Uncertainties of Reactivity Calculations with Respect to Nuclear Data for the Canadian SCWR

Abstract

The Canadian supercritical water-cooled reactor (SCWR) is a pressure tube reactor using heavy water moderator, similar to conventional pressurised heavy water reactors (PHWR). However, it is intended to operate with a coolant pressure of 25 MPa and temperatures of 350ºC (inlet) to 625ºC (outlet). Other novel features include PuO₂/ThO₂ based fuel and advanced fuel bundle and fuel channel designs. This paper presents results of the sensitivity of reactivity calculations such as coolant voiding and fuel temperature coefficients to nuclear data along with contributions to uncertainties of calculation for a radially reflected, axially finite fresh fuel SCWR.