[en] The accounting and safeguards system for nuclear materials used at the Rossendorf Central Nuclear Research Institute is based on national directives and decrees. The adaptation of the system to the Safeguards Agreement with the Agency, in connection with the accession of the German Democratic Republic to the Treaty on the Non-Proliferation of Nuclear Weapons, has merely required some minor amendments: at the same time, however, it has made necessary extensive preliminary work for the purpose of devising the clearest possible and non-time-consuming method of recording data. Experience already gained indicates that the safeguards system as developed fulfils its purpose. The overall labour requirement is about 0.5 man-years. Work is being done to improve the system further by cutting down the time expended. Besides giving a general description of the system, the authors discuss the data forms used in operating it. (author)

[en] Short communication

[en] The Rossendorf RRRJSEG configurations characterized by, energy-independent or continuously rising adjoint spectra have been recalculated using the full European scheme JEF2/ECCO/ERANOS. C/E-values are given for structural materials and fission product nuclides using the results of sample reactivity measurements at the central position of these configurations. Due to the specially designed adjoint spectra, capture or scattering cross- sections can be checked separately. Recommendations for data corrections are given based on perturbation theory calculations

[en] A short overview of the main characteristics of research and training reactors of GDR is given, including a description of their main use and fuel enrichment. From the point of view of Non - Proliferation Treaty and Physical Protection Agreements no objections exist against the use of MEU - fuel in two of the five research and training reactors. (orig.)

No abstract available

[en] Important preparatory work has been completed, so that decommissioning and dismantling work according to the decommissioning plan can be continued in 1998. The required licensing procedures turned out be more complicated and time consuming than expected and considerably influenced the progress of activities. Completion of the installations on site for radwaste management required relatively large technical and financial efforts and were successfully completed with a part permit for comissioning of the systems. Thus the physical protection level for nuclear materials on site was basically improved and the former, very inconvenient restrictions of access to the research site were lifted. (orig./CB)

[en] Important preparatory work has been completed, so that decommissioning and dismantling work according to the decommissioning plan can be continued in 1998. The required licensing procedures turned out be more complicated and time consuming than expected and considerably influenced the progress of activities. Completion of the installations on site for radwaste management required relatively large technical and financial efforts and were successfully completed with a part permit for commissioning of the systems. Thus the physical protection level for nuclear materials on site was basically improved and the former, very inconvenient restrictions of access to the research site were lifted. (orig./CB)

[en] Published in summary form only

[en] The GDR operates 5 research and training reactors: RFR, a 10 MW light water cooled and moderated reactor of the Soviet WWR-S type; RRR a zero power Argonaut type; RAKE a light water moderated and reflected tank type; ZLFR a 10 W tank type; AKR a 1 W solid homogeneous type. Activities include reactor physics, neutron diffraction, radioisotope production (40,000 packages per year), silicon transmutation doping, education and training. A computer based reactor control system is also described. (author)

[en] Up to now it is impossible to calculate completely the safety of nuclear reactors. Therefore the authors have collected and employed a number of at a high degree independent safety parameters for mathematical evaluation of the reactor safety. By means of computer programs such parameters from about 400 research reactors have been analysed and the fluctuation ranges of their greatest density were determined. The limits of these fluctuation ranges are quickly available and can be used as recommended values for the layout and for the safety estimation of research reactors. A comparison of the existing layout recommendations and the determined fluctuation ranges in most cases shows a good agreement. In some cases corrections and new layout recommendations have been proposed. The determined fluctuation ranges found their first practical application in the estimation of the Rossendorf Equipment for Critical Experiments (RAKE). (author)