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Title	Assessment of LONF ATWS for Maanshan PWR using TRACE code /
Format	online resource
Internet Access	https://purl.fdlp.gov/GPO/gpo46828
Author	Wang, Jong-Rong, author.
Published	Washington, DC : U.S. Nuclear Regulatory Commission, 2014.

SuDoc Number	Y 3.N 88:53/0436
Item Number	1051-H-41 (online)
LC Number	TK9203.P7 W35 2014
Variation of Title	Assessment of Loss Of Normal Feedwater Anticipated Transient Without Scram for Maanshan Pressurized Water Reactor using TRAC/RELAP Advanced Computational Engine code
Description	1 online resource (53 unnumbered pages) : color illustrations.
Content Type	text
Series	(International agreement report ; NUREG/IA-0436.)
General Note	Title from title screen (viewed March 13, 2014).
	"February 2014."
	"Prepared as part of The Agreement on Research Participation and Technical Exchange Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."
Bibliography	Includes bibliographical references (pages 6-1).
Subject - LC	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.
Added Entry	U.S. Nuclear Regulatory Commission, issuing body.
Linking Field	Print version: Wang, Jong-Rong. Assessment of LONF ATWS for Maanshan PWR using TRACE code (OCoLC)872581794
URL	http://pbadupws.nrc.gov/docs/ML1405/ML14056A027.pdf

Holdings	All items

OCLC Number	(OCoLC)872581811
CGP Record Link	https://catalog.gpo.gov:443/F/?func=direct&doc_number=000921744&local_base=GPO01PUB
System Number	000921744

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