Study on Neutronic/Thermal-Mechanical Coupling Calculation Method for Fast-neutron Pulse Reactor with Metallic Nuclear Fuel
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摘要: 为确保快中子脉冲堆的运行安全，防止超临界脉冲对材料造成物理损伤，需要对快中子脉冲堆脉冲工况进行模拟分析。本研究针对金属核燃料快中子脉冲堆，基于点堆动力学方法、蒙特卡罗方法和有限元力学方法，对Godiva-I脉冲堆开展了核热力耦合计算分析研究。计算结果表明，反应性温度系数和裂变率与实验值吻合良好，反应性、温升、表面位移、表面应力与实际情况相符合。因此，本文建立的“核-热-力”耦合计算方法可应用于金属核燃料快中子脉冲堆的分析计算，具有一定的可靠性。Abstract: In order to ensure the operational safety of the fast-neutron pulse reactor and prevent the supercritical pulse from causing physical damage to the material, it is necessary to simulate and analyze the pulse operating conditions of the fast-neutron pulse reactor. In this study, for the fast-neutron pulse reactor with metallic nuclear fuel, the neutronic/thermal-mechanical coupling calculation and analysis of Godiva-I pulse reactor are carried out based on the point reactor dynamics method, Monte Carlo method and finite element mechanics method. The calculation results show that the reactivity temperature coefficient and fission rate are in good agreement with the experimental values, and the reactivity, temperature rise, surface displacement and surface stress are consistent with the actual situation. Therefore, the "neutronic/thermal-mechanical" coupling calculation method established in this paper can be applied to the analysis and calculation of the fast-neutron pulse reactor with metallic nuclear fuel, and has certain reliability.
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Key words:
- Pulse reactor /
- Neutronic/thermal-mechanical coupling /
- ANSYS /
- Transient analysis
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图 1 金属核燃料快中子脉冲堆核热力耦合分析方法
Figure 1. Neutronic/Thermal-Mechanical Coupling Method for Fast-neutron Pulse Reactor with Metallic Nuclear Fuel
图 3 不同网格单元运行时间及最大相对偏差
Figure 3. Running Time and Maximum Relative Deviation of Different Grid Cells
图 4 网格数92019时内外表面位移与表面应力计算对比
Figure 4. Comparison of Internal and External Surface Displacement with Surface Stress of 92019 Grid Cells
图 5 绝热边界条件下不同温升下的径向位移变化
Figure 5. Changes of Radial Displacement at Different Temperature Rises under Adiabatic Boundary Conditions
图 6 初始周期16.2 μs时裂变率和反应性随时间的变化
tm—裂变率峰值时刻
Figure 6. Variation of Fission Rate and Reactivity with Time During the Initial Period of 16.2 μs
图 7 初始周期16.2 μs时温度分布云图和系统温升对比
Figure 7. Comparison of Temperature Distribution Nephogram and System Temperature Rise during the Initial Period of 16.2 μs
图 8 初始周期16.2 μs时系统表面位移和表面应力随时间的变化
Figure 8. Variation of Surface Displacement and Stress of the System with Time During the Initial Period of 16.2 μs
图 9 初始周期16.2 μs时形变和应力分布云图
Figure 9. Nephogram of Deformation and Stress Distribution During the Initial Period of 16.2 μs
表 1 物性参数
Table 1. Physical Property Parameters
参数 数值 密度/ (g·cm−3) 18.7398 泊松比 0.23 杨氏模量/GPa 208 热传导系数/ (W·m−1·K−1) 27.5 热膨胀系数/K−1 1.35×10−5 比热容/(J·kg−1·K−1) 117.72 
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[1] 贺仁辅, 邓门才. 快中子临界装置和脉冲堆实验物理[M]. 北京: 国防工业出版社, 2012: 34-37 [2] 钟力晗,高辉,梁文峰,等. 金属型脉冲堆惯性效应计算[J]. 强激光与粒子束,2017, 29(9): 096003. doi: 10.11884/HPLPB201729.170031 [3] 梁文峰,谢奇林,高辉,等. 基于波形逼近的快中子脉冲堆耦合计算[J]. 原子能科学技术,2016, 50(11): 2018-2022. [4] WILSON S C, BIEGALSKI S R, COATS R L. Computational modeling of coupled thermomechanical and neutron transport behavior in a Godiva-like nuclear assembly[J]. Nuclear Science and Engineering, 2007, 157(3): 344-353. doi: 10.13182/NSE06-28 [5] 梁文峰,邱东,杨成德,等. 燃料元件在热冲击下基于ANSYS的动态响应仿真[J]. 科学技术与工程,2014, 14(20): 51-55. doi: 10.3969/j.issn.1671-1815.2014.20.011 [6] KADIOGLU S Y, KNOLL D A, DE OLIVEIRA C. Multiphysics analysis of spherical fast burst reactors[J]. Nuclear Science and Engineering, 2009, 163(2): 132-143. doi: 10.13182/NSE09-07 [7] 邱东. 快中子脉冲反应堆爆发脉冲时堆体应力分布的数值模拟[J]. 核动力工程,2004, 25(1): 74-78+82. doi: 10.3969/j.issn.0258-0926.2004.01.018 [8] 陈硕,郑春,杜金峰. 高产额脉冲堆爆发脉冲过程力学特性数值模拟[J]. 强激光与粒子束,2019, 31(5): 056004. doi: 10.11884/HPLPB201931.180347 [9] 马誉高,刘旻昀,余红星,等. 热管冷却反应堆核热力耦合研究[J]. 核动力工程,2020, 41(4): 191-196. doi: 10.13832/j.jnpe.2020.04.0191 [10] 张驰,周琦,朱庆福,等. 金属核燃料系统瞬态特性分析研究[J]. 原子能科学技术,2016, 50(12): 2170-2174. doi: 10.7538/yzk.2016.50.12.2170 [11] 陈硕. 快中子脉冲堆安全限值与限制条件分析[D]. 绵阳: 中国工程物理研究院, 2019. [12] 高辉,钟力晗,梁文峰,等. 基于反应性温度系数的金属型脉冲堆波形计算[J]. 原子能科学技术,2017, 51(5): 798-802. doi: 10.7538/yzk.2017.51.05.0798 [13] CANAAN R E. Dynamic response of a pulse-heated, thick-walled, hollow sphere: validation of code numerics: UCRL-ID-137326[R]. Washington: USDOE Office of Defense Programs, 2000. [14] PETERSON R E, NEWBY G A. Lady Godiva: an unreflected uranium-235 critical assembly: LA-1614[R]. Los Alamos: Los Alamos National Laboratory, 1953. [15] WIMETT T F, ENGLE L B, GRAVES G A, et al. Time behavior of Godiva through prompt critical[R]. Los Alamos: Los Alamos Scientific Laboratory, 1956: 1-39. [16] AUFIERO M, FIORINA C, LAUREAU A, et al. Serpent--OpenFOAM coupling in transient mode: of a Godiva prompt critical burst[C]//Proceedings of Joint International Conference on Mathematics and Computation, Supercomputing in Nuclear Applications and the Monte Carlo Method. Nashville: ANS, 2015. [17] WANG Y Q, SCHUNERT S, ORTENSI J, et al. Demonstration of MAMMOTH strongly-coupled multiphysics simulation with the Godiva benchmark problem[C]//International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering. Jeju, Korea: Idaho National Lab., 2017. -
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