Finite-element procedure for calculating the three-dimensional inelastic bowing of fuel rods (AWBA development program)
An incremental finite element procedure is developed for calculating the in-pile lateral bowing of nuclear fuel rods. The fuel rod is modeled as a viscoelastic beam whose material properties are derived as perturbations of the results of an axisymmetric stress analysis of the fuel rod. The effects which are taken into account in calculating the rod's lateral bowing include: (a) lateral, axial, and rotational motions and forces at the rod supports, (b) transverse gradients of temperature, fast-neutron flux, and fissioning rate, and (c) cladding circumferential wall thickness variation. The procedure developed in this report could be used to form the basis for a computer program to calculate the time-dependent bowing as a function of the fuel rod's operational and environmental history.
- Research Organization:
- Bettis Atomic Power Lab., West Mifflin, PA (USA)
- DOE Contract Number:
- AC11-76PN00014
- OSTI ID:
- 5335604
- Report Number(s):
- WAPD-TM-1498; ON: DE82015127
- Country of Publication:
- United States
- Language:
- English
Similar Records
ACCEPT: a three-dimensional finite element program for large deformation elastic-plastic-creep analysis of pressurized tubes (LWBR/AWBA Development Program)
Theory and verification of a fuel rod mechanics model based on a two-dimensional finite element method with consideration of fuel/cladding contact and friction
Related Subjects
210500* -- Power Reactors
Breeding
BREEDER REACTORS
BURNUP
DEFORMATION
FUEL CANS
FUEL ELEMENTS
FUEL RODS
LWBR TYPE REACTORS
MATHEMATICAL MODELS
PERFORMANCE
REACTOR COMPONENTS
REACTORS
STRESSES
THERMAL REACTORS
THERMAL STRESSES
THREE-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS