Spacer grid effects during a reflood in an annulus flow channel
- Author
- CHO, Seok1 ; MOON, Sang-Ki1 ; CHUN, Se-Young1 ; KIM, Yeon-Sik1 ; BAEK, Won-Pil1
[1] Korea Atomic Energy Research Institute, 150 Deokjin-dong, Yuseong-gu, Daejeon 305-353, Korea, Republic of - Source
Journal of Nuclear Science and Technology. 2007, Vol 44, Num 7, pp 967-976, 10 p ; ref : 21 ref
- Publisher
- Atomic Energy Society of Japan, Tokyo
- Publication country
- Japan
- Document type
- Article
- Language
- English
- Author keyword
- quench front reflood rewetting temperature swirl vane type spacer grid
- Keyword (fr)
- Cale espacement Etude expérimentale Gaine (combustible) Haute température Installation essai Noyage Réacteur nucléaire Sous refroidissement Thermohydraulique
- Keyword (en)
- Spacer Experimental study Clad High temperature Test facility Flooding Nuclear reactor Subcooling Thermohydraulics
- Keyword (es)
- Calce espaciamiento Estudio experimental Vaina (combustible) Alta temperatura Instalación ensayo Inundación Reactor nuclear Subenfriamiento Termohidraúlica
- Classification
- Pascal
- 001 Exact sciences and technology / 001D Applied sciences / 001D06 Energy / 001D06D Energy. Thermal use of fuels / 001D06D04 Installations for energy generation and conversion: thermal and electrical energy. / 001D06D04D Fission nuclear power plants
- Discipline
- Energy
- Origin
- Inist-CNRS
- Database
- PASCAL
- INIST identifier
- 19189418
Sauf mention contraire ci-dessus, le contenu de cette notice bibliographique peut être utilisé dans le cadre d’une licence CC BY 4.0 Inist-CNRS / Unless otherwise stated above, the content of this bibliographic record may be used under a CC BY 4.0 licence by Inist-CNRS / A menos que se haya señalado antes, el contenido de este registro bibliográfico puede ser utilizado al amparo de una licencia CC BY 4.0 Inist-CNRS
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DOI
10.1080/18811248.2007.9711336 
https://dx.doi.org/10.1080/18811248.2007.9711336
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