Uncertainties of Reactivity Calculations with Respect to Nuclear Data for the Canadian SCWR
33rd Annual CNS Conference - 2012 June 10-13


Presented at:
33rd Annual CNS Conference
2012 June 10-13
Location:
Saskatoon, Canada
Session Title:
Fuel & Advanced Reactors

Authors:
Laura Blomeley (Atomic Energy of Canada Limited)
Jeremy Pencer (Atomic Energy of Canada Limited)
  

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.

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