Proof Test in Hot Condition on Steam Separation Device in Steam Generator for 1000MW PWR Nuclear Power Plant
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摘要: 对百万千瓦级压水堆核电厂蒸汽发生器汽水分离装置水-空气冷态试验确定的最佳结构进行了实际核电厂运行参数条件下的水-蒸汽热态验证试验,与国外先进结构汽水分离装置试验体在热态试验条件下的性能进行了对比。结果表明,在正常运行条件下,研制的汽水分离装置试验体出口蒸汽湿度(上携带)为0.0021%,远小于百万千瓦级压水堆核电厂蒸汽发生器设计规定的0.1%的湿度指标,其在恶劣工作条件下的汽水分离性能仍满足设计要求,并优于国外先进结构汽水分离装置试验体。Abstract: Steam-water proof test under nuclear power plant operation condition on the steam separation devices in steam generator for 1000MW PWR nuclear power plant has been conducted. The test result indicates that the steam humidity (carryover) in outlet of the steam separation device with optimized design features obtained by previous air-water screening test in cold condition is 0.0021% under nuclear power plant operation condition, which is less than the standard steam humidity (0.1%) required by the design of steam generator for 1000MW PWR nuclear power plant. Its performance under severe condition meets the design demand, and it is better than that of the advanced steam separation devices in other countries.
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Key words:
- Steam separator /
- Dryer /
- Carryover /
- Permission steam load
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