LOW TEMPERATURE CRACK PROPAGATION EVALUATION IN PRESSURIZED WATER REACTOR SERVICE

机译：加压水反应器服务中的低温裂纹扩展评估

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Low Temperature Crack Propagation (LTCP) is a form of hydrogen embrittlement which has yet to be identified in commercial nuclear reactors but which can cause severe degradation of the fracture resistance of certain nickel-base alloys in laboratory tests performed under specific conditions. This paper provides a review of the currently available laboratory test data together with the results of an initial attempt to assess the applicability of LTCP of nickel-alloy components under current Pressurized Water reactor (PWR) primary system service conditions.

机译：低温裂纹扩展（LTCP）是氢脆的一种形式，尚未在商用核反应堆中确定，但在特定条件下进行的实验室测试中，它可能导致某些镍基合金的抗断裂性严重降低。本文对当前可用的实验室测试数据进行了综述，并初步评估了在当前压水堆（PWR）初级系统服务条件下镍合金部件LTCP的适用性。

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来源
《12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors 2005 vol.2》|2005年|623-634|共12页
会议地点 Salt Lake CityUT(US)
作者
A. Demma; A. Mcllree; M. Herrera;
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作者单位

Electric Power Research Institute, 3412 Hillview Ave., Palo Alto, CA, 94304, USA;

Structural Integrity Associates, 3315 Almaden Expressway, Suite 24, San Jose, CA, 95118, USA;

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会议组织
原文格式 PDF
正文语种 eng
中图分类各种核反应堆、核电厂;
关键词
hydrogen; weld metal; nickel; inconel; welding; fracture; toughness; stress; stress intensity factor;

机译：氢;焊接金属镍;铬镍铁合金焊接;断裂;韧性;强调;应力强度因子;
入库时间 2022-08-26 13:59:49

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专利

1. Investigations On Crack Propagation Under Cyclical Isothermal And Thermo-mechanical Loadings For A Type 304-L Stainless Steel Used For Pressurized Water Reactor [J] . Cédric Gourdin, Gregory Perez, Patrick Le Delliou, MATEC Web of Conferences . 2018,第3期

机译：压水堆用304-L不锈钢在循环等温和热机械载荷下裂纹扩展的研究
2. Investigation of temperature fluctuation phenomena in a stratified steam-water two-phase flow in a simulating pressurizer spray pipe of a pressurized water reactor [J] . Miyoshi Koji, Takenaka Nobuyuki, Ishida Taisuke, Nuclear Engineering and Design . 2017,第MAY期

机译：压水堆模拟增压器喷水管内分层汽水两相流温度波动现象研究
3. Intergranular Stress Corrosion Cracking growth perpendicular to fatigue pre-cracks in T-L oriented compact tension specimens in simulated Pressurized Water Reactor primary water [J] . Yaguchi Seiji, Yonezawa Toshio Corrosion science . 2014,第sepa期

机译：在模拟压水反应堆一次水中，T-L取向致密拉伸试样中与疲劳预裂纹垂直的晶间应力腐蚀裂纹扩展
4. LOW TEMPERATURE CRACK PROPAGATION EVALUATION IN PRESSURIZED WATER REACTOR SERVICE [C] . A. Demma, A. McIlree, M. Herrera International Conference on Environmental Degradation of Materials in Nuclear Power Systems: Water Reactors . 2005

机译：加压水反应堆服务中的低温裂纹繁殖评价
5. Environmentally induced cracking in Alloy 600 and SA 302 steel in pressurized water reactor steam generator conditions. [D] . Rebak, Raul Basilio. 1993

机译：在压水堆蒸汽发生器条件下，合金600和SA 302钢在环境中引起的开裂。
6. Kinetic evaluation of a partially packed upflow anaerobic fixed film reactor treating low-strength synthetic rubber wastewater [O] . I. Nor Faekah, S. Fatihah, Zawawi Samba Mohamed 2020

机译：部分填充上流厌氧固定膜反应器处理低强度合成橡胶废水的动力学评价
7. Corrigendum to “A mechanistic study of the temperature dependence of the stress corrosion crack growth rate in SUS316 stainless steels exposed to pressurized water reactor primary water” Acta Mater. 114 (2016) 15–24 [O] . Martina Meisnar, Arantxa Vilalta-Clemente, Michael Moody, 2016

机译：勘探为“应力腐蚀裂纹裂纹率温度依赖性的机械研究，暴露于加压水反应器初级水”Acta Mater。 114（2016）15-24
8. Effect of Pressurized Water Reactor Environment on Fatigue Crack Propagation, Including Hole Times [R] . Bamford, W. H. 1976

机译：加压水反应器环境对疲劳裂纹扩展的影响

LOW TEMPERATURE CRACK PROPAGATION EVALUATION IN PRESSURIZED WATER REACTOR SERVICE

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