Campbell, F. R.
VIAF ID: 103908469 ( Personal )
Permalink: http://viaf.org/viaf/103908469
Preferred Forms
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- 100 1 0 ‡a Campbell, F. R.
Works
Title | Sources |
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Behaviour of concrete containment under over pressure conditions | |
In-reactor measurement of fuel-to-sheath heat transfer coefficients between UO2 and stainless steel | |
Interaction between graphite and UO₂ in operating nuclear fuel elements | |
The nature of reactor accidents : paper | |
Three Mile Island, 1980 | |
Transient fission gas release rates within UO₂ fuel elements following power increases. |