Experiment Research on Integral Hydraulic Simulation of ACP100 Reactor
-
摘要: 模块式先进小型压水堆(ACP100)是一种新型一体化小型反应堆,直流蒸汽发生器和主泵均直接集成在压力容器上,紧凑的结构导致其内部流场复杂。本研究应用1:3缩比模型模拟ACP100反应堆内部流场,开展反应堆整体水力模拟冷态试验。试验得到反应堆模型的总压降和分段压降,获得了反应堆模型总阻力系数以及主要流道分段阻力系数;并得到堆芯入口各燃料组件的流量分配因子。模型试验结果显示,主流道内的流动已进入第二自模区,流体的流型、流速分布以及阻力系数与原型反应堆相同;流动进入自模区后,反应堆模型的阻力系数为常数,阻力系数值为8.02,可直接用于原型反应堆压降计算;额定运行工况下,堆芯入口的流量分配因子值在0.91~1.08,满足设计需求;流量分配罩具有良好的整流作用,模拟失流事故工况下的流量分配仍较均匀。Abstract: Advanced Small Modular Pressurized Reactor (ACP100) is a new integrated small-scale reactor. Its once-through steam generators and reactor coolant pumps are directly integrated into the pressure vessel, and the compact design leads to a complex internal flow field. A 1/3 scaled-down model was used to simulate the entire internal flow field of the ACP100 reactor and carry out integral hydraulic simulation cold experiment for the reactor. In the experiment, the total pressure drop and segmented pressure drop of the model were obtained, as well as the total resistance coefficient and the segmented resistance coefficients of the main flow paths. The flow distribution factors of each fuel assembly at the core inlet were also acquired. The experiment results showed that the flow inside the main channels had entered the second self-modeling zone, and the flow pattern, velocity distribution and resistance coefficient of the fluid were consistent with those of the prototype reactor. After entering the second self-modeling zone, the total resistance coefficient of the model remained constant at 8.02, which can be used to calculate the pressure drop of the prototype directly. Under rated operating condition, all the distribution factors at the core inlet ranged from 0.91 to 1.08, meeting the design requirements. Besides, the flow distribution of LOFA simulation was uniform, indicating that the flow distributor had good rectifying effects.
-
Key words:
- ACP100 reactor /
- Integral hydraulic simulation /
- Self-model /
- Resistance coefficient /
- Flow distribution
-
表 1 各Eu分段值
Table 1. Various EuSection Values
模型分段 阻力系数 A-B入口段 1.71 B-C下降段与下腔室 0.38 C-D堆芯段 1.03 D-E上腔室 0.63 E-F蒸汽发生器段 3.38 F-G出口段 0.90 -
[1] 王建民,李经纬. 秦山核电二期工程反应堆水力学设计[J]. 核动力工程,2003, 24(S2): 24-27. [2] 眭曦,王盛,杨祖毛,等. 中国工程试验堆堆芯入口流量分配特性实验研究[J]. 原子能科学技术,2020, 54(2): 257-263. doi: 10.7538/yzk.2019.youxian.0105 [3] HETSRONI G. Use of hydraulic models in nuclear reactor design: NYO-3250-2[R]. Haddam: Connecticut Yankee Atomic Power Co., 1965. [4] HENSCH F. JULIETTE tests interpretation flow rate distribution and characterization of the head losses and pressure fields: NFPSDDC 1025[R]. Areva: Areva Group, 2006. [5] EUH D J, KWON T S, YOUN Y J, et al. Hydraulic characteristics of SMART reactor for a nominal condition[C]//Proceedings of the 9th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics. Malta: International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics, 2012. [6] 杨来生,宗桂芳,胡俊. 秦山核电二期工程反应堆水力模拟实验研究[J]. 核动力工程,2003, 24(S1): 208-211,226. [7] KHAN E U. Analytical investigation and design of a model hydro-dynamically simulating a prototype PWR core[J]. Nuclear Technology, 1972, 16(3): 479-496. doi: 10.13182/NT72-A31217