Cracking of 08X18H10T steel and XH35VT alloy used in steam generators in nuclear power plants

R. K. Melekhov; Kh. Tubilevich; O. D. Smiyan; L. M. Karvatskii; A. M. Krutsan; L. V. Kapinos

首页> 外文期刊>Защита Металлов >Cracking of 08X18H10T steel and XH35VT alloy used in steam generators in nuclear power plants

【24h】

Cracking of 08X18H10T steel and XH35VT alloy used in steam generators in nuclear power plants

机译：核电站蒸汽发生器中使用的08x18H10T钢和XH35VT合金的开裂

获取原文

获取原文并翻译 | 示例

掌桥外文数据库（机构版） >>

开具论文收录证明 >>

文献代查 >>

页面导航

著录项
相似文献
相关主题

著录项

来源
《Защита Металлов》 |1998年第3期|共12页
作者
R. K. Melekhov; Kh. Tubilevich; O. D. Smiyan; L. M. Karvatskii; A. M. Krutsan; L. V. Kapinos;
展开▼
作者单位

展开▼
收录信息
原文格式 PDF
正文语种 rus
中图分类金属腐蚀与保护、金属表面处理;
关键词

相似文献

外文文献
中文文献
专利

1. Cracking of 08X18H10T steel and XH35VT alloy used in steam generators in nuclear power plants [J] . R. K. Melekhov, Kh. Tubilevich, O. D. Smiyan, Защита Металлов . 1998,第3期

机译：核电站蒸汽发生器中使用的08X18H10T钢和XH35VT合金的开裂
2. Corrosion and electrochemical investigations of low-alloyed and austenitic stainless steel used in the steam generators of Kozloduy nuclear power plant [J] . G. M. Raichevski, N. D. Tsvetkova, N. S. Boshkov, Bulgarian chemical communications: Journal of the Chemical Institutes of the Bulgarian Academy of Sciences and of the Bulgarian Chemical Society . 2008,第3期

机译：Kozloduy核电站蒸汽发生器中使用的低合金和奥氏体不锈钢的腐蚀和电化学研究
3. The Effects of a Lithium-Ferritic Film on Slowing Down Corrosion Cracking of Heat-Exchange Tubes of Steam Generator at Nuclear Power Plants with VVER Reactors [J] . S. O. Ivanov, V. P. Gorbatykh Thermal engineering . 2007,第4期

机译：铁锂薄膜对带VVER反应堆的核电厂蒸汽发生器换热管减缓腐蚀开裂的影响
4. Crack Initiation Factor by Impact Fretting Wear at INCONEL Alloy for Steam Generator Tube in Nuclear Power Plants [C] . Chi Yong Park, Jeong Kun Lee, Tae Ryong Kim Pacific Rim International Conference on Advanced Materials and Processing . 2007

机译：核电站蒸汽发生器管Inconel合金中的冲击发起因子裂纹启动因子
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. Simulating Porous Magnetite Layer Deposited on Alloy 690TT Steam Generator Tubes [O] . Soon-Hyeok Jeon, Yeong-Ho Son, Won-Ik Choi, 2018

机译：模拟沉积在690TT合金蒸汽发生管上的多孔磁铁矿层
7. Growth Model of Circumferential Outer Diameter Stress Corrosion Crack in Retired Steam Generator Tube of Kori 1 Nuclear Power Plant [O] . Dong-jin Kim, Hong Pyo Kim, Joung Soo Kim, 2015

机译：Kori 1核电厂退役蒸汽发生器管周向外径应力腐蚀裂纹扩展模型
8. Tests of Types 51A and 51M Steam Generators at Bugey 4 and Tricastin 1 Nuclear Power Plants. Final Report [R] . Procaccia, H., David, J., de Penguern, L., 1982

机译：Bugey 4和Tricastin 1核电站的51a和51m型蒸汽发生器的试验。总结报告

Cracking of 08X18H10T steel and XH35VT alloy used in steam generators in nuclear power plants

著录项

相似文献

相关主题

期刊订阅