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华龙一号反应堆DNBR在线监测系统开发及验证

Development and Validation of DNBR On-line Monitoring System for HPR1000 Reactor

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传统的二代反应堆保护系统一般采用超温ΔT保护信号,这种保护方法比较保守,且属于间接方式,而偏离泡核沸腾比(DNBR)在线监测软件能够直接监督安全参数的变化.为了更直观地实时掌握华龙一号反应堆堆芯的安全裕量,进一步提高反应堆安全运行的灵活性,本文从压水堆堆芯的热工设计基础模型出发,提出了兼顾计算速度和求解精度的DNBR在线监测热工计算模型,开发了一套可用于华龙一号反应堆的DNBR在线监测系统,并从堆芯独立验证、模拟信号验证、华龙一号首堆实堆运行数据验证等三个方面对在线监测系统的计算模型进行了充分验证.结果表明,DNBR在线监测系统计算精度较高,与自主化子通道程序相当,能够满足华龙一号反应堆工程设计的需求.
In the traditional protection system of generation Ⅱ reactor,over-temperature protection signal is usually used.This protection method is conservative and indirect,however,the Departure from Nucleate Boiling Ratio(DNBR)on-line monitoring system can directly monitor the changes of safety parameters.In order to directly monitor the safety margin of Hualong Pressurized Reactor(HPR1000)and improve the flexibility of reactor safety operation,this paper puts forward a DNBR on-line monitoring calculation model with both calculation speed and solution accuracy based on the basic model of thermal design of PWR core,and develops a set of DNBR on-line monitoring system for HPR1000.The calculation model of on-line monitoring system is fully verified from three aspects:independent verification of core,verification of analog signal and verification of actual operation data of HPR1000.The results demonstrate that the precision of the on-line monitoring system is very high,and equvalent with the sub-channel code.In conclusion,the DNBR on-line monitoring system could satisfy the needs of HPR1000 engineering design.

HPR1000Departure from Nucleate Boiling Ratio(DNBR)On-line monitoring

陈曦、吴清、邓坚、刘余、任春明、王啸宇、彭欢欢

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中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213

华龙一号 偏离泡核沸腾比(DNBR) 在线监测

2024

核动力工程
中国核动力研究设计院

核动力工程

CSTPCD北大核心
影响因子:0.3
ISSN:0258-0926
年,卷(期):2024.45(2)