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FRAPCON-3.5 / prepared by K.J. Geelhood and W.G. Luscher.

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Format:
Book
Government document
Author/Creator:
Geelhood, K. J., author.
Luscher, W. G. (Walter G.), 1979- author.
Contributor:
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, issuing body.
Pacific Northwest National Laboratory (U.S.)
Language:
English
Subjects (All):
Nuclear fuel rods--Data processing.
Nuclear fuel rods.
Nuclear fuel claddings--Data processing.
Nuclear fuel claddings.
Nuclear fuel rods--Computer simulation.
Nuclear fuel rods--Computer programs.
Nuclear power plants--Accidents--Computer simulation.
Nuclear power plants.
Light water reactors--Accidents--Computer simulation.
Light water reactors.
Physical Description:
1 online resource (2 volumes) : color illustrations
Place of Publication:
Washington, DC : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, October 2014.
Contents:
v. 1. A computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup
v. 2. Integral assessment.
Notes:
Title from title screen (viewed on Nov. 27, 2015).
"Manuscript completed: May 2014 ; Date published: October 2014."
"NUREG/CR-7024, Rev. 1."
"PNNL-19418, Rev. 1."
Includes bibliographical references.
Other Format:
Paper version: Geelhood, K.J. FRAPCON-3.5
OCLC:
930865214

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