Burnup limitations are normally set to limit stresses in the fuel assembly components. The defined limits provide guidance to the fuel designer to minimize fuel failure during steady sate operation, and also prevent against some thermal and mechanical phenomena that could occur during overpower transients. In particular, a LHGR limit value is set to take into account physical phenomena that could lead to pellet-cladding interaction. This limit value directly relates to a PCI limit, which may be set based on experimental ramp tests. Thus, to avoid violating the PCI limit, fuel conditioning procedures are still required for both barrier and non-barrier fuel. Simulation of the power ramp procedures to be performed by the reactor operator during startup or power increase maneuvers is advisable as a preventive measure of possible overpower consequences on the fuel thermomechanical behavior. In this paper, the thermomechanical behavior of two different kinds of BWR fuel rods is analyzed for fuel preconditioning procedures. Five different preconditioning computations were performed, each with three different ascending linear power rate ramps. The starting point of the ramps was taken from data of the Cycle 8 of the Unit 1 of the Laguna Verde Nuclear Power Plant, located in MEXICO. The top limit of the ramps was the threshold linear power at which failure by PCI could occur, as a function of burnup. The analysis was performed with the FEMAXI-V code.
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14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4242-8
PROCEEDINGS PAPER
BWR Fuel Thermomechanical Evaluation for Preconditioning Procedures With FEMAXI-V Available to Purchase
He´ctor Herna´ndez-Lo´pez,
He´ctor Herna´ndez-Lo´pez
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Estado de Me´xico, Me´xico
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Marco A. Lucatero,
Marco A. Lucatero
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Estado de Me´xico, Me´xico
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Javier Ortiz-Villafuerte
Javier Ortiz-Villafuerte
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Estado de Me´xico, Me´xico
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He´ctor Herna´ndez-Lo´pez
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Estado de Me´xico, Me´xico
Marco A. Lucatero
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Estado de Me´xico, Me´xico
Javier Ortiz-Villafuerte
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Estado de Me´xico, Me´xico
Paper No:
ICONE14-89506, pp. 923-928; 6 pages
Published Online:
September 17, 2008
Citation
Herna´ndez-Lo´pez, H, Lucatero, MA, & Ortiz-Villafuerte, J. "BWR Fuel Thermomechanical Evaluation for Preconditioning Procedures With FEMAXI-V." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management. Miami, Florida, USA. July 17–20, 2006. pp. 923-928. ASME. https://doi.org/10.1115/ICONE14-89506
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