Nuclear Data Sensitivity and Uncertainty Analysis for the Canadian Supercritical Water-cooled Reactor (SCWR) 64 - element Fresh Fuel Lattice Cell

Abstract

One of the fundamental requirement for any nuclear reactor model is an accurate and complete nuclear data. The Canadian supercritical water-cooled reactor (SCWR) is an advanced GEN-IV reactor concept for which operating conditions and materials differ significantly from conventional reactors in addition to its design complexity illustrated with the high-efficiency re-entrant 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.