One of the fundamental requirement for any nuclear reactor model isan accurate and complete nuclear data. The Canadian supercritical water-cooled reactor (SCWR) is an advanced GEN-Ⅳ reactor concept for whichoperating conditions and materials differ significantly from conventional reactors in addition to its design complexity illustrated with thehigh-efficiency reentrant channel. Consequently, current nuclear data evaluations may not be suitable for modelling the Canadian SCWR. In this work, a simplified sensitivity and uncertainty analysis of the SCWR-64 elements lattice cell with fresh fuel was investigated at the inlet and the outlet of the channel using TSUNAMI-2D Code which is a part of the SCALE 6.1.3.
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