ANALYSIS OF COOLANT MIXING IN THE FFTF FUEL BUNDLE. [electronic resource]
Fast Test Reactor/fuel Rod Bundles Of, Heat Transfer And Coolant Mixing In, (t); Reactor Fuel Elements/coolant Mixing In Ftr Rod Bundles, (t); Heat Transfer/temperature And Coolant Flow Distribution In Ftr Fuel Rod Bundles, (t)
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Online Access |
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| Corporate Authors: | , |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Richland, Wash. : Oak Ridge, Tenn. :
Pacific Northwest National Laboratory (U.S.) ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1968.
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Internet
Online AccessOnline
| Call Number: |
E 1.99: conf-680832--3
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| E 1.99: conf-680832--3 | Available |