Light Water Reactor Sustainability Program Status Report on the Grizzly Code Enhancements

Novascone, Stephen R. ; Spencer, Benjamin W. ; Hales, Jason D.

Idaho National Laboratory

关键词: 11 Nuclear Fuel Cycle And Fuel Materials Contour Integral;    Reactor Pressure Vessel;    Fracture Mechanics;    Contour Integral;   

DOI  :  10.2172/1115617
RP-ID  :  INL/EXT-13-30315
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1115617

美国|英语

来源: UNT Digital Library

【 摘 要 】

This report summarizes work conducted during fiscal year 2013 to work toward developing a full capability to evaluate fracture contour J-integrals to the Grizzly code. This is a progress report on ongoing work. During the next fiscal year, this capability will be completed, and Grizzly will be capable of evaluating these contour integrals for 3D geometry, including the effects of thermal stress and large deformation. A usable, limited capability has been developed, which is capable of evaluating these integrals on 2D geometry, without considering the effects of material nonlinearity, thermal stress or large deformation. This report presents an overview of the approach used, along with a demonstration of the current capability in Grizzly, including a comparison with an analytical solution.