1International Atomic Energy Agency. Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: Steam Generators, IAEA-TECDOC-981 [R]. Vienna: IAEA, 1997.
2International Atomic Energy Agency. Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety Primary Piping in PWRs, IAEA-TECDOC-1361 [R]. Vienna: IAEA, 2003.
3Nuclear Regulatory Commission. Investigation and Evaluation of Stress Corrosion Cracking in Piping of Light Water Reactor Plants, NUREG-0531 [R]. Washington, DC: U.S. NRC, 1979.
4International Atomic Energy Agency. Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: BWR Pressure Vessels, IAEA-TECDOC-1470 JR]. Vienna: IAEA, 2005.
5International Atomic Energy Agency. Stress Corrosion Cracking in Light Water Reactors: Good Practices and Lessons Learned, NP-T- 3.13 [R]. Vienna: IAEA, 2011.
6Nuclear Regulatory Commission. Technical report on material selection and processing guidelines for BWR coolant pressure boun-dary piping, NUREG-0313 [R]. Washington, DC: U.S. NRC, 1988.
7American Society of Mechanical Engineers. Rules for in-service in- spection of nuclear power plant components [S]. New York, 2004.
8OGAWA N,NAGATA T,YAMADA M,et al.Verification test for radiation exposure reduction effect and material integrity on PWR primary system by zinc injection[C] ∥Proc.8th Internal.Conf.on Water Chemistry of Nuclear Power Systems.Kashiwazaki,Japan:[s.n.] ,1998:329.
9PASTINA B,ISABEY J,HICKEL B.The influence of water chemistry on the radiolysis of the primary coolant water in pressurized water reactors[J].Journal of Nuclear Materials,1999,64:309-318.
10CHEN P C,LEE M K.Zinc oxide nanostructures prepared by liquid phase deposition[D].Taiwan,China:Department of Electrical Engineering,National Sun Yat-Sen University,2006.
