核电站安全壳打压试验泄压速率优化研究  

Optimization of Pressure Release Rate in Nuclear Power Plant Containment Pressure Test

作　　者：郭裕丰 王志永 王洪凯 GUO Yufeng;WANG Zhiyong;WANG Hongkai(Fujian Fuqing Nuclear Power Co.,Ltd.,Fuqing 350318,China)

机构地区：[1]福建福清核电有限公司,福建福清350318

出　　处：《电工技术》2024年第11期226-228,共3页Electric Engineering

摘　　要：核电站安全壳打压试验是机组大修期间的绝对关键路径工作,试验执行质量影响机组大修的总体进度。其中泄压速率作为决定安全壳打压试验工期的重要因素,通过建立核电站安全壳内外结构仿真模型,对25 kPa/h泄压速率时安全壳结构的安全性进行分析,提出泄压速率提升的理论依据,同时将模拟数据与缩尺安全壳模型进行对比验证,旨在为安全壳打压试验全面优化提供技术指导。The containment pressure test of a nuclear power plant is an absolutely critical path work during unit overhaul period.The practical quality of containment pressure test affects the overall progress of unit overhaul,and the pressure relief rate is an important factor determining the test duration.This paper establishes a simulation model of internal and external structures of the nuclear power plant′s containment,studies and analyzes safety of the containment structure at a pressure relief rate of 25 kPa/h,and proposes a theoretical basis for improving pressure relief rate.Moreover,the simulation data are compared and verified with the scaled containment model,aiming to provide technical guidance for the comprehensive optimization of containment pressure testing.

关 键 词：核电站 安全壳 泄压速率 打压试验 数值仿真模型 

分 类 号：TM623[电气工程—电力系统及自动化]