Coupled neutronics and thermal-hydraulics based on JMCT and FLUENT
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摘要: 基于蒙特卡罗程序JMCT2.2和商用CFD程序FLUENT，通过C++语言，采用外耦合的方式开发了一套耦合接口程序。利用JMCT网格和FLUENT计算域之间一一映射的方式完成物理模型和CFD模型之间的网格匹配，实现了物理模型的简单划分和CFD模型网格的精细划分。利用该耦合程序计算了压水堆单根燃料棒模型和3×3带水洞的燃料子组件模型，并与MCNP与FLUENT耦合计算结果进行对比。计算结果表明，使用本文的方法，耦合JMCT程序与FLUENT程序能够用于物理-热工耦合计算并准确提供其反馈参数。Abstract: A coupling interface between Monte Carlo neutron transport code JMCT2.2 and commercial CFD code FLUENT was developed by C++ language. The one-by-one mapping strategy that one cell in the MCNP model logically corresponded to the computational domain in the FLUENT model was used in this coupling method to realize simple partition of the physical model and refinement of partition of CFD mesh. The calculated results of a PWR single cell model and a PWR 3×3 fuel model were compared between this program and the MCNP-FLUENT program to validate its accuracy. The results demonstrate that this coupling method between JMCT code and FLUENT code is reasonable and it can accurately calculate the feedback parameters.
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Key words:
- Monte Carlo /
- JMCT /
- FLUENT /
- neutronics/thermal-hydraulics coupling
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图 10 压水堆3×3组件模型温度对比
Figure 10. Comparison of temperature distribution of PWR 3×3 model
表 1 JMCT与MCNP单棒模型耦合对比结果
Table 1. Comparison of the single cell model coupling calculations
converged keff maximum power density/(MW·m-3) maximum cell temperature of fuel/K maximum cell temperature of moderator/K average temperature rise of coolant/K MCNP 0.654 27 411.961 1 398.25 581.06 11.12 JMCT 0.651 71 398.100 1 407.97 581.29 11.08 
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表 2 3×3模型对比结果
Table 2. Comparison of the 3×3 cell model coupling calculations
converged keff maximum power density/ (MW·m-3) maximum cell temperature of fuel/K maximum cell temperature of moderator/K average temperature rise of coolant/K MCNP 1.416 93 158.515 892.21 598.12 46.51 JMCT 1.417 20 160.334 896.21 598.24 46.58
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[1] Ivanov K, Avramova M. Challenges in coupled thermal-hydraulics and neutronics simulations for LWR safety analysis[J]. Annals of Nuclear Energy, 2007, 34(6): 501-513. doi: 10.1016/j.anucene.2007.02.016 [2] Chaudri K S, Su Y, Chen R, et al. Development of sub-channel code SACoS and its application in coupled neutronics/thermal hydraulics system for SCWR[J]. Annals of Nuclear Energy, 2012, 45: 37-45. https://www.sciencedirect.com/science/article/pii/S0306454912000606 [3] Ragusa J C, Mahadevan V S. Consistent and accurate schemes for coupled neutronics thermal-hydraulics reactor analysis[J]. Nuclear Engineering & Design, 2009, 239(3): 566-579. https://www.sciencedirect.com/science/article/pii/S0029549308005645 [4] Jareteg K, Vinai P, Demazière C. Fine-mesh deterministic modeling of PWR fuel assemblies: Proof-of-principle of coupled neutronic/thermal-hydraulic calculations[J]. Annals of Nuclear Energy, 2014, 68(3): 247-256. https://www.sciencedirect.com/science/article/pii/S0306454914000036 [5] Weber D P, Sofu T, Yang W S, et al. Coupled calculations using the numerical nuclear reactor for integrated simulation of neutronic and thermal-hydraulic phenomena[J]. EIRP Proceedings, 2004, 5(1): 13-16. [6] Jimenez G, Herrero J J, Gommlich A, et al. Boron dilution transient simulation analyses in a PWR with neutronics/thermal-hydraulics coupled codes in the NURISP project[J]. Annals of Nuclear Energy, 2014, 84: 86-97. https://www.sciencedirect.com/science/article/pii/S0306454914005829 [7] 史敦福, 李康, 秦桂明, 等. 蒙卡中子输运程序JMCT和子通道热工水力程序COBRA-EN耦合计算[J]. 强激光与粒子束, 2017, 29: 036007. doi: 10.11884/HPLPB201729.160383Shi Dunfu, Li Kang, Qing Guiming, et al. Coupling of Monte-Carlo code JMCT and sub-channel thermal-hydraulics code COBRA-EN. High Power Laser and Particle Beams, 2017, 29: 036007 doi: 10.11884/HPLPB201729.160383 [8] 李刚, 张宝印, 邓力, 等. 蒙特卡罗粒子输运程序JMCT研制[J]. 强激光与粒子束, 2013, 25(1): 158-162. doi: 10.3788/HPLPB20132501.0158Li Gang, Zhang Baoyin, Deng Li, et al. Development of Monte Carlo particle transport code JMCT. High Power Laser and Particle Beams, 2013, 25(1): 158-162 doi: 10.3788/HPLPB20132501.0158 [9] Seker V, Thomas J W, Downar T J. Reactor physics simulations with coupled Monte Carlo calculation and computational fluid dynamics[C]//Joint International Topical Meeting on Mathematics & Computations and Supercomputing in Nuclear Applications (M&C+SNA 2007). 2007. [10] 刘余, 李峰, 张虹, 等. 三维物理-热工耦合系统RECON的开发与验证[J]. 原子能科学技术, 2012, 46(10): 1226-1231. https://www.cnki.com.cn/Article/CJFDTOTAL-YZJS201210016.htmLiu Yu, Li Feng, Zhong Hong, et al. Development and validation of three dimensional neutronics and thermal-hydraulics coupled system REON. Atomic Energy Science and Technology, 2012, 46(10): 1226-1231 https://www.cnki.com.cn/Article/CJFDTOTAL-YZJS201210016.htm [11] 黄欢, 黄洪文, 郭海兵. 三维物理-热工耦合过程的网格优化[J]. 强激光与粒子束, 2017, 29: 116002. doi: 10.11884/HPLPB201729.170168Huang Huan, Huang Hongwen, Guo Haibin. Grid optimizing of coupling neutronics and thermal-hydraulics based on Monte Carlo method and CFD method. High Power Laser and Particle Beams, 2017, 29: 116002 doi: 10.11884/HPLPB201729.170168 [12] Vazquez M, Tsige-Tamirat H, Ammirabile L, et al. Coupled neutronics thermal-hydraulics analysis using Monte Carlo and sub-channel codes[J]. Nuclear Engineering & Design, 2012, 250(3): 403-411. https://www.sciencedirect.com/science/article/pii/S0029549312003251 [13] Cardoni J N. Nuclear reactor multi-physics simulations with coupled MCNP5 and STAR-CCM+[D]. USA: University of Illinois, 2011. -
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