APPLICATION OF THE FREY TRANSIENT FUEL CODE FOR DESIGN-BASIS EVENTS Conference Paper

abstract

• This paper describes the Fuel Rod Evaluation System (FREY) which was developed under the sponsorship of the Electric Power Research Institute to provide nuclear utilities with an independent capability for fuel transient behavior analysis. FREY is a two-dimensional, finite-element code capable of providing fully coupled thermal-hydraulic/thermomechanical solutions to a single rod/single channel problem. It can perform both best-estimate and licensing calculations depending on user-specified input options.

authors

• Peddicord, Kenneth

published proceedings

• TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY

author list (cited authors)

• PEDDICORD, K. L., DEVORE, C. V., MONTGOMERY, R. O., ADAMANTIADES, A. G., & YOUSEFFNIA, M. A.

complete list of authors

• PEDDICORD, KL||DEVORE, CV||MONTGOMERY, RO||ADAMANTIADES, AG||YOUSEFFNIA, MA

publication date

• December 1984

published in

• Transactions of the American Nuclear Society  Journal

start page

• 350

end page

• 351

volume

• 46