Development of a Vandellos II NPP model using the TRACE code : application to an actual transient of main coolant pumps trip and start-up /

Development of a Vandellos II NPP model using the TRACE code : application to an actual transient of main coolant pumps trip and start-up /

Bibliographic Details
Corporate Author: U.S. Nuclear Regulatory Commission
Other Authors: Lozano, O.
Format: Government Document eBook
Language:English
Published: Washington, DC : U.S. Nuclear Regulatory Commission, [2011]
Series:International agreement report ; NUREG/IA-0243.
Subjects:
Pressurized water reactors > Loss of coolant > Computer simulation.
Nuclear power plants > Accidents > Computer simulation.
Online Access:https://purl.fdlp.gov/GPO/gpo8057

Internet

https://purl.fdlp.gov/GPO/gpo8057

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Holdings details from Available Online
Call Number: Y 3.N 88:53/0243
 
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Y 3.N 88:53/0243 Available