摘要
压水堆核电厂中近似85%的电厂注锌的主要目的是为了控制辐射场(最有效和经济),同时缓解一回路水应力腐蚀开裂(PWSCC),此技术已经被认为是成熟的技术。新机组加锌,尤其是热态功能试验期间加锌,风险较小,效果较好。对于老机组加锌,对于注锌的前两个循环有一定风险,但经过国外多年研究证明其风险可控。对于首次注锌电厂,可分为两个阶段开展一回路加锌技术机组的应用研究:第一个阶段开展注锌前数据测量及收集、一回路注锌对机组影响评价、一回路注锌策略研究和确定;开展注锌相关改造和变更实施、开始注锌和注锌后数据测量收集、注锌效果评价等。国内压水堆核电机组中,三门和海阳1、2号机组在热态功能试验(HFT)期间已经开始注锌,通过样品测量和运行数据收集分析表明,已达到了预期的目的和效果。
Approximately 85% of PWR nuclear power plants are injected with zinc for the purpose of controlling radiation field(the most effective and economical) and alleviating primary water stress corrosion cracking(PWSCC), which has been considered as a mature technology. Adding zinc to the new unit, especially during the hot state functional test, has less risk and better effect. For the zinc addition of old units, there are certain risks for the first two cycles of zinc injection, but the risk is controllable after years of study abroad. For the first zinc injection of power plant, the application research of the primary zinc injection technology unit can be divided into two stages: in the first stage, the data measurement and collection before zinc injection, the impact evaluation of primary zinc injection on the unit, and the study and determination of the primary zinc injection strategy;in the second stage, zinc injection related transformation and change implementation, zinc injection and data measurement and collection after zinc injection, zinc injection effect evaluation, etc. Among the domestic PWR nuclear power units, Units 1 & 2 of Sanmen and Haiyang NPPshave started zinc injection during the hot state functional test(HFT). The sample measurement and operation data collection and analysis show that the expected purpose and effect have been achieved.
作者
付亚茹
梅其良
张嘉康
姜磊
毛兰方
刘健
FU Yaru;MEI Qiliang;ZHANG Jiakang;JIANG Lei;MAO Lanfang;LIU Jian(Shanghai Nuclear Engineering Research and Design Instititu,Shanghai 200233,China;Shangdong Nuclear Power Company Ltd.,Haiyang of Shangdong Prov.265100,China;Sanmen Nuclear Power Company Ltd,Ningbo of Zhejiang Prov.317100,China;Nuclear and Radiation Safety Center,Beijing 100142,China)
出处
《核科学与工程》
CAS
CSCD
北大核心
2022年第4期881-887,共7页
Nuclear Science and Engineering
基金
大型先进压水堆及高温气冷堆核电站国家科技重大专项“CAP1400放射性废物最小化关键技术与装置研发”。
关键词
一回路
注锌
技术方案
策略
效果评估
Primary coolant
Zinc injection
Technical proposal
Strategy
Effect evaluation