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TRAC code assessment using data from SCTF Core-III, a large-scale 2D/3D facility
TRAC code assessment using data from SCTF Core-III, a large-scale 2D/3D facility
1988
B. E. Boyack
P.R. Shire
S.C. Harmony
G. Rhee
Keywords:
Fluid mechanics
Hydraulics
Loss-of-coolant accident
Differential equation
Nuclear reactor
Nuclear engineering
TRAC
Engineering
Pressurized water reactor
code assessment
reactor safety
Correction
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