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Components Qualification for the Safe Operation of Nuclear Power Plants

Components Qualification for the Safe Operation of Nuclear Power Plants

作     者:Holger Schmidt Martin Beetz Ingo Ganzmann Achim Beisiegel Thomas Wagner Christian Bonneau Darryl Gordon Sun Jing 

作者机构:AREVA GmbH-Thermal Hydraulics and Components Testing Paul-Gossenstr 100 Erlangen 91052 Germany ARE VA GmbH-Thermal Hydraulics and Components Testing Seligenstadter Strasse 100 Karlstein 63791 Germany AREVA SAS-Thermal Hydraulics and Components Testing 30 boulevard de l'Industrie Le Creusot 71205 France ARE VA Inc.-Thermal Hydraulics and Components Testing 3315 Old Forest Road Lynchburg VA 24501 USA Keysur International F11 Tower A Millennium Plaza No. 72 Beijing 100037 China 

出 版 物:《Journal of Energy and Power Engineering》 (能源与动力工程(美国大卫英文))

年 卷 期:2016年第10卷第10期

页      面:581-590页

学科分类:0711[理学-系统科学] 080802[工学-电力系统及其自动化] 0808[工学-电气工程] 07[理学] 081104[工学-模式识别与智能系统] 08[工学] 0811[工学-控制科学与工程] 071102[理学-系统分析与集成] 081103[工学-系统工程] 

主  题:Components testing nuclear qualification thermal hydraulics testing nuclear safety 

摘      要:AREVA operates a world-wide unique thermal hydraulic platform to ensure high safety standards in the nuclear industries. This platform is operated as an accredited test and inspection body according to ISO 17025 and 17020 to grant a high and independently confmned quality standard. The accreditation also ensures the independency of the organization and confidentiality to the individual stakeholders, for example research centers, utilities, components suppliers, engineering companies and vendors. Especially for nuclear power plants, it is very relevant to consider that reliability depends on the integrity of its components during its life time-from design through construction, operation and maintenance. For example, a typical NPP (nuclear power plant) has 1,000 to 2,000 large valves and 7,500 to 12,500 small valves, of which about 200 to 400 are designated Safety Class 1. The qualification of these Safety Class 1 components is relevant for reactor new builds but also for installed plants. This paper explains newly established qualification tasks, the corresponding testing infrastructure, and the state of the art of testing technology. By way of example, the paper describes the program and possible sequence of qualifying NPP safety-related components.

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