[en] New methods of radioactive labelling - improved methods of investigation are necessary to get a better insight into the various mechanisms of physical and chemical processes. One such refined method is the tracer technique with broad application in research and industry. The successful practical application of this technique depends upon the development of suitable equipment. This paper deals with two automatic apparatus for use in process control. (orig.)

No abstract available

[en] 81 abstracts on autoradiography in pharmacology and toxicology were presented, divided into six sessions concerning: 1) methods 2) hormones and receptors, 3) drugs, 4) toxicology, 5) metals, 6) fetal distribution. (author)

No abstract available

[en] The schedule calls for hot operation of two waste repositories by the end of 1985, and these facilities will have to be licensed. This licensing requirement sets the commercial program apart from the ERDA defense waste program. Packaging criteria are discussed for commercial and ERDA wastes. The different NRC, DOT, and EPA criteria are considered

[en] The German, English and Russian versions of 228 terms relating to radioactive wastes are listed

[en] It is shown that the fusion reactor often evoked as the ideal ''clean'' energy source may involve some serious surprises in the field. Indeed, the reaction from which two hydrogen atoms merge to form an helium atom with an energy release does not create itself any radioactive ashes. However the fast neutrons emitted that carry away 80% of the energy, interact with the matter. Some of the atoms from the bombarded materials are converted into radioisotopes of long period that might constitute cumbersome dangerous residues. An ecological problem also arises in relation with the large amounts of tritium to be confined

[en] This invention relates to apparatus for and a method of sorting ore having a radio-active component. The method includes the steps of passing a stream of ore particles through a ring detector to detect ore in the stream having a radio-active emission intensity above a predetermined level and then sorting this ore from the remainder of the ore in the stream. Preferably the invention includes the step of determining the mass of each ore particle and correlating the mass and radio-active emission measurements of the particle to determine its grade

[en] The packing and transport container is designed and constructed as a self-sealing safety container.It consists of two major parts, the bottom part and the bell-shaped upper part which can be connected with each other by a seal and quick-action clamping elements. The upper part is a self-supporting lifting unit and has carrying elements inside which match with carrying elements on the structural member to be transported. The upper part can consist of telescopically interlocking components in order to adapt to the shape of the structural member. The components are again sealed by means of sealing elements. To serve as a protective screen, the container can be lined inside and outside with lead. (ORU)

[en] The effect of fission-product accumulation on the central sodium-void worth has been measured, using four different materials, B₄C, Mo, Nb and the Shroeder FS mixture for simulating the fission products. The measured results show that the per cent increase of sodium-void worth with burnup increase simulated using the FS mixture differs significantly from those simulated by the other materials - B₄C, Mo and Nb. Analysis of the measured result indicates that (1) the reactivity changes due to the distribution of these four materials in the central region of core are predicted fairly well. This was expected from the good agreement between measured and calculated sample reactivity worths of the fission products obtained at STEK in the Netherlands; (2) the effect on the sodium-void worth measured using the FS mixture was not predicted to be different from those measured by using other materials. Therefore, the effect of cross-section uncertainty in the simulation materials on the sodium-void worth was investigated by means of sensitivity analysis in the 70 energy-group structure. The sensitivity analysis indicates that the sodium-void worth is sensitive to the capture cross-section of the fission products in the vicinity of the dominant sodium resonance at 2.8 keV. Therefore, to reach a definite conclusion on the sodium-void worth from the measured results, it is necessary to examine the influence of the resonance cross-section of the FS mixture, especially that of ¹⁴²Nd which is contained in the FS mixture, but not in the real fission products. It is concluded from the analysis that more accurate information on the resonance cross-section of the fission products, especially in the vicinity of 2.8 keV, is necessary to predict the sodium-void worth in high burnup cores. (author)