BEHAVE-4: light water reactor fuel rod analysis code
Robert W. Stuart, Sidney Oldberg, Dan Stevenson, E.T. Rumble
Abstract
Open-access reader
Robert W. Stuart, Sidney Oldberg, Dan Stevenson, E.T. Rumble
Abstract
Open-access reader
This report describes the BEHAVE-4 code for light water reactor fuel rod analysis and provides instructions for its use. The code employs the finite element method with cylindrical symmetry and generalized plane strain to predict fuel and cladding temperatures, stresses, and deformations during normal power operations. The method of solution is generally similar to that in BEHAVE-2, a fast reactor code, since BEHAVE-2 was modified to form a basis for BEHAVE-4.
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This report describes the BEHAVE-4 code for light water reactor fuel rod analysis and provides instructions for its use. The code employs the finite element method with cylindrical symmetry and generalized plane strain to predict fuel and cladding temperatures, stresses, and deformations during normal power operations. The method of solution is generally similar to that in BEHAVE-2, a fast reactor code, since BEHAVE-2 was modified to form a basis for BEHAVE-4.
Key concepts: Cladding (metalworking), Light-water reactor, Code (set theory), Finite element method, Nuclear engineering, Symmetry (geometry), Computer science, Materials science