[en] It is proposed to mix biologically harmful wastes, especially radwaste, with cement directly in the drum intended for ultimate storage. In order to avoid propagation of contamination a stirring device is used consisting of a freely movable and a fixed part and being left in the drum as a 'lost' agitator. The freely movable piece has got a closed frame with several staggered stirring arms and a middle axis consisting of an interrupted hollow rod; it is axially guided by the fixed part. Using this device a homogeneous mixture suited for ultimate storage is obtained in the standard drums. (RB)

No abstract available

[en] This paper reviews the problems created by the recent recommendations of SI-units for radiological quantities. Risk-cost-benefit studies clearly point out the need for rethinking, long trials, careful reevaluation of the situation and for long, well planned transition periods once a suitable solution has been found. The solution will almost certainly be a compromise between the 'old' and new units. Examples from other applications of SI-units show that such compromises are quite common for practical reasons. The units rad, rem and Curie can be defined as multiples or fractions of the proposed new basic units and thus can be given a status of special units and be used besides 'Gray' and 'Becquerel'. Several recent proposals of that kind are discussed. IRPA is asked to initiate a comprehensive program for the study and evaluation of these problems by working groups of the associate societies and of IRPA as a whole. Suitable investigation and test programs should be carried out over several years in order to collect and evaluate the practical experiences and problems of the use of 'old' and new units. On this basis a solution should be proposed and submitted to the associate societies for approval before transmittal to the appropriate international bodies. IRPA is also asked to take steps to prevent future solitary actions of international committees without prior and proper consultation and cooperation of IRPA, ICPR and ICRU

[en] A method is described for embedding high- or medium-level radioactive wastes in a metallic (Al or Al-Mg alloys) matrix for terminal storage by pressing the waste with a metal powder at room temperature to form a molded substance. The retention capabilities for radioactive materials is improved by using an insert or an internal coating in the terminal storage container. (orig./PW)

[en] The range of activities of the Technical Association includes practical radiation protection, the promotion of research and technology, education and training, collaboration in drafting laws and standards, and information for the public. This publication gives an idea of the historical development of the Technical Association and shows the many areas of work, its international relationships and its events and publications. (DG)

No abstract available

[en] Radioactive, particularly tritium-containing, waste must be stored in such manner that the environment is not endangered. This is done by conditioning the waste and embedding it in concrete whereby a central temperature of the product of 90-95⁰C. must not be exceeded and therewith a dilution is necessary. These difficulties are overcome by inserting the waste in a metal matrix so that the waste is pressed with a metal powder at room temperature to molded bodies

[en] The waste which is cold formed into shapes with aluminium or high quality steel powder at room temperatures is inserted into high quality steel cans for final storage. (DG)

[en] To separate cations, especially alkaline earth metals, lanthanides and actinides, synthetic crandallites of the standard composition Me-Al₃(PO₄)(OH)₅.H₂O (Me=alkaline earth metal) are applied, pH values being greater than 6 and temperatures lying above 40⁰C. There are several production modes for crandallites featuring as elements of patent claims. (orig./RB)

[en] During the R and D program on quality assurance, started in 1979 and carried on in 1982-85 by NUKEM, experimental tests for ensuring the final storage of low level and medium level radioactive waste were carried out. The focal point was the characterization of the cemented and other forms of solid waste from reprocessing and the quality assurance by means of process control and product control, especially with regard to the planned ultimate disposal of the waste in the Konrad and Gorleben repositories. The studies comprised investigations in inactively simulated waste forms on the laboratory scale and on the 1:1 scale. (orig./RB)