A Digital Controller for Reactivity Monitoring and Power Control

IF 1 4区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Science and Technology of Nuclear Installations Pub Date : 2023-08-07 DOI:10.1155/2023/2839654
V. Vo, V. Nguyen, Van-Diep Le, Q. Phan, L. Phan, Huy-Bach Nguyen, Nhi-Dien Nguyen
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Abstract

This paper introduces a controller unit for reactivity monitoring and automatic power control that was designed and constructed for the 500 kW Dalat Nuclear Research Reactor (DNRR). For power control and reactivity calculations, frequency signals from neutron measurement channels of starting and working ranges of the reactor are used. Two abovementioned independent functions were combined in an Artix-7 FPGA board for determining reactivity values by solving the point reactor kinetics equations with six delayed neutron groups and for stabilizing the reactor power at preset levels by determining the unbalance voltage signal to control the automatic control rod. With real-time calculations, the newly developed controller can monitor the reactor reactivity and control the reactor power online. The developed controller unit’s reactivity measuring and power stabilizing capabilities were assessed using the DNRR in normal operation and assumed emergency conditions and compared with those of the preexisting imported BNO-102R1 module of the DNRR control and protection system, known as ASUZ-14R. The results of the experiments show that the produced FPGA-based unit and the BNO-102R1 unit have the same technical characteristics and features, with the disparities being less than 5% and 1%, respectively, in reactivity measurement and power stabilization. The experimental data of reactivity measurements by the FPGA-based unit and the calculation results were also compared and found that the relative deviations between those are also less than 10%. The developed controller unit is capable of carrying out a variety of training and operational experiments on the DNRR.
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一种用于反应性监测和功率控制的数字控制器
本文介绍了为500 kW达拉特核研究反应堆(DNRR)。对于功率控制和反应性计算,使用来自反应堆启动和工作范围中子测量通道的频率信号。在Artix-7 FPGA板中结合了上述两个独立功能,用于通过求解具有六个延迟中子组的点反应堆动力学方程来确定反应性值,以及通过确定不平衡电压信号来控制自动控制棒来将反应堆功率稳定在预设水平。通过实时计算,新开发的控制器可以在线监测反应堆反应性和控制反应堆功率。在正常运行和假设的紧急情况下,使用DNRR评估了开发的控制器单元的反应性测量和功率稳定能力,并将其与DNRR控制和保护系统的现有进口BNO-102R1模块(ASUZ-14R)进行了比较。实验结果表明,所生产的基于FPGA的单元和BNO-102R1单元具有相同的技术特性和特点,在反应性测量和功率稳定方面的差异分别小于5%和1%。将基于FPGA的单元测量反应性的实验数据与计算结果进行了比较,发现两者之间的相对偏差也小于10%。所开发的控制器单元能够在DNRR上进行各种训练和操作实验。
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来源期刊
Science and Technology of Nuclear Installations
Science and Technology of Nuclear Installations NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
2.30
自引率
9.10%
发文量
51
审稿时长
4-8 weeks
期刊介绍: Science and Technology of Nuclear Installations is an international scientific journal that aims to make available knowledge on issues related to the nuclear industry and to promote development in the area of nuclear sciences and technologies. The endeavor associated with the establishment and the growth of the journal is expected to lend support to the renaissance of nuclear technology in the world and especially in those countries where nuclear programs have not yet been developed.
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