مدیریت مادام العمر برای سیستم های مکانیکی، ساختار ها و قطعات در نیروگاه های هسته ای

Guidelines, codes and standards contain regulations and requirements with respect to the quality of mechanical systems, structures and components (SSC) of nuclear power plants. These concern safe operation during the total lifetime (lifetime management), safety against ageing phenomena (ageing management) as well as proof of integrity (e.g. break exclusion or avoidance of fracture). Within this field the ageing management is a key element. Depending on the safety-relevance of the SSC under observation including preventive maintenance various tasks are required in particular to clarify the mechanisms which contribute system-specifically to the damage of the components and systems and to define their controlling parameters which have to be monitored and checked. Appropriate continuous or discontinuous measures are to be considered in this connection. The approach to ensure a high standard of quality in operation and the management of the technical and organisational aspects are demonstrated and explained.

In most countries it has been stipulated that the licensing of nuclear power plants and their subsequent operation is based mainly on proof of the plant safety (e.g. strength analysis for operational conditions, postulated accidents, etc.). In Germany the atomic energy act [1] requires that “every necessary precaution has been taken in the light of existing scientific knowledge and technology to prevent damage resulting from construction and operation of the installation”. This has been realised in guidelines and in the nuclear standards [2], [3] and [4] with their indications and requirements for plant safety. According to these documents it has to be ensured that: • safety with respect to the quality of the systems, structures and components (SSC) is provided by the design, the material and the manufacture; • the quality of the SSC has to be guaranteed and documented throughout the lifetime (extensive quality assurance during design, manufacture, and operation); • the operational parameters (damage mechanisms) relevant for the integrity of the SSC are monitored and • operational experience is recorded continuously and safety-related information is evaluated.

Guidelines, codes and standards contain regulations and requirements with respect to the quality of mechanical SSC of nuclear power plants. This concerns safe operation during the total lifetime (lifetime management), safety against ageing phenomena (ageing management) and proof of integrity (e.g. break exclusion). Within this, ageing management is a key element. Depending on the safety-relevance of the SSC under observation, including preventive maintenance, various engineering measures are required. In particular to be considered in this connection are the mechanisms which contribute system-specifically to the damage of the mechanical SSC and define their controlling parameters which have to be monitored and supervised by appropriate continuous or discontinuous measures. The approach to assure the high standard of quality in operation and the processing of the technical and organisational aspects are demonstrated and explained.