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

Journal Article · Thu Aug 01 04:00:00 EDT 1991 · Nuclear Technology; (United States)

OSTI ID:5758829

Nissen, K L ^[1]

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1. Siemens AG, Postfach 3220, W-8520 Erlangen (DE)

This paper reports on fuel rod computer models utilized to predict cladding tube integrity under normal operating or transient accident conditions in a nuclear fission reactor. The METHOD2D computer code, which includes a fuel rod mechanics model based on an axisymmetric finite element formulation, is developed and verified. This two-dimensional approach gives results for the axial and radial deformation of the fuel pellets and the cladding tube for the whole fuel rod. Because an algorithm for fuel pellet/cladding tube radial contact and axial friction is incorporated, the analysis of closed fuel/cladding gap situations is possible. Calculation results for a whole fuel rod are compared with a transient CABRI experiment that led to partial fuel melting but not to cladding failure.

• OSTI ID: 5758829
• Journal Information: Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 95:2; ISSN 0029-5450; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CODES
COMPUTERIZED SIMULATION
FINITE ELEMENT METHOD
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
KINETICS
M CODES
MELTING
NUMERICAL SOLUTION
PERFORMANCE TESTING
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTOR MONITORING SYSTEMS
SIMULATION
TESTING
TWO-DIMENSIONAL CALCULATIONS