Open Access
Issue
EPJ Web Conf.
Volume 153, 2017
ICRS-13 & RPSD-2016, 13th International Conference on Radiation Shielding & 19th Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society - 2016
Article Number 05020
Number of page(s) 4
Section 5. Fission Facilities, Fuel Cycle & Waste Management Facilities, Decommissioning
DOI https://doi.org/10.1051/epjconf/201715305020
Published online 25 September 2017
  1. T. Goorley, et al., Initial MCNP6 Release Overview, Nuclear Technology 180, pp 298-315 (12/2012) [Google Scholar]
  2. S. W. Mosher, et al., ADVA1VTG-An Automated Variance Reduction Parameter Generator, ORNL/TM-2013/416 (08/2015) [Google Scholar]
  3. I. C. Gauld, ORIGEN-S: Depletion Module to Calculate Neutron Activation, Actinide Trans-mutation, Fission Product Generation, and Radiation Source Terms, in Ft], Sect. F7 (06/2011) [Google Scholar]
  4. SCALE: A Comprehensive Modelling and Simulation Suite for Nuclear Safety Analyses and Design, ORNL/TM-2005/39, Version 6.1(06/2011), upgrade to Version 6.1.2 (02/2012) [Google Scholar]
  5. M. Pantelias, B. Volmert, Activation Neutronics for a Swiss Pressurized Water Reactor, Nuclear Technology 192, pp 278-285 (2015) [CrossRef] [Google Scholar]

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