Conference Proceedings Paper
NEUTRONIC ANALYSIS OF AN IN-CORE CO-60 PRODUCTION IN CANDU6 REACTOR
13th International Conference on CANDU Fuel - 2016 Aug. 15-18
J. Lyu (KAIST)
M.A. Motalab (Korea Advanced Institute of Science and Technology)
Y. Kim (Korea Advanced Institute of Science and Technology)
In this study, an innovative way of producing Co-60 in CANDU6 reactors is introduced and neutronic analysis is performed. Unlike the conventional Co-60 production, the central fuel element in the standard fuel bundle is replaced by a Co-59 target and Co-60 is obtained after the fuel bundle is discharged. Various lattice based studies are performed to determine the possible amount of Co-59 loading and to derive an optimal Co target configuration in the center pin of a fuel bundle. Through the lattice depletion analysis, the achievable fuel burnup is evaluated and the possible Co-60 production capacity has also been evaluated with several neutronic assumptions. Major safety parameters including fuel temperature coefficient, void reactivity, and coolant temperature coefficient are also evaluated and compared with those of the standard CANDU6 core. For a more reliable investigation, a 3-D equilibrium core is determined by using the standard time-average methods for a Co-loaded CANDU6 core by using the Serpent-COREDAX code system. To compensate for the negative reactivity due to the Co loading, some of the adjuster rods are removed to achieve the typical fuel burnup of ~7,200 MWD/tU. Derived equilibrium core performances are evaluated in terms of fuel burnup, power profile. The power coefficient of reactivity is also evaluated for the 3-D equilibrium core. Also, in this work, Co-60 production in the 3D time-average core is compared with those obtained with simple lattice-based analyses. It is found that this new approach can produce more Co-60 than that of conventional method maintaining all the safety constrains.
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