摘要
出于增加经济性和运行灵活性的考虑,核电站一般要求具备延伸运行能力。延伸运行通常在堆芯寿期末进行,硼浓度过低不能再稀释引入反应性,仅依靠降低冷却剂温度或者堆芯功率来延长运行的运行模式。目前国内仅少数核电厂实施过延伸运行,缺乏对不同延伸运行方式的分析研究,另外大型三代压水堆的延伸运行能力有待研究。基于我国大型三代压水堆“华龙一号”堆型,本文从堆芯物理角度,首次分析了不同延伸运行方式的实现过程,并讨论了不同延伸运行方式的经济性及安全评价的影响。
Strech out operation usually arises from a change in energy requirements or a change in planned shutdown date.Usually it happens in the end of cycle when the boron concentration is too low to induce reactivity.Several methods of cycle extension are possible,including power coastdown,temperature coastdown,and varying combinations of these.Few nuclear powered plants have operated with stretch out operation in China,research or demonstration should be done for different kinds of operations especially for the large-scale nuclear powered plants.This paper for the first time researches the coastdown operation capability of HPR1000 from the view of core physics.The results show the performances of power coastdown,temperature coastdown,and varying combinations of these of HPR1000.Economy and safety for different kinds of operations are also discussed in this paper.
作者
谢运利
于颖锐
陈长
李满仓
娄磊
王星博
刘琨
刘勇
XIE Yun-li;YU Ying-rui;CHEN Zhang;LI Man-cang;LOU Lei;WANG Xing-bo;LIU Kun;LIU Yong(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,Sichuan Prov.610041,China)
出处
《中国核电》
2020年第2期144-147,共4页
China Nuclear Power
关键词
华龙一号
三代压水堆型
延伸运行
HPR1000
generationⅢpressurized reactor
stretch out operation