| [1] 王永东, 李辉, 包章根. 蒸汽发生器用Incoloy 800 核级管子技术条件[R]. 上海: 上海核工程研究设计院, 2009.[2] Steam Generator Management. Alloy 800 steam generator tubing experience [R]. USA: EPRI, 2012: 3-5.[3] Steam Generator Management. Pressurized water reactor generic tube degradation predictions: recirculation steam generators with alloy 600TT, alloy 690TT, and alloy 800NG tubing [R].USA: EPRI, 2013: 2-10.[4] Frederick G, Hernalsteen P, Stubbe J. Qualification of remedial methods to prevent primary-side stress corrosion cracking of steam generator tubing: shot peening [R]. USA: EPRI,1987: 5-8.[5] Lee Y H, Kim H K, Kim H D. A comparative study on the fretting wear of steam generator tubes in Korean power plants [J]. Wear, 2003, 255(7): 1198-1208.[6] Lucan D, Fulger M, Jinescu G. Corrosion process of Incoloy-800 in high pressure and temperature aqueous environment [J]. Chiminform Data, 2008, 59(9): 1026-1029.[7] Stellwag B, Wieling N, Stieding L. Corrosion resistance of SG tubing materials alloy 800 and alloy 690—a comparative study [C]// Proc 2nd Int Symp on Environmental Degradationof Materials in Nuclear Power Systems. 1986: 301.[8] 黄德伦, 孔德生, 杨武. 冷加工对800合金抗碱性应力腐蚀破裂的影响[J]. 腐蚀与防护, 1997, 18(6): 9-12.[9] 李钧, 苏诚, 张磊, 等. 晶界工程处理对Incoloy 800 合金耐腐蚀性能和力学性能的影响[J]. 上海大学学报: 自然科学版, 2013, 13(5): 540-544.[10] 黄春波, 李光福, 吕战鹏, 等. 某些加工因素对改性800 合金碱性应力腐蚀破裂敏感性的影响[J]. 原子能科学技术, 2015, 29(S1): 37-41.[11] 郑兆麟. 800 合金U 型管表面喷丸工艺的研究与实践[J]. 钢管, 1998, 27(5): 4-8.[12] 黄静娴. 核电站用蒸汽发生器800 合金U 形管的研制[J]. 钢管, 1998, 27(6): 6-11.[13] 高玉魁. 陶瓷丸在喷丸强化中的发展与应用[J]. 热处理, 2008(1/2): 59-60.[14] 钦征骑. 金属表面强化处理用复合锆质陶瓷喷丸的研制及应用[J]. 江苏陶瓷, 2010, 43(5): 5-8.[15] ASTM International. Standard practice for estimating the approximate residual circumferential stress of straight thin-walled tube [S]. West Conshohocken: ASTM International, 2013.[16] 戈大钫, 穆树人, 张文华. 用X 射线仪测定Incoloy 800 合金圆管的表面压应力[J]. 实验室研究与探索, 1996(2): 44-47.[17] 戈大钫, 郑经绂, 丁亚平, 等. 喷丸改善800 合金传热管在高温苛性碱溶液中的应力腐蚀性能的研究[J]. 理化检验: 物理分册, 1996, 32(5): 34-37. |
