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 : 80 28/11/2024 07:51:06
Seq	Ano	Ipen_doc	Tipo	Circ.	Título
1	2024	30532	Texto completo de evento	Internacional	Nuclear power plants
2	2024	30570	Texto completo de evento	Internacional	Assessment of burnable poison reactivity in the ATF fuel assembly
3	2024	30604	Texto completo de evento	Internacional	Improving the technical management of nuclear licensing processes in Brazil
4	2024	30638	Texto completo de evento	Internacional	Analysis of the CASP2 experiment in the Battelle Containment model using the code COCOSYS
5	2024	30639	Texto completo de evento	Internacional	Nodalization of MISTRA facility for ISP-47 experiment using lumped parameter code COCOSYS
6	2023	29620	Artigo de periódico	Internacional	Effectiveness of Ni-based and Fe-based cladding alloys in delaying hydrogen generation for small modular reactors with increased accident tolerance
7	2023	29731	Tese	Nacional	Análise neutrônica e do comportamento sob irradiação de combustíveis tolerantes à falha
8	2023	29914	Artigo de periódico	Internacional	Assessment of minimum allowable thickness of advanced steel (FeCrAl) cladding for accident tolerant fuel
9	2023	29915	Artigo de periódico	Internacional	Best estimate plus uncertainty analysis of metal-water reaction transient experiment
10	2022	29118	Artigo de periódico	Nacional	Passive Autocatalytic Recombiner perfomance assessment using COCOSYS
11	2021	27926	Artigo de periódico	Nacional	Modification of fuel performance code to evaluate iron-based alloy behavior under LOCA scenario
12	2021	28256	Texto completo de evento	Internacional	Passive Autocatalytic Recombiner perfomance assessment using COCOSYS code
13	2021	28287	Texto completo de evento	Internacional	The FeCrAl cladding assessment under accident condition using TRANSURANUS fuel performance code
14	2020	26854	Texto completo de evento	Internacional	Assessment of high conductivity ceramic fuel concept under normal and accident conditions
15	2020	26855	Texto completo de evento	Internacional	Reactivity initiated accident assessment for ATF cladding materials
16	2020	27361	Artigo de periódico	Internacional	On the nuclear safety improvement by post-inerting small modular reactor with stainless steel cladding
17	2020	27578	Artigo de periódico	Internacional	Oxidation of AISI 304L and 348 stainless steels in water at high temperatures
18	2020	27614	Texto completo de evento	Internacional	Main experiments performed at the IPEN/MB-01 RR using UO2 fuel rods core
19	2020	27620	Texto completo de evento	Internacional	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
20	2020	27691	Capítulo de livro	Internacional	Preliminary neutronic assessment of iron based alloy fuel cladding
21	2020	27693	Capítulo de livro	Internacional	Neutronic screening of potential candidate for accident tolerant fuel
22	2019	26341	Texto completo de evento	Internacional	Neutron flux intercomparison and ex-core neutron detector optimization in a SMR reactor using MCNP6 code and MAVRIC sequence
23	2019	26355	Texto completo de evento	Internacional	Sensitivity analysis of fuel rod parameters in steady state condition using TRANSURANUS code
24	2019	26356	Texto completo de evento	Internacional	Fuel performance of iron-based alloy cladding using modified TRANSURANUS code
25	2019	26363	Texto completo de evento	Internacional	Modification of TRANSURANUS fuel performance code in the ATF framework
26	2019	26711	Capítulo de livro	Internacional	Development and application of modified fuel performance code based on stainless steel as cladding under steady state, transient and accident conditions
27	2019	27963	Texto completo de evento	Internacional	Preliminary assessment of iron alloy cladding as accident tolerant fuel cladding
28	2018	26904	Texto completo de evento	Internacional	Fuel performance assessment of enhanced accident tolerant fuel using iron-based alloys as cladding
29	2017	24009	Texto completo de evento	Internacional	Analysis of UO2-BEO fuel under transient using fuel performance code
30	2017	24011	Texto completo de evento	Internacional	Assessment of uranium dioxide fuel performance with the addition of beryllium oxide
31	2017	24012	Texto completo de evento	Internacional	Modification of fuel performance code to evaluate iron-based alloy behavior under loca scenario
32	2017	24013	Texto completo de evento	Internacional	Simulation of accident-tolerant U3Si2 fuel using FRAPCON code
33	2017	24014	Texto completo de evento	Internacional	High density fuels using dispersion and monolithic fuel
34	2017	24021	Texto completo de evento	Internacional	Sensitivity assessment of fuel performance codes for loca accident scenario
35	2017	24947	Texto completo de evento	Internacional	Analysis of the combined effects on the fuel performance of UO2-BeO as fuel and iron-based alloy as cladding
36	2016	22767	Artigo de periódico	Internacional	Assessment of stainless steel 348 fuel rod performance against literature available data using TRANSURANUS code
37	2016	23518	Artigo de periódico	Internacional	Evaluation of corrosion on the fuel performance of stainless steel cladding
38	2015	21070	Texto completo de evento	Internacional	Preliminary neutronic assessmento for ATF (Accident Tolerant Fuel) based on iron alloy
39	2015	21144	Texto completo de evento	Internacional	Simulation of the effects of the extend fuel rod burn-up under loca scenario
40	2015	21150	Texto completo de evento	Internacional	The quest for safe and reliable fuel cladding materials
41	2014	20415	Artigo de periódico	Internacional	Revisiting stainless steel as PWR fuel rod cladding after Fukushima daiichi accident
42	2013	19235	Texto completo de evento	Internacional	Evaluation of fuel performance with different enrichment degrees for an experimental device
43	2013	19274	Texto completo de evento	Internacional	Heavy steel reflector evaluation using diffusion theory
44	2013	19313	Texto completo de evento	Internacional	Mechanical stress analysis for fuel rod under normal operating conditions
45	2013	19370	Texto completo de evento	Internacional	Reactivity effect of a hevy water tank as reflector in the IPEN/MB-01 reactor
46	2013	19417	Texto completo de evento	Internacional	Nuclear criticality safety parameter evaluation for uranium metallic alloy
47	2011	16872	Texto completo de evento	Internacional	Fuel performance evaluation for the cafe experimental device
48	2011	16921	Texto completo de evento	Internacional	A variable reflector size experiment at IPEN/MB-01 critical facility
49	2011	16924	Texto completo de evento	Internacional	Reactivity experiments with different boric acid concentrations in the IPEN/MB-01 reactor
50	2010	15546	Capítulo de livro	Internacional	Reactor physics experiments in the IPEN/MB-01 research reactor facility
51	2009	14730	Artigo de periódico	Internacional	New experimental results for the inversion point of the isothermal reactivity coeficient of the IPEN-MB-01 reactor
52	2009	15266	Texto completo de evento	Internacional	Critical loading configurations of the IPEN/MB-01 reactor with UOsub(2)GDsun(2)Osub(3) burnable poison rods
53	2008	13927	Capítulo de livro	Internacional	Critical loading configurations of the IPEN/MB-01 reactor with UOsub(2), stainless and copper roads LEU-COMP-THERM-044
54	2008	13928	Capítulo de livro	Internacional	Critical loading configurations of the IPEN/MB-01 reactor with a heavy SS-3 reflector LEU-COMP-THERM-043
55	2005	10722	Texto completo de evento	Internacional	Analise teorica do ponto de inversao do coeficiente de reatividade isotermico do reator IPEN/MB-01
56	2005	10782	Texto completo de evento	Internacional	Utilização do material aço inox como barra de controle do reator IPEN/MB-01
57	2005	10884	Capítulo de livro	Internacional	Critical loading configurations of the IPEN/MB-01 reactor with a big central void
58	2005	10982	Capítulo de livro	Internacional	Critical loading configurations of the IPEN/MB-01 reactor with a central cruciform rod
59	2004	10550	Texto completo de evento	Internacional	A set of critical loading configurations of the IPEN/MB-01 reactor
60	2003	09468	Texto completo de evento	Internacional	Experimental utilization of the IPEN/MB-01 reactor
61	2002	08689	Texto completo de evento	Internacional	Experimento do vazio local no reator IPEN/MB-01
62	2002	08690	Texto completo de evento	Internacional	Avaliacao do sistema SCALE 4.4a no Reator IPEN/MB-01
63	2002	09341	Artigo de periódico	Nacional	Experimento do vazio local no reator IPEN/MB-01
64	2002	09343	Artigo de periódico	Nacional	Avaliacao do sistema SCALE 4.4a no Reator IPEN/MB-01
65	2001	07058	Artigo de periódico	Internacional	A proposal for benchmarking sup(235)U nuclear data
66	2000	06813	Texto completo de evento	Internacional	Criticality analyses based on the coupled NJOY/AMPX-II/TORT systems
67	2000	06815	Texto completo de evento	Nacional	Medidas e calculos de espectro de energia de neutrons emergentes de um duto em uma blindagem
68	2000	07212	Texto completo de evento	Nacional	Experimento de carregamento do nucleo do reator IPEN/MB-01
69	2000	07213	Texto completo de evento	Nacional	Experimento sobre detetores out-of-core no reator IPEN/MB-01
70	1999	07507	Texto completo de evento	Nacional	Uma proposta de estudo brasileira visando a utilizacao de torio em reatores
71	1997	05012	Texto completo de evento	Nacional	Analise de sistema de calculo para blindagem de radiacao
72	1997	05021	Texto completo de evento	Nacional	Analise de criticalidade utilizando o codigo MCNP4A
73	1995	05902	Texto completo de evento	Nacional	Analise de experimentos criticos de oxidos mistos utilizando o codigo HAMMER-TECHNION com tratamentos de autoblindagem via metodos de Bondarenko
74	1993	02108	Texto completo de evento	Nacional	Implementacao do metodo de Bondarenko para o tratamento da autoblindagem no codigo HAMMER-TECHNION
75	1993	02135	Texto completo de evento	Nacional	Verificacao das bibliotecas JENDL-3 e ENDF/B-VI para o ciclo TANDEM
76	1991	04134	Texto completo de evento	Nacional	Analise de experimento critico contendo oxido misto PuOsub(2)UOsub(2) utilizando a biblioteca de dados nucleares JENDL-3
77	1991	04142	Texto completo de evento	Nacional	Tema especial de fisica de reatores do VIII ENFIR
78	1990	03577	Texto completo de evento	Internacional	Burn-up physics in a coupled HAMMER-TECHNION/CINDER-2 system and ENDF/B-V aggregate fission product thermal cross section validation
79	1990	03980	Dissertação	Nacional	Analise de transmutacao considerando o tratamento explicito dos produtos de fissao num sistema acoplado, composto pelos codigos Hammer-Technion e
80	1990	06728	Texto completo de evento	Nacional	Hancind: Sistema acoplado HAMMER TECHNION e CINDER-2 para calculo celular com tratamento explicito dos produtos de fissao e nuclideos actinideos