Ceramic nuclear fuel fracture modeling with the extended finite element method
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Duke Univ., Durham, NC (United States). Civil and Environmental Engineering
Ceramic fuel pellets used in nuclear light water reactors experience significant fracture due to the high thermal gradients experienced under normal operating conditions. This has important effects on the performance of the fuel system. Because of this, a realistic, physically based fracture modeling capability is essential to predict fuel behavior in a wide variety of normal and off-normal conditions. The extended finite element method (X-FEM) is a powerful method to represent arbitrary propagating discrete cracks in finite element models, and has many characteristics that make it attractive for nuclear fuel performance analysis. This paper describes the implementation of X-FEM in a multiphysics fuel performance code and presents applications of that capability. These applications include several thermal mechanics fracture benchmark problems, which demonstrate the accuracy of this approach. It also includes application of this capability to study nuclear fuel fracture, both on stationary and propagating cracks. The study on stationary cracks shows the effects that varying the number of radial cracks and the length of those cracks have on the energy release rate. Here, the propagating crack case demonstrates random initiation and subsequent propagation of interacting thermally induced cracks during an initial ramp to full power with fresh fuel.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE); Idaho National Laboratory LDRD
- Grant/Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1575375
- Alternate ID(s):
- OSTI ID: 1775732
- Report Number(s):
- INL/JOU-18-44950-Rev000; TRN: US2001147
- Journal Information:
- Engineering Fracture Mechanics, Vol. 223; ISSN 0013-7944
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Web of Science
Similar Records
Discrete Modeling of Early-Life Thermal Fracture in Ceramic Nuclear Fuel
Pellet cladding mechanical interaction modeling using the extended finite element method