Assessment of LONF ATWS for Maanshan PWR using TRACE code
By: prepared by : Jong-Rong Wang [and three others]
Contributors: U.S. Nuclear Regulatory Commission
Series: International agreement report -- NUREG/IA-0436; International agreement report -- NUREG/IA-0436.
Publisher: U.S. Nuclear Regulatory Commission
Published: 2014
Place of publication: Washington, DC
Language: eng
Subjects: Pressurized water reactors; Loss of coolant; Computer simulation; Accidents; Nuclear power plants; Safety measures
Other titles: Assessment of Loss Of Normal Feedwater Anticipated Transient Without Scram for Maanshan Pressurized Water Reactor using TRAC/RELAP Advanced Computaional Engine code
Notes: 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 Appliacations and Maintenance Program (CAMP)."

Format not distributed to depository libraries.

Includes bibliographical references (pages 6-1).