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001 ocn872581811;

003 OCoLC;

005 20141212064245.0;

006 m o d f ;

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

008 140313s2014 dcua ob f000 0 eng d;

035 a| (Sirsi) o872581811;

043 a| a-cc---;

049 a| ERE#;

074 a| 1051-H-41 (online);

086 0 a| Y 3.N 88:53/0436;

100 1 a| Wang, Jong-Rong,e| author.=| ^A1400820;

245 10 a| Assessment of LONF ATWS for Maanshan PWR using TRACE code /c| prepared by: Jong-Rong Wang [and three others].;

246 3 a| Assessment of Loss Of Normal Feedwater Anticipated Transient Without Scram for Maanshan Pressurized Water Reactor using TRAC/RELAP Advanced Computational Engine code;

264 1 a| Washington, DC :b| U.S. Nuclear Regulatory Commission,c| 2014.;

300 a| 1 online resource (53 unnumbered pages) :b| color illustrations.;

336 a| textb| txt2| rdacontent;

337 a| computerb| c2| rdamedia;

338 a| online resourceb| cr2| rdacarrier;

490 1 a| International agreement report ;v| NUREG/IA-0436;

500 a| Title from title screen (viewed March 13, 2014).;

500 a| "February 2014.";

500 a| "Prepared as part of The Agreement on Research Participation and Technical Exchange Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP).";

504 a| Includes bibliographical references (pages 6-1).;

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

650 0 a| Nuclear power plantsz| Chinax| Safety measures.=| ^A43906;

710 2 a| U.S. Nuclear Regulatory Commissione| issuing body.=| ^A198030;

776 08 i| Print version:a| Wang, Jong-Rong.t| Assessment of LONF ATWS for Maanshan PWR using TRACE codew| (OCoLC)872581794;

830 0 a| International agreement reportv| NUREG/IA-0436.=| ^A463558;

856 40 u| https://purl.fdlp.gov/GPO/gpo46828;

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

998 a| 3452195;

998 a| u3452195;

596 a| 1;

999 a| CLICK ON WEB ADDRESSw| ASISc| 1i| 3452195-1001l| JNETm| JOYNERr| Ys| Yt| JNE1DOu| 4/3/2014x| EDOCUMENTz| JERESOURCE;

Assessment of LONF ATWS for Maanshan PWR using TRACE code / prepared by: Jong-Rong Wang [and three others].

Author/creator	Wang, Jong-Rong author.
Other author	U.S. Nuclear Regulatory Commission issuing body.
Format	Electronic
Publication	Washington, DC : U.S. Nuclear Regulatory Commission, 2014.
Description	1 online resource (53 unnumbered pages) : color illustrations.
Supplemental Content	https://purl.fdlp.gov/GPO/gpo46828
Subjects	Pressurized water reactors--China. --Loss of coolant. --Computer simulation. Pressurized water reactors--Accidents. --China. --Computer simulation. Nuclear power plants--China. --Computer simulation. Nuclear power plants--China. --Safety measures.

Variant title	Assessment of Loss Of Normal Feedwater Anticipated Transient Without Scram for Maanshan Pressurized Water Reactor using TRAC/RELAP Advanced Computational Engine code
Series	International agreement report ; NUREG/IA-0436 International agreement report NUREG/IA-0436. ^A463558
General note	Title from title screen (viewed March 13, 2014).
General note	"February 2014."
General note	"Prepared as part of The Agreement on Research Participation and Technical Exchange Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."
Bibliography note	Includes bibliographical references (pages 6-1).
Issued in other form	Print version: Wang, Jong-Rong. Assessment of LONF ATWS for Maanshan PWR using TRACE code
GPO item number	1051-H-41 (online)
Govt. docs number	Y 3.N 88:53/0436

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Assessment of LONF ATWS for Maanshan PWR using TRACE code / prepared by: Jong-Rong Wang [and three others].

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