期刊文献+

某核电站蒸汽发生器杂质隐藏返回研究 被引量:10

Investigation of Hideout Return of Steam Generator Impurities in a Nuclear Power Plant
原文传递
导出
摘要 压水堆核电站运行过程中,蒸汽发生器二次侧流动受限区域的表面污垢及缝隙中的有害杂质离子(如Cl-,SO42-,Ca2+,Mg2+,Al3+等)因水的蒸发会出现局部浓缩.通过监测机组停运期间的水化学可以推断机组正常运行期间蒸汽发生器二次侧的杂质浓缩情况.本文分析和评估了某核电站降功率、降温期间蒸汽发生器的3次杂质隐藏返回试验数据.结果表明,隐藏区内的Al3+浓度逐年增加;根据隐藏返回数据得到的高温pH值(pHT)在正常的耐腐蚀pH值范围内;建议机组降温的时间应该进一步延长,以便杂质离子尤其是阴离子完全返回进入大空间溶液并通过排污水系统排出. During ordinary operation of a pressurized water reactor (PWR) of nuclear power plant (NPP), some deleterious ionic impurities such as Cl-, SO42-, Ca2+, Mg2+, AP+ etc. hidden in fouling and crevices for secondary side of steam generator (SG) would concentrate especially in flow-restricted regions. Concentrating situation of the deleterious impurities could be evaluated through secondary water chemistry measurement. In this paper, evaluation and analysis were made from three sets of practical hideout retum (HOR) testing data for a NPP. The results indicated that pHT in crevice was in ordinary range from viewpoint of corrosion resistance according to HOR data. However, the concentration ofAP3+ increased year by year and the reasons need to be further investigated. It is suggested that the time of hideout return tests during steady state should be extended so that the impurities could be completely returned.
出处 《腐蚀科学与防护技术》 CAS CSCD 北大核心 2012年第3期199-203,共5页 Corrosion Science and Protection Technology
关键词 核电站 杂质离子 隐藏返回 水化学腐蚀 nuclear power plant, ionic impurity, hideout return, water chemistry, corrosion
  • 相关文献

参考文献10

  • 1SawochkaS G, Choi S S, Fruzzetti K. Relationship between bulk and local chemistries (hideout return) in Molar ratio control and non Molar ratio control[A]. Proceedings in Improving the Under- Standing and Control of Corrosion on the Secondary Side of Steam Generators[C]. Airlie, VA, USA. 1996, 601.
  • 2Chemistry SW, Committee G R. PWR Secondary Water Chemistry Guidelines- Revision 3 (EPRI-TR-102134)[M].California: EPRI, 1993.
  • 3IAEA.Water Chemistry of WWER Nuclear Power Plants[M].Aus- tria, IAEA, 2007.
  • 4Lurie S, Eaker R, Bucci G, et al. PWR Molar Ratio Control Appli- cation Guidelines Volume 1: Summary[M]. California: EPRI, 1995.
  • 5Stutzmann, Nordmann A F, OllarE Measurement of hideout return. Proceedings in Control of Corrosion on the Secondary Side of Steam Generator[C]. Houston: NACE, 1996.
  • 6Rogers P M, McNeil M. Sodium Chloride Hideout in a Simulated Steam Generator Tube and Tube Support Plate Crevice (Report TR-110803)[M]. CA: EPRI, 1998.
  • 7Odar S, Nordmann F. PWR and VVER secondary system water chemistry[A]. Advanced Nuclear Technology International Europe [C]. ABANT International, 2010:5.
  • 8Gui C. Integrity assessment of steam generator tubing in QNPC 310 MWe nuclear power unit (Chinese)[A]. China Nuclear Power Operation Technology Corporation[C]. LTD, 2008:17.
  • 9Lu Y C. Electrochemical aspect of defining the safe potential/pH zone for corrosion prevention of Alloy 800 SG tubing[A]. AECL 4th CNS International Steam Generator Conference[C]. Canada, 2002.
  • 10Lu Y C. Evaluation of SCC susceptibility of alloy 800 under CANDU SG secondary side condition[A].AECL 5th CNS Interna- tional Steam Generator Gonference[C]. Canada, 2006.

同被引文献29

引证文献10

二级引证文献14

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部