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FRAPCON-3.4 : a computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods for high burnup /

Bibliographic Details
Main Author: Geelhood, K. J.
Corporate Authors: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Pacific Northwest National Laboratory (U.S.)
Other Authors: Luscher, W. G. (Walter G.), 1979-, Beyer, C. E.
Format: Government Document eBook
Language:English
Published: Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2011]
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.
Online Access:https://purl.fdlp.gov/GPO/gpo26424
Description
Item Description:"Date published: March 2011."
"NUREG/CR-7022, Volume 1."
"PNNL-19418, Volume 1."
Title from title screen (viewed on Aug. 8, 2012).
Electronic resource.
Physical Description:1 online resource (143 unnumbered pages) : color illustrations
Bibliography:Includes bibliographical references (page 4.1-4.4).