2007, Volume 3, n°2

Published

Summary

• Deterministic and probabilistic approaches to fatigue crack growth in nuclear pressure vessels
  A.S. Francisco, P.F. Frutuoso e Melo
  pp 110 – 117
• Tritium dispersion simulation in the atmosphere from ANGRA I Nuclear Power Plant
  Davidson Martins Moreira, Marco Tullio Vilhena, Jonas da Costa Carvalho
  pp 118 - 130
• Preliminary results on modelling of primary water stress corrosion cracking at control rod drive mechanism nozzles of PWR nuclear plants
  Omar F. Aly, A.H.P. Andrade, M. Mattar Neto
  pp 131 - 138
• Fractional divergence for neutron flux profile in nuclear reactors
  Shantanu Das, Bibhuranjan Basudeb Biswas
  pp 139 - 159
• Thermal behaviour of the IPR-R1 TRIGA nuclear reactor
  Amir Zacarias Mesquita, Hugo Cesar Rezende
  pp 160 - 169
• Experimental determination of heat transfer coefficients in uranium zirconium hydride fuel rod
  Amir Zacarias Mesquita, Hugo Cesar Rezende
  pp 170 - 179
• Integrated system for regulatory control of the radioactive waste management in radioactive installations
  Marilia T. Christovao, Tarcisio P. Ribeiro De Campos
  pp 180 - 195
• A forward tracking scheme for solving radionuclide advective problems in unsaturated porous media
  J. Aquino, F. Pereira, H.P. Amaral Souto, A.S. Francisco
  pp 196 - 205