Drag coefficients for reactor loose parts
- Author
- LIANG SHI1 ; DOSTER, J. M1 ; MAYO, C. W1
[1] North Carolina State University, Department of Nuclear Engineering Box 7909, Raleigh, North Carolina 27695, United States - Source
Nuclear technology. 1999, Vol 127, Num 1, pp 24-37 ; ref : 7 ref
- CODEN
- NUTYBB
- ISSN
- 0029-5450
- Scientific domain
- Energy; Metallurgy, welding
- Publisher
- American Nuclear Society, La Grange Park, IL
- Publication country
- United States
- Document type
- Article
- Language
- English
- Keyword (fr)
- Barre Boulon Circuit refroidissement Coefficient traînée Ecrou Mesure Réacteur nucléaire Corps migrant
- Keyword (en)
- Bar Bolt Cooling circuit Drag coefficient Nut Measurement Nuclear reactor Loose part
- Keyword (es)
- Barra Perno Circuito renfriamiento Coeficiente resistencia aerodinámica Tuerca Medida Reactor nuclear
- 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
- 1868349
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
10.13182/NT99-A2981 
https://dx.doi.org/10.13182/NT99-A2981
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