissão para UO2 dopado por Cr2O3
3	2022	29341	Texto completo de evento	N	Combustível composto avançado UO2-UN com condutividade térmica melhorada e alta densidade
4	2022	29342	Texto completo de evento	N	Avaliação de combustível cerâmicos compostos baseados em urânio, tório e plutônio para reatores nucleares
5	2021	27926	Artigo de periódico	N	Modification of fuel performance code to evaluate iron-based alloy behavior under LOCA scenario
6	2021	28181	Texto completo de evento	I	Advanced nuclear fuels based on thorium mixed oxides
7	2021	28183	Texto completo de evento	I	Analysis of chromium oxide doped pellet for LWRs using FRAPCON code
8	2021	28185	Texto completo de evento	I	Assessment of the UO2-graphene composite fuel proposed for nuclear reactors
9	2021	28629	Texto completo de evento	I	Assessment of advanced ferritic alloys used as cladding materials in nuclear power reactors
10	2021	28630	Texto completo de evento	I	Progress of enhanced conductivity fuels using UO2-graphene
11	2020	26854	Texto completo de evento	I	Assessment of high conductivity ceramic fuel concept under normal and accident conditions
12	2020	27620	Texto completo de evento	I	The IPEN/CNEN contribution to IAEA FUMAC benchmark using modified fuel performance code based on stainless steel as cladding under steady state, transient and accident conditions
13	2020	27658	Resumo de eventos científicos	I	Thermal analysis of nuclear fuel using silicon carbide nanocomposite dispersion in UO2
14	2020	27659	Resumo de eventos científicos	I	A survey of accident tolerant fuel composed of uranium dioxide sintered with graphene nanoplatalet
15	2020	28749	Texto completo de evento	I	Computational assessment using sensitivity analysis of more tolerant fuels
16	2019	26359	Texto completo de evento	I	Behavior of thorium plutonium fuel on light water reactors
17	2019	26360	Texto completo de evento	I	Analysis of a pressurized power reactor using thorium mixed fuel under regular operation
18	2019	26361	Texto completo de evento	I	Importance of uncertainty modelling for nuclear safety analysis
19	2019	26364	Texto completo de evento	I	Performance analysis of UO2-SiC fuel under normal conditions
20	2019	26377	Texto completo de evento	I	Comparative analysis of silicon carbide with zirconium-based alloys
21	2019	26378	Texto completo de evento	I	Combining probabilistic and deterministic methods for accident analysis
22	2019	26711	Capítulo de livro	I	Development and application of modified fuel performance code based on stainless steel as cladding under steady state, transient and accident conditions
23	2019	26770	Texto completo de evento	I	Study of thoria-urania fuel during accidents
24	2019	27963	Texto completo de evento	I	Preliminary assessment of iron alloy cladding as accident tolerant fuel cladding
25	2018	25989	Texto completo de evento	I	Uncertainty evaluation and sensitivity analysis under accident scenarios
26	2018	26904	Texto completo de evento	I	Fuel performance assessment of enhanced accident tolerant fuel using iron-based alloys as cladding
27	2017	24007	Texto completo de evento	I	Simulating fuel behavior under transient conditions using fraptran and uncertainty analysis using DAKOTA
28	2017	24009	Texto completo de evento	I	Analysis of UO2-BEO fuel under transient using fuel performance code
29	2017	24011	Texto completo de evento	I	Assessment of uranium dioxide fuel performance with the addition of beryllium oxide
30	2017	24012	Texto completo de evento	I	Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenario
31	2017	24013	Texto completo de evento	I	Simulation of accident-tolerant U3Si2 fuel using FRAPCON code
32	2017	24014	Texto completo de evento	I	High density fuels using dispersion and monolithic fuel
33	2017	24015	Texto completo de evento	I	Improving performance with accident tolerant-fuels
34	2017	24021	Texto completo de evento	I	Sensitivity assessment of fuel performance codes for loca accident scenario
35	2017	24023	Texto completo de evento	I	Sensitivity and uncertainty evaluation applied to the failure process of nuclear fuel
36	2017	24688	Artigo de periódico	I	Nuclear fuel safety threshold determined by logistic regression plus uncertainty
37	2017	24947	Texto completo de evento	I	Analysis of the combined effects on the fuel performance of UO2-BeO as fuel and iron-based alloy as cladding
38	2016	23518	Artigo de periódico	I	Evaluation of corrosion on the fuel performance of stainless steel cladding
39	2015	20986	Texto completo de evento	I	Adaptation on fuel code for light water reactor with austenitic steel rod cladding
40	2015	21113	Texto completo de evento	I	Importance of nuclear station load factor in applied to energy policies
41	2015	21114	Texto completo de evento	I	Identification of the security threshold by logistic regression applied to fuel under accident conditions
42	2015	21144	Texto completo de evento	I	Simulation of the effects of the extend fuel rod burn-up under loca scenario
43	2014	20415	Artigo de periódico	I	Revisiting stainless steel as PWR fuel rod cladding after Fukushima daiichi accident
44	2014	20536	Tese	N	Simulação com programas computacionais de desempenho do combustível em regimes permanente e transiente de varetas combustíveis de aço inoxidável austenítico
45	2013	19235	Texto completo de evento	I	Evaluation of fuel performance with different enrichment degrees for an experimental device
46	2011	16872	Texto completo de evento	I	Fuel performance evaluation for the cafe experimental device
47	2011	16899	Texto completo de evento	I	Angra 1 high burnup fuel behaviour under reactivity initiated accident conditions