|Revisiting stainless steel as PWR fuel rod cladding after Fukushima Daiichi accident|
A Abe, C Giovedi, D da Souza Gomes, AT e Silva
Journal of Energy and Power Engineering 8 (6), 2014
|Program for in-pile qualification of high density silicide dispersion fuel at IPEN/CNEN-SP|
JER da Silva, LAA Terremoto, M Durazzo
|A model for release of fission products from a breached fuel plate under wet storage|
LAA Terremoto, RS Seerban, CA Zeituni, JER da Silva, AT e Silva, ...
Progress in Nuclear Energy 50 (7), 818-827, 2008
|Neutronic, thermal-hydraulics and accident analysis calculations for an irradiation device to be used in the qualification process of dispersion fuels in the IEA-R1 research …|
DB Domingos, PE Umbehaun, JER Silva, TN Conti, M Yamaguchi
|Neutronic analysis for production of fission molybdenum-99 at IEA-R1 and RMB research reactors|
DB Domingos, AT Silva, JER Silva, TG João
RRFM 2011, 2011
|Comparison of the mechanical properties and corrosion resistance of zirlo and other zirconium alloys|
CA Teodoro, JER da Silva, LAA Terremoto, M Castanheira, AT e Silva, ...
International Nuclear Atlantic Conference–INAC, 2007
|Evaluation of corrosion on the fuel performance of stainless steel cladding|
D de Souza Gomes, A Abe, AT e Silva, C Giovedi, MR Martins
EPJ Nuclear Sciences & Technologies 2, 40, 2016
|Fuel performance evaluation for the cafe experimental device|
C Giovedi, LT Hirota, DS Gomes, AY Abe
|Neutronic analysis of a U–Mo–Al fuel and europium as burnable poison|
ROR Muniz, A dos Santos, M Yamaguchi, PCR Rossi, DB Domingos, ...
Annals of Nuclear Energy 92, 46-51, 2016
|Test section for experimental simulation of loss of coolant accident in an instrumented fuel assembly irradiated in the IEA-R1 reactor|
E Maprelian, WM Torres, PE Umbehaun, G Sabundjian
|Angra 1 high burnup fuel behaviour under reactivity initiated accident conditions|
|Non destructive testing of irradiated fuel assemblies at the IEA-R1 research reactor|
JER da Silva, LAA Terremoto, M Castanheira, CA Teodoro, AT e Silva, ...
International Nuclear Atlantic Conference-INAC, Santos, SP, Brazil, Sept …, 2007
|Evaluation of debris fretting failure on PWR fuel by post-irradiation examination and modeling in the degrad-1 code|
M Castanheira, JER da Silva, G Lucki, LAA Terremoto, AT e Silva, ...
International Nuclear Atlantic Conference-INAC, 2007
|Design and construction of an irradiation apparatus with controlled atmosphere and temperature for radiation damage evaluation of nuclear materials in the IEA-R1 Research Reactor|
G Lucki, JER da Silva, M Castanheira, LA Albiac, CAT Terremoto, ...
|Uncertainty Evaluation and Sensitivity Analysis Under Accident Scenarios|
D de Souza Gomes, AT e Silva
2018 26th International Conference on Nuclear Engineering, V003T02A001 …, 2018
|Thermal hydraulic analysis improvement for the IEA-R1 research reactor and fuel assembly design modification|
PE UMBEHAUN, WM TORRES, JAB SOUZA, M Yamaguchi, AT SILVA, ...
World Journal of Nuclear Science and Technology, 2018
|Application of nondestructive methods for qualification of high density fuels in the IEA-R1 reactor|
JER Silva, AT Silva, DB Domingos, LAA Terremoto
|Application of the failure modes and effects analysis technique to theemergency cooling system of an experimental nuclear power plant|
|Power upgrading and modernization of IEA-R1 Brazilian research reactor|
JR Maiorino, AV Gomes, AT e Silva, DKS Ting, H Pasqualetto
|ADAPTATION OF FUEL CODE FOR LIGHT WATER REACTOR WITH AUSTENITIC STEEL ROD CLADDING|
D de Souza Gomes, AT e Silva, C Giovedi