Reactor internals and hold down spring stiffness/reaction calculation

Background: Hold down spring is a structural component that supports the reactor pressure vessel. It is located between the flange and barrel components, and has a function that transfers the force caused by reactor pressure vessel cap to barrel flange. Purpose: This paper attempts to have an analysis calculation and comparison of AP1OOO and LPP Hold down spring. Methods: This article inherited Qinshan nuclear power hold down spring analysis method, use analytical method and FEM method to solve the problem. Results: The stress and deflection of HDS are calculated. Since the friction coefficient may have a large effect, the results of different friction coefficients are also analyzed. Conclusions: This paper compared the Qinshan, AP1000 and LPP HDS design advantages and disadvantages and proposed two kinds of new design, expected to have a reference value for follow-up engineers. (authors)