FRAP-GCFR [electronic resource] : a code for the transient analysis of gas-cooled fast reactors
- Washington, D.C. : United States. Dept. of Energy, 1979. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 6 : digital, PDF file
- Additional Creators:
- United States. Department of Energy and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- 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 equalization 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.
- Published through SciTech Connect., 01/01/1979., "conf-790816-3", International meeting on fast reactor safety technology, Seattle, WA, USA, 19 Aug 1979., Peck, S O; Hagrman, D L; Bohn, M P., and Idaho National Engineering Lab., Idaho Falls (USA)
- Funding Information:
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