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

 

Publicações do autor   ALFREDO YUUITIRO ABE   depositadas no Repositório Digital/IPEN - Total : 75 31/05/2023 23:08:55
Seq	Ano	Ipen_doc	Tipo	Circ.	Título
1	2023	29620	Artigo de periódico	I	Effectiveness of Ni-based and Fe-based cladding alloys in delaying hydrogen generation for small modular reactors with increased accident tolerance
2	2022	29118	Artigo de periódico	N	Passive Autocatalytic Recombiner perfomance assessment using COCOSYS
3	2021	27926	Artigo de periódico	N	Modification of fuel performance code to evaluate iron-based alloy behavior under LOCA scenario
4	2021	28256	Texto completo de evento	I	Passive Autocatalytic Recombiner perfomance assessment using COCOSYS code
5	2021	28287	Texto completo de evento	I	The FeCrAl cladding assessment under accident condition using TRANSURANUS fuel performance code
6	2020	26854	Texto completo de evento	I	Assessment of high conductivity ceramic fuel concept under normal and accident conditions
7	2020	26855	Texto completo de evento	I	Reactivity initiated accident assessment for ATF cladding materials
8	2020	27361	Artigo de periódico	I	On the nuclear safety improvement by post-inerting small modular reactor with stainless steel cladding
9	2020	27578	Artigo de periódico	I	Oxidation of AISI 304L and 348 stainless steels in water at high temperatures
10	2020	27614	Texto completo de evento	I	Main experiments performed at the IPEN/MB-01 RR using UO2 fuel rods core
11	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
12	2020	27691	Capítulo de livro	I	Preliminary neutronic assessment of iron based alloy fuel cladding
13	2020	27693	Capítulo de livro	I	Neutronic screening of potential candidate for accident tolerant fuel
14	2019	26341	Texto completo de evento	I	Neutron flux intercomparison and ex-core neutron detector optimization in a SMR reactor using MCNP6 code and MAVRIC sequence
15	2019	26355	Texto completo de evento	I	Sensitivity analysis of fuel rod parameters in steady state condition using TRANSURANUS code
16	2019	26356	Texto completo de evento	I	Fuel performance of iron-based alloy cladding using modified TRANSURANUS code
17	2019	26363	Texto completo de evento	I	Modification of TRANSURANUS fuel performance code in the ATF framework
18	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
19	2019	27963	Texto completo de evento	I	Preliminary assessment of iron alloy cladding as accident tolerant fuel cladding
20	2018	26904	Texto completo de evento	I	Fuel performance assessment of enhanced accident tolerant fuel using iron-based alloys as cladding
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	24021	Texto completo de evento	I	Sensitivity assessment of fuel performance codes for loca accident scenario
27	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
28	2016	22767	Artigo de periódico	I	Assessment of stainless steel 348 fuel rod performance against literature available data using TRANSURANUS code
29	2016	23518	Artigo de periódico	I	Evaluation of corrosion on the fuel performance of stainless steel cladding
30	2015	21070	Texto completo de evento	I	Preliminary neutronic assessmento for ATF (Accident Tolerant Fuel) based on iron alloy
31	2015	21144	Texto completo de evento	I	Simulation of the effects of the extend fuel rod burn-up under loca scenario
32	2015	21150	Texto completo de evento	I	The quest for safe and reliable fuel cladding materials
33	2014	20415	Artigo de periódico	I	Revisiting stainless steel as PWR fuel rod cladding after Fukushima daiichi accident
34	2013	19235	Texto completo de evento	I	Evaluation of fuel performance with different enrichment degrees for an experimental device
35	2013	19274	Texto completo de evento	I	Heavy steel reflector evaluation using diffusion theory
36	2013	19313	Texto completo de evento	I	Mechanical stress analysis for fuel rod under normal operating conditions
37	2013	19370	Texto completo de evento	I	Reactivity effect of a hevy water tank as reflector in the IPEN/MB-01 reactor
38	2013	19417	Texto completo de evento	I	Nuclear criticality safety parameter evaluation for uranium metallic alloy
39	2011	16872	Texto completo de evento	I	Fuel performance evaluation for the cafe experimental device
40	2011	16921	Texto completo de evento	I	A variable reflector size experiment at IPEN/MB-01 critical facility
41	2011	16924	Texto completo de evento	I	Reactivity experiments with different boric acid concentrations in the IPEN/MB-01 reactor
42	2010	15546	Capítulo de livro	I	Reactor physics experiments in the IPEN/MB-01 research reactor facility
43	2009	14730	Artigo de periódico	I	New experimental results for the inversion point of the isothermal reactivity coeficient of the IPEN-MB-01 reactor
44	2009	15266	Texto completo de evento	I	Critical loading configurations of the IPEN/MB-01 reactor with UOsub(2)GDsun(2)Osub(3) burnable poison rods
45	2008	13400	Texto completo de evento	I	Heavy reflector experiment in the IPEN/MB-01 reactor
46	2008	13927	Capítulo de livro	I	Critical loading configurations of the IPEN/MB-01 reactor with UOsub(2), stainless and copper roads LEU-COMP-THERM-044
47	2008	13928	Capítulo de livro	I	Critical loading configurations of the IPEN/MB-01 reactor with a heavy SS-3 reflector LEU-COMP-THERM-043
48	2005	10722	Texto completo de evento	I	Analise teorica do ponto de inversao do coeficiente de reatividade isotermico do reator IPEN/MB-01
49	2005	10781	Texto completo de evento	I	Uma contribuicao brasileira para o International Handbook of Evaluiation Criticality Safety Benchmark Experiments
50	2005	10782	Texto completo de evento	I	Utilização do material aço inox como barra de controle do reator IPEN/MB-01
51	2005	10830	Artigo de periódico	I	The inversion point of the isothermal reactivity coefficient of the IPEN/MB-01 reactor-II: theoretical Analysis
52	2005	10884	Capítulo de livro	I	Critical loading configurations of the IPEN/MB-01 reactor with a big central void
53	2005	10982	Capítulo de livro	I	Critical loading configurations of the IPEN/MB-01 reactor with a central cruciform rod
54	2004	10550	Texto completo de evento	I	A set of critical loading configurations of the IPEN/MB-01 reactor
55	2003	09468	Texto completo de evento	I	Experimental utilization of the IPEN/MB-01 reactor
56	2002	08689	Texto completo de evento	I	Experimento do vazio local no reator IPEN/MB-01
57	2002	08690	Texto completo de evento	I	Avaliacao do sistema SCALE 4.4a no Reator IPEN/MB-01
58	2002	09341	Artigo de periódico	N	Experimento do vazio local no reator IPEN/MB-01
59	2002	09343	Artigo de periódico	N	Avaliacao do sistema SCALE 4.4a no Reator IPEN/MB-01
60	2001	07058	Artigo de periódico	I	A proposal for benchmarking sup(235)U nuclear data
61	2000	06813	Texto completo de evento	I	Criticality analyses based on the coupled NJOY/AMPX-II/TORT systems
62	2000	06815	Texto completo de evento	N	Medidas e calculos de espectro de energia de neutrons emergentes de um duto em uma blindagem
63	2000	07212	Texto completo de evento	N	Experimento de carregamento do nucleo do reator IPEN/MB-01
64	2000	07213	Texto completo de evento	N	Experimento sobre detetores out-of-core no reator IPEN/MB-01
65	1999	07507	Texto completo de evento	N	Uma proposta de estudo brasileira visando a utilizacao de torio em reatores
66	1997	05012	Texto completo de evento	N	Analise de sistema de calculo para blindagem de radiacao
67	1997	05021	Texto completo de evento	N	Analise de criticalidade utilizando o codigo MCNP4A
68	1995	05902	Texto completo de evento	N	Analise de experimentos criticos de oxidos mistos utilizando o codigo HAMMER-TECHNION com tratamentos de autoblindagem via metodos de Bondarenko
69	1993	02108	Texto completo de evento	N	Implementacao do metodo de Bondarenko para o tratamento da autoblindagem no codigo HAMMER-TECHNION
70	1993	02135	Texto completo de evento	N	Verificacao das bibliotecas JENDL-3 e ENDF/B-VI para o ciclo TANDEM
71	1991	04134	Texto completo de evento	N	Analise de experimento critico contendo oxido misto PuOsub(2)UOsub(2) utilizando a biblioteca de dados nucleares JENDL-3
72	1991	04142	Texto completo de evento	N	Tema especial de fisica de reatores do VIII ENFIR
73	1990	03577	Texto completo de evento	I	Burn-up physics in a coupled HAMMER-TECHNION/CINDER-2 system and ENDF/B-V aggregate fission product thermal cross section validation
74	1990	03980	Dissertação	N	Analise de transmutacao considerando o tratamento explicito dos produtos de fissao num sistema acoplado, composto pelos codigos Hammer-Technion e
75	1990	06728	Texto completo de evento	N	Hancind: Sistema acoplado HAMMER TECHNION e CINDER-2 para calculo celular com tratamento explicito dos produtos de fissao e nuclideos actinideos