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SISTEMA INTEGRAL DE INFORMACIÓN ACADÉMICA - PÚBLICO
Título del libro: Proceedings Of The 20th Pacific Basin Nuclear Conference, Vol 1 Título del capítulo: Sensitivity and Uncertainty Analysis of a SCWR from Monte Carlo Simulations
SCWR; Monte Carlo; Sensitivity analysis; Numerical code
Resumen:
In this paper the sensitivity and uncertainty analysis of a SCWR
applying a methodology based on Monte Carlo with reduced order models is
presented. The numerical code to simulate the SCWR performance of the
thermal hydraulics considers a three-pass core design with multiple
heat-up steps. A model using an average channel simulates each pass. The
neutronic calculations were performed with HELIOS-2 and the results were
used to evaluate the reactivity feedback, caused by changes in the fuel
temperature and supercritical water density, which was used to simulate
the neutronic process with the point kinetics model. The Monte Carlo's
simulation was applied to establish the operating domain of SCWRs which
are not yet in operation, therefore the thermal-hydraulic and nuclear
processes rely on numerical modeling with the purpose of developing or
confirming the design basis. This methodology has into account an
invariability test in order to obtain the representative sample, i.e.,
invariable results with the simulation size. Additionally, the relative
standard deviation is calculated and presented for power, temperature
and pressure drop, as well as the regression analysis.