Analysis of fuel behavior during LOCA tests using FALCON MOD01. This paper describes the analysis capabilities of FALCON MOD01 for LOCA events and summarizes the results from calculations performed for the Argonne National Laboratory LOCA integral tests, the OECD Halden IFA-650 LOCA tests, the Japan Atomic Energy Research Institute LOCA integral thermal shock tests, and from early LOCA tests performed at the Idaho National Engineering Laboratory. The FALCON code, developed under the sponsorship of the Electric Power Research Institute, uses a fully two-dimensional finite element analysis methodology to represent the thermal and mechanical behavior of the fuel and cladding under a variety of irradiation conditions. In addition, FALCON contains unique models and capabilities that allow analysis of fuel rod behavior during the heatup, oxidation, and reflood/quench phases of a LOCA. A total of 12 test fuel rods from 4 different experimental programs have been analyzed to validate the analysis capabilities of FALCON and to access the impact of burnup on fuel behavior during a LOCA. These programs cover a large range of code applications for severe transient analysis. The FALCON calculations show good agreement with on-line measurements and results from post-test examinations. For the calculations performed to date on irradiated fuel rods, burnup appears to have only a limited impact on the fuel rod ballooning and burst behavior during the heat phase of LOCA.
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- Philip, Bobby; Berrill, Mark A.; Allu, Srikanth; Hamilton, Steven P.; Sampath, Rahul S.; Clarno, Kevin T.; Dilts, Gary A.: A parallel multi-domain solution methodology applied to nonlinear thermal transport problems in nuclear fuel pins (2015)