PWR-1000XL核蒸汽供应系统设计  

Design of the Nuclear Steam Supply System for PWR-1000XL

作　　者：张富源[1] 张森如[1] 彭诗念[1] 

机构地区：[1]中国核动力研究设计院,成都610041

出　　处：《核动力工程》2003年第1期4-7,共4页Nuclear Power Engineering

摘　　要：国产化1000MW级压水堆核电站(PWR-1000XL)是中国核动力研究设计院拟向国内用户推荐的计划在“十五”后期开始建造的核电站方案之一。PWR-1000XL的设计寿命60年。核蒸汽供应系统的主要设计特点是:采用Performance+燃料组件,换料周期18个月;堆芯平均线功率密度165.2W/cm,堆芯热工裕量大于15%。堆顶结构一体化,设置RPV顶盖事故排气系统,无测温旁路系统;稳压器容积45m3,选用Δ75型蒸汽发生器和100D型主泵;采用破前漏技术,设置可燃气体控制系统;采用数字化仪表和控制系统。PWR-1000XL is a 1084 MW PWR nuclear power plant with 60-year design life. The major design features of PWR-1000XL nuclear steam supply system include: lower average linear power density of fuel rod, 18-month refueling, core thermal margin greater than 15%, integrated structure on reactor pressure vessel upper head, reactor pressure vessel gas release system, cancellation of temperature measure bypass system, larger pressurizer volume, Delta 75 steam generator, 100D main coolant pump, leak-before-break technology, engineering safety systems improvement, combustible gas control system, digital I and C system. This paper briefly introduces the NSSS design and its major features.

关 键 词：压水堆 核蒸汽供应系统 加长型燃料组件 

分 类 号：TL421.1[核科学技术—核技术及应用]