Open Access
Issue
EPJ Web Conf.
Volume 225, 2020
ANIMMA 2019 – Advancements in Nuclear Instrumentation Measurement Methods and their Applications
Article Number 04032
Number of page(s) 5
Section Research Reactors
DOI https://doi.org/10.1051/epjconf/202022504032
Published online 31 January 2020
  1. X-5 Monte Carlo Team, MCNP − A General Monte Carlo N-Particle Transport Code, Version 5, Volume I & II, 2003. [Google Scholar]
  2. L. Snoj et al., “Computational analysis of irradiation facilities at the JSI TRIGA reactor”, Applied Radiation and Isotopes, Vol. 70, pp. 483–488, 2011 [CrossRef] [Google Scholar]
  3. K. Ambrožič et al., “ Computational analysis of the dose rates at JSI TRIGA reactor irradiation facilities≪, Applied Radiation and Isotopes, Vol. 130, pp. 140–152, 2017 [CrossRef] [Google Scholar]
  4. L. Snoj et al., “ Analysis of neutron flux distribution for the validation of computational methods for the optimization of research reactor utilization”, Applied Radiation Isotopes, Vol. 69, pp. 136–141, 2011 [CrossRef] [PubMed] [Google Scholar]
  5. S.W. Mosher et. al., ADVANTG − An Automated Variance Reduction Parameter Generator, ORNL/TM-2013/416, Oak Ridge National Laboratory, 2013. [CrossRef] [Google Scholar]
  6. M. B. Chadwick et. al., ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology, Nuclear Data Sheets, Special Issue on Evaluated Nuclear Data File ENDF/B- VII.0, 2006. [Google Scholar]
  7. T.M. Evans, et. al., Denovo: a new three dimensional parallel discrete ordinates code in SCALE, Nucl. Technol. 171, 171–200, 2010. [Google Scholar]
  8. J.C. Wagner, 2014. FW-CADIS method for global and semi-global variance reduction of Monte Carlo radiation transport calculations, Nucl. Sci. Eng. 176, 37–57, 2014. [Google Scholar]
  9. A. Jazbec, L. Snoj, 3D Model of Jozef Stefan Institute TRIGA Mark II Reactor, NENE 2016, Portoroz 2016. [Google Scholar]
  10. ICRP, Data for protection against ionizing from external sources − supplement to ICRP Publication 15 ICRP Publication 21. Ann ICRP. 1973. [Google Scholar]
  11. G. Žerovnik, M. Podvratnik, L. Snoj, On normalization of fluxes and reaction rates in MCNP criticality calculations, Annals of Nuclear Energy, Vol. 63, pp. 126–128, 2014 [Google Scholar]
  12. B. Kos, L. Snoj, On using Grasshopper add-on for CAD to MCNP conversion, PHYSOR 2016, Idaho, 2016. [Google Scholar]
  13. ICRP Publication 103, The 2007 Recommendations of the International Commission on Radiological Protection, 2007. [Google Scholar]
  14. Operating manual, Neutron Probe LB 6411, Id. No. 1-20188-82042 BA2, Rev. No. 01, 1996. [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.