Parallelization of subchannel thermal-hydraulic code CTF of reactor core based on domain decomposition
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摘要: 分别用CTF和反应堆蒙卡程序RMC对BEAVRS基准题进行全堆精细建模,由RMC统计径向及轴向功率分布并作为CTF的功率输入。利用CTF的区域分解技术,进行BEAVRS全堆pin by pin子通道计算,采用193个核并行计算,耗时268 s,得到了精细的燃料棒中心及表面温度、冷却剂温度及密度、空泡份额、包壳温度等重要参数,验证了CTF进行全堆子通道计算的高效性及可靠性,为实现基于RMC和CTF的核热耦合计算奠定了重要基础。Abstract: CTF (Coolant Boiling in Rod Arrays-Two Fluid) is a new sub-channel thermal/hydraulic simulation code developed by CASL (The Consortium for Advanced Simulation of Light Water Reactors) and PSU (Pennsylvania State University). It can solve steady or transient-state problems efficiently for both single assembly and full-core reactor. Thus, this code solves the computational efficiency and memory consumption problems effectively. First, CTF computes the BEAVRS benchmark in parallel with the domain decomposition technology. The power data which CTF uses are calculated by RMC(a Monte Carlo code for reactor core analysis). After calculating for 268 s, we get detailed fuel pin temperature, water temp and density output results. Accordingly, the efficiency and reliability of CTF is verified. On this basic work of CTF calculation for BEAVRS benchmark,the coupling between RMC and CTS for full-core problem will achieved soon.
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Key words:
- BEAVRS /
- domain decomposition /
- parallelization /
- CTF /
- RMC
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