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Transient analysis of the PIUS advanced reactor design with the TRAC-PF1/MOD2 code
Transient analysis of the PIUS advanced reactor design with the TRAC-PF1/MOD2 code
1995
B.E. Boyack
Jean L. Steiner
S.C. Harmony
Keywords:
Nuclear reactor core
Scram
Nuclear meltdown
Nuclear reactor
Reactor pressure vessel
Nuclear power
Nuclear engineering
Containment building
Engineering
Pressurized water reactor
Correction
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