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 : 40
Seq	Ano	Ipen_doc	Tipo	Circ.	Título
1	2021	27926	Artigo de periódico	N	Modification of fuel performance code to evaluate iron-based alloy behavior under LOCA scenario
2	2021	28181	Texto completo de evento	I	Advanced nuclear fuels based on thorium mixed oxides
3	2021	28183	Texto completo de evento	I	Analysis of chromium oxide doped pellet for LWRs using FRAPCON code
4	2021	28185	Texto completo de evento	I	Assessment of the UO2-graphene composite fuel proposed for nuclear reactors
5	2020	26854	Texto completo de evento	I	Assessment of high conductivity ceramic fuel concept under normal and accident conditions
6	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
7	2020	27658	Resumo de eventos científicos	I	Thermal analysis of nuclear fuel using silicon carbide nanocomposite dispersion in UO2
8	2020	27659	Resumo de eventos científicos	I	A survey of accident tolerant fuel composed of uranium dioxide sintered with graphene nanoplatalet
9	2019	26359	Texto completo de evento	I	Behavior of thorium plutonium fuel on light water reactors
10	2019	26360	Texto completo de evento	I	Analysis of a pressurized power reactor using thorium mixed fuel under regular operation
11	2019	26361	Texto completo de evento	I	Importance of uncertainty modelling for nuclear safety analysis
12	2019	26364	Texto completo de evento	I	Performance analysis of UO2-SiC fuel under normal conditions
13	2019	26377	Texto completo de evento	I	Comparative analysis of silicon carbide with zirconium-based alloys
14	2019	26378	Texto completo de evento	I	Combining probabilistic and deterministic methods for accident analysis
15	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
16	2019	26770	Texto completo de evento	I	Study of thoria-urania fuel during accidents
17	2019	27963	Texto completo de evento	I	Preliminary assessment of iron alloy cladding as accident tolerant fuel cladding
18	2018	25989	Texto completo de evento	I	Uncertainty evaluation and sensitivity analysis under accident scenarios
19	2018	26904	Texto completo de evento	I	Fuel performance assessment of enhanced accident tolerant fuel using iron-based alloys as cladding
20	2017	24007	Texto completo de evento	I	Simulating fuel behavior under transient conditions using fraptran and uncertainty analysis using DAKOTA
21	2017	24009	Texto completo de evento	I	Analysis of UO2-BEO fuel under transient using fuel performance code
22	2017	24011	Texto completo de evento	I	Assessment of uranium dioxide fuel performance with the addition of beryllium oxide
23	2017	24012	Texto completo de evento	I	Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenario
24	2017	24013	Texto completo de evento	I	Simulation of accident-tolerant U3Si2 fuel using FRAPCON code
25	2017	24014	Texto completo de evento	I	High density fuels using dispersion and monolithic fuel
26	2017	24015	Texto completo de evento	I	Improving performance with accident tolerant-fuels
27	2017	24021	Texto completo de evento	I	Sensitivity assessment of fuel performance codes for loca accident scenario
28	2017	24023	Texto completo de evento	I	Sensitivity and uncertainty evaluation applied to the failure process of nuclear fuel
29	2017	24688	Artigo de periódico	I	Nuclear fuel safety threshold determined by logistic regression plus uncertainty
30	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
31	2016	23518	Artigo de periódico	I	Evaluation of corrosion on the fuel performance of stainless steel cladding
32	2015	20986	Texto completo de evento	I	Adaptation on fuel code for light water reactor with austenitic steel rod cladding
33	2015	21113	Texto completo de evento	I	Importance of nuclear station load factor in applied to energy policies
34	2015	21114	Texto completo de evento	I	Identification of the security threshold by logistic regression applied to fuel under accident conditions
35	2015	21144	Texto completo de evento	I	Simulation of the effects of the extend fuel rod burn-up under loca scenario
36	2014	20415	Artigo de periódico	I	Revisiting stainless steel as PWR fuel rod cladding after Fukushima daiichi accident
37	2014	20536	Tese	N	Simulação com programas computacionais de desempenho do combustível em regimes permanente e transiente de varetas combustíveis de aço inoxidável austenítico
38	2013	19235	Texto completo de evento	I	Evaluation of fuel performance with different enrichment degrees for an experimental device
39	2011	16872	Texto completo de evento	I	Fuel performance evaluation for the cafe experimental device
40	2011	16899	Texto completo de evento	I	Angra 1 high burnup fuel behaviour under reactivity initiated accident conditions