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

 

Publicações do autor depositadas no Repositório Digital/IPEN - Total : 27
Seq	Ano	Ipen_doc	Tipo	Circ.	Título
1	2019	26359	Texto completo de evento	I	Behavior of thorium plutonium fuel on light water reactors
2	2019	26360	Texto completo de evento	I	Analysis of a pressurized power reactor using thorium mixed fuel under regular operation
3	2019	26361	Texto completo de evento	I	Importance of uncertainty modelling for nuclear safety analysis
4	2019	26364	Texto completo de evento	I	Performance analysis of UO2-SiC fuel under normal conditions
5	2019	26377	Texto completo de evento	I	Comparative analysis of silicon carbide with zirconium-based alloys
6	2019	26378	Texto completo de evento	I	Combining probabilistic and deterministic methods for accident analysis
7	2018	25989	Texto completo de evento	I	Uncertainty evaluation and sensitivity analysis under accident scenarios
8	2017	24007	Texto completo de evento	I	Simulating fuel behavior under transient conditions using fraptran and uncertainty analysis using DAKOTA
9	2017	24009	Texto completo de evento	I	Analysis of UO2-BEO fuel under transient using fuel performance code
10	2017	24011	Texto completo de evento	I	Assessment of uranium dioxide fuel performance with the addition of beryllium oxide
11	2017	24012	Texto completo de evento	I	Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenario
12	2017	24013	Texto completo de evento	I	Simulation of accident-tolerant U3Si2 fuel using FRAPCON code
13	2017	24014	Texto completo de evento	I	High density fuels using dispersion and monolithic fuel
14	2017	24015	Texto completo de evento	I	Improving performance with accident tolerant-fuels
15	2017	24021	Texto completo de evento	I	Sensitivity assessment of fuel performance codes for loca accident scenario
16	2017	24023	Texto completo de evento	I	Sensitivity and uncertainty evaluation applied to the failure process of nuclear fuel
17	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
18	2016	23518	Artigo de periódico	I	Evaluation of corrosion on the fuel performance of stainless steel cladding
19	2015	20986	Texto completo de evento	I	Adaptation on fuel code for light water reactor with austenitic steel rod cladding
20	2015	21113	Texto completo de evento	I	Importance of nuclear station load factor in applied to energy policies
21	2015	21114	Texto completo de evento	I	Identification of the security threshold by logistic regression applied to fuel under accident conditions
22	2015	21144	Texto completo de evento	I	Simulation of the effects of the extend fuel rod burn-up under loca scenario
23	2014	20415	Artigo de periódico	I	Revisiting stainless steel as PWR fuel rod cladding after Fukushima daiichi accident
24	2014	20536	Tese	N	Simulação com programas computacionais de desempenho do combustível em regimes permanente e transiente de varetas combustíveis de aço inoxidável austenítico
25	2013	19235	Texto completo de evento	I	Evaluation of fuel performance with different enrichment degrees for an experimental device
26	2011	16872	Texto completo de evento	I	Fuel performance evaluation for the cafe experimental device
27	2011	16899	Texto completo de evento	I	Angra 1 high burnup fuel behaviour under reactivity initiated accident conditions