[en] Decontamination is becoming more and more important within the framework of procedural development for inspection and repair. To meet ALARA requirements, increasing dose rates of nuclear power plants with age make efforts to reduce occupational radiation exposure by decontamination essential. Steadily increasing attention is therefore being given to plant components or, better still, entire systems and loop decontamination. Furthermore, decontamination of a whole system or of a complete primary loop is sometimes easier to perform than cleaning of a single component. Since Siemens offers several decontamination processes there is always a single process or a combination of processes available to meet the specific requirements of a decontamination task. For decontamination of a complete system it is obvious that the process to be applied should be 'soft', i.e., low concentration. Use of a high chemical concentration 'hard' process would lead to too large amounts of waste. Due to problems and costs associated with waste handling for the decontamination of dismantled components, soft decontamination processes have now also been developed and applied. 1 fig., 2 tabs

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[en] Since the ALARA principle was introduced explicitly as a cornerstone of the dose limitation system recommended by ICRP about 15 years ago, an extensive volume of work has been devoted worldwide first to its interpretation then to its implementation. Within the European context, all along this period, the CEPN and the NRPB (UK) with the support of the CEC and in close cooperation with the nuclear industry, have been very active in the promotion of the principle through publications and participation in conferences and training. In this perspective, the present paper reflects the views of the two organisations on the current ALARA developments with regard to some concepts and techniques. This paper also elucidates the conceptual framework underlying ALARA tools and delineates the basic functions they have to fulfil to be really effective. (Author)

[en] The basis of present day radiation protection regulation, based on the recommendations of the International Commission on Radiological Protection is reviewed

[en] Early ICRP recommendations were interpreted as putting the emphasis on individual dose limits, with no particular incentive to reduce individual doses much below the limit, even though some of the recommendations implied an ALARA approach. Current ICRP recommendations can be interpreted as requiring collective doses to be minimised without special regard for individual doses, provided that they are all below the limit. In spite of these different emphases, the operational health physicist appears to have applied a form of ALARA with emphasis on individual doses throughout the period. It is suggested that for both practical and social reasons emphasis needs to be put on reducing individual doses and sharing the exposures evenly among the work force. To this end a modified ALARA formula is suggested, that places the emphasis on individual doses, but includes collective doses. 14 refs. (Author)

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[en] This paper discussed an overview of nuclear safety. Among the topics emphasized were radiation risks estimates from three study groups, ALARA and radiation standards set up by the ICRP and the U.S. NCRPM. (ELC)

[en] This report makes part of a series of eight reports which have been drawn up in behalf of the dutch Policy Notition Radiation Standards (BNS). The aim of the project with which this report deals, is to assess an accountability system for application of ALARA (As Low As Reasonable Achievable)/optimisation and from these forthcoming bottlenecks. Herein (for this subproject) ALARA is defined as optimization of radiation protection below a risk limit which is to be assessed in another framework. In ch. 2 this discussed further. First it is indicated which categories applications/activities are to be distinguished. Then the elements of the accountability system are elaborated further. In ch. 3 a discussion is given of the actual legislation, the actual policy (national and international), the practice developed with regard to ALARA/optimization and the boundary condition forthcoming from these. In ch. 4 finally the results of ch. 2 are enlightened upon governmental consequences against the background of the actual situation, outlined in ch. 3. In behalf of the insight in the actual practice of ALARA/optimization and the governmental consequences of the in ch. 2 elaborated system interviews have been made with radiation-protection specialists. These are summarized in appendix 2. (H.W.)

[en] The existence of an International Information System on Occupational Exposure (ISOE) would facilitate the ability of participants to get access to up-dated information on radiation protection matters including dose-saving methods, task-related doses, etc. The Pilot Project described was set up in order to apply on an experimental basis the scheme proposed for the ISOE System, and to demonstrate the feasibility of an interest in setting it up. It included the participation of nuclear electric utilities from eight countries. The Brookhaven National Laboratories (BNL) in the United States and the CEPN (Centre d'etudes sur l'evaluation de la protection dans le domaine nucleaire) in France acted as Technical Centres, i.e., provided the technical services to the Pilot Project and developed the necessary computer software for data handling and management. (Author)

No abstract available