FRAPCON-3
Subtitle: a computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods for high burnup
By: prepared by G.A. Berna ... [et al.] ; prepared for Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
Contributors: Berna, Gary A.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology.
Publisher: The Commission
Published: 1997
Place of publication: Wasington, DC
Language: eng
Subjects: Fuel burnup (Nuclear engineering) -- Mathematical models -- Data processing.; Nuclear fuel rods -- Mathematical models -- Data processing.; Nuclear fuel claddings -- Mathematical models -- Data processing.; Computer-aided engineering.
Notes: Includes bibliographical references.
"NUREG/CR-6534, vol. 2. PNNL-11513."