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001 ocn930865214;

003 OCoLC;

005 20160202100917.0;

006 m o d f ;

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

008 151203e201410 dcua obt f000 0 eng c;

035 a| (Sirsi) o930865214;

042 a| pcc;

043 a| n-us---;

049 a| ERE#;

074 a| 1051-H-11 (online);

086 0 a| Y 3.N 88:25/7022/VOL.1-2/REV.1;

088 a| NUREG/CR-7022;

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

245 10 a| FRAPCON-3.5 /c| prepared by K.J. Geelhood and W.G. Luscher.;

264 1 a| Washington, DC :b| United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,c| October 2014.;

300 a| 1 online resource (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. 27, 2015).;

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

500 a| "NUREG/CR-7024, Rev. 1.";

500 a| "PNNL-19418, Rev. 1.";

504 a| Includes bibliographical references.;

505 0 a| 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.;

536 c| V6197;

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

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

650 0 a| Nuclear fuel rodsx| Computer simulation.=| ^A687288;

650 0 a| Nuclear fuel rodsx| Computer programs.=| ^A687288;

650 0 a| Nuclear power plantsx| Accidentsx| Computer simulation.=| ^A83889;

650 0 a| Light water reactorsx| Accidentsx| Computer simulation.=| ^A443802;

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

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| Paper version:a| Geelhood, K. J.t| FRAPCON-3.5w| (OCoLC)894520970;

856 40 u| https://purl.fdlp.gov/GPO/gpo63353;

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

998 a| 4351977;

998 a| u4351977;

596 a| 1;

999 a| CLICK ON WEB ADDRESSw| ASISc| 1i| 4351977-1001l| JNETm| JOYNERr| Ys| Yt| JNE1DOu| 1/12/2016x| EDOCUMENTz| JERESOURCE;

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

Author/creator	Geelhood, K. J. author.
Other author	Luscher, W. G. (Walter G.), 1979- author.
Other author	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, issuing body.
Other author	Pacific Northwest National Laboratory (U.S.)
Format	Electronic
Publication	Washington, DC : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, October 2014.
Description	1 online resource (2 volumes) : color illustrations
Supplemental Content	https://purl.fdlp.gov/GPO/gpo63353
Subjects	Nuclear fuel rods--Data processing. Nuclear fuel claddings--Data processing. Nuclear fuel rods--Computer simulation. Nuclear fuel rods--Computer programs. Nuclear power plants--Accidents. --Computer simulation. Light water reactors--Accidents. --Computer simulation.

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.
General note	Title from title screen (viewed on Nov. 27, 2015).
General note	"Manuscript completed: May 2014 ; Date published: October 2014."
General note	"NUREG/CR-7024, Rev. 1."
General note	"PNNL-19418, Rev. 1."
Bibliography note	Includes bibliographical references.
Funding information	V6197
Issued in other form	Paper version: Geelhood, K. J. FRAPCON-3.5
Technical rpt number	NUREG/CR-7022
GPO item number	1051-H-11 (online)
Govt. docs number	Y 3.N 88:25/7022/VOL.1-2/REV.1

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

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