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THE FREADM-1 CODE: A FAST REACTOR EXCURSION AND ACCIDENT DYNAMICS MODEL.
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Publications
THE FREADM-1 CODE: A FAST REACTOR EXCURSION AND ACCIDENT DYNAMICS MODEL.
THE FREADM-1 CODE: A FAST REACTOR EXCURSION AND ACCIDENT DYNAMICS MODEL.
DF
D. D. Freeman
D. D. Freeman
EL
E. G. Leff
E. G. Leff
DB
D. J. Bender
D. J. Bender
WM
W. G. Meinhardt
W. G. Meinhardt
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1 January 1970
report
Published by
Office of Scientific and Technical Information (OSTI)
https://doi.org/10.2172/4074815
Abstract
No abstract available
Keywords
N38180* -POWER REACTOR DEVELOPMENT-SAFETY & SITING
EXCURSIONS
FAILURES
FAST REACTORS
FLUID FLOW
FORTRAN
FREADM-CODE
FUEL ELEMENTS
GE 635 COMPUTER
HEAT TRANSFER
HYDRAULICS
POWER
REACTIVITY
REACTOR ACCIDENTS
REACTOR CORE
TRANSIENTS
COMPUTER PROGRAMS/FREADM-1
FOR FAST REACTOR EXCURSION AND ACCIDENT DYNAMICS ANALYSIS
FORTRAN IV FOR GE 635
REACTORS
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