Tools

LEADER 01824nam 2200433Ia 4500

001 ocn708256786;

003 OCoLC;

005 20141212063907.0;

006 m d f ;

007 cr bn|||||||||;

008 110323s2010 dcua obt f000 0 eng d;

035 a| (Sirsi) o708256786;

040 a| GPOc| GPOd| GPOd| UtOrBLW;

049 a| ERE#;

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

086 0 a| Y 3.N 88:25/CR-6976;

245 00 a| Rod bundle heat transfer test facility description /c| prepared by E.R. Rosal [and others] ; K. Tien, NRC project manager.;

260 a| Washington, D.C. :b| U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,c| [2010];

300 a| 1 online resource (209 unnumbered pages) :b| illustrations;

336 a| text2| rdacontent;

337 a| computer2| rdamedia;

338 a| online resource2| rdacarrier;

500 a| Title from PDF title screen (viewed on Mar. 23, 2011).;

500 a| "Manuscript completed: April 2008. Date published: July 2010.";

504 a| Includes bibliographical references.;

500 a| "NUREG/CR-6976.";

513 a| Technical report.b| Nov. 1997-Feb. 2003.;

536 c| NRC job code W6855;

650 0 a| Pressurized water reactorsx| Loss of coolant.=| ^A684932;

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

650 0 a| Heatx| Transmission.=| ^A18327;

776 08 i| Print version:t| Rod bundle heat transfer test facility descriptionw| (OCoLC)708254308;

700 1 a| Rosal, E. R.=| ^A1033528;

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

856 40 u| http://purl.fdlp.gov/GPO/gpo5388;

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

596 a| 1;

998 a| 2472592;

999 a| CLICK ON WEB ADDRESSw| ASISc| 1i| 2472592-1001l| JNETm| JOYNERr| Ys| Yt| JNE1DOu| 4/26/2011x| EDOCUMENTz| JERESOURCE;

Rod bundle heat transfer test facility description / prepared by E.R. Rosal [and others] ; K. Tien, NRC project manager.

Other author	Rosal, E. R.
Other author	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
Format	Electronic
Publication Info	Washington, D.C. : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2010]
Description	1 online resource (209 unnumbered pages) : illustrations
Supplemental Content	http://purl.fdlp.gov/GPO/gpo5388
Subjects	Pressurized water reactors--Loss of coolant. Nuclear fuel rods--Testing. Heat--Transmission.

General note	Title from PDF title screen (viewed on Mar. 23, 2011).
General note	"Manuscript completed: April 2008. Date published: July 2010."
General note	"NUREG/CR-6976."
Bibliography note	Includes bibliographical references.
Report note	Technical report. Nov. 1997-Feb. 2003.
Funding information	NRC job code W6855
Issued in other form	Print version: Rod bundle heat transfer test facility description
GPO item number	1051-H-11 (online)
Govt. docs number	Y 3.N 88:25/CR-6976

Click here for more information about this title