Open Access
EPJ Web of Conferences
Volume 106, 2016
ISRD 15 – International Symposium on Reactor Dosimetry
Article Number 03010
Number of page(s) 8
Section Transport Calculations (Neutron and Gamma-Ray) and Modeling
Published online 03 February 2016
  1. Serpent Website [referenced 24.3.2014] [Google Scholar]
  2. J. Leppänen, “Development of a new Monte Carlo reactor physics code.” D.Sc. Thesis, Helsinki University of Technology (2007) [Google Scholar]
  3. T. Viitanen and A. Räty, “Calculating the nuclide inventory of FiR 1 TRIGA Mk-II reactor”, VTT Reports, VTT-R-05511-12 (2012, unpublished) [Google Scholar]
  4. I. Auterinen et al., “Metamorphosis of a 35 year-old triga reactor into a modern BNCT facility”, Frontiers in Neutron Capture Therapy , 1, Kluwer Academic / Plenum Publishers, New York, 67–275 (2001) [Google Scholar]
  5. A. Santamarina et al. “The JEFF-3.1.1 Nuclear Data Library”, OECD/NEA, ISBN 978-92-64-99074-6 (2009) [Google Scholar]
  6. International Atomic Energy Agency, “International Reactor Dosimetry File 2002 (IRDF-2002)”, STI/DOC/010/452, ISBN 92-0-105106-9, (2006) [Google Scholar]

Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.

Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.

Initial download of the metrics may take a while.