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

Format:

Book

Government document

Author/Creator:

Wang, Jong-Rong, author.

Contributor:

U.S. Nuclear Regulatory Commission, issuing body.

Series:

International agreement report ; NUREG/IA-0436.

International agreement report ; NUREG/IA-0436

Language:

English

Subjects (All):

Pressurized water reactors--China--Loss of coolant--Computer simulation.

Pressurized water reactors.

Pressurized water reactors--Accidents--China--Computer simulation.

Nuclear power plants--China--Computer simulation.

Nuclear power plants.

Nuclear power plants--China--Safety measures.

Nuclear power plants--Computer simulation.

Nuclear power plants--Safety measures.

Pressurized water reactors--Loss of coolant--Computer simulation.

China.

Physical Description:

1 online resource ([53] pages) : color illustrations.

Other Title:

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

Place of Publication:

Washington, DC : U.S. Nuclear Regulatory Commission, 2014.

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 Applications and Maintenance Program (CAMP)."

Includes bibliographical references (pages 6-1).

Other Format:

Print version: Wang, Jong-Rong. Assessment of LONF ATWS for Maanshan PWR using TRACE code

OCLC:

872581811