FRAPTRAN-1.5 /

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Bibliographic Details
Author / Creator:Geelhood, K. J., author.
Imprint:Washington, D.C. : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, October 2014.
Description:2 volumes : color illustrations
Language:English
Subject:
Format: E-Resource U.S. Federal Government Document Book
URL for this record:http://pi.lib.uchicago.edu/1001/cat/bib/10756463
Hidden Bibliographic Details
Other authors / contributors:Luscher, W. G. (Walter G.), 1979- author.
Cuta, Judith M., author.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, issuing body.
Pacific Northwest National Laboratory (U.S.)
Notes:Title from title screen (viewed on Nov. 30, 2015).
"NUREG/CR-7023, Rev. 1."
"PNNL-19400."
"Manuscript completed: May 2014 ; Date published: October 2014."
Includes bibliographical references.
Other form:Print version: Geelhood, K. J. FRAPTRAN-1.5
GPO item no.:1051-H-53 (online)
Govt.docs classification:Y 3.N 88:25/7023/VOL.1-2/REV.1

MARC

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245 1 0 |a FRAPTRAN-1.5 /  |c prepared by K.J. Geelhood, W.G. Luscher, and J.M. Cuta. 
264 1 |a Washington, D.C. :  |b United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,  |c October 2014. 
300 |a 2 volumes :  |b color illustrations 
336 |a text  |2 rdacontent  |0 http://id.loc.gov/vocabulary/contentTypes/txt 
337 |a computer  |2 rdamedia  |0 http://id.loc.gov/vocabulary/mediaTypes/c 
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500 |a Title from title screen (viewed on Nov. 30, 2015). 
500 |a "NUREG/CR-7023, Rev. 1." 
500 |a "PNNL-19400." 
500 |a "Manuscript completed: May 2014 ; Date published: October 2014." 
504 |a Includes bibliographical references. 
505 0 |a Vol. 1. A computer code for the transient analysis of oxide fuel rods -- vol. 2. Integral assessment. 
650 0 |a Nuclear fuel rods  |x Computer simulation. 
650 0 |a Nuclear fuel rods  |x Performance  |x Analysis. 
650 0 |a Nuclear fuel rods  |x Data processing. 
650 0 |a Nuclear fuel claddings  |x Data processing. 
650 0 |a Nuclear power plants  |x Computer simulation. 
650 7 |a Nuclear fuel claddings  |x Data processing.  |2 fast  |0 http://id.worldcat.org/fast/fst01040173 
650 7 |a Nuclear fuel rods  |x Data processing.  |2 fast  |0 http://id.worldcat.org/fast/fst01040194 
650 7 |a Nuclear power plants  |x Computer simulation.  |2 fast  |0 http://id.worldcat.org/fast/fst01040456 
700 1 |a Luscher, W. G.  |q (Walter G.),  |d 1979-  |e author.  |0 http://id.loc.gov/authorities/names/no2011127042  |1 http://viaf.org/viaf/185000922 
700 1 |a Cuta, Judith M.,  |e author. 
710 2 |a U.S. Nuclear Regulatory Commission.  |b Office of Nuclear Regulatory Research,  |e issuing body.  |0 http://id.loc.gov/authorities/names/n77012273  |1 http://viaf.org/viaf/140695594 
710 2 |a Pacific Northwest National Laboratory (U.S.)  |0 http://id.loc.gov/authorities/names/no96029656  |1 http://viaf.org/viaf/131071343 
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