Academic Company Events NI Developer Zone Support Solutions Products & Services Contact NI MyNI

Measurement and Automation Experiments

Featured Author

Featured Author - José Luiz Horacio Faccini, Institute of Nuclear Engineering, Brazil Mr. Faccini is the co-author of Natural Circulation Analysis, which is part of the Measurement and Automation Experiments Library.

Education
José Luiz Horacio Faccini received his Bachelor in Mechanical Engineering degree from the Engineering School of the Federal University Fluminense of Rio de Janeiro, Brazil, in 1980 and his M. Sc. degree in Mechanical Engineering from the Federal University of Rio de Janeiro, Rio de Janeiro, Brazil, in 1986.

Research and Development
Since 1987 Mr. Faccini is a Researcher in the Nuclear Reactor Division of the Institute of Nuclear Engineering (IEN) www.ien.gov.br of the Brazilian Nuclear Energy Commission (CNEN) www.cnen.gov.br. Mr. Faccini has collaborated with Dr. Botelho and others co-workers in research topics including experimental nuclear reactor thermal hydraulics and safety. He is responsible for the IEN's Experimental Thermal Hydraulics Laboratory (LTE) where it was constructed a small scale natural convection circuit similar to a prototype passive residual heat removal system of innovative PWR like the Westinghouse AP600.

Academic Experience

  • Heat Transfer Classes of Mechanical Engineering in the School of Engineering of the Catholic University of Petrópolis, in Rio de Janeiro: 1988-1992.
  • Laboratory Classes of Centrifugal Pumps Performance in the LTE for the Engineering School of the Federal University of Rio de Janeiro, in Rio de Janeiro: since 2001.

Other Work Organizations

  • Assembling Engineer at the Nuclebrás Heavyweight Equipment (NUCLEP), in Rio de Janeiro: 1981-1982.
  • Pump Designer Engineer at DANCOR Mechanical Industry, in Rio de Janeiro: 1986-1987.

Authorship
Mr. Faccini has collaborated in many papers published in Brazilian national and international Symposium since 1986, most of them in the field of experimental nuclear reactor thermal-hydraulics.

Previous Featured Authors