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[en] At decommissioning, some accelerators leave a legacy of low-level induced radioactivity in massive components. Although guidelines for acceptable surface contamination levels for release of materials and equipment to the general public do exist, there are presently no standards for release of materials and equipment with radioactivity distributed throughout their volumes. The decommissionings of five AEC-funded accelerators were examined. One common feature of these decommissionings was that major components usually were assigned and shipped for use or storage at other accelerator laboratories. In addition to reviewing selected past decommissionings, the authors also examined various aspects of decommissioning accelerators presently operating. The estimated cost ($ 1978) of decommissioning ranges from $8.8 x 104 for an electron linac to $7.0 x 106 for the ZGS
Journal
IEEE Transactions on Nuclear Science; ISSN 0018-9499; 
; v. NS-26(3); p. 4286-4288
; v. NS-26(3); p. 4286-4288
[en] The hydrological and orographic situation of Austria is described. Water quality and the organization of its control are discussed. The results of these investigations are converted into water quality maps issued in regular intervals. The importance of pollution abatement in lakes is mentioned. The Austrian Danube is taken as a typical example of a conventionally polluted river. Complications arising from the construction of hydroelectric plants are discussed and the different sedimentation and the risks of deoxygenation are considered. The radiological control of inland waters was started in 1961 after the nuclear test series. The data collected from 16 sampling points at monthly intervals serve now as the guideline for the issue of licences for nuclear power plants and the limits for radiological releases. The radiological data so far collected by the Federal Ministry of Health and Environmental Protection cover atmospheric and aqueous contamination. A Federal Law regulates the maximum permissible impacts on the population and the environment. All relevant data are issued regularly by the above mentioned Ministry. The influence of already existing and planned nuclear power stations in the neighbouring countries (upstream of Austria: Switzerland, Federal Republic of Germany, Czechoslovakia) is considered. Radiological control in connection with the first Austrian nuclear plant (capacity 700 MW) and the following ones is discussed. The initiatives of several international organizations to install a multinational control system are mentioned. The system would be planned for all riparian countries of the Danube catchment area. (author)
Source
International Atomic Energy Agency, Vienna (Austria); Proceedings series; p. 395-402; ISBN 92-0-020375-2; ; 1975; IAEA; Vienna; International symposium on radiological impacts of releases from nuclear facilities into aquatic environments; Otaniemi, Finland; 30 Jun 1975; IAEA-SM--198/36
; 1975; IAEA; Vienna; International symposium on radiological impacts of releases from nuclear facilities into aquatic environments; Otaniemi, Finland; 30 Jun 1975; IAEA-SM--198/36
[en] In most countries discharge limits are still determined as from permissible maximum concentrations. But allowing for radioecological data in the adaptation to concrete cases is still to a large extent a question of practice. A trend is emerging, particularly in the Federal Republic of Germany and in the United States, to replace the PMC's by an immission principle or the 30m/rem, consisting in setting a potential exposure limit of the surrounding population, given the radioecological conditions
Source
CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Dept. de Protection; Electricite de France, 75 - Paris. Dept. Etudes Generales Programmes-Sites Environnement; 774 p; ISBN 2-7272-0050-1; ; 1980; p. 95-116; CEA; Cadarache, France; 2. International symposium on radioecology; Cadarache, France; 19 - 22 Jun 1979; Available from Service de Documentation, CEN Cadarache, BP no.1, 13115, Saint-Paul-lez-Durance (France)
; 1980; p. 95-116; CEA; Cadarache, France; 2. International symposium on radioecology; Cadarache, France; 19 - 22 Jun 1979; Available from Service de Documentation, CEN Cadarache, BP no.1, 13115, Saint-Paul-lez-Durance (France)
[en] The strategy developed here permits standard values for contaminated skin to be derived from previously determined threshold for the relevant body dose. Those standards can only be set up following calculation of dose-equivalent-rate factors, on the basis of which threshold values for the dermal dose may be expressed as standard values for skin decontamination measures. The strategy offers the possibility of performing the required decontamination using a suitable, non-aggresive method that excludes any unnecessary or untoward measures. A dose of 10 bq/cm2 as a standard value for beta-radiating materials is a reliable criterion in any decisions on further measures to be taken, as it is compatible with radiation protection requirements and also an answer to legal questions concerning the general behaviour in the event of unremovable contaminations. (orig./HP)
[de]
Es wird ein Konzept fuer die Ableitung von Richtwerten fuer die Kontamination der Haut aus den bereits vorhandenen Grenzwerten der Koerperdosis aufgestellt. Voraussetzung dafuer ist die Berechnung von Aequivalentdosisleistungsfaktoren, mit denen die Grenzwerte der Hautdosis in Richtwerte fuer Massnahmen zur Hautdekontamination umgerechnet werden koennen. Das Konzept bietet in Verbindung mit geforderten Dekontaminationsmassnahmen die Moeglichkeit einer schonenden, unnoetige Massnahmen ausschliessenden Hautdekontamination. Die Benutzung eines Richtwertes von 10 Bq/cm2 fuer Beta-Strahler stellt eine Entscheidungshilfe fuer weitere Massnahmen dar, die fuer den Strahlenschutz ausreichend sicher ist und die Rechtsunsicherheit ueber das Verhalten nach nicht entfernbaren Kontaminationen beseitigt. (orig./HP)Source
Gumprecht, D.; Kindt, A. (Bundesamt fuer Strahlenschutz, Geschaeftsstelle der Strahlenschutzkommission, Bonn (Germany)); Kemmer, W.; Johnke, G. (Bundesministerium fuer Umwelt, Naturschutz und Reaktorsicherheit, Bonn (Germany)) (comps.); Bundesministerium fuer Umwelt, Naturschutz und Reaktorsicherheit, Bonn (Germany); Veroeffentlichungen der Strahlenschutzkommission; v. 18; 149 p; ISBN 3-437-11450-6; ; 1992; p. 107-120; G. Fischer; Stuttgart (Germany)
; 1992; p. 107-120; G. Fischer; Stuttgart (Germany)
[en] Dismantling activities began in 1988; they will give rise to some 500 Mg of activated steel not exceeding 2.105 Bq/g. Under the German Atomic Energy Act and the requirements expressed by the German Advisory Committee on Radiological Protection, dismantled parts and components of the plant with up to 0.1 Bq/g and, under some conditions, up to 1.0 Bq/g, must be reused safely. The Bavarian Technical Inspectorate (TUeV Bayern) examined KKN and defined clearance levels for recycling and reuse. Dismantling will be finished with the recultivation of the site probably in early 1994. (orig./HP)
[de]
Im Jahre 1988 wurde mit den Demontagearbeiten begonnen, bei denen ca. 500 Mg aktivierter Stahl mit im Mittel ca. 2.105 Bq/g, ca. 500 Mg aktivierter Beton mit im Mittel ca. 7 Bq/g und ca. 1 700 Mg kontaminierter Stahl und Beton mit im Mittel ca. 60 Bq/g anfallen. Gemaess Atomgesetz wird fuer abgebaute Anlagenteile und Komponenten eine schadlose Verwertung, bzw. falls das nicht vertretbar ist, eine Beseitigung als radioaktiver Abfall gefordert. Der TUeV Bayern hat KKN begutachtet und Freigabegrenzwerte fuer die Verwertung festgelegt. Die Demontage wird mit der Rekultivierung des Gelaendes voraussichtlich Anfang 1994 abgeschlossen sein. (orig./HP)Journal
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