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TRACE assessment for effect of spacer grid in RBHT reflood heat transfer experiments /

Bibliographic Details
Main Authors: Byung-Gilm, Huh (Author), Cheong, Ae-Ju (Author), Yi, Kyŏng-wŏn (Author)
Format: Government Document eBook
Language:English
Published: Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, February 2018.
Series:International agreement report ; NUREG/IA-0480.
Subjects:
Pressurized water reactors > Loss of coolant.
Nuclear fuel elements > Testing.
Online Access:https://purl.fdlp.gov/GPO/gpo90002

Internet

https://purl.fdlp.gov/GPO/gpo90002

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Call Number: Y 3.N 88:53/0480
 
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Y 3.N 88:53/0480 Available