NUCLEAR DATA SENSITIVITY AND UNCERTAINTY ANALYSIS FOR THE CANADIAN SUPERCRITICAL WATER- COOLED REACTOR (SCWR) 64 – ELEMENT FRESH FUEL LATTICE CELL
39th Annual CNS-CNA Student Conference - 2015 June 01


Presented at:
39th Annual CNS-CNA Student Conference
2015 June 01
Location:
Toronto, Canada
Session Title:
Student Session

Authors:
A. Moghrabi (McMaster University)
D. Novog (McMaster University)
  

Abstract

Accurate and complete nuclear data are a fundamental requirement for any nuclear reactor model. The Canadian supercritical water-cooled reactor (SCWR) is an advanced reactor concept for which, like all advanced GEN-IV reactor concepts, operating conditions and materials differ significantly from conventional reactors. Consequently, current nuclear data evaluations may not be suitable for modeling 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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