Open Access
EPJ Web of Conferences
Volume 106, 2016
ISRD 15 – International Symposium on Reactor Dosimetry
Article Number 05010
Number of page(s) 8
Section Experimental Techniques
Published online 03 February 2016
  1. X-5 Monte Carlo Team, MCNP – A General Monte Carlo N-Particle Transport Code, Vers. 5, LA-UR-03-1987, Los Alamos National Lab (2003, revised 2008)
  2. M. Pantelias, S.W. Mosher, Monte Carlo, Hybrid and Deterministic Calculations for the Activation Neutronics of Swiss LWRs, Trans. Am. Nucl. Soc., 109 (2013)
  3. B. Straathof, Neutron fluence rate determinations in Mühleberg and Gösgen Nuclear Power Plants, NRG Report 22967/119647 rev. nr. D, Petten (April 2013)

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