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001 ocn805389587;

003 OCoLC;

005 20141212032454.0;

006 m | d f ;

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

008 120808s2011 dcua ob f000 0 eng c;

035 a| (Sirsi) o805389587;

040 a| GPOc| GPOd| GPOd| UtOrBLW;

042 a| pcc;

049 a| ERE#;

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

086 0 a| Y 3.N 88:25/7022/V.1;

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

245 10 a| FRAPCON-3.4 :b| a computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods for high burnup /c| prepared by K.J. Geelhood, W.G. Luscher, C. E. Beyer.;

260 a| Washington, DC :b| U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,c| [2011];

300 a| 1 online resource (143 unnumbered pages) :b| color illustrations;

336 a| text2| rdacontent;

337 a| computer2| rdamedia;

338 a| online resource2| rdacarrier;

500 a| "Date published: March 2011.";

500 a| "NUREG/CR-7022, Vol. 1.";

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

500 a| Title from title screen (viewed on Aug. 8, 2012).;

504 a| Includes bibliographical references (p. 4.1-4.4).;

650 0 a| Fuel burnup (Nuclear engineering)x| Mathematical modelsx| Data processing.=| ^A690721;

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

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

650 0 a| Computer-aided engineering.=| ^A304148;

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

700 1 a| Beyer, C. E.=| ^A1014461;

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

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

776 08 i| Print version:a| Geelhood, K. J.t| FRAPCON-3.4w| (OCoLC)805389611;

856 40 u| https://purl.fdlp.gov/GPO/gpo26424;

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

998 a| 3100187;

998 a| u3100187;

596 a| 1;

999 a| CLICK ON WEB ADDRESSw| ASISc| 1i| 3100187-1001l| JNETm| JOYNERr| Ys| Yt| JNE1DOu| 9/10/2012x| EDOCUMENTz| JERESOURCE;

FRAPCON-3.4 : a computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods for high burnup / prepared by K.J. Geelhood, W.G. Luscher, C. E. Beyer.

Author/creator	Geelhood, K. J.
Format	Electronic
Publication Info	Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2011]
Description	1 online resource (143 unnumbered pages) : color illustrations
Supplemental Content	https://purl.fdlp.gov/GPO/gpo26424
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.

Other author/creator	Luscher, W. G. (Walter G.), 1979-
Other author/creator	Beyer, C. E.
Other author/creator	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
Other author/creator	Pacific Northwest National Laboratory (U.S.)
General note	"Date published: March 2011."
General note	"NUREG/CR-7022, Vol. 1."
General note	"PNNL-19418, Vol. 1."
General note	Title from title screen (viewed on Aug. 8, 2012).
Bibliography note	Includes bibliographical references (p. 4.1-4.4).
Issued in other form	Print version: Geelhood, K. J. FRAPCON-3.4
GPO item number	1051-H-11 (online)
Govt. docs number	Y 3.N 88:25/7022/V.1

FRAPCON-3.4 : a computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods for high burnup / prepared by K.J. Geelhood, W.G. Luscher, C. E. Beyer.

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