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Jeong, Chang Joon,Choi, Hangbok IEEE 2005 IEEE transactions on nuclear science Vol.52 No.1
The regional overpower protection (ROP) system of a Canada deuterium uranium (CANDU) reactor was assessed for the direct use of spent pressurized water reactor fuel in CANDU reactors (DUPIC), including the validation of the Winfrith improved multigroup scheme (WIMS)/reactor fuelling simulation program (RFSP)/reduction power (ROVER) code system used for the calculation of the ROP trip setpoint (TSP). Comparative calculations showed that the WIMS/RFSP/ROVER code system produced results consistent with the current design code system for estimating the ROP TSP of the standard natural uranium CANDU reactor. For the DUPIC fuel CANDU core, the ROP TSP was estimated to be 123.4%, which was almost the same as that of the standard natural uranium core. The extra margin of the ROP TSP for the DUPIC fuel system was enhanced by the flattened axial channel power distribution as well as the reduced refueling ripple of the channel power. This study has shown that the DUPIC fuel does not deteriorate the current ROP TSP designed for the natural uranium CANDU reactor.
An Evolutionary Optimization of the Refueling Simulation for a CANDU Reactor
Quang Binh Do,Hangbok Choi,Gyu Hong Roh IEEE 2006 IEEE transactions on nuclear science Vol.53 No.5
<P>This paper presents a multi-cycle and multi-objective optimization method for the refueling simulation of a 713 MWe Canada deuterium uranium (CANDU-6) reactor based on a genetic algorithm, an elitism strategy and a heuristic rule. The proposed algorithm searches for the optimal refueling patterns for a single cycle that maximizes the average discharge burnup, minimizes the maximum channel power and minimizes the change in the zone controller unit water fills while satisfying the most important safety-related neutronic parameters of the reactor core. The heuristic rule generates an initial population of individuals very close to a feasible solution and it reduces the computing time of the optimization process. The multi-cycle optimization is carried out based on a single cycle refueling simulation. The proposed approach was verified by a refueling simulation of a natural uranium CANDU-6 reactor for an operation period of 6 months at an equilibrium state and compared with the experience-based automatic refueling simulation and the generalized perturbation theory. The comparison has shown that the simulation results are consistent from each other and the proposed approach is a reasonable optimization method of the refueling simulation that controls all the safety-related parameters of the reactor core during the simulation</P>
Implementation of a Dry Process Fuel Cycle Model into the DYMOND Code
Park Joo Hwan,Jeong Chang Joon,Choi Hangbok Korean Nuclear Society 2004 Nuclear Engineering and Technology Vol.36 No.2
For the analysis of a dry process fuel cycle, new modules were implemented into the fuel cycle analysis code DYMOND, which was developed by the Argonne National Laboratory. The modifications were made to the energy demand prediction model, a Canada deuterium uranium (CANDU) reactor, direct use of spent pressurized water reactor (PWR) fuel in CANDU reactors (DUPIC) fuel cycle model, the fuel cycle calculation module, and the input/output modules. The performance of the modified DYMOND code was assessed for the postulated once-through fuel cycle models including both the PWR and CANDU reactor. This paper presents modifications of the DYMOND code and the results of sample calculations for the PWR once-though and DUPIC fuel cycles.