Nonlinear analysis of hydraulic buckling instability of ANS involute fuel plates

Technical Report · Mon Mar 01 00:00:00 EST 1993

DOI:https://doi.org/10.2172/6689742· OSTI ID:6689742

Sartory, W K

The hydraulic buckling instability of the involute fuel plates and hydraulic coolant channels in the Advanced Neutron Source (ANS) uranium fission reactor is analyzed nonlinearly using the commercial ABAQUS finite element computer program for the fuel plates in conjunction with a user-written element for the two-dimensional fluid flow in the coolant channels. This methodology has been used for several purposes, including determination of the effect of the aluminum-clad plate plastic behavior and the effect of three-dimensional plate temperature distributions on hydraulic buckling. The present report concentrates on a study of the effect of hydraulic channel imperfections on buckling. The specific form of imperfection considered is an error in fluid channel thickness that is uniform within any one channel but that varies from one channel to the next. The calculated bifurcation (linear buckling) coolant velocity is about 45 m/s, whereas the present design coolant velocity is 25 m/s. At the design velocity, the calculated fluid-induced plate deflection due to the imperfection is somewhat less in magnitude and opposite in direction from the imperfection itself.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6689742
• Report Number(s): ORNL/TM-12319; ON: DE93010834
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
IRRADIATION REACTORS
BUCKLING
FUEL PLATES
HYDRAULICS
INSTABILITY
REACTOR COOLING SYSTEMS
COOLING SYSTEMS
FLUID MECHANICS
FUEL ELEMENTS
MECHANICS
REACTOR COMPONENTS
REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors