The usage of fissile material for nuclear fuel causes that alongside radioactive wastes are produced. These waste materials are created during all handling or usage operations within the nuclear fuel cycle. The main source of radiotoxicity is produced during the usage of nuclear fuel within the reactor. Energy is released by neutron induced fission reactions in heavy isotopes. Parts of the created fission products have large radiotoxicities. Due to neutron capture within the nuclear fuel the radiotoxicity is furthermore increased. These waste streams from the nuclear fuel cycle must be stored in a safe way to prevent any contamination of the biosphere and any harm to the civilization or the environment. The waste packages must be treated and conditioned for the final disposal. These created packages are subject to an independent product control to ensure there acceptability for transport, interim and final storage. The independent product control is a significant component of an effective waste management system. The aim of this work is the development of a software system used for the assessment of radioactive waste packages. The software shall permit the auditor to perform scenario analysis to forecast the product properties of a certain waste stream and therefore optimize the needed inspection scope in preparation of a new campaign. The software is designed as a modular library this permits the most flexible use of the software components and a high reusability of written analysis software. The software system is used for coupling of established and well-known simulation programs used for nuclear systems. The results of Monte-Carlo simulations and burn-up calculations are automatically imported and prepared for user interaction. The usage of simulation programs cause different challenges to the computing infrastructure. The scenario analyses need a large number of parameter variations which are bound to the computing time. For this reason additional to the development of the software system the construction and implementation of a computer cluster was promoted. The design of this system was optimized on the requirements of the simulation programs. This system is used as a platform for future extensions and use cases. To verify the accurateness of the developed software-components several comparative calculations with international benchmarks were performed. The performed calculations and the additional analysis with the created software system show that the results of the benchmarks and the calculations match. These calculations were used to verify the basic quality of the software system. To verify that the software system is capable to be used as a tool for the inspection of radioactive waste products the product properties of the high level glass products from the vitrification plant in Karlsruhe (VEK) were calculated from the available compound documentations. The thermal power as well as the dose-rate for the compounds were calculated using different models. This analysis showed that the calculated and declared product properties are in a good agreement. It was concluded from this benchmark that the created software system is reliable to be used as a tool for the evaluation of radioactive waste products. The software is used for scenario analysis of waste products. This feature is used for the super-compacted metallic waste stream from the reprocessing plants to forcast their product properties. Therefore the basic functionalities of the developed software system were used to create a scenario analysis of the reprocessing plant. This virtual plant contains all necessary processing steps with their material flow and mass balance. The process parameters which affect the material flow were collected from pubic resources. The expected product properties depending on the approved raw waste are valid within the current approved waste product properties. Finally the scenario analysis was extended to test the validity of the current approved product properties for the super-compacted waste stream if the raw waste properties are extended for high burn-up or mixed oxide fuels. These cases are treated separately and discussed in comparison with the current approval of the waste product properties. The approach to implement a software platform for the analysis of radioactive waste products based on top of world-wide accepted and well-known tools was demonstrated in this work. The results of the created software system show that already during the testing phase reliable forecasts about the product properties were achieved. It is assumed that this software system will play a vital role for the product control.
Record of discussions in full wording: Hearing on the Ahaus storage facility for spent-fuel transport containers, June 21-29, 1983. Hearing concerning a project of the Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH, Hannover, and STEAG Kernenergie GmbH, Essen, to establish a long-term storage facility for spent-fuel transport containers in Ahaus, Landkreis Borken, Nordrhein-Westfalen. Pt. 3
This third part of the record of the Ahaus Hearing presents the full wording of the discussions and statements concerning the topics of radiation protection and protection of the environment during operation of the planned facility. The problems considered can be summarized under the following keynotes: Wastes, effluents, environmental monitoring, radiological protection of workers, micro-climate, accidents and their impacts on the environment, site selection, development trends, physical protection, emergency service. The final debates are concerned with the radwaste disposal and management concept of the Federal German Government, with alternative methods or techniques for waste storage, and with the transport of radwaste. The hearing was organized by the PTB in its capacity as a licensing authority under atomic energy law, and this organisation will be responsible of examining and evaluating the objections stated with a view to the requirements set by section 6 of the Atomic Energy Act. (HSCH) [de
Weh, R.; Hakkila, E.A.; Canty, M.J.
A technical workshop on the subject of near-real-time material accounting in an industrial scale reprocessing plant was held. Organized within the context of the US DOE - FR German Ministry of Research and Technology (BMFT) agreement in the field of international safeguards, the workshop was initiated by the Deutsche Gesellschaft fur Wiederaufarbeitung von Kernbrennstoffen, responsible for the construction and operation of a planned industrial scale reprocessing plant in the FR Germany. The workshop's objective was to establish the current state of the art for near-real-time accounting and to bring out a common understanding and consensus among experts from both countries which seve as a basis for the definition of problems still to be solved. A summary of the workshop presentations, preliminary conclusions drawn by the experts attending as well as some implications for the application of dynamic balancing are given
The Institut fuer Neutronenphysik und Reaktortechnik carries out research in nuclear enginering especially in the context of the development of sodium-cooled fast breeder reactors. The institute does theoretical and experimental work in equal shares. Most of the work is done in cooperation with other institutes and industrial groups. In the framework of the Projekt Schneller Brueter , the institute investigates the layout and safety problems, from a reactor physics point of view of large fast breeder cores. Problems concerning the effects of LWR accidents on population and environment are investigated in the Projekt Nukleare Sicherheit . To the Projekt Wiederaufarbeitung , the institute is contributing work on fuel cycle physics and the development of a suitable instrumentation. In the field of nuclear safeguards, the implementation of monitoring systems is being investigated. Research outside projects is being done on technical and physical problems of fusion by inertial confinement and application of nuclear power on the transportation sector with hydrogen as an energy source. The main results obtained in 1980 in the various projects are presented. (orig./RW) [de
Under the waste management concept of the German Federal Government the utilities are to assume responsibility for waste management of the German nuclear power plants within the framework of the polluter pays principle, the ultimate storage of radioactive waste remaining a responsibility of the government. The duties of industry chiefly include planning, construction and operation of the facilities for fuel element storage, reprocessing and waste treatment and for processing the recovered nuclear fuel. The German utilities operating and planning nuclear power plants have set up the Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH (DWK), which is to build the Waste Management Center and also works on the interim solutions planned for continuous waste management up to the completion of the planned Waste Management Center. For this purpose, DWK plans to construct temporary fuel storage facilities and has entered into agreements to secure reprocessing abroad of fuel elements from German nuclear power plants. In discharging its obligations DWK has acquired the extensive know-how available in the Federal Republic in the field of reprocessing spent fuel elements. (orig.) [de
Following the formation of United Reprocessors (U.R.G.) in 1976 by British Nuclear Fuels Limited (B.N.F.L.) in the United Kingdom, the Commissariat a l'Energie Atomique (C.E.A.) in France and K.E.W.A. Kernbrennstoff-Wiederaufarbeitungs-Gesellschaft MBH (K.E.W.A.) in Germany, collaboration is now well established for the marketing of their reprocessing services for irradiated oxide fuel from thermal reactors. In addition collaboration in the continued evolution of the technology has progressed and an extensive research and development programme has been established, the results of which are exchanged between the shareholders. During 1976 the U.K. Government has given approval to B.N.F.L. to sign further contracts with foreign customers, subject to certain conditions. In France, the fuel cycle activities of the C.E.A. have been vested in a new company (Compagnie Generale Des Matieres Nucleaires (C.O.G.E.M.A.)) and their La Hague plant has commenced reprocessing operations on irradiated oxide fuel. In Germany, an agreement has been signed between K.E.W.A. and P.W.K. for the pre-project study for the proposed German plant. Against this background this paper reviews the present status of reprocessing by the shareholders of U.R.G. and the prospects for reprocessing
Goeyse, A. de; De, A.K.; Demonie, M.; Iseghem, P. van
In the framework of a general quality assurance and quality control (QA/QC) programme, the quality of a conditioned waste product is achieved in two phases. The first phase is the design of a process and facility which will ensure the required quality of the product. In the second phase the conformance of the product with the preset requirements is verified. NIRAS/ONDRAF, as the agency responsible for the management of all radioactive waste in Belgium (including treatment, conditioning, storage and disposal), controls compliance with the quality requirements during both phases. The purpose of the paper is to describe the different phases of this general procedure in the case of a vitrified HLW product resulting from a vitrification campaign in the PAMELA facility at the BELGOPROCESS site. The active glass product of type SM527 produced during the vitrification of highly enriched waste concentrate (HEWC) (resulting from the reprocessing of highly enriched uranium fuel) has been selected for illustration. During the process qualification phase, the Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH, responsible for the development of the vitrification process of PAMELA, defined and performed and R and D programmed for each glass product originating from the vitrification of the different HEWC solutions stored at the BELGOPROCESS site. At the end of this qualification phase a data catalogue was prepared. In order to ensure that the active glass product corresponds with the selected product from the data catalogue, the QA/QC handbook for the vitrification process describes all measures to be taken by the waste producer, BELGOPROCESS, during the vitrification. Finally, verification analyses are performed by the characterization of inactive and active samples by an independent laboratory. This phase is called the product quality verification phase. The details of the characterization programmes performed during the different phases and their results