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India’s PFBR attains criticality at last
Prime Minister Narendra Modi proclaimed it “a proud moment for India” when on April 6 the 500-MWe, sodium-cooled Prototype Fast Breeder Reactor (PFBR) achieved initial criticality. This milestone, which comes some 22 years after the continually delayed PFBR project began, marks India’s entrance into the second stage of its three-stage nuclear program, which has the ultimate goal of supporting the country’s nuclear power program with its significant thorium reserves.
Victor C. Leite, Roberto Schirru, Miguel Mattar Neto
Nuclear Technology | Volume 205 | Number 5 | May 2019 | Pages 637-645
Technical Paper | doi.org/10.1080/00295450.2018.1516056
Articles are hosted by Taylor and Francis Online.
One of the main roles of the nuclear fuel bundle spacer grid (SG) is to safely support the fuel rods (FRs) through springs and dimples. The SG design is an important matter for nuclear power plant operation when a damaged FR could release fission products. For this work, Particle Swarm Optimization (PSO) is applied to define the geometries of the springs and dimples existing in a SG. Other algorithms had been used to optimize these geometries but not PSO. This paper proposes a PSO variable model and its fitness function in order to define an optimized geometry for the spring and the dimple so that they can provide sufficient gripping forces and minimize stresses. The implemented PSO was able to generate geometries of springs and dimples with stresses minimized and with a specific required stiffness value. The results of these two characteristics are compared with other results in the literature. For further work, PSO will be used to optimize other important design characteristics of a SG: grid-to-rod fretting, coolant flow-induced vibration, and the function of mixing coolant.