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 | 05004 | |
| Number of page(s) | 6 | |
| Section | 5. Fission Facilities, Fuel Cycle & Waste Management Facilities, Decommissioning | |
| DOI | https://doi.org/10.1051/epjconf/201715305004 | |
| Published online | 25 September 2017 | |
- Los Alamos National Laboratory. MCNP — A General N-Particle Transport Code, Version 5 — Volume I: Overview and Theory, X-5 Monte Carlo Team, LA-UR-03-1987, April 2003. [Google Scholar]
- Oak Ridge National Laboratory, SCALE: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design, June 2011. [Google Scholar]
- SpaceClaim Corporation, SpaceClaim2015. [Google Scholar]
- FDS, SuperMC (Monte Carlo Automatic Modeling Program for Radiation) 5.1 Professional, 2015. [Google Scholar]
- ICRP, International Commission on Radiological Protection. ICRP-119, Compendium of Dose Coefficients based on ICRP Publication 60. [Google Scholar]
- Oak Ridge National Laboratory, ADVANTG 3.03 — Automated Variance Reduction Generator. [Google Scholar]
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