Image de couverture de livre

Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation

Fuente: Redalyc

Enregistré dans:

Détails bibliographiques
Auteur principal:	Eduardo Madeira Borges
Format:	Artículo científico
Langue:	en
Publié:	Sociedade Brasileira de Proteção Radiológica - SBPR 2021
Sujets:	Biología ANGRA 2 RELAP5 code Safety analysis Nuclear reactor
Accès en ligne:	Acceder al recurso
Tags:	Ajouter un tag Pas de tags, Soyez le premier à ajouter un tag!

Documents similaires

Thermal study of the modular high-temperature gascooled reactor
par: M.C. Ramos
Publié: (2022)

RELAP5 Modeling of a Siphon Break Effect on the Brazilian Multipurpose Reactor
par: Humberto Vitor Soares
Publié: (2020)

Thermophysical properties of nanofluids MWCNT (multi-walled carbon nanotubes) in water for emergency coolant from nuclear reactors
par: Alexandre Melo Oliveira
Publié: (2020)

A simulation model for capacity planning of nuclear fuel plants for research reactors
par: Miguel L. N. Negro
Publié: (2021)

Comparison of computer programs to analyze the irradiation performance of U-Mo monolithic fuel plates and UO2 cylindrical fuel rods in power reactors
par: André Luiz Candido Silva
Publié: (2021)

Computer simulator for the research reactor IPEN/MB-01
par: Marcelo Casorla
Publié: (2020)

Journal of Nuclear Engineering
Publié: (2021)

Evaluation of “Safety Related” and “Important to Safety” terminology for safety classification of nuclear installation items in Brazil
par: D. B. Baroni
Publié: (2022)

Potential advantages of molten salt reactor for merchant ship propulsion
par: Luiz Gonzaga de Freitas Neto
Publié: (2021)

Uso de un reactor de lecho empacado para la producción de biodiesel
par: Anabel González
Publié: (2011)

Estudo Diagnóstico geocientífico e socioambiental do rio Bracuí, Angra dos Reis (RJ)
par: Pedroso, Enrico Campos, et autres
Publié: (2026)

Physical-chemical and operational performance of an anaerobic baffled reactor (ABR) treating swine wastewater
par: Erlon Lopes Pereira
Publié: (2010)

Development of a PID-Fuzzy controller in the water level control of a pressurizer of a nuclear reactor
par: Thiago Souza Pereira de Brito
Publié: (2020)

Problemas y soluciones en el diseño de reactores enzimáticos
par: Luis Eduardo Ceballos Camargo
Publié: (2016)

Design of a digital system for operational parameters simulation of IPR-R1 Triga nuclear research reactor
par: Aldo M. F. Lage
Publié: (2019)

Adhesion of the marine bacterium Pseudomonas sp. NCIMB 2021 to different hydrogel surfaces
par: Rasmussen, K., Ostgaard, K
Publié: (2021)

Probabilistic Safety Analysis and Risk-Based Inspection of nuclear research reactors: state-of-the-art and implementation proposal
par: Raíssa Oliveira Marques
Publié: (2020)

Thermal and epithermal neutron fluence rates in the irradiation facilities of the TRIGA IPR-R1 nuclear reactor
par: Dante Marco Zangirolami
Publié: (2010)

International Cooperation for Enhancing Nuclear Safety, Security, Safeguards and Non-proliferation–60 Years of IAEA and EURATOM: Proceedings of the XX Edoardo Amaldi Conference, Accademia Nazionale dei Lincei, Rome, Italy, October 9-10, 2017
Publié: (2018)

Preliminary neutronic study of the S-PRISM fast reactor
par: João Manoel Losada Moreira
Publié: (2020)

Nuclear Engineering and Technology
Publié: (2016)

Two-dimensional transient thermal analysis of a fuel rod by finite volume method
par: Rhayanne Yalle Negreiros Costa
Publié: (2020)

Monitoring of Coolant Flow Rate and Velocity in the Hot Channel of the IPR-R1 TRIGA Reactor Core
par: Amir Zacarias Mesquita
Publié: (2010)

Human factors engineering and participatory design in theproject of a nuclear research reactor control center
par: Larissa Pereira Farias
Publié: (2021)

Human factors engineering and participatory design in the project of a nuclear research reactor control centre
par: L. P. Farias
Publié: (2019)

Analytical solution of the multigroup neutron diffusion equation coupled with an iterative method
par: Adilson Costa da Silva
Publié: (2022)

Risk-based design of electric power systems for nonconventional nuclear facilities at shutdown modes
par: S. S. Borsoi
Publié: (2022)

Análisis mediante dinámica de fluidos computacional de la conducción de calor de un elemento combustible del reactor nuclear TRIGA MARK III
par: David Rojas-Valdez
Publié: (2021)

Arranque de un reactor anaerobio
par: José Pacheco
Publié: (2003)

Anaerobic treatment of real textile wastewater with a fluidized bed reactor
par: Sen, S., Demirer, G
Publié: (2003)

Influence of flow direction in the performance of anaerobic filters
par: Ronaldo Fia
Publié: (2012)

Estudio de distribución de tiempos de residencia en un reactor biológico de lecho empacado cerámico
par: Luz Helena Pinzón
Publié: (2004)

Hybrid reactor for priority pollutant nitrobenzene removal
par: Sarathi, P., Gupta, S
Publié: (2003)

Efecto de dos metales pesados, cadmio y níquel, sobre la eficiencia de remoción de carga orgánica de un reactor UASB a escala de laboratorio
par: Luis Eduardo Forero
Publié: (2004)

Science and Technology of Nuclear Installations
Publié: (2007)

Intensificación del proceso de producción de biodiesel utilizando un micro-reactor tubular
par: Enrique A. López-Guajardo
Publié: (2011)

Reactor network synthesis for isothermal conditions
par: Lincoln Kotsuka da Silva
Publié: (2008)

Continuous electrochemical treatment of phenolic wastewater in a tubular reactor
par: Korbahti, B., Tanyolac, A
Publié: (2003)

Evaluación de la biomasa en el lodo granular anaerobio en reactores por carga
par: Magaly Chávez
Publié: (2003)

Simplified CFD model of coolant channels typical of a plate-type fuel element: an exhaustive verification of the simulations
par: J. G. Mantecón
Publié: (2019)