Abstract
A three-dimensional hexagonal PWR core fuel management code package TPFAP-H/CSIM-H has been developed. A two-dimensional transport code for hexagonal assembly based on the transmission probability and response matrix method is developed and implemented to modify and reform the existing PWR square assembly code TPFAP to the TPFAP-H which has the capability of hexagonal assembly calculation, keeping all the original functions of TPFAP. Based on the advanced 3D hexagonal diffusion nodal code, the hexagonal PWR core fuel management code CSIM-H is developed. Both codes have been linked together to form the code package TPFAP-H/CSIM-H, which considers the all feedbacks of burnup, power distribution, moderator density and control rod insertion, ... etc. The verification and validation of the code system has been examined through the IAEA WWER-1000 type PWR reactor Kalinin NPP benchmark problem. The numerical results are in good agreement with measurements and close to those of other international institutes. The errors of critical boron concentration and power distribution are all within the permissible limits of engineering requirement.
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