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Inherently safe core design considerations in an LMFBR for a hypothetical unscrammed loss-of-flow transient
Inherently safe core design considerations in an LMFBR for a hypothetical unscrammed loss-of-flow transient
1983
R. D. Coffield
J.E. Kalinowski
R. A. Markley
R.K. Sievers
Keywords:
Scram
Nuclear reactor
Thermal conductivity
Coolant
Energy system
Nuclear engineering
Safety engineering
Systems analysis
Engineering
reactor safety
Flow (psychology)
Correction
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