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氟盐冷却高温堆半实物仿真及初步测试

阮见 邹杨 KENDRICK J 李明海 PETERSON P F 徐洪杰

原子能科学技术2018,Vol.52Issue(4):659-665,7.
原子能科学技术2018,Vol.52Issue(4):659-665,7.DOI:10.7538/yzk.2017.youxian.0411

氟盐冷却高温堆半实物仿真及初步测试

Fluoride-salt-cooled High-temperature Reactor Hardware-in-the-loop Simulation and Preliminary Test

阮见 1邹杨 2KENDRICK J 1李明海 3PETERSON P F 1徐洪杰3

作者信息

  • 1. 中国科学院上海应用物理研究所,上海 201800
  • 2. 中国科学院大学,北京 100049
  • 3. University of California,Berkeley CA 94706,USA
  • 折叠

摘要

Abstract

Based on the theory of hardware-in-the-loop simulation, the functions of the compact integral effects test facility at the University of California, Berkeley, and integral effects test simulating the integral thermal-hydraulic response of fluoride-salt-cooled high-temperature reactors(FHRs)under forced and natural circulation operation, were improved to better reflect the characteristics of this kind of reactor's operation. Modifications made on the facility's control system including a neutron kinetics model, a reactivity feedback model, and temperature control and power control models were the foundational work necessary to make the facility simulate the behavior of an FHR. Results from temperature control experiments indicate that the facility's heater can respond rap idly to the controller's output and achieve the target temperature, similar to prototypical fuel temperature behavior. Better power control parameters and control results were then obtained by optimizing PID parameters of the point-reactor-based power control model, laying the foundation for the subsequent optimization of control logic and the study of the impact of parameter uncertainties.

关键词

氟盐冷却高温堆/半实物仿真/串口通信/控制逻辑

Key words

fluoride-salt-cooled high-temperature reactor/hardware-in-the-loop simulation/serial communication/control logic

分类

能源科技

引用本文复制引用

阮见,邹杨,KENDRICK J,李明海,PETERSON P F,徐洪杰..氟盐冷却高温堆半实物仿真及初步测试[J].原子能科学技术,2018,52(4):659-665,7.

基金项目

中国科学院战略性先导科技专项资助(XDA0201002) (XDA0201002)

上海市科学技术委员会项目资助(11JC1414900) (11JC1414900)

中国科学院前沿科学重点研究项目资助(QYZDY-SSW-JSCO16) (QYZDY-SSW-JSCO16)

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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