A Model for Assessment of Failure of LWR Fuel during an RIA
Conference
·
OSTI ID:21229322
- Center for Advanced Nuclear Energy Systems, Department of Nuclear Science and Engineering Massachusetts Institute of Technology, 77 Massachusetts Ave. Cambridge MA 02139 (United States)
This paper presents a model for Pellet-Cladding Mechanical Interaction (PCMI) failure of LWR fuel during an RIA. The model uses the J-integral as a driving parameter to characterize the failure potential during PCMI. The model is implemented in the FRAPTRAN code and is validated by CABRI and NSRR simulated RIA test data. Simulation of PWR and BWR conditions are conducted by FRAPTRAN to evaluate the fuel failure potential using this model. Model validation and simulation results are compared with the strain-based failure model of PNNL and the SED/CSED model of EPRI. Our fracture mechanics model has good capability to differentiate failure from non-failure cases. The results reveal significant effects of power pulse width: a wider pulse width generally increases the threshold for fuel failure. However, this effect is less obvious for highly corroded cladding. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 21229322
- Country of Publication:
- United States
- Language:
- English
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