Nuclear Reactors
A Mesquita - 2012 - books.google.com
This book presents a comprehensive review of studies in nuclear reactors technology from
authors across the globe. Topics discussed in this compilation include: thermal hydraulic …
authors across the globe. Topics discussed in this compilation include: thermal hydraulic …
Experimental study of temperature distribution and development of a power monitoring channel for the IPR-R1 TRIGA® research nuclear reactor
AZ Mesquita, VF de Almeida, DAP Palma - Nuclear Engineering and …, 2024 - Elsevier
The natural convection and forced cooling experiments were conducted to confirm the
cooling capability in the IPR-R1 TRIGA® nuclear research reactor. Temperature …
cooling capability in the IPR-R1 TRIGA® nuclear research reactor. Temperature …
Thermal behaviour of the IPR-R1 TRIGA nuclear reactor
AZ Mesquita, HC Rezende - International Journal of …, 2007 - inderscienceonline.com
Experimental and analytical studies have been performed at the Nuclear Technology
Development Center? CDTN (Belo Horizonte) to find out the temperature distribution in the …
Development Center? CDTN (Belo Horizonte) to find out the temperature distribution in the …
The Method to Predict First Critical Core Loading for Nuclear Reactors
SŞ Lüle - Sakarya University Journal of Science, 2020 - dergipark.org.tr
Nuclear power plants have an important role in carbon free electricity production in the
world. One of the important steps of commissioning a nuclear power plant is the first core …
world. One of the important steps of commissioning a nuclear power plant is the first core …
UNCERTAINTY ANALYSIS ON THERMOHYDRAULIC PARAMETERS OF THE IPR-R1 TRIGA RESEARCH REACTOR
ACL da Costa, AZ Mesquita - repositorio.cdtn.br
This paper presents the uncertainty analysis in the results of the thermohydraulic
experiments performed in the IPR-R1 TRIGA Mark 1 research nuclear reactor of …
experiments performed in the IPR-R1 TRIGA Mark 1 research nuclear reactor of …
[PDF][PDF] Determination of the thermal-hydraulic parameters of ITU Triga Mark-II Reactor
A Durmayaz, EH Özkul - 2000 - kurumsalarsiv.tenmak.gov.tr
In this study, a transient, one-dimensional thermal-hydraulic subchannel analysis for ITU
TRIGA Mark-II reactor was employed. Mixed convection is considered in modelling to …
TRIGA Mark-II reactor was employed. Mixed convection is considered in modelling to …
[引用][C] Experimental investigation temperature patterns in the IPR-R1 triga nuclear reactor
AZ Mesquita, HC Rezende - 3rd World Triga Users Conference, Belo Horizonte …, 2020