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作 者:卢叶艇 游兆金 沈亚芳 田民顺 LU Ye-ting;YOU Zhao-jin;SHEN Ya-fang;TIAN Min-shun(Nuclear Power Operation Management Co.,Ltd.,CNNC,Haiyan,Zhenjiang Prov.314300)
出 处:《中国核电》2022年第1期89-91,共3页China Nuclear Power
摘 要:在燃料元件包壳未破损的情况下,来自蒸汽发生器传热管、堆内组件等设备表面的腐蚀或磨损产物对堆外辐射场的贡献率超过了90%。为了降低反应堆停役期间的剂量或缩短大修工期,在停堆前采用氧化运行工艺,将空气或H;O;引入主回路水中,使活化腐蚀产物释放,然后通过树脂床快速去除回路中的腐蚀产物,降低停役时的辐射场剂量。本文对目前氧化运行释放和去除堆芯活化腐蚀产物进行研究,并对强迫氧化运行与自然氧化运行进行了深入的分析。Under the condition that the cladding of fuel element is undamaged, the contribution rate of corrosion or wear products from the surfaces of steam generator heat transfer tubes, in-reactor components and other equipment to the radiation field outside the reactor exceeds 90%. In order to reduce the dose during shutdown or shorten the overhaul period, the oxidation operation process was adopted before shutdown, and air or H;O;was introduced into the main loop water to release the activated corrosion products, and then the corrosion products in the loop were quickly removed through the resin bed to reduce the radiation field dose during shutdown. In this paper, the release and removal of core activated corrosion products in current oxidation operation are studied, and the forced oxidation operation and natural oxidation operation are deeply analyzed.
分 类 号:TL38[核科学技术—核技术及应用]
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