![]() Although this is true, the uncertainty due to other parameters must always be considered together with nuclear data, since some of them could be significant. Nuclear data uncertainty has been identified to be the highest contributor of uncertainty of the VVER-1000 fuel assembly. The calculations are carried out using KENO-VI to perform the neutronics calculations and TSUNAMI-2D/3D and SAMPLER to perform the sensitivity and uncertainty analysis. The sources of uncertainties are classified into three groups, namely uncertainties due to nuclear data, manufacturing tolerances and numerical uncertainties due to methods’ implementations. In this study, Phase I of the benchmark was considered for the uncertainty quantification. Three reactor systems are also studied, viz. The benchmark consists of three phases, each with three exercises. The main contribution of this paper is the quantification of uncertainties in the Kozloduy-6 VVER-1000 fuel assembly using SCALE-6.2.1 methodology. Only the emails with the correct format will stay in your list. The objective of the benchmark is to determine and verify uncertainty bounds for results of calculations of LWRs based on operating data using best-estimate codes. Atomic Mail Verifier provides a three-step verification process that will allow you to weed out the maximum number of nonexistent email addresses Syntax check This program will remove emails with typos like kateaol,com. Abstract: This work is based on the benchmark for uncertainty analysis in modelling of light water reactors compiled by the Nuclear Energy Agency within the Organisation for Economic Cooperation and Development (OECD/NEA). Uncertainty due to other parameters could be significant to the overall uncertainty.Nuclear data uncertainty was identified to be the highest contributor of uncertainty.TSUNAMI-2D/3D and SAMPLER were used for the sensitivity and uncertainty analysis.KENO-VI was used to perform the neutronics calculations.Uncertainties are due to nuclear data, manufacturing tolerance and numerical method.SCALE-6.2.1 is used to quantify the neutronics uncertainties of the fuel assembly.This work is based on the OECD/NEA Benchmark for Uncertainty Analysis of LWRs.
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