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游泳池式轻水反应堆池壁池底及关键构件老化评估

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核反应堆老化问题是决定反应堆安全运行的重要因素之一.中国原子能科学研究院游泳池式轻水反应堆(简称 49-2堆)是一座典型的延寿运行的研究堆,也是中国目前运行时间最长的反应堆,开展老化研究对评估其继续延寿运行具有重要意义.本文主要以游泳池式轻水反应堆池底池壁(L03铝材)作为研究对象,对某些点缺陷的腐蚀情况进行分析,结果表明,49-2堆一次水水质条件引起铝合金的化学腐蚀较小,通过水下摄像机的检查,发现点缺陷无扩大和其他性质的变化,同时对池底地脚螺栓的检测,发现螺栓腐蚀程度轻微,X射线探伤表明内部无结构损伤情况,可侧面判定反应堆池壁池底的腐蚀情况较为良好,不会产生破口失水事故的发生.该结果对许可证延续申请具有重要参考价值.
Aging Evaluation of the Inner Lining Wall and Key Structure Component of the Swimming Pool Reactor
The aging of nuclear reactor is one of the key problems for nuclear operation safety.The swimming pool reactor(SPR)in China Institute of Atomic Energy(CIAE)is a typical life-extending research reactor,which is a longest operating reactor in China.It is of great significance for the life-extending application when studying the SPR aging.In this work,we aim to obtain and value the corrosion condition of the inner lining wall(which made by Al)in the pool.It is found that the chemical corrosion of the Al alloy caused by the primary water quality of 49-2 SPR was relatively small.There is no apparently expand and variation of physical properties of spot defects through the underwater camera test.In addition,the X-ray inspection of the bolt in the pool shows that the bolt is basically free of corrosion and no internal crack,which indicates that the primary water leak accident would never happen.The results have important value for the license renewal of 49-2 reactor life-extending operation.

Swimming pool reactorReactor agingCorrosionLife-extending

蔡光博、杨笑、李保青、李艾娟、陈晓亮

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中国原子能科学研究院,北京 102413

游泳池式轻水反应堆 老化 腐蚀 延续运行

国家科技重大专项子课题

2017ZX06002004

2024

核科学与工程
中国核学会

核科学与工程

CSTPCD北大核心
影响因子:0.586
ISSN:0258-0918
年,卷(期):2024.44(2)
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