FRAP-GCFR: a code for the transient analysis of gas-cooled fast reactors Page: 1 of 6
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FRAP-GCFR: A Code For the Transient Analysis
of Gas-Cooled Fast Reactors
S. 0. Peck
P. L. Hagrman
M. P. Bohn
EG&G Idaho, Inc.
TWi upon w prepared m m account of work
•pomofrf by the Unktd Sum Gomunmt. Neither Ac
Unlled Stale* nor the United State* D^wumt of
Eiteijy, nor any of their cmploym, nor aoy of ihcir
contract ora, wfccoMncton. or their emptoym, mkn
ary warranty, expmi or implied, or mnN any legal
B^Mily or rraponrtbUity for the accuracy, compfetenraa
or weruinara of any infonnHion, appMtu*. product or
procea dMckreed. or repeerntt that ju we would not
infrinie privately owned ifhta.
The fuel rod analysis computer program (FRAP-T) has been modified
to analyze transient fuel rod behavior in the gas cooled fast
reactor (GCFR). Major features modeled include -the effects of
helium coolant, ribbed cladding* pressure equalization system, and
316 stainless-steel material properties. The code capabilities
include models of elastic-plastic-creep deformation behavior, two^
dimensional heat conduction, rod ballooning, and transient axial
gas flow. The models are particularly relevant to GCFR transient
analysis in that partial or full blockage of the pressure equal-
ization system could cause a significant pressure differential
to exist during a helium depressurization, the GCFR design basis
accident. An analysis of the design, basis accident illustrating
the predictive capabilities of the code is presented.
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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/m1/1/: accessed July 20, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.