Abstract
Virtual Environmental for Reactor Analysis (VERA) benchmark was released by the Consortium for Advanced Simulation of Light water reactors (CASL) project in 2012. VERA benchmark includes more than ten problems at different levels, from 2D fuel pin case to 2D fuel assembly case to 3D core refuelling case, in addition, reference results and experimental measured data of some problems were provided by CASL. Fuel assemblies in VERA benchmark are various, including control rod assemblies, Pyrex assembly, IFBA assembly, WABA assembly and gadolinium poison assembly, and so on. In this paper, various fuel assembly models in the VERA benchmark have been built by using KYIIN-V2.0 code to verify its calculation ability from 2D fuel pin case to 2D fuel assembly case to 2D 3x3 fuel assembly case, and making a comparative analysis on the reference results in VERA benchmark, as well as the calculation results of the Monte Carlo code RMC. KYLIN-V2.0 is an advanced neutron transport lattice code developed by Nuclear Power Institute of China (NPIC). The subgroup resonance calculation method is used in KYIIN-V2.0 to obtain effective resonance selfshielding cross section, method of modular characteristics (MOC) is adopted to solve the neutron transport equation, and CRAM method and PPC method is adopted to solve the depletion equation. The numerical results show that KYLIN-V2.0 code has the reliable capability of direct heterogeneous calculation of 2D fuel assembly, and the effective multiplication factor, assembly power distribution, rod power distribution and control rod reactivity worths of various fuel assemblies that are calculated by KYLIN-V2.0 are in better agreement with the reference.
Highlights
In order to simulate the various fuel assemblies with complex structure geometry, and to meet the requirement of design and development, Nuclear Power Institute of China (NPIC) has developed an advanced neutron transport lattice code, named KYLIN-V2.0 [1, 2]
The effective multiplication factor is been compared with the reference results calculated by KENO-VI code from Virtual Environmental for Reactor Analysis (VERA) benchmark
It can be seen that pin power relative difference is less than 0.5% except for the very few rods of central control rod assembly, which is more than 1.0% and appears where the relative pin-power is as low as 0.48, fuel rods near the center tube
Summary
In order to simulate the various fuel assemblies with complex structure geometry, and to meet the requirement of design and development, Nuclear Power Institute of China (NPIC) has developed an advanced neutron transport lattice code, named KYLIN-V2.0 [1, 2]. Method of modular characteristics (MOC) is adopted to solve the two-dimensional steady-state multi-group neutron transport equation. The graphical input and display interface are developed to make sure the KYLIN-V2.0 code can be used by engineers
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