Journal
PROGRESS IN NUCLEAR ENERGY
Volume 52, Issue 5, Pages 494-502Publisher
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.pnucene.2009.11.002
Keywords
TRIGA; Reactor physics; Monte Carlo; Neutron flux; Critical parameter
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The aim of this work was to develop a methodological approach based on Monte Carlo code for the neutronic analysis of the first core configuration of the TRIGA Mark II research reactor of the University of Pavia and the validation of the results by benchmarking with the experimental and operational data reported in the reactor Fist Criticality Final Report. The neutron analysis was realised by means of the 3-D continuous-energy Monte Carlo code MCNP4C. The reactor model implemented represents in good detail all core components and allows the description of different core and fuel configurations with good versatility. Continuous-energy cross section data from ENDF/B-VI and ENDF/B-V and S(alpha, beta) scattering functions from the ENDF/B-VI library were used. The results of the MCNP simulations and the experimental values show a very good agreement proving the goodness of the model. (C) 2009 Elsevier Ltd. All rights reserved.
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