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001 ocn930784880;

003 OCoLC;

005 20160202100916.0;

006 m o d f ;

007 cr mn||||a||||;

008 151202e201410 dcua obt f000 0 eng d;

035 a| (Sirsi) o930784880;

043 a| n-us---;

049 a| ERE#;

074 a| 1051-H-53 (online);

086 0 a| Y 3.N 88:25/7023/VOL.1-2/REV.1;

088 a| NUREG/CR-7023, Rev. 1;

088 a| PNNL-19400, Rev. 1;

100 1 a| Geelhood, K. J.,e| author.=| ^A1043332;

245 10 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| text2| rdacontent;

337 a| computer2| rdamedia;

338 a| online resource2| rdacarrier;

500 a| Title from title screen (viewed on Nov. 30, 2015).;

500 a| "NUREG/CR-7023, Rev. 1.";

500 a| "PNNL-19400.";

504 a| Includes bibliographical references.;

500 a| "Manuscript completed: May 2014 ; Date published: October 2014.";

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 rodsx| Computer simulation.=| ^A687288;

650 0 a| Nuclear fuel rodsx| Performancex| Analysis.=| ^A687288;

650 0 a| Nuclear fuel rodsx| Data processing.=| ^A687288;

650 0 a| Nuclear fuel claddingsx| Data processing.=| ^A849440;

650 0 a| Nuclear power plantsx| Computer simulation.=| ^A43906;

700 1 a| Luscher, W. G.q| (Walter G.),d| 1979-e| author.=| ^A1121496;

700 1 a| Cuta, Judith M.,e| author.?| UNAUTHORIZED;

710 2 a| U.S. Nuclear Regulatory Commission.b| Office of Nuclear Regulatory Research,e| issuing body.=| ^A420721;

710 2 a| Pacific Northwest National Laboratory (U.S.)=| ^A566447;

776 08 i| Print version:a| Geelhood, K. J.t| FRAPTRAN-1.5w| (OCoLC)894559455;

856 40 u| https://purl.fdlp.gov/GPO/gpo63376;

949 a| Click on web addressw| ASISh| JOYNER94;

998 a| 4351962;

998 a| u4351962;

596 a| 1;

999 a| CLICK ON WEB ADDRESSw| ASISc| 1i| 4351962-1001l| JNETm| JOYNERr| Ys| Yt| JNE1DOu| 1/12/2016x| EDOCUMENTz| JERESOURCE;

FRAPTRAN-1.5 / prepared by K.J. Geelhood, W.G. Luscher, and J.M. Cuta.

Author/creator	Geelhood, K. J. author.
Format	Electronic
Publication	Washington, D.C. : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, October 2014.
Description	2 volumes : color illustrations
Supplemental Content	https://purl.fdlp.gov/GPO/gpo63376
Subjects	Nuclear fuel rods--Computer simulation. Nuclear fuel rods--Performance. --Analysis. Nuclear fuel rods--Data processing. Nuclear fuel claddings--Data processing. Nuclear power plants--Computer simulation.

Other author/creator	Luscher, W. G. (Walter G.), 1979- author.
Other author/creator	Cuta, Judith M., author.
Other author/creator	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, issuing body.
Other author/creator	Pacific Northwest National Laboratory (U.S.)
Contents	Vol. 1. A computer code for the transient analysis of oxide fuel rods -- vol. 2. Integral assessment.
General note	Title from title screen (viewed on Nov. 30, 2015).
General note	"NUREG/CR-7023, Rev. 1."
General note	"PNNL-19400."
General note	"Manuscript completed: May 2014 ; Date published: October 2014."
Bibliography note	Includes bibliographical references.
Issued in other form	Print version: Geelhood, K. J. FRAPTRAN-1.5
Technical rpt number	NUREG/CR-7023, Rev. 1
Technical rpt number	PNNL-19400, Rev. 1
GPO item number	1051-H-53 (online)
Govt. docs number	Y 3.N 88:25/7023/VOL.1-2/REV.1

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