核级低合金钢高温水腐蚀疲劳机制及环境疲劳设计模型

doi:10.11900/0412.1961.2014.00421

金属学报

2015, Vol. 51

Issue (3): 298-306 DOI: 10.11900/0412.1961.2014.00421

本期目录 | 过刊浏览

核级低合金钢高温水腐蚀疲劳机制及环境疲劳设计模型

吴欣强^1,²(

), 谭季波^1,², 徐松^1,², 韩恩厚^1,², 柯伟^1,²

1 中国科学院金属研究所核用材料与安全评价重点实验室, 沈阳 110016
2 中国科学院金属研究所辽宁省核电材料安全与评价技术重点实验室, 沈阳 110819

CORROSION FATIGUE MECHANISM OF NUCLEAR-GRADE LOW ALLOY STEEL IN HIGH TEMPERATURE PRESSURIZED WATER AND ITS ENVIRONMENTAL FATIGUE DESIGN MODEL

WU Xinqiang^1,²(

), TAN Jibo^1,², XU Song^1,², HAN En-Hou^1,², KE Wei^1,²

1 Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016
2 Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016

引用本文:

吴欣强, 谭季波, 徐松, 韩恩厚, 柯伟. 核级低合金钢高温水腐蚀疲劳机制及环境疲劳设计模型[J]. 金属学报, 2015, 51(3): 298-306.
Xinqiang WU, Jibo TAN, Song XU, En-Hou HAN, Wei KE. CORROSION FATIGUE MECHANISM OF NUCLEAR-GRADE LOW ALLOY STEEL IN HIGH TEMPERATURE PRESSURIZED WATER AND ITS ENVIRONMENTAL FATIGUE DESIGN MODEL[J]. Acta Metall Sin, 2015, 51(3): 298-306.

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摘要:

通过模拟核电高温高压循环水腐蚀疲劳实验, 研究了核级低合金钢环境疲劳损伤规律与控制机理, 构建了一个植入环境效应的疲劳设计模型, 给出了便于工程应用的环境疲劳设计曲线, 并建立了核电站实际构件的环境疲劳安全评估流程, 给出了尝试实施例.

关键词 ：核级低合金钢, 高温高压水, 腐蚀疲劳, 设计模型, 环境疲劳安全评估

Abstract：

The service degradation and life assessment of key components in light water reactor nuclear power plants (NPPs) mainly depend on the accumulation of service property data of component materials, understanding of environmental degradation mechanism, and construction of evaluation models or methods. The current ASME design fatigue code does not take full account of the interactions of environmental, loading and material's factors. In the present work, based on the corrosion fatigue tests in simulated NPPs' high temperature pressurized water, the environmental fatigue behavior and dominant mechanism of nuclear-grade low alloy steel have been investigated. A design fatigue model was constructed by taking environmentally assisted fatigue effects into account and the corresponding design curves were given for the convenience of engineering applications. The process for environmental fatigue safety assessment of NPPs' components was proposed, based on which some tentative assessment cases have been given.

Key words： nuclear-grade low alloy steel high temperature pressurized water corrosion fatigue design model environmental fatigue safety assessment

ZTFLH:

TG172

基金资助:* 国家重点基础研究发展计划项目2011CB610506和国家科技重大专项项目2011ZX06004-009资助

作者简介: null

吴欣强, 男, 1971年生, 研究员

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https://www.ams.org.cn/CN/10.11900/0412.1961.2014.00421 或 https://www.ams.org.cn/CN/Y2015/V51/I3/298

图1 国产核级低合金钢SA508-III在高温高压水中的腐蚀疲劳寿命

图2 核级低合金钢表面疲劳裂纹形貌

图3 核级低合金钢疲劳断口形貌[3]

图4 核级低合金钢(SA508-III和A533B)在空气中的最佳拟合曲线和误差分析

图5 核级低合金钢(SA508-III和A533B)高温高压水腐蚀疲劳寿命影响因素

图6 核级低合金钢(SA508-III和A533B)的环境疲劳设计曲线

图7 核电站实际构件的环境疲劳寿命评估流程

S_alt/ MPa	T / ℃	$ε ˙$ / %s^-¹	Design cycle / cyc	N_ASME	U_air	N_env	U_env
567.2	200	0.028	120	1024	0.1172	92	1.304
500.6		0.026		1429	0.0630	142	0.634
444.1	200	0.026	142	1967	0.0722	231	0.615
268.8	200	0.002	555	9272	0.0599	2191	0.253
201.9	200	0.001	10	23830	0.0004	7149	1.40×10^-³
143.8	200	0.001	120	81350	0.0015	88833	1.35×10^-³
132.4	200	0.001	98	115630	0.0008	231742	4.23×10^-⁴
121.1	200	0.001	10	159810	0.0001	703538	1.42×10^-⁵
120.2	288	0.001	10	163810	0.0001	777252	1.29×10^-⁵
95.5	288	0.001	222	444850	0.0005	1000000	2.22×10^-⁴
92.6	200	0.001	666	523970	0.0013	1000000	6.66×10^-⁴
91.9	288	0.001	120	560450	0.0002	1000000	1.20×10^-⁴
					Total 0.317		Total 2.81

表1 某沸水堆碳钢给水管的安全端疲劳损伤评价 [29~31]

表2 典型运行瞬态的总设计周次、40 a和60 a的周次 [31]

表3 某压水堆进水管嘴的疲劳延寿评估[31]

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