FRAP-GCFR: a code for the transient analysis of gas-cooled fast reactors Page: 3 of 6
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or full blockage of the pressure equalization system could cause a sig
nificant pressure differential to exist during a depressurization
accident with the potential of fuel rod ballooning.
The FRAP-T code has recently been interactively linked with the
COBRA-IV thermal hydraulic code. The COBRA code performs a two-dimen-
sional, thermal -hydraulic analysis at each axial elevation of a cluster
of fuel rods. Coolant mixing is provided by varying friction factors
in each coolant channel with elevation. The FRAP-T/COBRA link provides
for fully coupled rod-coolant calculations in multirod clusters.
Although considerable differences exist in fuel rod design and
operating environment between LWRs and GCFRs, the modular structure
and transient analysis capabilities of the FRAP-T code made modifica-
tion of the code for GCFR analysis relatively simple. The primary
advantage of using FRAP-T as the basis for the GCFR analysis code is
that no modifications were necessary to handle the complex transient
conditions that arise in GCFR safety analysis, even though the condi-
tions that constitute a serious accident for a GCFR differ somewhat
from those of an LWR for which the FRAP code was developed. Since
the transient capabilities of the code did not need to be changed,
the modifications necessary to analyze GCFR fuel behavior consisted
primarily of including GCFR material properties and modeling specific
The differences between the two fuel rod designs include fuel
and cladding dimensions, fuel enrichment, oxide constituents, cladding
material and design, the existence of a natural uranium blanket in the
GCFR fuel rod and the GCFR fuel rod venting system. The dimensional
differences, high fuel enrichment and presence of plutonia in the GCFR
fuel rods posed no problem for FRAP as these parameters were already
considered variable in the input of the light water reactor version of
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Peck, S O; Hagrman, D L & Bohn, M P. FRAP-GCFR: a code for the transient analysis of gas-cooled fast reactors, article, January 1, 1979; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc1104234/m1/3/: accessed January 20, 2019), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.