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Comparison of SERPENT and SCALE methodology for LWRs transport calculations and additionally uncertainty analysis for cross-section perturbation with SAMPLER module

In nuclear safety research, the quality of the results of simulation codes is widely determined by the reactor design and safe operation, and the description of neutron transport in the reactor core is a feature of particular importance. | Comparison of SERPENT and SCALE methodology for LWRs transport calculations and additionally uncertainty analysis for cross-section perturbation with SAMPLER module EPJ Nuclear Sci. Technol. 2 11 2016 Nuclear Sciences A. Labarile et al. published by EDP Sciences 2016 amp Technologies DOI 10.1051 epjn e2016-50002-7 Available online at http www.epj-n.org REGULAR ARTICLE Comparison of SERPENT and SCALE methodology for LWRs transport calculations and additionally uncertainty analysis for cross-section perturbation with SAMPLER module Antonella Labarile Nicolas Olmo Rafael Miró Teresa Barrachina and Gumersindo Verd u Institute for Industrial Radiophysical and Environmental Safety ISIRYM Universitat Politècnica de València Camí de Vera s n 46022 Valencia Spain Received 28 April 2015 Received in final form 30 October 2015 Accepted 12 January 2016 Published online 18 March 2016 Abstract. In nuclear safety research the quality of the results of simulation codes is widely determined by the reactor design and safe operation and the description of neutron transport in the reactor core is a feature of particular importance. Moreover for the long effort that is made there remain uncertainties in simulation results due to the neutronic data and input specification that need a huge effort to be eliminated. A realistic estimation of these uncertainties is required for finding out the reliability of the results. This explains the increasing demand in recent years for calculations in the nuclear fields with best-estimate codes that proved confidence bounds of simulation results. All this has lead to the Benchmark for Uncertainty Analysis in Modelling UAM for Design Operation and Safety Analysis of LWRs of the NEA. The UAM-Benchmark coupling multi-physics and multi- scale analysis using as a basis complete sets of input specifications of boiling water reactors BWR and pressurized water reactors PWR . In this study the results of the transport calculations carried out using the SCALE-6.2 .