Saved in:
| Main Author: | Clarysson Alberto Mello da Silva |
|---|---|
| Format: | Artículo científico |
| Language: | en |
| Published: |
Sociedade Brasileira de Proteção Radiológica - SBPR
2020
|
| Subjects: | |
| Online Access: | https://www.redalyc.org/articulo.oa?id=722280907007 |
| Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
Similar Items
Neutronic Evaluation of MSBR System Using MCNP Code
by: Clarysson Alberto Mello da Silva
Published: (2021)
by: Clarysson Alberto Mello da Silva
Published: (2021)
Medidas experimentais e simulação MCNPX para avaliar coeficiente de atenuação linear e mássico de catalisador ativado utilizado no processo de FCC
by: V. H. F. F. Silva
Published: (2020)
by: V. H. F. F. Silva
Published: (2020)
Validation and study of different parameters in the simulation of diagnostic X-ray spectra using the MCNPX code
by: K. C. W. Consatti
Published: (2023)
by: K. C. W. Consatti
Published: (2023)
Determination of fluid dynamic parameters through imports of CFD images validated in experiments for the MCNPX code
by: Victor Hugo Farias Ferreira da Silva
Published: (2020)
by: Victor Hugo Farias Ferreira da Silva
Published: (2020)
Criticality and depletion analysis of the European LeadCooled Training Reactor (ELECTRA)
by: A. L. P. Oliveira
Published: (2022)
by: A. L. P. Oliveira
Published: (2022)
Study of radioactive particle tracking using MCNPX code and artificial neural network
by: Roos Sophia de Freitas Dam
Published: (2021)
by: Roos Sophia de Freitas Dam
Published: (2021)
Analytical solution of the multigroup neutron diffusion equation coupled with an iterative method
by: Adilson Costa da Silva
Published: (2022)
by: Adilson Costa da Silva
Published: (2022)
Comparison of computer programs to analyze the irradiation performance of U-Mo monolithic fuel plates and UO2 cylindrical fuel rods in power reactors
by: André Luiz Candido Silva
Published: (2021)
by: André Luiz Candido Silva
Published: (2021)
Nuclear Engineering and Technology
Published: (2016)
Published: (2016)
Review of Regulatory Requirements for Implementing an Aging Management System for the IPR-R1 Triga Reactor of CDTN
by: A.R. Baliza
Published: (2022)
by: A.R. Baliza
Published: (2022)
Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation
by: Eduardo Madeira Borges
Published: (2021)
by: Eduardo Madeira Borges
Published: (2021)
Development of a PID-Fuzzy controller in the water level control of a pressurizer of a nuclear reactor
by: Thiago Souza Pereira de Brito
Published: (2020)
by: Thiago Souza Pereira de Brito
Published: (2020)
Preliminary neutronic study of the S-PRISM fast reactor
by: João Manoel Losada Moreira
Published: (2020)
by: João Manoel Losada Moreira
Published: (2020)
Design of a digital system for operational parameters simulation of IPR-R1 Triga nuclear research reactor
by: Aldo M. F. Lage
Published: (2019)
by: Aldo M. F. Lage
Published: (2019)
A simulation model for capacity planning of nuclear fuel plants for research reactors
by: Miguel L. N. Negro
Published: (2021)
by: Miguel L. N. Negro
Published: (2021)
Two-dimensional transient thermal analysis of a fuel rod by finite volume method
by: Rhayanne Yalle Negreiros Costa
Published: (2020)
by: Rhayanne Yalle Negreiros Costa
Published: (2020)
Probabilistic Safety Analysis and Risk-Based Inspection of nuclear research reactors: state-of-the-art and implementation proposal
by: Raíssa Oliveira Marques
Published: (2020)
by: Raíssa Oliveira Marques
Published: (2020)
Biodegradación de polietilenglicol 400 con consorcio de Pseudomonas sp. y Rhizobium trifolii
by: Paula Andrea Sánchez Rengifo
Published: (2023)
by: Paula Andrea Sánchez Rengifo
Published: (2023)
Reactor network synthesis for isothermal conditions
by: Lincoln Kotsuka da Silva
Published: (2008)
by: Lincoln Kotsuka da Silva
Published: (2008)
PARAMETRIC STUDY FOR ENHANCING THE RADIOISOTOPE PRODUCTION IN THE IEA-R1 RESEARCH REACTOR
by: Giovanni Laranjo de Stefani
Published: (2021)
by: Giovanni Laranjo de Stefani
Published: (2021)
Knowledge base about risk and safety of nuclear facilities to support analysts and decision-makers
by: Antonio Souza Vieira Neto
Published: (2021)
by: Antonio Souza Vieira Neto
Published: (2021)
Computer simulator for the research reactor IPEN/MB-01
by: Marcelo Casorla
Published: (2020)
by: Marcelo Casorla
Published: (2020)
Thermophysical properties of nanofluids MWCNT (multi-walled carbon nanotubes) in water for emergency coolant from nuclear reactors
by: Alexandre Melo Oliveira
Published: (2020)
by: Alexandre Melo Oliveira
Published: (2020)
Simplified CFD model of coolant channels typical of a plate-type fuel element: an exhaustive verification of the simulations
by: J. G. Mantecón
Published: (2019)
by: J. G. Mantecón
Published: (2019)
Uso de un reactor de lecho empacado para la producción de biodiesel
by: Anabel González
Published: (2011)
by: Anabel González
Published: (2011)
Long term comparison between reprocessed nuclear fuel cycles
by: F. B. G. L. Estanislau
Published: (2022)
by: F. B. G. L. Estanislau
Published: (2022)
Journal of Nuclear Engineering
Published: (2021)
Published: (2021)
Human factors engineering and participatory design in theproject of a nuclear research reactor control center
by: Larissa Pereira Farias
Published: (2021)
by: Larissa Pereira Farias
Published: (2021)
Human factors engineering and participatory design in the project of a nuclear research reactor control centre
by: L. P. Farias
Published: (2019)
by: L. P. Farias
Published: (2019)
Physical-chemical and operational performance of an anaerobic baffled reactor (ABR) treating swine wastewater
by: Erlon Lopes Pereira
Published: (2010)
by: Erlon Lopes Pereira
Published: (2010)
Monitoring of Coolant Flow Rate and Velocity in the Hot Channel of the IPR-R1 TRIGA Reactor Core
by: Amir Zacarias Mesquita
Published: (2010)
by: Amir Zacarias Mesquita
Published: (2010)
Potential advantages of molten salt reactor for merchant ship propulsion
by: Luiz Gonzaga de Freitas Neto
Published: (2021)
by: Luiz Gonzaga de Freitas Neto
Published: (2021)
Cultivos de alta densidad celular por retención interna: aplicación a la fermentación continua de etanol
by: Berta Carola Pérez
Published: (2004)
by: Berta Carola Pérez
Published: (2004)
Influence of flow direction in the performance of anaerobic filters
by: Ronaldo Fia
Published: (2012)
by: Ronaldo Fia
Published: (2012)
Methodology for Management and Physicochemical Monitoring and Quality Control of the Cooling Water of IPR-R1 Triga Nuclear Research Reactor
by: J.G.O. Marques
Published: (2022)
by: J.G.O. Marques
Published: (2022)
Validation Analysis Methodology to Determine the Cadmium, Indium and Impurities Concentration in Nuclear Grade Silver-indium-cadmium Alloys
by: L. C. OLIVEIRA
Published: (2022)
by: L. C. OLIVEIRA
Published: (2022)
Proposal for a radiation shielding study aiming the implantation of neutrons beam shutter in the j-9 radiation channel of the argonauta reactor of the nuclear engineering institute
by: Larissa Rocha Pitta Xavier
Published: (2019)
by: Larissa Rocha Pitta Xavier
Published: (2019)
Evaluación del tratamiento anaerobio de las aguas residuales de una comunidad universitaria
by: Sandra Crombet Grillet
Published: (2016)
by: Sandra Crombet Grillet
Published: (2016)
Journal of Nuclear Research and Applications
Published: (2024)
Published: (2024)
COMPUTATIONAL SIMULATION OF A TEST FACILITY IN REDUCED SCALE FOR ANALYSIS OF BORON DISPERSION IN A PRESSURIZER OF AN INTEGRAL COMPACT AND MODULAR REACTOR
by: Leorlen Y. Rojas Mazaira
Published: (2020)
by: Leorlen Y. Rojas Mazaira
Published: (2020)
Similar Items
-
Neutronic Evaluation of MSBR System Using MCNP Code
by: Clarysson Alberto Mello da Silva
Published: (2021) -
Medidas experimentais e simulação MCNPX para avaliar coeficiente de atenuação linear e mássico de catalisador ativado utilizado no processo de FCC
by: V. H. F. F. Silva
Published: (2020) -
Validation and study of different parameters in the simulation of diagnostic X-ray spectra using the MCNPX code
by: K. C. W. Consatti
Published: (2023) -
Determination of fluid dynamic parameters through imports of CFD images validated in experiments for the MCNPX code
by: Victor Hugo Farias Ferreira da Silva
Published: (2020) -
Criticality and depletion analysis of the European LeadCooled Training Reactor (ELECTRA)
by: A. L. P. Oliveira
Published: (2022)