In nuclear reactors such as pressurized water reactors (PWR), heavy section components, manufactured using low alloy steels, are connected to stainless steel piping systems through dissimilar metal welds (DMW). These welds are highly susceptible to stress corrosion cracking. Fracture mechanics and structural integrity assessments are currently being undertaken for the primary circuit at China General Nuclear Power (CGN) nuclear power station to manage the risk of primary water stress corrosion cracking (PWSCC). Consequently, knowledge of the magnitude and distribution of residual stress is of considerable importance. The purpose of the proposed experiments is to provide through thickness residual stresses in two components of different thicknesses to validate finite element models and contour method measurements.