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Li Zhigang,Pan Junjie,Xia Bangyang,Qiang Shenglong,Lu Wei,Li Qing 한국원자력학회 2023 Nuclear Engineering and Technology Vol.55 No.9
As an important part of the digital reactor, the pin-by-pin wise fine coupling calculation is a research hotspot in the field of nuclear engineering in recent years. It provides more precise and realistic simulation results for reactor design, operation and safety evaluation. CORCA-K a nodal code is redeveloped as a robust pin-by-pin wise neutronics and thermal-hydraulic coupled calculation code for pressurized water reactor (PWR) core. The nodal green's function method (NGFM) is used to solve the threedimensional space-time neutron dynamics equation, and the single-phase single channel model and one-dimensional heat conduction model are used to solve the fluid field and fuel temperature field. The mesh scale of reactor core simulation is raised from the nodal-wise to the pin-wise. It is verified by two benchmarks: NEACRP 3D PWR and PWR MOX/UO2. The results show that: 1) the pin-by-pin wise coupling calculation system has good accuracy and can accurately simulate the key parameters in steadystate and transient coupling conditions, which is in good agreement with the reference results; 2) Compared with the nodal-wise coupling calculation, the pin-by-pin wise coupling calculation improves the fuel peak temperature, the range of power distribution is expanded, and the lower limit is reduced more
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Jingang Liang,Kan Wang,Yishu Qiu,Xiaoming Chai,Shenglong Qiang 한국원자력학회 2016 Nuclear Engineering and Technology Vol.48 No.3
Because of prohibitive data storage requirements in large-scale simulations, the memoryproblem is an obstacle for Monte Carlo (MC) codes in accomplishing pin-wise threedimensional(3D) full-core calculations, particularly for whole-core depletion analyses. Various kinds of data are evaluated and quantificational total memory requirements areanalyzed based on the Reactor Monte Carlo (RMC) code, showing that tally data, materialdata, and isotope densities in depletion are three major parts of memory storage. Thedomain decomposition method is investigated as a means of saving memory, by dividingspatial geometry into domains that are simulated separately by parallel processors. For thevalidity of particle tracking during transport simulations, particles need to be communicatedbetween domains. In consideration of efficiency, an asynchronous particle communicationalgorithm is designed and implemented. Furthermore, we couple the domain decompositionmethod with MC burnup process, under a strategy of utilizing consistent domain partition inboth transport and depletion modules. A numerical test of 3D full-core burnup calculationsis carried out, indicating that the RMC code, with the domain decomposition method, iscapable of pin-wise full-core burnup calculations with millions of depletion regions.
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