Standard Requirements and Localization Development Trend for Nuclear Power Plant Key Components Material

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The production capacity of Nuclear Island Mechanical Components (NIMC) falls far behind of massive demand of nuclear power increasement. To achieve the goal of nuclear power development in China, the localization progress of key NIMC needs to be speeded up. Taking material of NIMC (not including nuclear fuel and related material) for example, through the analysis and discussion of the standard or norm, status quo of supply and research, production capacity and existing problems of material of NIMC in China, the major obstacles and factors restricting development of nuclear power plant are found out, and the countermeasures and suggestions are also introduced to accelerate the localization progress of key NIMC in this paper.

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Periodical:

Edited by:

Fangping Zhang

Pages:

406-409

Citation:

S. J. Zhang et al., "Standard Requirements and Localization Development Trend for Nuclear Power Plant Key Components Material", Applied Mechanics and Materials, Vol. 628, pp. 406-409, 2014

Online since:

September 2014

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[1] Gu Junyang, Shi Wen. At the present stage of China's development of nuclear power reactor type selection [J]. China electric power, 2006, 39 (1): 50-54. [In Chinese].

[2] 杨孟嘉,任俊生,周志伟. 未来10年核电先进堆型介绍[J]. 国际电力,2004,8(3): 32-35.

[2] Yang Mengjia, Ren Junsheng, Zhou Zhiwei. The next 10 years the introduction of advanced nuclear reactors [J]. international electric power, 2004, 8 (3): 32-35. [In Chinese].

[3] 邹树梁. 世界核电发展的历史、现状与新趋势[J]. 南华大学学报(社会科学版),2005,6(6): 38-42.

[3] Zou Shuliang. The world nuclear power development history, present situation and trend [J]. Journal of University of South China (SOCIAL SCIENCE EDITION), 2005, 6 (6): 38-42. [In Chinese].

[4] 吴宗鑫,张作义. 世界核电发展趋势与高温气冷堆[J]. 核科学与工程,2000,20(3): 211-219.

[5] 广东核电培训中心编. 900MW压水堆核电站系统与设备[M]. 原子能出版社,(2005).

[4] Guangdong Nuclear Power Training Center. 900MW PWR nuclear power plant system and equipment [M]. Atomic Energy Press, 2005. [In Chinese].

[6] 上海发电设备成套设计研究院. 压水堆核电站核岛主设备材料和焊接[M]. 上海科学技术文献出版社,(2008).

[5] Shanghai power equipment research institute. The pressurized water reactor nuclear power station nuclear island main equipment and materials and welding of [M]. Shanghai science and Technology Press, (2008).

[7] 李士模,汤美玲,朱正清. 核电厂核岛机械设备材料标准的现状及对材料标准的需求(上) [J]. 核标准计量与质量 , 2003, (1): 13-23.

[6] Li Shimo, Tang Meiling, Zhu Zhengqing. Current situation of nuclear island equipment material standard and requirement for material standard (on) [J]. nuclear standards and Metrology and quality, 2003, (1): 13-23.

[8] 李士模,汤美玲,朱正清. 核电厂核岛机械设备材料标准的现状及对材料标准的需求(下)[J]. 核标准计量与质量 , 2003, (2) : 9-20.

[7] Design and construction rules for mechanical components of PWR nuclear islands (RCC-M)[S]. French association for design, construction and in-service inspection rules for nuclear island components (AFCEN): Edition 2000 & addendum June (2002).

DOI: https://doi.org/10.1016/0029-5493(91)90134-4

[8] ASME boiler and pressure vessel code [S]. American society of mechanical engineers, 2004 Edition.

[11] 杨武. 核电工业的发展及其对腐蚀防护技术的需求[J]. 腐蚀与防护 , 1997,18(03): 3-7.