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Atlanta, GA|Atlanta Marriott Marquis
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Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
Klaus L. Nissen
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 175-192
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A34555
Articles are hosted by Taylor and Francis Online.
Fuel rod computer models are utilized to predict cladding tube integrity under normal operating or transient accident conditions in a nuclear fission reactor. The METHOD2D computer code, which includes a fuel rod mechanics model based on an axisymmetric finite element formulation, is developed and verified. This two-dimensional approach gives results for the axial and radial deformation of the fuel pellets and the cladding tube for the whole fuel rod. Because an algorithm for fuel pellet/cladding tube radial contact and axial friction is incorporated, the analysis of closed fuel/cladding gap situations is possible. Calculation results for a whole fuel rod are compared with a transient CABRI experiment that led to partial fuel melting but not to cladding failure.