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Sample records for karlsruhe forschungszentrum

  1. InfiniBand-Experiences at the Forschungszentrum Karlsruhe

    Schwickerath, Ulrich; Heiss, Andreas

    2006-01-01

    The Institute for Scientific Computing (IWR) at the Forschungszentrum Karlsruhe has been evaluating the InfiniBand [InfiniBand Trade Association, InfiniBand Architecture Specification, Release 1.0, October 24, 2000] technology since end of the year 2002. The performance of the interconnect has been tested on different platforms and architectures using MPI. Sequential file transfer performance was measured with the RFIO protocol running on native InfiniBand [Ulrich Schwickerath, Andreas Heiss, Nucl. Instr. and Meth. A 534 (2004) 130, http://www.fzk.de/infiniband], and a newly developed InfiniBand-enabled version of the XROOTD

  2. Past and present situation of nuclear research at Forschungszentrum Karlsruhe

    Scholtyssek, W.

    2001-01-01

    The case of Forschungszentrum Karlsruhe is presented which had to transform from a centre devoted to nuclear power R and D to one in which this activity is allocated only 20% of the resources. A large number of operating nuclear power reactors coupled with the Government decision to phase out nuclear power is causing serious concerns regarding the availability of human resources for meeting the long term needs of nuclear facilities. The Energy Division of the research centre currently focuses mainly on safety research and on nuclear fusion. Another Division of the centre has nuclear facility decommissioning as one of the programmes. Independent research in areas of essential need for nuclear facilities must be carried out to maintain know how. (author)

  3. Forschungszentrum Karlsruhe Technik und Umwelt. Research and development program 2002

    2001-01-01

    The five main fields of research and the activities under the R and D program 2002 are explained in great detail in five chapters with the following captions: 1. ENVIRONMENT. Programs: - Sustainable development, energy and environmental engineering (UMWELT). - Earth atmosphere and climate research (ATMO). 2. PUBLIC HEALTH. Programs: - Biomedical research (BIOMED). - Medical engineering (MEDTECH). 3. ENERGY. Programs: - Thermonuclear fusion (FUSION). - Nuclear safety (NUKLEAR). 4. KEY TECHNOLOGIES. Programs: - Microsystems engineering (MIKRO). - Nanotechnology (NANO). - Materials science (MATERIAL). - Chemical process engineering (CHEMIE). - Superconductivity (SUPRA). 5. MATTER and STRUCTURE. Program: The structure of matter (STRUKTUR). The sixth chapter presents cross-cutting activities under the program: Technology transfer and marketing (TTM). The concluding chapter lists and briefly presents the activities of the scientific and technical institutes of the Karlsruhe Research Center. (CB) [de

  4. Forschungszentrum Karlsruhe Technik und Umwelt. Research and development programme 1999

    1999-01-01

    The Karlsruhe Research Center is a national research establishment placed under the responsibility of the Federal Republic of Germany and the Federal Land of Baden-Wuerttemberg, and as a member of the Hermann von Helmholtz-Gemeinschaft Deutscher Forschungszentren belongs to the most important and independent research centers in Germany working in the fields of the natural sciences and engineering sciences. The center's research and development activities are defined in coordination with the policy and programmes of the two responsible Federal and Land Governments and span the range from pre-industrial research through to product and process development, research of a provident nature, and fundamental scientific research work, with almost all R and D activities of the center relating in one way or other to technology and the environment. The research programme of the center today covers subjects and aspects relating to the environment, energy, key technologies, and fundamental research, whereas at the time the center was founded, nuclear science and engineering was the dominating field of activities. The current spectrum of activities reflects the evolution in the past and is characterized by a great complexity of problems involved, which requires cross-disciplinary cooperation, and foresight in the definition of tasks and time horizons. (orig./CB) [de

  5. Karlsruhe Research Center, Nuclear Safety Research Project (PSF). Annual report 1994; Forschungszentrum Karlsruhe, Projekt Nukleare Sicherheitsforschung. Jahrsbericht 1994

    Hueper, R. [ed.

    1995-08-01

    The reactor safety R and D work of the Karlsruhe Research Centre (FZKA) has been part of the Nuclear Safety Research Projet (PSF) since 1990. The present annual report 1994 summarizes the R and D results. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status of early 1995. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [Deutsch] Seit Beginn 1990 sind die F+E-Arbeiten des Forschungszentrum Karlsruhe (FZKA) zur Reaktorsicherheit im Projekt Nukleare Sicherheitsforschung (PSF) zusammengefasst. Der vorliegende Jahresbericht 1994 enthaelt Beitraege zu aktuellen Fragen der Sicherheit von Leichtwasserreaktoren und innovativen Systemen sowie der Umwandlung von minoren Aktiniden. Die konkreten Forschungsthemen und -vorhaben werden mit internen und externen Fachgremien laufend abgestimmt. An den beschriebenen Arbeiten sind die folgenden Institute und Abteilungen des FZKA beteiligt: Institut fuer Materialforschung IMF I, II, III; Institut fuer Neutronenphysik und Reaktortechnik INR; Institut fuer Angewandte Thermo- und Fluiddynamik IATF; Institut fuer Reaktorsicherheit IRS; Hauptabteilung Ingenieurtechnik HIT; Hauptabteilung Versuchstechnik HVT sowie vom KfK beauftragte externe Institutionen. Die einzelnen Beitraege stellen den Stand der Arbeiten zum Fruehjahr 1995 dar und sind entsprechend dem F+E-Programm 1994 numeriert. Den in deutscher Sprache verfassten Beitraege sind Kurzfassungen in englischer Sprache vorangestellt. (orig.)

  6. Research on transmutation and accelerator-driven systems at the Forschungszentrum Karlsruhe

    Knebel, J.U.; Heusener, G.

    2000-01-01

    Transmutation is considered a promising technology worldwide for significantly reducing the amount and, thereby, the long-term radiotoxicity of high active waste (HAW) produced by the operation of nuclear power plants such as light water reactors (LWR). The maximum reduction of radiotoxicity could be by a factor of about 100. Transmutation is thus an alternative to the direct deposition of large volumes of highly radioactive waste. Transmutation presents the possibility of closing the fuel cycle including the minor actinides. Plutonium, minor actinides and long-lived fission products can be transmuted in a so called Accelerator Driven Sub-critical System (ADS), which consists of an accelerator, a target module and a subcritical blanket. This paper describes the work performed at Forschungszentrum Karlsruhe which is critically evaluating an ADS mainly with respect to its potential for transmuting minor actinides, to its feasibility and to safety aspects. The work is being done in the area of core design, neutronics, safety, system analyses, materials and corrosion. (orig.) [de

  7. An overview of the severe accident research activities within the LACOMERA platform at the Forschungszentrum Karlsruhe

    Miassoedov, A.; Alsmeyer, H.; Meyer, L.; Steinbrueck, M.; Tromm, W.

    2006-01-01

    The LACOMERA project at the Forschungszentrum Karlsruhe, Germany, is a 4 year action within the 5th Framework Programme of the EU which started in September 2002. Overall objective of the project is to offer research institutions from the EU member countries and associated states access to four large-scale experimental facilities QUENCH, LIVE, DISCO, and COMET. These facilities can be used to investigate core melt scenarios from the beginning of core degradation to melt formation and relocation in the vessel, possible melt dispersion to the reactor cavity, and finally corium concrete interaction and corium coolability in the reactor cavity. The paper summarises the main results obtained in the following experiments performed up to now. QUENCH-L1: Impact of air ingression on core degradation. The test provides unique data for the investigation of air ingress phenomenology in conditions as representative of a spent fuel pool accident as possible; QUENCH-L2: Boil-off of a flooded bundle. The test is of a generic interest for all reactor types, provided a link between the severe accident and design basis areas, and would deliver oxidation and thermal hydraulic data at high temperatures. DISCO-L1: Thermal hydraulic behaviour of the corium melt dispersion neglecting the chemical effects such as hydrogen generation and combustion. COMET-L1: Long-term 2D concrete ablation in a siliceous concrete cavity at intermediate decay heat power level with a top flooding phase after a phase of dry concrete erosion. COMET-L2: Investigation of long-term melt-concrete interaction of metallic corium in a cylindrical siliceous concrete cavity under dry conditions with decay heat simulation of intermediate power during the first test phase, and subsequently at reduced power during the second test phase. (author)

  8. Forschungszentrum Karlsruhe Technik und Umwelt. Research and development program 2001 and program budget 2001

    2001-01-01

    The Karlsruhe Research Center is a national research center founded and substantially funded by the German Federal Government and the Land government of Baden-Wuerttemberg, the federal state where it is located. It is a member of the Hermann von Helmholtz-Gemeinschaft Deutscher Forschungszentren and is one of the most important, independent research centers in Germany working in the fields of the natural sciences and engineering sciences. The Center's R and D programmes encompass research activities up to pre-industrial scale as well as product and process development, research for precautionary policy and purposes, and fundamental research. The focal points of the R and D programme 2001 are explained under the following subject titles: - Environment - Public Health - Energy - Key Technologies - Fundamental Research. The programme reveals the shift of emphasis of activities which commenced in the early 1980s, away from nuclear engineering as the major focus in the early days towards a much wider spectrum of activities today, characterized by aspects such as complexity of tasks, long-term planning, and the need for cross-disciplinary and multilateral cooperation. The second volume of the publication explains the programme budget and apportionment of funds. (orig./CB) [de

  9. Forschungszentrum Karlsruhe Technik und Umwelt. Program budget for research and development 2001. Planning period 2001 - 2004

    2000-11-01

    The Karlsruhe Research Center is a national research center founded and substantially funded by the German Federal Government and the Land government of Baden-Wuerttemberg, the federal state where it is located. It is a member of the Hermann von Helmholtz-Gemeinschaft Deutscher Forschungszentren and is one of the most important, independent research centers in Germany working in the fields of the natural sciences and engineering sciences. The Center's R and D programmes encompass research activities up to pre-industrial scale as well as product and process development, research for precautionary policy and purposes, and fundamental research. The focal points of the R and D programme 2001 are explained under the following subject titles: - Environment - Public Health - Energy - Key Technologies - Fundamental Research. The programme reveals the shift of emphasis of activities which commenced in the early 1980s, away from nuclear engineering as the major focus in the early days towards a much wider spectrum of activities today, characterized by aspects such as complexity of tasks, long-term planning, and the need for cross-disciplinary and multilateral cooperation. The second volume of the publication explains the programme budget and apportionment of funds. (orig./CB) [de

  10. Materials specific work at Forschungszentrum Karlsruhe and in cooperation with the industrial partners ALKEM and Interatom for the development of nuclear oxide fuels for fission reactors

    Kleykamp, H.; Muehling, G.

    2005-09-01

    The fabrication of uranium-plutonium oxide fuel started in Forschungszentrum Karlsruhe and at ALKEM company to begin for the criticality experiments in the SNEAK reactor and subsequently for stationary fuel pin irradiations in the FR2, BR2, DFR, Rapsodie, Phenix and KNK II reactors. The production methods comprised first the mechanical blending of UO2 and PuO2 followed by direct pressing and sintering of the pellets, later the advanced methods such as optimized comilling and ammonium uranyl plutonyl coprecititation. The fabrication of pellets was described in the main, further the alternative fuel pin manufacturing processes by vibrational compaction and hot-impact densification were discussed. The first capsule and pin irradiations in the FR2 and BR2 reactors contributed to the assessment of the maximum operation parameters within the fuel pin development such as linear heat rating, cladding temperature and burnup. Subsequently, small-bundle and largebundle irradiations were made in fast reactors in cooperation with Interatom company in order to verify the specifications for the commercial fast reactor SNR 300. Milestones were the maximum burnup of 175 GWd/t metal, corresponding 18.6 % of the heavy atoms, obtained in one of the KNK II fuel pin assemblies, and the displacement rates in the cladding materials of 140 dpa NRT attained in the Phenix reactor. Higher implications gained later the stationary irradiations of defected mixed-oxide pins, the mild fuel pin transient operations, the local blockage experiments and the severe hypothetic accidents in the respective Siloe, HFR, BR2 and CABRI reactors. These experiments were made solely in international partnership. Further activities were the chemical analyses of solid residues and coprecipitations of irradiated mixed-oxide fuels in the head-end of the reprocessing. All these actions were coordinated in the then fast breeder project. Furthermore, irradiated fuels and fuel pins of other reactor types were

  11. Scientists from all over the world attend the Frederic Joliot/Otto Hahn summer school at the Karlsruhe Research Center; Wissenschaftler aus aller Welt bei der Frederic Joliot/Otto Hahn Summer School im Forschungszentrum Karlsruhe

    Heinzel, V.

    2003-11-01

    The Frederic Joliot/Otto Hahn Summer School organized jointly by the Karlsruhe Research Center and the Commissariat a l'Energie Atomique was held in Karlsruhe in 2003 for the third time. The main topics this year focused on recent developments and findings in the fields of fuels and materials for reactors. Applications of nuclear technology beyond the confines of electricity generation were covered in discussions shout methods of hydrogen production. Specialized seminars dealt with current aspects of fusion research and the activities of the Institute for Transuranium Elements (ITU). (orig.)

  12. The QUENCH programme at Forschungszentrum Karlsruhe (FZK)

    Steinbrueck, M.; Schanz, G.; Sepold, L.; Stuckert, J.; Hering, W.; Homann, C.; Miassoedov, A.

    2004-01-01

    The QUENCH programme at FZK was launched to investigate the hydrogen source term during reflood of an overheated reactor core. It consists of large scale bundle experiments, separate-effects tests, modelling activities and application and validation of severe fuel damage (SFD) code systems. The paper describes the experimental part of the programme, namely the experimental facilities and test rigs as well as selected results obtained during the recent years. (author)

  13. Forschungszentrum Karlsruhe, Technik und Umwelt. Progress report 1994

    1995-01-01

    The points of main effort which are discussed reflect the institution's R and D scheme. The summaries submitted by the different institutes and departments are compiled by the topics and fields they deal with. The report gives an account of the progress under each of the KfK R and D projects. This correlation facilitates comparisons between the targets and actual achievements and elucidates the general relation between the individual tasks which often are in the care of several institutes at a time. The departments and institutes and their respective tasks are introduced, and a comprehensive appendix is attached which lists the 1994 publications. (orig.) [de

  14. Forschungszentrum Juelich. Annual report 2013; Forschungszentrum Juelich. Jahresbericht 2013

    Frick, Frank; Roegener, Wiebke

    2014-07-15

    The annual report 2013 of the Forschungszentrum Juelich covers research activities, including high-lights of brain science, electrically controllable quantum bits, climate science and atmosphere research, knowledge management, including education and international cooperation, and an economic survey.

  15. Forschungszentrum Juelich. Annual report 2015

    Frick, Frank; Lueers, Katja; Roegener, Wiebke; Stettien, Annette; Trautwein, Ilse; Stahl-Busse, Brigitte

    2016-07-01

    The annual report 2015 of the Forschungszentrum Juelich covers research activities, including high-lights of brain science, electrically controllable quantum bits, climate science and atmosphere research, knowledge management, including education and international cooperation, and an economic survey.

  16. Forschungszentrum Juelich. Annual report 2013

    Frick, Frank; Roegener, Wiebke

    2014-07-01

    The annual report 2013 of the Forschungszentrum Juelich covers research activities, including high-lights of brain science, electrically controllable quantum bits, climate science and atmosphere research, knowledge management, including education and international cooperation, and an economic survey.

  17. Forschungszentrum Juelich. Annual report 2016; Forschungszentrum Juelich. Jahresbericht 2016

    Frick, Frank; Lueers, Katja; Roegener, Wiebke; Stahl-Busse, Brigitte

    2017-07-15

    The annual report 2016 of the Forschungszentrum Juelich covers research activities, including high-lights of structural biochemistry (Alzheimer research), material research (skyrmions), computer simulation (e.g. of flexible blood cells), quantum physics (100 qubit era), photovoltaics, battery research, environmental research, climate research, biotechnology and community codes, including education and international cooperation.

  18. Forschungszentrum Juelich. Annual report 2016

    Frick, Frank; Lueers, Katja; Roegener, Wiebke; Stahl-Busse, Brigitte

    2017-07-01

    The annual report 2016 of the Forschungszentrum Juelich covers research activities, including high-lights of structural biochemistry (Alzheimer research), material research (skyrmions), computer simulation (e.g. of flexible blood cells), quantum physics (100 qubit era), photovoltaics, battery research, environmental research, climate research, biotechnology and community codes, including education and international cooperation.

  19. CONDITIONING OF INTERMEDIATE-LEVEL WASTE AT FORSCHUNGSZENTRUM JUELICH GMBH

    Krumbach, H.

    2003-01-01

    This contribution to the group of low-level, intermediate, mixed and hazardous waste describes the conditioning of intermediate-level mixed waste (dose rate above 10 mSv/h at the surface) from Research Centre Juelich (FZJ). Conditioning of the waste by supercompaction is performed at Research Centre Karlsruhe (FZK). The waste described is radioactive waste arising from research at Juelich. This waste includes specimens and objects from irradiation experiments in the research reactors Merlin (FRJ-1) and Dido (FRJ-2) at FZJ. In principle, radioactive waste at Forschungszentrum Juelich GmbH is differentiated by the surface dose rate at the waste package. Up to a surface dose rate of 10 mSv/h, the waste is regarded as low-level. The radioactive waste described here has a surface dose rate above 10 mSv/h. Waste up to 10 mSv/h is conditioned at the Juelich site according to different conditioning methods. The intermediate-level waste can only be conditioned by supercompaction in the processing facility for intermediate-level waste from plant operation at Research Centre Karlsruhe. Research Centre Juelich also uses this waste cell to condition its intermediate-level waste from plant operation

  20. Prof. Manfred Popp, Chairman of the Executive Board, Forschungszentrum Karlsruhe GmbH

    Patrice Loïez

    2003-01-01

    Prof. Popp is pictured here in the ATLAS detector assembly hall with Dr. Horst Wenninger of CERN.Photo 01: Prof. Popp (right) and Dr. Wenninger in front of one of the two vacuum vessels for the ATLAS end-cap toroid magnets.Photo 02: Prof. Popp (right) and Dr. Wenninger in front of one of eight 25-metre-long aluminium-alloy coil casings that will house the racetrack coils of the barrel toroid magnet system.

  1. Nuclear fusion project. Annual report of the Association Forschungszentrum Karlsruhe/EURATOM. October 1994 - September 1995

    Kast, G.

    1996-01-01

    Today about fifty percent of FZK's fusion programme is contracted to ITER via the contribution of the European home team. With the recent selection of blanket concepts in the European frame, a concentration process has been initiated which will result in some restructuring of the blanket programme. The results are documented. Closely related to blanket development is the long term materials programme. FZK has concentrated on reduced activation ferritic-martensitic steels. Important project resources for irradiation and hot cell work are devoted to characterize and improve the performance of suitable structural materials. ITER references are given in the nomenclature. The annexes provide with some information on departments and project management. (DG)

  2. Forschungszentrum Karlsruhe Technik und Umwelt. Research and development program 1995. As of December 2, 1994

    1995-01-01

    After giving a survey of the major research areas of the Centre the author explains the projects in the fields of environment, energy, microsystems engineering and fundamental research. The medium-term aim, present state of development, 1995 programme, cooperation within the centre, cooperation with external partners and financial expenditure are explained on a project-by-project basis. (UA) [de

  3. Annual report 1995 of the Central Safety Department, Research Center Karlsruhe

    Koelzer, W.

    1996-04-01

    The Central Safety Department is responsible for supervising, monitoring and, to some extent, also executing measures of radiation protection, industrial health and safety as well as physical protection and security at and for the institutes and departments of the Karlsruhe Research Center (Forschungszentrum Karlsruhe GmbH), and for monitoring liquid effluents and the environment of all facilities and nuclear installations on the premises of the Research Center. In addition, research and development work is carried out in the fields of behavior of tritium in the air/soil/plant system, tritium balances for nuclear fusion fuel cycles, and assessments of mining and ore dressing spoils. This report gives details of the different duties and reports the results of 1995 routine tasks, investigations and developments of the working groups of the Department. The reader is referred to the English translation of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

  4. LACOMERA - large scale experiments on core degradation, melt retention and coolability at the Forschungszentrum Karslruhe

    Miassoedov, A.; Alsmeyer, H.; Meyer, L.

    2003-01-01

    The LACOMERA project at the Forschungszentrum Karlsruhe is a 3 year shared-cost action within the Fifth Framework Programme which started in September 2002. The overall objectives of the LACOMERA project are to provide research institutions from the EU member countries and associated states access to large scale experimental facilities at the Forschungszentrum Karlsruhe which shall be used to increase the knowledge of the quenching of a degraded core and regaining melt coolability in the reactor pressure vessel, of possible melt dispersion to the cavity, of molten core concrete interaction and of ex-vessel melt coolability. One major aspect is to understand how these events affect the safety of European reactors so as to lead to soundly-based accident management procedures. The project will bring together interested partners of different European member states in the area of severe accident analysis and control, with the goal to increase the public confidence in the use of nuclear energy. Moreover, partners from the newly associated states should be included as far as possible, and therefore the needs of Eastern, as well as Western, reactors will be considered in LACOMERA project. The project offers a unique opportunity to get involved in the networks and activities supporting VVER safety, and for Eastern experts to get an access to large scale experimental facilities in a Western research organisation to improve understanding of material properties and core behaviour under severe accident conditions. As a result of the first call for proposals a project on air ingress test in the QUENCH facility has been selected. A second call for proposals is opened with a deadline of 31 December 2003. (author)

  5. Conditioning of intermediate-level waste at Forschungszentrum Juelich GmbH

    Krumbach, H.

    2003-01-01

    This contribution to the group of low-level, intermediate, mixed and hazardous waste describes the conditioning of intermediate-level mixed waste (dose rate above 10 mSv/h at the surface) from Research Centre Juelich (FZJ). Conditioning of the waste by supercompaction is performed at Research Centre Karlsruhe (FZK). The waste described is radioactive waste arising from research at Juelich. This waste includes specimens and objects from irradiation experiments in the research reactors Merlin (FRJ-1) and Dido (FRJ-2) at FZJ. In principle, radioactive waste at Forschungszentrum Juelich GmbH is differentiated by the surface dose rate at the waste package. Up to a surface dose rate of 10 mSv/h, the waste is regarded as low-level. The radioactive waste described here has a surface dose rate above 10 mSv/h. Waste up to 10 mSv/h is conditioned at the Juelich site according to different conditioning methods. The intermediate-level waste can only be conditioned by supercompaction in the processing facility for intermediate-level waste from plant operation at Research Centre Karlsruhe. Research Centre Juelich also uses this waste cell to condition its intermediate-level waste from plant operation. (orig.)

  6. Forschungszentrum Rossendorf, Institute of Radiochemistry. Annual report 2000

    2001-05-01

    The Institute of Radiochemistry (IRC), one of the five institutes of the Forschungszentrum Rossendorf (FZR) performs basic and applied research in the fields of radiochemistry and radioecology. Main goal is the quantification of the interaction and mobility of radionuclides in the geo- and biosphere. Because of their high radiotoxicity and long half-life the actinides are of special interest. Among the actinides uranium and its manifold interactions plays a major role in the institute's research activities. In addition the interactions of some important long-lived fission and decay products are studied. More than 60 scientists, technicians and PhD students are employed in the Institute of Radiochemistry. The research is focused on understanding the fundamental processes relevant for the behavior of radionuclides in the environment. Main topics are: Aquatic chemistry, Radionuclide interaction with mineral surfaces, Radionuclide interaction with biological materials (microbes and plants), Modeling the radionuclide transport, Development of spectroscopic speciation methods. Further progress was achieved in understanding the interaction mechanism of actinides with humic acids. The coordination numbers and bond distances of the coordinated oxygens have been determined by X-ray absorption spectroscopy for tetra- and pentavalent actinides (Np(IV) and Np(V)). It was shown that the carboxylic groups of the humic acid form monodentate complexes with the neptonyl ions. We extended our laser spectroscopic capabilities by installing a new laser system with ultra-short pulses (130 fs) for fluorescence measurements of organic substances. We intend to gain information on actinide complexes with organic ligands by studying the fluorescence properties of the organics with very short life times. The laser system and the method were successfully validated by the determination of the well-known uranyl-salicylic acid complexation. Although surface complexation concepts are more and more

  7. Activities at Forschungszentrum Juelich in Safeguards Analytical Techniques and Measurements

    Duerr, M.; Knott, A.; Middendorp, R.; Niemeyer, I.; Kueppers, S.; Zoriy, M.; Froning, M.; Bosbach, D.

    2015-01-01

    The application of safeguards by the IAEA involves analytical measurements of samples taken during inspections. The development and advancement of analytical techniques with support from the Member States contributes to strengthened and more efficient verification of compliance with non-proliferation obligations. Since recently, a cooperation agreement has been established between Forschungszentrum Juelich and the IAEA in the field of analytical services. The current working areas of Forschungszentrum Juelich are: (i) Production of synthetic micro-particles as calibration standard and reference material for particle analysis, (ii) qualification of the Forschungszentrum Juelich as a member of the IAEA network of analytical laboratories for safeguards (NWAL), and (iii) analysis of impurities in nuclear material samples. With respect to the synthesis of particles, a dedicated setup for the production of uranium particles is being developed, which addresses the urgent need for material tailored for its use in quality assurance and quality control measures for particle analysis of environmental swipe samples. Furthermore, Forschungszentrum Juelich has been nominated as a candidate laboratory for membership in the NWAL network. To this end, analytical capabilities at Forschungszentrum Juelich have been joined to form an analytical service within a dedicated quality management system. Another activity is the establishment of analytical techniques for impurity analysis of uranium-oxide, mainly focusing on inductively coupled mass spectrometry. This contribution will present the activities at Forschungszentrum Juelich in the area of analytical measurements and techniques for nuclear verification. (author)

  8. PREFACE: Selected invited contributions from the International Conference on Magnetism (Karlsruhe, Germany, 26-31 July 2009) Selected invited contributions from the International Conference on Magnetism (Karlsruhe, Germany, 26-31 July 2009)

    Goll, Gernot; Löhneysen, Hilbert v.; Loidl, Alois; Pruschke, Thomas; Richter, Manuel; Schultz, Ludwig; Sürgers, Christoph; Wosnitza, Jochen

    2010-04-01

    The International Conference on Magnetism 2009 (ICM 2009) was held in Karlsruhe, Germany, from 26 to 31 July 2009. Previous conferences in this series were organized in Edinburgh, UK (1991), Warsaw, Poland (1994), Cairns, Australia (1997), Recife, Brazil (2000), Rome, Italy (2003), and Kyoto, Japan (2006). As with previous ICM conferences, the annual Conference on Strongly Correlated Electron Systems (SCES) was integrated into ICM 2009. The topics presented at ICM 2009 were strongly correlated electron systems, quantum and classical spin systems, magnetic structures and interactions, magnetization dynamics and micromagnetics, spin-dependent transport, spin electronics, magnetic thin films, particles and nanostructures, soft and hard magnetic materials and their applications, novel materials and device applications, magnetic recording and memories, measuring techniques and instrumentation, as well as interdisciplinary topics. We are grateful to the International Advisory Committee for their help in coordinating an attractive program encompassing practically all aspects of magnetism, both experimentally and theoretically. The Program Committee comprised A Loidl, Germany (Chair), M A Continentino, Brazil, D E Dahlberg, USA, D Givord, France, G Güntherodt, Germany, H Mikeska, Germany, D Kaczorowski, Poland, Ching-Ray Chang, South Korea, I Mertig, Germany, D Vollhardt, Germany, and E F Wassermann, Germany. E F Wassermann was also head of the National Organizing Committee. His help is gratefully acknowledged. The scientific program started on Monday 27 July 2009 with opening addresses by the Conference Chairman, the Deputy Mayor of Karlsruhe, Ms M Mergen and the Chairman of the Executive Board of Forschungszentrum Karlsruhe, E Umbach. ICM 2009 was attended by the Nobel Laureates P W Anderson, A Fert and P Grünberg who gave plenary talks. A special highlight was the presentation of the Magnetism Award and Néel Medal to S S P Parkin who also presented his newest results

  9. Karlsruhe nuclear research center. Main activities

    The article reports on problems of securing the fuel supply for nuclear power generation, on reprocessing and ultimate storage of radioactive material, on the safety of nuclear facilities, on new technologies and basic research, and on the infrastructure of the Karlsruhe nuclear research center, as well as finance and administration. (HK) [de

  10. Status of nuclear data activities at Karlsruhe

    Kawano, Toshihiko [Kyushu Univ., Fukuoka (Japan)

    1997-03-01

    This is a brief introduction to nuclear data activity at Karlsruhe Research Center. Some URLs concerned are given. Topics mentioned here are, the FENDL and JEF/EFF project at INR, and measurements of neutron capture cross sections at IK III. (author)

  11. Forschungszentrum Rossendorf. Institute of Safety Research. Annual report 1998

    Weiss, F.P.; Rindelhardt, U.

    1999-07-01

    The Institute of Safety Research is one of the five scientific institutes of Forschungszentrum Rossendorf e.V. The Forschungszentrum Rossendorf is a member of the 'Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz' und is funded by the Federal Ministry of Education and Research and by the Saxon Ministry of Science and Arts with 50% each. The research work of the institute aims at the assessment and increase of the safety and environmental sustainability of technical plants. The emphasis is put on the development and validation of mathematical and physical models for process and plant analysis, and of techniques for process and components monitoring. Subject of investigations are equally nuclear plants and installations of process industries. (orig.)

  12. TASKA - Tandem Spiegelmaschine Karlsruhe. Vol. 1

    1982-06-01

    TASKA (Tandem Spiegelmaschine Karlsruhe) is a near term engineering test facility based on a tandem mirror concept with thermal barriers. The main objectives of this study were to develop a preconceptual design of a facility that could provide engineering design information for a Demonstration Fusion Power Reactor. Thus TASKA has to serve as testbed for technologies of plasma engineering, superconducting magnets, materials, plasma heating, breeding and test blankets, tritium technology, and remote handling. (orig.) [de

  13. TASKA - Tandem Spiegelmaschine Karlsruhe. Vol. 2

    1982-06-01

    TASKA (Tandem Spiegelmaschine Karlsruhe) is a near term engineering test facility based on a tandem mirror concept with thermal barriers. The main objectives of this study were to develop a preconceptual design of a facility that could provide engineering design information for a Demonstration Fusion Power Reactor. Thus TASKA has to serve as testbed for technologies of plasma engineering, superconducting magnets, materials, plasma heating, breeding and test blankets, tritium technology, and remote handling. (orig.) [de

  14. List of publications of Karlsruhe University (T.H.) and Karlsruhe Nuclear Research Centre

    1977-01-01

    This 19th volume of the list of publications compiled by Karlsruhe University (T.H.) in cooperation with Karlsruhe Nuclear Research Centre and some other institutions closely connected with the university gives the publications of the year 1976 as well as some supplements from 1975. The publications listed are books and journals, articles from journals and symposia, research reports, dissertations and theses for habilitation published by these institutions, their organs and institutes, their staff and scientific personnel, as well as patents. As a rule, theses for diplomas, newspaper articles, book reviews, internal reports and information have been left out. (orig.) [de

  15. List of publications of the Karlsruhe University and the Karlsruhe Nuclear Research Centre

    1987-01-01

    This 19th annual bibliography of publications from the Karlsruhe University, the Karlsruhe Nuclear Research Centre, and some closely cooperating institutions covers all publications prepared in the year 1986, and a few supplementary data on 1985 publications. The bibliography refers to books and journals, contributions to journals or serial publications, research reports, doctoral theses and theses qualifying for lecturing at a university, and to patents. Diploma theses, contributions to newspapers, book reviews, internal reports or communications generally do not form part of the bibliography. (orig./GG) [de

  16. The Karlsruhe program system KAPROS. Pt. 2

    Bachmann, H.; Kleinheins, S.

    1976-07-01

    The system nucleus of the Karlsruhe modular program system KAPROS is described from the point of view of the system programmer. In short reviews it is explained, how the module management, the data management, the buffer management, the error handling and the statistics work. The tables, the datasets, the routines and the commons of the system nucleus as well as some utility programs for the handling of system datasets are explained in full detail. The program listening of the system nucleus belongs to this documentation as a separate appendix. (orig.) [de

  17. Information on the Karlsruhe Nuclear Research Center

    Reuter, H.H.

    1980-01-01

    A short overview is given about the origins of Karlsruhe Nuclear Research Center. The historical development of the different companies operating the Center is shown. Because the original task assigned to the Center was the construction and testing of the first German reactor exclusively built by German companies, a detailed description of this reactor and the changes made afterwards is presented. Next, today's organizational structure of the Center is outlined and the development of the Center's financing since its foundation is shown. A short overview about the structure of employees from the Center's beginning up to now is also included as well as a short description of today's main activities. (orig.)

  18. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2004

    Weiss, F.P.; Rindelhardt, U.

    2005-01-01

    The Institute of Safety Research (ISR) is one of the six Research Institutes of Forschungszentrum Rossendorf e.V. (FZR e.V.) which is a member institution of the Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz (Leibniz Association). Together with the Institute of Radiochemistry, ISR constitutes the research programme ''Safety and Environment'' which is one from three scientific programmes of FZR. In the framework of this research programme, the institute is responsible for the two subprogrammes ''Plant and Reactor Safety'' and ''Thermal Fluid Dynamics'', respectively. We also provide minor contributions to the sub-programme ''Radio-Ecology''. Moreover, with the development of a pulsed photo-neutron source at the radiation source ELBE (Electron linear accelerator for beams of high brilliance and low emittance), we are involved in a networking project carried out by the FZR Institute of Nuclear and Hadron Physics, the Physics Department of TU Dresden, and ISR. (orig.)

  19. Casa Wächter Karlsruhe Alemania Federal

    Lehmann, Friedrich

    1979-06-01

    Full Text Available Wächter Residence, Karlsruhe - West Germany The design of this home in Karlsruhe v/as presided over by two basic criteria: function and human scale, carried up to their ultimate consequences. The first criteria had a decisive influence on the roof arrangement, as an extension of the neighboring buildings, and on the selection of construction materials to match the suburban environment where the site is located, not to forget the shaping of Windows and skylights, reflecting the internal functions and providing lighting while protecting the privacy of the interior from the exterior lines of view. The second criteria affects aspects so different from one another as the unexpected but valid room arrangement following a spiral path leading from the entrance to the master bedroom at the other end with the remaining rooms at intermediate levels affording the required degree of privacy; or the arrangement of the mechanical installations, resembling the human backbone; or, finally, the paint finish chosen, pleasing man's taste for ornamentality.

    La realización de esta vivienda, en Karlsruhe, estuvo marcada por dos criterios fundamentales: la funcionalidad y la escala humana, llevadas ambas hasta sus últimas consecuencias. La primera influyó desde la disposición de las cubiertas, como prolongación de las construcciones vecinas, hasta la elección de los materiales constructivos, acordes con el entorno suburbano de la parcela, sin olvidar la configuración de las ventanas y lucernarios que, con sus diferentes formatos, indican el uso del interior, al tiempo que posibilitan la iluminación, protegiendo de las vistas exteriores. La segunda característica afecta a aspectos tan dispares como la original, pero válida, secuencia de habitaciones —según una espiral que, desde la entrada, conduce, en el extremo opuesto, al dormitorio de los padres, quedando las restantes dependencias situadas en los niveles intermedios según su exigencia

  20. Publications of the University of Karlsruhe (T.H.) and the Nuclear Research Center Karlsruhe 1981

    1982-01-01

    This is the 14th volume of the joint list of publications of the University of Karlsruhe (T.H.), the Nuclear Research Center Karlsruhe and some institutions which are closely linked to the University. It contains the publications of the year 1981 as well as some addenda from 1980. Included were books and journals, journal articles and contributions from compilations, research reports, dissertations and habilitation theses which were written or published by these institutions, their bodies and institutes as well as their teachers and scientific staff, and also patents. Not included were, as a rule, diploma theses, newspaper articles, reviews, internal reports and bulletins. The list of publications from University is mainly based on entries made by the institutes and chairs; its completeness can not be granted here. (orig./RW) [de

  1. Karlsruhe nuclide chart - new 9. edition 2015

    Soti, Zsolt [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Postfach 2340, DE-76125 Karlsruhe, (Germany); Magill, Joseph; Pfennig, Gerda; Derher, Raymond [Nucleonica GmbH, c/o European Commission, Postfach 2340, DE-76125 Karlsruhe, (Germany)

    2015-07-01

    Following the success of the 8. Edition of the Karlsruhe Nuclide Chart 2012, a new edition is planned for 2015. Since the 2012 edition, more than 100 nuclides have been discovered and about 1400 nuclides have been updated. In summary, the new 9. edition contains decay and radiation data on approximately 3230 ground state nuclides and 740 isomers from 118 chemical elements. The accompanying booklet provides a detailed explanation of the nuclide box structure used in the Chart. An expanded section contains many additional nuclide decay schemes to aid the user to interpret the highly condensed information in the nuclide boxes. The booklet contains - in addition to the latest values of the physical constants and physical properties - a periodic table of the elements, tables of new and updated nuclides, and a difference chart showing the main changes in the Chart graphically. (authors)

  2. Karlsruhe nuclide chart - new 9. edition 2015

    Soti, Zsolt; Magill, Joseph; Pfennig, Gerda; Derher, Raymond

    2015-01-01

    Following the success of the 8. Edition of the Karlsruhe Nuclide Chart 2012, a new edition is planned for 2015. Since the 2012 edition, more than 100 nuclides have been discovered and about 1400 nuclides have been updated. In summary, the new 9. edition contains decay and radiation data on approximately 3230 ground state nuclides and 740 isomers from 118 chemical elements. The accompanying booklet provides a detailed explanation of the nuclide box structure used in the Chart. An expanded section contains many additional nuclide decay schemes to aid the user to interpret the highly condensed information in the nuclide boxes. The booklet contains - in addition to the latest values of the physical constants and physical properties - a periodic table of the elements, tables of new and updated nuclides, and a difference chart showing the main changes in the Chart graphically. (authors)

  3. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2004

    Weiss, F.P.; Rindelhardt, U. (eds.)

    2005-07-01

    The Institute of Safety Research (ISR) is one of the six Research Institutes of Forschungszentrum Rossendorf e.V. (FZR e.V.) which is a member institution of the Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz (Leibniz Association). Together with the Institute of Radiochemistry, ISR constitutes the research programme ''Safety and Environment'' which is one from three scientific programmes of FZR. In the framework of this research programme, the institute is responsible for the two subprogrammes ''Plant and Reactor Safety'' and ''Thermal Fluid Dynamics'', respectively. We also provide minor contributions to the sub-programme ''Radio-Ecology''. Moreover, with the development of a pulsed photo-neutron source at the radiation source ELBE (Electron linear accelerator for beams of high brilliance and low emittance), we are involved in a networking project carried out by the FZR Institute of Nuclear and Hadron Physics, the Physics Department of TU Dresden, and ISR. (orig.)

  4. Forschungszentrum Rossendorf, Institute of Radiochemistry. Annual report 2001

    Fanghaenel, T.; Bernhard, G.; Engelmann, H.J.

    2002-05-01

    The Institute of Radiochemistry (IRC), one of the five institutes of the Forschungszentrum Rossendorf (FZR) performs basic and applied research in the fields of radiochemistry and radioecology. Main goal is the quantification of the interaction and mobility of radionuclides in the geo- and biosphere. Because of their high radiotoxicity and long half-life the actinides are of special interest. Among the actinides uranium and its manifold interactions plays a major role in the institute's research activities. In addition the interactions of some important long-lived fission and decay products are studied. More than 60 scientists, technicians and PhD students are employed in the Institute of Radiochemistry. The research is focused on understanding the fundamental processes relevant for the behavior of radionuclides in the environment. Main topics are: Aquatic chemistry, Radionuclide interaction with mineral surfaces, Radionuclide interaction with biological materials (bacteria and plants), Modeling the radionuclide transport, Development of spectroscopic speciation methods We accomplished many new scientific results in the past year, which are presented in this Annual Report. (orig.)

  5. Cost accounting at the Kernforschungszentrum Karlsruhe GmbH

    Neck, E.

    1979-01-01

    A presentation of the Nuclear Research Center Karlsruhe and its main research activities is given. Company structure, planning and control system in the R and D field are explained. The cost accounting system of the Nuclear Research Center Karlsruhe is discussed in detail, a survey of cost accounting as practiced by other German research establishments and comments on cost accounting as a tool of performance gauging are given. (A.N.)

  6. Fusion Technologies: 2nd Karlsruhe International Summer School

    Bahm, W.

    2008-01-01

    Nuclear fusion promises to deliver a future non-polluting energy supply with nearly unlimited fuel reserves. To win young scientists and engineers for nuclear fusion, the Karlsruhe Research Center, together with other partners in the European Fusion Education Network being established by the European Commission, organizes the 2nd Karlsruhe International Summer School on Fusion Technologies on September 1-12, 2008. The program covers all key technologies necessary for construction and operation of a fusion reactor. (orig.)

  7. List of scientific publications of Nuclear Research Center Karlsruhe 1983

    1984-04-01

    This report contains the titles of the publications edited in the year 1983. The scientific and technical-scientific publications of the Nuclear Research Center Karlsruhe are printed as books, as original contributions in scientific or technical specialists' journals, as scripts for habilitation, thesis, scripts for diploma, as patents, as KfK-Reports (KfK=Kernforschungszentrum Karlsruhe) and are being presented as lectures on scientific meetings. No further separate abstracts of this list of publications were prepared. (orig./HBR) [de

  8. Gas chromatography at the Tritium Laboratory Karlsruhe

    Laesser, R.; Gruenhagen, S.

    2003-08-01

    Among the analytical techniques (mass spectrometry, laser Raman spectroscopy, gas chromatography, use of ionisation chambers) employed at the Tritium Laboratory Karlsruhe (TLK), gas chromatography plays a prominent role. The main reasons for that are the simplicity of the gas chromatographic separation process, the small space required for the equipment, the low investment costs in comparison to other methods, the robustness of the equipment, the simple and straightforward analysis and the fact that all gas species of interest (with the exception of water) can easily be detected by gas chromatographic means. The conventional gas chromatographs GC1 and GC2 used in the Tritium Measurement Techniques (TMT) System of the TLK and the gas chromatograph GC3 of the experiment CAPER are presented in detail, by discussing their flow diagrams, their major components, the chromatograms measured by means of various detectors, shortcomings and possible improvements. One of the main disadvantages of the conventional gas chromatography is the long retention times required for the analysis of hydrogen gas mixtures. To overcome this disadvantage, micro gas chromatography for hydrogen analysis was developed. Reduction of the retention times by one order of magnitude was achieved. (orig.)

  9. The Karlsruhe 4π barium fluoride detector

    Wisshak, K.; Guber, K.; Kaeppeler, F.; Krisch, J.; Mueller, H.; Rupp, G.; Voss, F.

    1989-12-01

    A new experimental approach has been implemented for accurate measurements of neutron capture cross sections in the energy range from 5 to 200 keV. The Karlsruhe 4π Barium Fluoride Detector consists of 42 crystals shaped as hexagonal and pentagonal truncated pyramids forming a spherical shell with 10 cm inner radius and 15 cm thickness. All crystals are supplied with reflector and photomultiplier, thus representing independent gamma-ray detectors. Each detector module covers the same solid angle with respect to a gamma-ray source located in the centre. The energy resolution of the 4π detector is 14% at 662 keV and 7% at 2.5 MeV gamma-ray energy, the overall time reslution is 500 ps and the peak efficiency 90% at 1 MeV. The detector allows to register capture cascades with 95% probability above a threshold energy of 2.5 MeV in the sum energy spectrum. Neutrons are produced via the 7 Li(p,n) 7 Be reaction using the pulsed proton beam of a Van de Graaff accelerator. The neutron spectrum can be taylored according to the experimental requirements in an energy range from 5 to 200 keV by choosing appropriate proton energies. A collimated neutron beam is passing through the detector and hits the sample in the centre. The energy of captured neutrons is determined via time of flight, the primary flight path being 77 cm. The combination of short primary flight path, a 10 cm inner radius of the spherical BaF 2 shell, and the low capture cross section of barium allows to discriminate background due to capture of sample scattered neutrons in the scintillator by time of flight, leaving part of the neutron energy range completely undisturbed. (orig./HSI) [de

  10. Forschungszentrum Rossendorf, Institute of Radiochemistry. Annual report 2004

    Bernhard, G [ed.

    2005-07-01

    The Institute of Radiochemistry (IRC), one of the six Institutes of the Forschungszentrum Rossendorf (FZR) performs basic and applied research in the fields of radiochemistry and radioecology. Motivation and background of our research are environmental processes relevant for the installation of nuclear waste repositories, for remediation of uranium mining and milling sites, and for radioactive contaminations caused by nuclear accidents and fallout. Because of their high radiotoxicity and long half-life the actinides are of special interest. The research is focused on a better understanding of the chemical behavior of actinides in the environment on a molecular level. We will increase our efforts to study both the speciation of actinides on bio-molecular interfaces and their transport in bio-systems. Current topics of our research work are: aquatic chemistry of actinides, actinides in bio-systems, interaction of actinides with solid phases, Reactive transport of actinides. About 60 scientists, technicians and PhD students are employed at the Institute of Radiochemistry. We accomplished many new scientific results in the past year, which are presented in this annual report. Among them only few can be highlighted in this preface. Further progress was achieved in understanding the formation and characterization of uranium containing colloids. The newly installed method of laser-induced breakdown detection was very helpful for the identification of uranium colloids under anoxic conditions. We were very successful in the determination of formation pathways and structure of various actinide complexes. These results contribute to a better understanding of actinide speciation in geo- and bio-systems, especially with respect to the chemical processes on the interfaces. The results achieved in the characterization of the properties, modification, and interaction of the S-layers of Bacillus sphaericus with uranium and some other heavy metals strengthen our hope to use this

  11. Forschungszentrum Rossendorf, Institute of Radiochemistry. Annual report 2004

    Bernhard, G.

    2005-01-01

    The Institute of Radiochemistry (IRC), one of the six Institutes of the Forschungszentrum Rossendorf (FZR) performs basic and applied research in the fields of radiochemistry and radioecology. Motivation and background of our research are environmental processes relevant for the installation of nuclear waste repositories, for remediation of uranium mining and milling sites, and for radioactive contaminations caused by nuclear accidents and fallout. Because of their high radiotoxicity and long half-life the actinides are of special interest. The research is focused on a better understanding of the chemical behavior of actinides in the environment on a molecular level. We will increase our efforts to study both the speciation of actinides on bio-molecular interfaces and their transport in bio-systems. Current topics of our research work are: aquatic chemistry of actinides, actinides in bio-systems, interaction of actinides with solid phases, Reactive transport of actinides. About 60 scientists, technicians and PhD students are employed at the Institute of Radiochemistry. We accomplished many new scientific results in the past year, which are presented in this annual report. Among them only few can be highlighted in this preface. Further progress was achieved in understanding the formation and characterization of uranium containing colloids. The newly installed method of laser-induced breakdown detection was very helpful for the identification of uranium colloids under anoxic conditions. We were very successful in the determination of formation pathways and structure of various actinide complexes. These results contribute to a better understanding of actinide speciation in geo- and bio-systems, especially with respect to the chemical processes on the interfaces. The results achieved in the characterization of the properties, modification, and interaction of the S-layers of Bacillus sphaericus with uranium and some other heavy metals strengthen our hope to use this

  12. Processing and monitoring liquid, radioactive effluents from the Wiederaufarbeitungsanlage Karlsruhe

    Hoehlein, G.; Huppert, K.L.; Winter, M.

    1977-01-01

    The Wiederaufarbeitungsanlage Karlsruhe (WAK) serves as a demonstration plant for the processing of highly-irradiated uranous oxide. The high active waste concentrates find interim storage at the WAK until they are solidified at a later stage. In contrast to this, the slightly- and the medium-active liquid wastes are transported to the decontamination facility of the Nuclear Research Centre Karlsruhe, where they are immediately processed. These liquid wastes contain about 1 per thousand of the activity inventary of the fuel elements processed. Monitoring of the radioactive waste water of the WAK is carried out by the Nuclear Research Centre's department radiation protection and safety. (orig.) [de

  13. Dispersion factors - tables and diagrams for the Karlsruhe site

    Papadopoulos, D.; Baer, M.; Honcu, S.

    1984-02-01

    Dispersion experiments were performed at the Nuclear Research Center for the Karlsruhe site. The evaluation of these experiments allowed to determine the parameters of lateral or vertical atmospheric dispersions. This report is a compilation of tables and diagrams showing the dispersion factors calculated with the help of the dispersion parameters. These dispersion factors are valid for the Karlsruhe site. They have been normalized to 1 m/s wind speed and to 1 g/s (or 1 Bq/s) source strength. (orig.) [de

  14. Forschungszentrum Rossendorf, Institute of Ion Beam Physics and Materials Research. Annual Report 1994

    Moeller, W.; Wieser, E.; Kirch, S.

    1995-03-01

    This volume contains the 1994 annual report describing the scientific activity of the Institute of Ion Beam Physics and Material Research (Forschungszentrum Rossendorf, FZR). This institute is devoted to the application of ion beams for the modification and analysis of near-surface layers of solids. (MSA)

  15. Computer aided operation of the Karlsruhe isochronous cyclotron using CAMAC

    Kappel, W.; Karbstein, W.; Kneis, W.; Moellenbeck, J.; Schweickert, H.; Volk, B.

    1976-01-01

    An extensive branch system is used with a NOVA 2/10 computer as an aid to the operation of the Karlsruhe Isochronous Cyclotron. The accelerator operator calls the different tasks by an interactive program system ''CICERO'' under BASIC. CAMAC operations are called by means of the ordinary BASIC Call mechanism through assembler routines

  16. Karlsruhe: En route to a superconducting r.f. separator

    1973-01-01

    A superconducting r.f. separator is under construction at Karlsruhe for use at the SPS in the beam-line to the Omega spectrometer. Tests on a section of the first 3 m deflector have given results close to the desired parameters.

  17. Bituminization of radioactive wastes at the Nuclear Research Center Karlsruhe

    Hild, W.; Kluger, W.; Krause, H.

    1976-05-01

    A summary is given of the main operational experience gained at the Nuclear Research Center Karlsruhe in 4 years operation of the bituminization plant for evaporator concentrates from low- and medium level wastes. At the same time some of the essential results are compiled that have been obtained in the R + D activities on bituminization. (orig.) [de

  18. List of scientific publications, Nuclear Research Center Karlsruhe 1984

    1985-04-01

    The report abstracted contains a list of works published in 1984. Papers not in print yet are listed separately. Patent entries take account of all patent rights granted or published in 1984, i.e. patents or patent specifications. The list of publications is classified by institutes. The project category lists but the respective reports and studies carried out and published by members of the project staff concerned. Also listed are publications related to research and development projects of the 'product engineering project' (PFT/Projekt 'Fertigungstechnik'). With different companies and institutes cooperating, PFT is sponsored by Nuclear Research Center Karlsruhe GmbH. The latter is also responsible for printing above publications. Moreover the list contains the publications of a branch of the Bundesforschungsanstalt fuer Ernaehrung which is located on the KfK-premises. The final chapter of the list summarizes publications dealing with guest-experiments and research at Nuclear Research Center Karlsruhe. (orig./PW) [de

  19. The Karlsruhe Nuclear Research Centre is being re-equipped

    Boehm, H.; Koerting, K.; Huncke, W.; Knapp, W.

    1986-01-01

    The Nuclear Research Centre in Karlsruhe was established over 25 years ago for the express purpose of studying nuclear engineering and its peaceful use. This goal has been achieved - what now. For some time a change has been taking place at the Research Centre: in the direction of man and environmental engineering. 'Bild der Wwissenschaft' has talked to Professor Horst Boehm, the chairman of the Nuclear Centre, about this change and the new areas of research to be concentrated on. (orig.) [de

  20. Forschungszentrum Rossendorf. Institute of Safety Research. Report. January 1998 - June 1999

    Weiss, F P; Rindelhardt, U [eds.

    1999-09-01

    The Institute of Safety Research is one of the five scientific institutes of Forschungszentrum Rossendorf e.V. The Forschungszentrum Rossendorf is a member of the 'Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz' and is funded by the Federal Ministry of Education and Research and by the Saxon Ministry of Science and Arts with 50% each. The research work of the institute aims at the assessment and increase of the safety and environmental sustainability of technical plants. The emphasis is put on the development and validation of mathematical and physical models for process and plant analysis, and of techniques for process and components monitoring. Subject of investigations are equally nuclear plants and installations of process industries. To analyse the thermo-fluiddynamics of normal plant operation and of the behaviour during accidents, physical models and computer codes are developed for multi-phase and multi-component flows, and for the space and time dependent heat release (neutron kinetics, chemical kinetics). (orig.)

  1. Forschungszentrum Rossendorf. Institute of Safety Research. Report. January 1998 - June 1999

    Weiss, F.P.; Rindelhardt, U. [eds.

    1999-09-01

    The Institute of Safety Research is one of the five scientific institutes of Forschungszentrum Rossendorf e.V. The Forschungszentrum Rossendorf is a member of the 'Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz' and is funded by the Federal Ministry of Education and Research and by the Saxon Ministry of Science and Arts with 50% each. The research work of the institute aims at the assessment and increase of the safety and environmental sustainability of technical plants. The emphasis is put on the development and validation of mathematical and physical models for process and plant analysis, and of techniques for process and components monitoring. Subject of investigations are equally nuclear plants and installations of process industries. To analyse the thermo-fluiddynamics of normal plant operation and of the behaviour during accidents, physical models and computer codes are developed for multi-phase and multi-component flows, and for the space and time dependent heat release (neutron kinetics, chemical kinetics). (orig.)

  2. Proceedings of the IEA-technical workshop on the test cell system for an international fusion materials irradiation facility, Karlsruhe, Germany, July 3-6, 1995. IEA-implementing agreement for a programme of research and development on fusion materials

    Moeslang, A.; Lindau, R.

    1995-09-01

    After a Conceptual Design Activity (CDA) study on an International Fusion Material Irradiation Facility (IFMIF) has been launched under the auspices of the IEA, working groups and relevant tasks have been defined and agreed in an IEA-workshop that was held September 26-29 1994 at Karlsruhe. For the Test Cell System 11 tasks were identified which can be grouped into the three major fields neutronics, test matrix/users and test cell engineering. In order to discuss recently achieved results and to coordinate necessary activities for an effective design integration, a technical workshop on the Test Cell System was initiated. This workshop was organized on July 3-6 1995 by the Institute for Materials Research I at the Forschungszentrum Karlsruhe and attended by 20 specialists working in the fields neutronics, fusion materials R and D and test cell engineering in the European Union, Japan, and the United States of America. The presentations and discussions during this workshop have shown together with the elaborated lists of action items, that has been achieved in all three fields, and that from the future IFMIF experimental program for a number of materials a database covering widerspread loading conditions up to DEMO-reactor relevant end-of-life damage levels can be expected. (orig.)

  3. The ''Nuclear-Karlsruhe'' air-filter system

    Berliner, P.; Ohlmeyer, M.; Stotz, W.

    1976-01-01

    Increasing requirements for exhaust-air filter systems used in nuclear facilities induced the Gesellschaft fuer Kernforschung to develop the ''Nuclear-Karlsruhe'' HEPA filter system. This novel development has profited by experience gained in previous incidents as well as by maitenance and decontamination work performed with different HEPA filter systems. The proved ''Nuclear-Karlsruhe'' system takes equally into account the demands for optimum safety, maximum efficiency and economy, and is distinguished by the following features: (1) The air current is defected by 180 0 in the casing. Deflection causes quite a number of improvements, results in substantial reduction of space requirements, and avoids the dispersion of pollutants to the clean-air side. Besides, the HEPA filter is protected from damage by condensed particles or foreign materials entrained; (2) The ''Nuclear-Karlsruhe'' system allows gas-tight filter replacement. Special replacement collars have been provided at the casing, which allow the tight fastening of replacement bags which are self-locking. (3) In-place testing in the operating condition can be carried out very conveniently because the air is deflected. Minimum leaks in the filter medium or in the filter gasket can be detected by the high-sensitivity visual oil-thread test, which makes leaks distinctly visible as oil mist threads through a transparent front window provided on the clean-air side. The test takes only some minutes and its sensitivity is hardly matched by any other technique. (4) The clamping mechanism is installed outside the casing, i.e. outside the polluted or aggressive media. The contact force is spring-loaded absolutely uniformly to the circular filter gasket. (5) For practical and econmic reasons the filter casings can be locked individually so as to be gas-tight. (6) The entire system is made of stainless or coated steel and metal parts which are corrosion and fire-resistant. (author)

  4. GSF-Forschungszentrum fuer Umwelt und Gesundheit, Institut fuer Hydrologie. Annual report 1995; GSF-Forschungszentrum fuer Umwelt und Gesundheit, Institut fuer Hydrologie. Jahresbericht 1995

    NONE

    1996-09-01

    The 1995 annual report of the Institute of Hydrology presents the findings of 19 current research projects on different subjects in hydrology. It is supplemented by information on cooperation with other scientific institutions in the form of lists of publications and reports, lectures and posters, university teaching projects, and finished and current dissertations. (VHE) [Deutsch] Der Jahresbericht 1995 des Institutes fuer Hydrologie im GSF-Forschungszentrum fuer Umwelt und Gesundheit stellt die Ergebnisse von derzeit 19 laufenden Untersuchungen zu unterschiedlichen hydrologischen Themen vor. Ergaenzt werden die Ausfuehrungen durch einen Ueberblick ueber die Zusammenarbeit mit anderen wissenschaftlichen Institutionen in Form von Verzeichnissen der Veroeffentlichungen und Berichte, der Vortraege und Poster, der Beitraege zur Lehre an Hochschulen sowie der abgeschlossenen und laufenden Dissertationen. (VHE)

  5. Materials research in the Nuclear Research Centre Karlsruhe

    Kleykamp, H.

    1990-03-01

    This report gives a survey of the research work done at the Institute for Material and Solids Research at Karlsruhe. The following subjects are dealt with: Instrumental analysis; producing thin films; corrosion; failure mechanism and damage analysis; fuel elements, ceramic nuclear fuels and can and structure materials for fast breeder reactors; material problems and ceramic breeding materials for nuclear fusion plants; glass materials for the treatment of radioactive waste; super-conducting materials; amorphous metals, new high alloyed steels; ceramic high performance materials; hard materials; compound materials and polymers. (MM) [de

  6. Status report on the Karlsruhe prototype superconducting proton linerar accelerator

    Citron, A.

    1974-01-01

    A short intoduction about linear accelerators in general and the advantage of using superconducting resonators is given. Subsequently some basic efforts on r.f. superconductivity are recalled and the status of technology of surface preparations is reported. The status of the Karlsruhe accelerator is given. In the low energy region some difficulties caused by mechanical instabilities had to be overcome. Protons have been accelerated in this part. Model studies for the subsequent sections of the accelerator have been started and look promising. (author)

  7. 2nd Karlsruhe International Summer School on Fusion Technologies

    Bahm, W.; Stycz, K.

    2008-01-01

    For the second time, the Karlsruhe Research enter together with European research institutions and industries invited young scientists and engineers to its ''International Summer School on Fusion Technologies.'' Fifty participants from all over Europe attended the lectures by 35 experts preesenting contributions from their areas of competence. Ten young scientists from India and another 10 from China were connected to the events by video link. Physics student Kornelia Stycz describes her impressions as a participant in the ''2 nd International Summer School on Fusion Technologies.'' (orig.)

  8. Waste management at the Karlsruhe Nuclear Research Center

    Hoehlein, G.; Lins, W.

    1982-01-01

    In the Karlsruhe Nuclear Research Center the responsibility for waste management is concentrated in the Decontamination Department which serves to collect and transport all liquid waste and solid material from central areas in the center for further waste treatment, clean radioactive equipment for repair and re-use or for recycling of material, remove from the liquid effluents any radioactive and chemical pollutants as specified in legislation on the protection of waters, convert radioactive wastes into mechanically and chemically stable forms allowing them to be transported into a repository. (orig./RW)

  9. Twenty-fifth anniversary of the Karlsruhe Nuclear Research Center

    Harde, R.

    1981-01-01

    The Karlsruhe Nuclear Research Center was founded on July 19, 1956. The initial company, in which the Federal Republic of Germany held a 30% interest, the State of Baden-Wuerttemberg 20%, and German industry 50%, was founded mainly for the purposes of building and operating a German-designed research reactor. In 1959, the Gesellschaft fuer Kernforschung mbH was founded for execution of the research and development activities, in which the Federal Republic of Germany held 75%, the State of Baden-Wuerttemberg 25% of the shares. The two companies were merged in 1963, after industry had donated its holdings in the initial company to the new company. In 1972, the financial holdings of the Federal Government were raised to 90%. On January 1, 1978, the company was named Kernforschungszentrum Karlsruhe GmbH (KfK). Over the past 25 years, KfK has received approx. DM 7 billion out of public funds. Important milestones in the development of nuclear technology in the Federal Republic contributed by KfK include the development of the fast breeder line and responsibility for construction of the first German fast breeder reactor, KNK; development of reprocessing technologies and responsibility for construction of the first German reprocessing plant, WAK; development of a uranium enrichment technique (separation nozzle method); important contributions to reactor safety, fusion research, and training in nuclear technology. (orig.) [de

  10. Getting Scientists Ready for Open Access: The Approaches of Forschungszentrum Jülich

    Thomas Arndt

    2018-05-01

    Full Text Available Many scientific institutions are faced with the question of how they should inform their scientists and scientific coordinators about the option of publishing open access. This task is one that libraries have taken upon themselves: libraries are familiar with the market participants and have years of experience in teaching information and publication literacy. This case report looks at two approaches taken by the Central Library of Forschungszentrum Jülich in 2017. It highlights the motivation, strategy, resources and implementation, as well as the first evaluation of both approaches. The first approach was a redesign of the training courses offered by the Central Library with a focus on the target groups and new contents. The second approach was implemented as part of International Open Access Week and involved offering an information event tailored to each scientific institute. The event was customized to meet the needs of the target group defined by each institute, the institute itself, and was organized individually. As a result of these efforts, the open access rate increased over the last few months and at 48% open access in 2017, Forschungszentrum Jülich is well on its way to achieving the open access goals set by the Helmholtz Association.

  11. Nuclear Research Center Karlsruhe, Central Safety Department. Annual report 1992

    Koelzer, W.

    1993-05-01

    The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, biophysics of multicellular systems, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1992 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

  12. Mapping the nuclear landscape. 50 years of the Karlsruher Nuklidkarte

    Normand, C.; Pfennig, G.; Magill, J.; Dreher, R.

    2009-01-01

    Radioactivity has been known for more than a hundred years. Nuclear data compilations through nuclide charts began in the 1920s with the work of Soddy, and were later rationalized in the Karlsruher Nuklidkarte. For 50 years, it has depicted the status of our nuclear knowledge in an easy reading form. It was born as an educational and scientific tool that gives access to the basic bricks that the nuclear Physics community needs to build the physics knowledge at the femtometer (10 -15 m) level. Nuclide data is a bridge between research and development. On the one hand, the nucleus can be regarded as a vast laboratory with, the possibility to test from fundamental concepts of the Standard Model to the genesis of the elements in the Universe. On the other hand, this data is also leading to applications in many areas of everyday life such as health care or environmental monitoring. (author)

  13. Operation of the Karlsruhe Isochronous Cyclotron in 1975

    Schulz, F.; Schweickert, H.

    1976-06-01

    The operation of the Karlsruhe Isochronous Cyclotron in 1975 is briefly surveyed. The main reasons for a very short period for maintenance, repair and installation, and several additional efforts to improve the reliability of the accelerator installation, are discussed. The status and the results of several technical developments for the cyclotron are described: 1) the axial injection system; 2) computer aided cyclotron operation; 3) ion source development; 4) capacitive current measurement at the external beam; 5) new correction coils for the cyclotron; 6) improvement of the neutron time-of-flight spectrometer. As there is an increasing interest in using this type of accelerator for research in fields other than nuclear physics, it was felt appropriate to present short surveys on investigations at our cyclotron in 1975 in the fields of: 1) solid state physics; 2) engineering; 3) materials research; 4) nuclear medicine; 5) nuclear chemistry. (orig.) [de

  14. 30th anniversary of Karlsruhe Nuclear Research Centre

    Koerting, K.

    1986-01-01

    One of the main goals in mind in 1956 when the Karlsruhe Nuclear Research Centre was founded, was to promote the peaceful uses of nuclear energy in the Federal Republic of Germany. The work accomplished since then by the various institutes of the Centre was particularly successful in the following: Development and construction of the first research reactor as an entirely national achievement; installation and operation of the MZFR reactor, as well as the compact sodium-cooled KNK reactor; the Nuclear Safety Project; the development of the separation nozzle method for uranium enrichment; and specific methods and equipment developed for safeguards systems to prevent nuclear materials diversion. Looking into the future, the tasks ahead will concentrate on the technology of energy generation by thermonuclear fusion, and on environmental pollution control and related methods, as well as industrial processes such as materials handling and process control by PDV and CAD. (orig./PW) [de

  15. Research and development at Kernforschungszentrum Karlsruhe - progress report 1991

    1992-01-01

    The Kernforschungszentrum Karlsruhe progress report is the 1991 issue of the scientific reports the institution is bound to submitt each year according to para. 13.4 of its articles of partnership. The points of main effort which are discussed reflect the institution's R and D scheme. The summaries submitted by the different institutes and departments are compiled by the topics and fields they deal with. The report gives an account of the progress under each of the KfK R and D projects. This correlation facilitates comparisons between the targets and actual achievements and elucidates the general relation between the individual tasks which often are in the care of several institutes at a time. The departments and institutes and their respective tasks are introduced, and a comprehensive appendix is attached which lists the 1991 publications. (orig./UA) [de

  16. Research and development at Kernforschungszentrum Karlsruhe - brief report 1991

    1992-01-01

    Research at Kernforschungszentrum Karlsruhe in the nineties is focussed on environmentally compatible high technologies with emphasis on environmental engineering, power engineering, microsystems technology, and selected fields of fundamental research. The KfK research and development trends are reflected by this brief report. The facts and figures inform researchers and specialists by summarizing the major results of the current research projects and by informing about the main targets and trends of long-time research programs and individual projects. The brief reports are completed by comprehensive, annual progress reports which discuss the implementation and results of the KfK research activities and compile references which list the various scientifico-technical reports, contributions to journals, conference papers, and other publications. (orig.) [de

  17. Karlsruhe Nuclear Research Center, Central Safety Department. Annual report 1993

    Koelzer, W.

    1994-04-01

    The Central Safety Department is responsible for handling all tasks of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: behavior of trace elements in the environment and decontamination of soil, behavior of tritium in the air/soil-plant system, improvement in radiation protection measurements and personnel dosimetry. This report gives details of the different duties, indicates the results of 1993 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

  18. Recent progress in the LACOMERA Project (Large-Scale Experiments on Core Degradation, Melt Retention and Coolability) at the Forschungszentrum Karslruhe

    Miassoedov, A.; Alsmeyer, H.; Eppinger, B.; Meyer, L.; Steinbrueck, M.

    2004-01-01

    The LACOMERA Project at the Forschungszentrum Karlsruhe (FZK) is a 3 year action within the 5 th Framework Programme of the EU. The overall objective of the project is to offer research institutions from the EU member countries and associated states access to four large-scale experimental facilities QUENCH, LIVE, DISCO-H, and COMET which can be used to investigate core melt scenarios from the beginning of core degradation to melt formation and relocation in the vessel, possible melt dispersion to the reactor cavity, and finally corium concrete interaction and corium coolability in the reactor cavity. As a result of two calls for proposals, seven organisations from four countries are expected to profit from the LACOMERA Project participating in preparation, conduct and analysis of the following experiments: QUENCH-L1: Air ingression impact on core degradation. The test has provided unique data for the investigation of air ingress phenomenology in conditions as representative as possible of the reactor case regarding the source term. QUENCH-L2: Boil-off of a flooded bundle. The test will be of a generic interest for all reactor types, providing a link between the severe accident and design basis areas, and would deliver oxidation and thermal hydraulic data at high temperatures. LIVE-L1: Simulation of melt relocation into the Reactor Pressure Vessel (RPV) lower head for VVER conditions. The experiment will provide important information on the melt pool behaviour during the stages of air circulation at the outer RPV surface with a subsequent flooding of the lower head. LIVE-L2: Transient corium spreading and its impact on the heat fluxes to the RPV wall and on the final shape of the melt in the RPV lower head. The test will address the questions of melt stabilisation and the effects of crust formation near the RPV wall for a nonsymmetrical melt pool shape. COMET-L1: Long-term 2D concrete ablation in siliceous concrete cavity at intermediate decay heat power level with

  19. Experiences with ATM in a multivendor pilot system at Forschungszentrum Julich

    Kleines, H.; Ziemons, K.; Zwoll, K.

    1998-08-01

    The ATM technology for high speed serial transmission provides a new quality of communication by introducing novel features in a LAN environment, especially support of real time communication, of both LAN and WAN communication and of multimedia streams. In order to evaluate ATM for future DAQ systems and remote control systems as well as for a high speed picture archiving and communications system for medical images, Forschungszentrum Julich has build up a pilot system for the evaluation of ATM and standard low cost multimedia systems. It is a heterogeneous multivendor system containing a variety of switches and desktop solutions, employing different protocol options of ATM. The tests conducted in the pilot system revealed major difficulties regarding stability, interoperability and performance. The paper presents motivations, layout and results of the pilot system. Discussion of results concentrates on performance issues relevant for realistic applications, e.g., connection to a RAID system via NFS over ATM.

  20. 19 February 2015 - Professor Holger Hanselka President Karlsruhe Institute of Technology Federal Republic of Germany

    Gadmer, Jean-Claude

    2015-01-01

    visiting the CMS cavern with CMS Collaboration Deputy Spokesperson K. Borras and CMS Collaboration, Team Leader, Karlsruhe Institut fur Technologie T. Muller and signing the Guest book with CERN Director-General R. Heuer. C. Schaefer present throughout.

  1. The economic and structural effects of the Nuclear Research Centre in Karlsruhe on its area

    Tebbert, H.; Sperling, P.

    The great building activity on the site of the Nuclear Research Centre in Karlsruhe, the setting up and maintenance of technical installations from an experimental setup on a laborytory scale to a prototype nuclear-powered system are of considerable, economic importance for numerous firms in the near and broader vicinity. In 1979, for example orders worth DM 100 million were placed with 850 firms in the town and the rural district of Karlsruhe by the Nuclear Research Centre. (orig.) [de

  2. Incineration of radioactive wastes at the Nuclear Research Center Karlsruhe

    Baehr, W; Hempelmann, W; Krause, H

    1976-06-01

    In 1971 a large incineration plant started operation in the Nuclear Research Center Karlsruhe. This plant is serving for routine incineration of up to 100 kg of combustible radioactive solids or 40 l of contaminated organic liquids and oils per hour. A dry off-gas cleaning system has been developed for this installation in which the fumes are cleaned by ceramic filter candles. After passing the filtering system and cooling, the off-gas is discharged directly through a stack. The activity concentration in the off-gas is measured by a continuous monitoring system. The ashes arising from the incineration are mixed with cement grout and filled into 200 l-drums. By this way approximately one drum of fixed ashes results from 100 drums of combustible wastes. During the first four years of operation, more than 4,000 m/sup 3/ of combustible solids and about 60 m/sup 3/ organic solvents have been incinerated in the plant. The operating experiences are presented.

  3. Recent advancements in fault tree methodology at Karlsruhe

    Caldarola, L.; Wickenhaeuser, A.

    1977-01-01

    A very fast analytical computer program for fault tree evaluation has already been developed at the German nuclear research center of Karlsruhe. This program can evaluate coherent systems assuming binary component states. Four different classes of components can be handled by the program: (1) unrepairable components, (2) repairable components with revealed faults, (3) repairable components with faults remaining unrevealed until next demand occurs and (4) repairable components with faults which are detected upon inspection. The program can perform also time dependent calculations. In particular the program can analyse systems characterized by two phases, one following the other in time (two time axis). A new computer program is also being developed. This computer program will be capable to analyse noncoherent systems with multistate components. The mathematical theory supporting the new program is described in the paper. In particular the algorithm for the identification of the prime implicants and the theory for the calculation of the occurrence probability and of the first occurrence probability of the TOP event are discussed

  4. Operation of the Karlsruhe Isochronous Cyclotron in 1976

    Schulz, F.; Schweickert, H.

    1977-08-01

    The operation of the Karlsruhe Isochronous Cyclotron in 1976 is briefly surveyed. The status and the results of the following technical developments are briefly described: 1) Computer aided cyclotron operation; 2) New correction coils for the cyclotron; 3) Non-intercepting measurement of the extraction rate; 4) Lambshift source for polarized deuterons; 5) Improvements of the 6 Li 3+ -Penning ion source; 6) New beam line to an irradiation room for machine parts; 7) Nova 2 computer system for nuclear physics experiments; 8) Routine production of Iodine-123 for nuclear medicine. - In the annual report 1975 we have included a section consisting of a series of brief reports on applied research in progress. This year we give a compilation of the current basic nuclear physics work at our cyclotron. The short papers prepared by the experimental groups are arranged according to the following topics: 1) Experiments using the 156 MeV 6 Li 3+ -beam; 2) Experiments using the 52 MeV polarized deuteron beam; 3) Further nuclear reactions; 4) Nuclear spectroscopy; 5) Measurements of nuclear magnetic moments; 6) Measurements with the neutron time-of-flight spectrometer. (orig.) [de

  5. List of scientific publications of the Kernforschungszentrum Karlsruhe in 1975

    1976-04-01

    The scientific and technical-scientific publications of the Gesellschaft fuer Kernforschung mbH Karlsruhe are published in the form of books, as primary contributions to scientific or technical journals, as theses as such for habilitation, or submitted for a diploma, as lectures at meetings, as patents, as 'KFK' reports, or as external reports. This report KFK 2325 contains the titles of documents published in 1975. Lectures have been included if the written text is available in the central library. In the case of patents, only first grants of a patent, patent specifications, or patents for public inspection have been considered. The list of publications is arranged according to institutes. Under projects, only the project reports and the publications by members of the project staff are listed. Registered, too, are the publications from the R+D activities within the projects entitled Process Control by Data Processing Systems (PDU) and Computer Aided Design and Development (CAD) which were published in the Nuclear Research Centre; the Gesellschaft fuer Kernforschung carries out these projects in cooperation with industrial enterprises and institutes. In addition to the Gesellschaft fuer Kernforschung's publications, those of the Institut fuer Strahlentechnologie of the Bundesanstalt fuer Ernaehrung have been included. The last chapter contains publications on experiments in the irradiation facilities of the Gesellschaft fuer Kernforschung, carried out by scientists, institutes, etc. not belonging to the Nuclear Research Centre. (orig./HK) [de

  6. Drawing the nuclear landscape: 50 years of the Karlsruhe Nuklidkarte; Trazando el paisaje nuclear 50 anos de historia de la Karlsruher Nuklidkarte

    Garcia Borge, M. J.; Normand, C.

    2010-07-01

    The map has been Nuklidkarte Karlsruhe nuclei since 1958 the work of thousands of physicists and hundreds of thousands experimental results produced in institutes research worldwide. With excellence as rule, has become over the years a reference the field of nuclear information. (Author) 19 refs.

  7. Current research and development at the Nuclear Research Center Karlsruhe

    Kuesters, H.

    1982-01-01

    The Nuclear Research Center Karlsruhe (KfK) is funded to 90% by the Federal Republic of Germany and to 10% by the State of Baden-Wuerttemberg. Since its foundation in 1956 the main objective of the Center is research and development (R and D) in the aera of the nuclear technology and about 2/3 of the research capacity is now devoted to this field. Since 1960 a major activity of KfK is R and D work for the design of fast breeder reactors, including material research, physics, and safety investigations; a prototype of 300 MWe is under construction now in the lower Rhine Valley. For enrichment of 235 U fissile material KfK developed the separation nozzle process; its technical application is realized within an international contract between the Federal Republic of Germany and Brazil. Within the frame of the European Programme on fusion technology KfK develops and tests superconducting magnets for toroidal fusion systems; a smaller activity deals with research on inertial confinement fusion. A broad research programme is carried through for safety investigations of nuclear installations, especially for PWRs; this activity is supplemented by research and development in the field of nuclear materials' safeguards. Development of fast reactors has to initiate research for the reprocessing of spent fuel and waste disposal. In the pilot plant WAK spent fuel from LKWs is reprocessed; research especially tries e.g. to improve the PUREX-process by electrochemical means, vitrification of high active waste is another main activity. First studies are being performed now to clarify the necessary development for reprocessing fast reactor fuel. About 1/3 of the research capacity of KfK deals with fundamental research in nuclear physics, solid state physics, biology and studies on the impact of technology on environment. Promising new technologies as e.g. the replacement of gasoline by hydrogen cells as vehicle propulsion are investigated. (orig.)

  8. Treatment of tritiated exhaust gases at the Tritium Laboratory Karlsruhe

    Hutter, E.; Besserer, U. [Kernforschungszentrum Karlsruhe GmbH (Germany); Jacqmin, G. [NUKEM GmbH, Industreistr, Alzenau (Germany)

    1995-02-01

    The Tritium Laboratory Karlsruhe (TLK) accomplished commissioning; tritium involving activities will start this year. The laboratory is destined mainly to investigating processing of fusion reactor fuel and to developing analytic devices for determination of tritium and tritiated species in view of control and accountancy requirements. The area for experimental work in the laboratory is about 800 m{sup 2}. The tritium infrastructure including systems for tritium storage, transfer within the laboratory and processing by cleanup and isotope separation methods has been installed on an additional 400 m{sup 2} area. All tritium processing systems (=primary systems), either of the tritium infrastructure or of the experiments, are enclosed in secondary containments which consist of gloveboxes, each of them connected to the central depressurization system, a part integrated in the central detritiation system. The atmosphere of each glovebox is cleaned in a closed cycle by local detritiation units controlled by two tritium monitors. Additionally, the TLK is equipped with a central detritiation system in which all gases discharged from the primary systems and the secondary systems are processed. All detritiation units consist of a catalyst for oxidizing gaseous tritium or tritiated hydrocarbons to water, a heat exchanger for cooling the catalyst reactor exhaust gas to room temperature, and a molecular sieve bed for adsorbing the water. Experiments with tracer amounts of tritium have shown that decontamination factors >3000 can be achieved with the TLK detritiation units. The central detritiation system was carefully tested and adjusted under normal and abnormal operation conditions. Test results and the behavior of the tritium barrier preventing tritiated exhaust gases from escaping into the atmosphere will be reported.

  9. Forschungszentrum Rossendorf. Institute of Bioinorganic and Radiopharmaceutical Chemistry. Annual report 2002

    Johannsen, B.; Seifert, S.

    2003-01-01

    In 2002 the Institute of Bioinorganic and Radiopharmaceutical Chemistry, one of five institutes in the Forschungszentrum Rossendorf e.V., continued and further developed its basic and application-oriented research. Research was focused on radiotracers as molecular probes to make the human body biochemically transparent with regard to individual molecular reactions. While further pursuing and extending our chemical, biological and medical activities in the PET Centre and being engaged in the coordination chemistry and radiopharmacology of technetium, rhenium and other metals, new lines of activity have also been opened up recently. This involves bioactive substances as they are present in food. Such substances may cause a health risk or may exert effects not yet fully understood. New biotechnological procedures in food processing also give rise to new questions that can be addressed by PET. As illustrated by the majority of contributions in this report, the Institute is predominantly engaged in radiopharmaceutical chemistry of both radiometals and the PET nuclides carbon-11 and fluorine-18. The improvement of labelling methods continued to remain an area of considerable endeavour. The review article on radiochemistry with the short-lived positron emitters 11 C and 18 F is meant to emphasize this field of research and to help to classify our contribution to this area. As for the radiometals, our studies agree with the more and more demanding insight that the coordination has a not sufficiently predictable impact on the in vivo behaviour of the molecule into which the chelate unit is integrated. Therefore, attempts to better understand and adjust the in vivo behaviour of the radiotracers are being continued. In order to reflect on and identify trends and perspectives, the Institute organized on March 7-8, 2002, an international conference on advances and perspectives in radiotracer development. The Institute's chemically and radiopharmacologically oriented activities

  10. Vom auf der Planeten im Spiegel des Chorgesangs. Knabenchor Tallinn und Orchester aus Estland geben ein Konzert in der Karlsruher Stephanskirche / Bernd Willimek

    Willimek, Bernd

    1992-01-01

    Planeetide liikumise peegeldus koorilaulus. Tallinna poistekoor ja orkester Eestist andsid kontserdi Karlsruhe Stephanskirhes. Eesti kultuuripäevadest Karlsruhes. Eesti muusikast esitati Urmas Sisaski, Mihkel Lüdigi, Veljo Tormise ja Rudolf Tobiase loomingut

  11. Analysis of simulated data for the KArlsruhe TRItium Neutrino experiment using Bayesian inference

    Riis, Anna Sejersen; Hannestad, Steen; Weinheimer, C.

    2011-01-01

    The KATRIN (Karlsruhe Tritium Neutrino) experiment will analyze the tritium β spectrum to determine the mass of the neutrino with a sensitivity of 0.2 eV (90% C.L.). This approach to a measurement of the absolute value of the neutrino mass relies only on the principle of energy conservation and can...

  12. Forschungszentrum Rossendorf. Institute of Bioinorganic and Radiopharmaceutical Chemistry. Annual report 2002

    Johannsen, B.; Seifert, S. (eds.)

    2003-01-01

    In 2002 the Institute of Bioinorganic and Radiopharmaceutical Chemistry, one of five institutes in the Forschungszentrum Rossendorf e.V., continued and further developed its basic and application-oriented research. Research was focused on radiotracers as molecular probes to make the human body biochemically transparent with regard to individual molecular reactions. While further pursuing and extending our chemical, biological and medical activities in the PET Centre and being engaged in the coordination chemistry and radiopharmacology of technetium, rhenium and other metals, new lines of activity have also been opened up recently. This involves bioactive substances as they are present in food. Such substances may cause a health risk or may exert effects not yet fully understood. New biotechnological procedures in food processing also give rise to new questions that can be addressed by PET. As illustrated by the majority of contributions in this report, the Institute is predominantly engaged in radiopharmaceutical chemistry of both radiometals and the PET nuclides carbon-11 and fluorine-18. The improvement of labelling methods continued to remain an area of considerable endeavour. The review article on radiochemistry with the short-lived positron emitters {sup 11}C and {sup 18}F is meant to emphasize this field of research and to help to classify our contribution to this area. As for the radiometals, our studies agree with the more and more demanding insight that the coordination has a not sufficiently predictable impact on the in vivo behaviour of the molecule into which the chelate unit is integrated. Therefore, attempts to better understand and adjust the in vivo behaviour of the radiotracers are being continued. In order to reflect on and identify trends and perspectives, the Institute organized on March 7-8, 2002, an international conference on advances and perspectives in radiotracer development. The Institute's chemically and radiopharmacologically

  13. List of the scientific publications of the Kernforschungszentrum Karlsruhe published in the year 1973

    1974-05-01

    The scientific and technical/scientific publications of the Gesellschaft fuer Kernforschung m.b.H. Karlsruhe are published as books, as primary publications in scientific or technical journals, as habilitations, theses, papers submitted for diplomas, as papers presented at scientific conferences, as patents, KFK (= Kernforschungszentrum Karlsruhe)-reports or as external reports. Report KFK 2025 contains all titles of the publications published in 1973. The list is arranged according to institutes. Under the heading 'Projekt' are only those reports which deal with projects and the publications of members of the project staff. Supplementary to the publications of the Gesellschaft fuer Kernforschung are those of the Institut fuer Strahlentechnologie der Bundesforschungsanstalt fuer Lebensmittelfrischhaltung, as this institute is situated on the premises of the nuclear research centre. (orig./LN) [de

  14. Karlsruhe Research Center, Nuclear Safety Research Project (PSF). Annual report 1994

    Hueper, R.

    1995-08-01

    The reactor safety R and D work of the Karlsruhe Research Centre (FZKA) has been part of the Nuclear Safety Research Projet (PSF) since 1990. The present annual report 1994 summarizes the R and D results. The research tasks are coordinated in agreement with internal and external working groups. The contributions to this report correspond to the status of early 1995. An abstract in English precedes each of them, whenever the respective article is written in German. (orig.) [de

  15. Cooperation between NIEP and Karlsruhe University in crust and upper mantle studies of the Vrancea area

    Prodehl, Claus

    2002-01-01

    Active cooperation between seismologists at Bucharest and Karlsruhe started in 1974 with the installation of seismic stations at Romanian dam sites. These stations also recorded the destructive earthquake of 1977 and formed the nucleus for a broader cooperation between seismologists at Bucharest and Karlsruhe and was followed by a continuing exchange of knowledge by vice versa research visits. The cooperation was finally intensively increased by the installation of a major priority research program on earthquake risk problems of Karlsruhe University with Romanian research institutions in 1996, when Romanian and German scientists from various fields (geology, seismology, civil engineering, operation research) organized themselves in the Collaborative Research Center 461 (CRC 461) 'Strong earthquakes: a challenge for geosciences and civil engineering' (Germany) and the Romanian Group for Strong Vrancea Earthquakes (RGVE) in a multidisciplinary attempt towards earthquake mitigation. The cooperation between the Geophysical and Geological Institutes of Karlsruhe University with both NIEP and the Faculty of Geology of Bucharest University focussed in particular on the deep geology of the Vrancea area and surrounding provinces with emphasis on seismicity studies and crust and upper-mantle investigations. Two long-range seismic wide-angle profiles from Bacau to the Danube south of Bucharest recorded in 1999 and from Transylvania to the Dobrogea recorded in 2001, both crossing each other in the Vrancea area, will provide a detailed 3-dimensional crustal structure image of Vrancea and adjacent Carpathians and their surrounding basins, while a temporary array of 120 mobile stations distributed throughout southeastern Romania recorded local and far-distant earthquakes for about 6 months in 1999 which will allow to derive a 3-dimensional tomographic image of the underlying uppermost mantle to depths of about 300 km. (author)

  16. Program budget 1992 of the Karlsruhe Nuclear Research Center. As of November 19, 1991

    1992-01-01

    In the future, the research program of the Nuclear Research Center in Karlsruhe will concentrate on three areas, which are of the same status over the medium term: Environmental research, energy research and micro system technology and fundamental research. The central infrastructure, the financial planning and the assignment of research and development projects of the Nuclear Research Center are presented in tables. (orig./HP) [de

  17. Design of a simple magnetic spectrograph for the Karlsruhe isochronous cyclotron

    Gils, H.J.

    1980-12-01

    The ion-optical design of a simple magnetic spectrograph for studies of nuclear reactions on the Karlsruhe cyclotron is described. The spectrograph allows to determine the nuclear charge, the mass number, the reaction angle and the impulse (energy) of charged particles, which are emitted from the target. The spectrographs possibilities cover an appropriate range of likely nuclear reactions which are induced by light and heavy particles up to mass number A=20 and energies of 26 MeV per nucleon [de

  18. The Karlsruhe code MODINA for model independent analysis of elastic scattering of spinless particles

    Gils, H.J.

    1983-12-01

    The Karlsruhe code MODINA (KfK 3063, published November 1980) has been extended in particular with respect to new approximations in the folding models and to the calculation of errors in the fourier-Bessel potentials. The corresponding subroutines replacing previous ones are compiled in this first supplement. The listings of the fit-routine-package FITEX missing in the first publication of MODINA are also included now. (orig.) [de

  19. Labour Court Karlsruhe, decision of October 15, 1985 (co-determination in matters of security control)

    Anon.

    1986-01-01

    In its decision of October 15, 1985, the Labour Court of Karlsruhe deals with the order for security controls in nuclear research centres. The co-determination of the works council in this field is excluded, if the operator is obliged by the licensing authority to carry out these controls pursuant to the operating licence according to sec. 7 and sec. 17 of the Atomic Energy Act. (WG) [de

  20. List of scientific publications from the Karlsruhe Nuclear Research Centre of the year 1977

    1978-03-01

    The scientific and technical-scientific publications from the Karlsruhe Nuclear Research Centre comprise books, original papers in scientific or technical journals, diploma, doctoral and habilitation theses, as well as papers held at scientific conferences, patents, KfK reports, and external reports (KfK = Kernforschungszentrum Karlsruhe). The present report, KfK 2625, contains the titles of the 1977 publications, scientific papers being listed only after the manusscript has been filed in the Central Library of the research centre. As for patents, the titles given refer to either first issues of a patent, or to patents laid open for inspection. Progress reports are listed according to subjects involved. The whole list of publications is ordered according to the names of institutes and of projects, the latter group covering the titles of published project reports and of publications written by individual cooperators of a given project, as well as publications printed by the Karlsruhe Nuclear Research Centre, written by cooperators of the following projects: 'Process control with data processing plants', (PDV), and 'Computer-assisted development' (CAD). These projects are carried out together with other firms and instutes. Yet another group of publications covered are those of the Federal Institute for Food Research, and of guest scientists working in the Centre. (orig./HK) [de

  1. News from the Library: The 8th edition Karlsruhe nuclide chart has been released

    CERN Library

    2012-01-01

    The 8th edition of the Karlsruhe Nuclide Chart contains new data not found in the 7th edition.   Since 1958, the well-known Karlsruhe Nuclide Chart has provided scientists with structured, valuable information on the half-lives, decay modes and energies of radioactive nuclides. The chart is used in many disciplines in physics (health physics, radiation protection, nuclear and radiochemistry, astrophysics, etc.) but also in the life and earth sciences (biology, medicine, agriculture, geology, etc.). The 8th edition of the Karlsruhe Nuclide Chart contains new data on 737 nuclides not found in the 7th edition. In total, nuclear data on 3847 experimentally observed ground states and isomers are presented. A new web-based version of this chart is in the final stages of development for use within the Nucleonica Nuclear Science Portal - a portal for which CERN has an institutional license. The chart is also available in paper format.   If you want to buy a paper version of the chart, ple...

  2. Partitioning of minor actinides: research at Juelich and Karlsruhe Research Centres

    Geist, A.; Weigl, M.; Gompper, K.; Modolo, G.

    2007-01-01

    Full text of publication follows. The work on minor actinide (MA) partitioning carried out at Karlsruhe and Juelich is integrated in the EC FP6 programme, EUROPART. Studies include the DIAMEX process (co-extraction of MA and lanthanides from PUREX raffinate) and the SANEX process (separation of MA from lanthanides). Aspects ranging from developing and improving highly selective and efficient extraction reagents, to fundamental structural studies, to process development and testing are covered. SANEX is a challenge in separation chemistry because of the chemical similarity of trivalent actinides and lanthanides. The extracting agents 2,6-di(5,6-di-propyl-1,2,4-triazine-3-yl)pyridine (n-Pr-BTP), developed at Karlsruhe, and the synergetic mixture of di(chloro-phenyl)di-thio-phosphinic acid (R2PSSH) with tri-n-octyl-phosphine oxide (TOPO), developed at Juelich, are considered a breakthrough because of their high separation efficiency in acidic systems. Separation factors for americium over lanthanides of more than 30 (R2PSSH+TOPO) and 130 (n-Pr-BTP) are achieved. To gain understanding of these selectivities, comparative investigations on the structures of curium and europium complexed with these SANEX ligands were performed at Karlsruhe. Extended X-ray absorption fine structure (EXAFS) analysis revealed distinct structural differences between curium and europium complexed with R2PSSH + TOPO, though no such differences were found for n-Pr-BTP. These investigations were therefore complemented by time-resolved laser fluorescence spectroscopic investigations (TRLFS), showing complex stabilities and speciation to differ between n-Pr-BTP complexes of curium and europium. Kinetics of mass transfer was studied for both R2PSSH+TOPO and n-Pr-BTP systems. For the R2PSSH + TOPO system, diffusion was identified to control extraction rates. For the n-Pr-BTP system, a slow chemical reaction was identified as the rate-controlling process. These results were implemented into computer

  3. Efficient data management techniques implemented in the Karlsruhe Monte Carlo code KAMCCO

    Arnecke, G.; Borgwaldt, H.; Brandl, V.; Lalovic, M.

    1974-01-01

    The Karlsruhe Monte Carlo Code KAMCCO is a forward neutron transport code with an eigenfunction and a fixed source option, including time-dependence. A continuous energy model is combined with a detailed representation of neutron cross sections, based on linear interpolation, Breit-Wigner resonances and probability tables. All input is processed into densely packed, dynamically addressed parameter fields and networks of pointers (addresses). Estimation routines are decoupled from random walk and analyze a storage region with sample records. This technique leads to fast execution with moderate storage requirements and without any I/O-operations except in the input and output stages. 7 references. (U.S.)

  4. Computer aided process control equipment at the Karlsruhe reprocessing pilot plant, WAK

    Winter, R.; Finsterwalder, L.; Gutzeit, G.; Reif, J.; Stollenwerk, A.H.; Weinbrecht, E.; Weishaupt, M.

    1991-01-01

    A computer aided process control system has been installed at the Karlsruhe Spent Fuel Reprocessing Plant, WAK. All necessary process control data of the first extraction cycle is collected via a data collection system and is displayed in suitable ways on a screen for the operator in charge of the unit. To aid verification of displayed data, various measurements are associated to each other using balance type process modeling. Thus, deviation of flowsheet conditions and malfunctioning of measuring equipment are easily detected. (orig.) [de

  5. PV market in Germany and activities of the metropolitan utility of Karlsruhe

    Weissmueller, G.; Lewald, N.

    2001-01-01

    The introduction of the Renewable Energy Law in Germany in combination with the 100,000 roof program lead to an explosion of the market for grid-connected PV systems, with all possible effects such as the formation of new PV companies, job creation and the installation of a huge number of PV systems. But there is also one negative aspect: higher prices for the modules due to production bottle-necks. The Municipal Utility of Karlsruhe (SWK) commits itself to the sector of renewable energy especially PV. Some of these activities are also described in the paper

  6. Summary of the contributions to reactor safety research commissioned by the Republic of Austria and done by the Forschungszentrum Seibersdorf from 1987 to 1990

    Sonneck, G.; Sdouz, G.

    1991-09-01

    In 1987 the Forschungszentrum Seibersdorf was commissioned by the Republic of Austria with the collaboration in the Nuclear Safety Research Index, the OECD-LOFT-Programme and the International Coordinated Assessment and Application Programme (ICAAP). This report summarises the work done from 1987 to 1990, mainly in the field of thermal hydraulics, fuel rod behaviour and source term. Besides some analyses for experiments done in loops based on BWRs and PWRs of western design the work concentrated on safety researchs for WWERS. (Authors)

  7. Compact sodium cooled nuclear power plant with fast core (KNK II- Karlsruhe), Safety Report

    1977-09-01

    After the operation of the KNK plant with a thermal core (KNK I), the installation of a fast core (KNK II) had been realized. The planning of the core and the necessary reconstruction work was done by INTERATOM. Owner and customer was the Nuclear Research Center Karlsruhe (KfK), while the operating company was the Kernkraftwerk-Betriebsgesellschaft mbH (KBG) Karlsruhe. The main goals of the KNK II project and its special experimental test program were to gather experience for the construction, the licensing and operation of future larger plants, to develop and to test fuel and absorber assemblies and to further develop the sodium technology and the associated components. The present safety report consists of three parts. Part 1 contains the description of the nuclear plant. Hereby, the reactor and its components, the handling facilities, the instrumentation with the plant protection, the design of the plant including the reactor core and the nominal operation processes are described. Part 2 contains the safety related investigation and measures. This concerns the reactivity accidents, local cooling perturbations, radiological consequences with the surveillance measures and the justification of the choice of structural materials. Part three finally is the appendix with the figures, showing the different buildings, the reactor and its components, the heat transfer systems and the different auxiliary facilities [de

  8. List of scientific publications of the Kernforschungszentrum Karlsruhe of the year 1982

    1983-04-01

    The scientific and technical-scientific publications of the Kernforschungszentrum Karlsruhe are published as books, as original contributions in scientific or technical journals, as habilitation theses, doctoral theses, diploma theses, as patens, as KfK reports (KfK=Kernforschungszentrum Karlsruhe), and are held as lectures at scientific meetings. This report KfK 3425 contains the titles of the documents which are published in 1982. Lectures which have not been printed yet are listed separately from the literature. All patent rights issued or published in the yeaer 1982 are cited: patents,(Offenlegungsschriften) published patent applications examined only as to abvious defects but not as to patentability (DE-OS), (Auslegeschriften) printed specifications of patent applications after examination (DE-AS). The list of publications is arranged by institutes. Unter ''projects'' only the published project reports as well as publications of the members of the respective project staff are listed. The publications printed at the Kernforschungszentrum from the r and d project ''production engineering (PFT)'' performed by the Kernforschungszentrum as the responsible body in cooperation with firms and institutes, as well as the projects ''process control with data processing devices (PDV)'' and ''computer-aided development, construction and fabrication (CAD)'' have also been included in the list. Moreover, the list contains the publications of the Kernforschungszentrum branch of the Bundesforschungsanstalt fuer Ernaehrung. In the last chapter-publications on guest experiments at the Kernforschungszentrum have been compiled. (orig./GG) [de

  9. Radiation exposure to the staff of the Karlsruhe Nuclear Research Center, 1969-1981

    Koelzer, W.

    1983-07-01

    Evaluation of the data from the personnel dosimetry of the staff monitored from 1969 until 1981 at the Karlsruhe Nuclear Research Center (Kernforschungszentrum Karlsruhe GmbH) gives a total external dose of 6,335 rem including natural radiaiton background. The occupational exposure of the radiation workers within this period comes to 3,076 rem, which gives an average annual external occupational exposure of 0.14 rem. In 1,832 cases an annual dose between 0.5 and 1.5 rem per year and in 353 cases a dose of more than 1.5 rem per year have been measured. The highest value, measured in 1972, amounted to 6.8 rem. During the period from 1969 until 1981 more than 34,000 incorporation measurements were performed with the whole body counter and the lung counter, 1,963 cases with positive findings. In 96% of the cases the values of incorporated activity were inferior to 1% - in 70% even inferior to 0.1% - of the maximum permissible body burden values of ICRP 2. Only 5 cases exceeded these values. (orig.) [de

  10. Muusikamaail. "Musica nova" Helsingis. Händeli festival Karlsruhes. Ooperikonkurss algas. Preemiaid ja tunnustusi. Ka Parmas uus ooperimaja. / Priit Kuusk

    Kuusk, Priit, 1938-

    2002-01-01

    Soomes toimuvast uue muusika festivalist. Händeli festivalist Karlsruhes. Üle-euroopalisest noorte ooperilauljate konkursist. Ooperilaulja Doris Soffel sai Rootsi riigilt Kuningliku Põhjatähe ordeni. Sebastian Baumgarten sai ooperi "Tosca" eest noore režissööri preemia. Parmas valmis uus ooperimaja

  11. Bituminization of radioactive wastes at the Nuclear Research Center Karlsruhe. Experience from plant operation and development work

    Hild, W; Kluger, W; Krause, H

    1976-05-01

    A summary is given of the main operational experience gained at the Nuclear Research Center Karlsruhe in 4 years operation of the bituminization plant for evaporator concentrates from low- and medium level wastes. At the same time some of the essential results are compiled that have been obtained in the R + D activities on bituminization.

  12. Experiences in the management of plutonium-containing solid-wastes at the Nuclear Research Center Karlsruhe

    Baehr, W.; Hild, W.; Scheffler, K.

    1974-10-01

    Solid-plutonium-containing wastes from a fuel production plant, a reprocessing plant and several research laboratories are treated at the decontamination department of the Karlsruhe Nuclear Research Center for disposal in the Asse salt mine. Conditioning as well as future aspects in α-waste management are the subject of this Paper. (orig.) [de

  13. Overview of LWR severe accident research activities at the Karlsruhe Institute of Technology

    Miassoedov, Alexei; Albrecht, Giancarlo; Foit, Jerzy-Jan; Jordan, Thomas; Steinbrück, Martin; Stuckert, Juri; Tromm, Walter

    2012-01-01

    The research activities in the light water reactor (LWR) severe accidents domain at Karlsruhe Institute of Technology (KIT) are concentrated on the in- and ex-vessel core melt behavior. The overall objective is to investigate the core melt scenarios from the beginning of core degradation to melt formation and relocation in the vessel, possible melt dispersion to the reactor cavity and to the containment, corium concrete interaction and corium coolability in the reactor cavity, and hydrogen behaviour in reactor systems. The results of the experiments contribute to a better understanding of the core melt sequences and thus improve safety of existing and, in the long-term, of future reactors by severe accident mitigation measures and by safety installations where required. This overview paper describes the experimental facilities used at KIT for severe accident research and gives an overview of the main directions and objectives of the R&D work. (author)

  14. Analytic of tritium-containing gaseous species at the Tritium Laboratory Karlsruhe

    Laesser, R.; Caldwell-Nichols, C.; Doerr, L.; Glugla, M.; Gruenhagen, S.; Guenther, K.; Penzhorn, R.-D.

    2001-01-01

    At the Tritium Laboratory Karlsruhe (TLK) laser Raman spectroscopy, gas chromatography, mass spectroscopy, calorimetry and ionisation chambers are used to determine the composition of tritium gas mixtures. For the first time a laser Raman experiment was assembled with an actively controlled resonator which yields a 50 times higher Raman signal and with all components (laser, optics, Raman cell and spectrometer) installed inside a glove box. Three gas chromatographs, each with up to six detectors, can determine the gases and their tritiated fractions expected in fusion devices down to the sub-ppm range. Tritium in solids, liquids and gases is determined by means of three calorimeters with a dynamic ranges of up to five orders of magnitude and a lower detection limit of 1 GBq. Since any of these techniques has its shortcomings the best analytical approach is to analyse a sample by more than one method

  15. EL CONGRESO DE KARLSRUHE: PASO DEFINITIVO HACIA LA QUÍMICA MODERNA

    Ramón Cid Manzano

    2009-01-01

    Full Text Available Estamos celebrando en este año 2009 el 140 aniversario de la publicación de la primera tabla periódica y el 90 aniversario de la creación del IUPAC. Ambos acontecimientos se relacionan directamente con el congreso de Karlsruhe llevado a cabo en esa ciudad alemana en 1860. Este congreso fué convocado para que los químicos europeos pudieran discutir sobre asuntos muy controvertidos, como la naturaleza atómica de la materia, la nomenclatura química y los pesos atómicos. El objetivo de este artículo es proporcionar a los lectores algunos datos sobre este congreso para entender mejor cómo la tabla periódica fue desarrollada y cómo la química se convirtió en una ciencia moderna.

  16. KNK II, Compact Sodium-Cooled Reactor in the Nuclear Research Center Karlsruhe

    1978-01-01

    The report gives an overview of the project of the sodium-cooled fast reactor KNK II in the nuclear research center KfK in Karlsruhe. This test reactor was the preparatory stage of the prototype plant SNR 300 and had several goals: to train operating personal, to practice the licensing procedures in Germany, to get experience with the sodium technology and to serve as a test bed for fast breeder core components. The report contains contributions of KfK as the owner and project managing organization, of INTERATOM as the design and construction company and of the KBG as the plant operating organization. Experience with and results of relevant aspects of the project are tackled: project management, reactor core and component design, safety questions and licensing, plant design and test programs [de

  17. Research and development at Karlsruhe Nuclear Research Center. Progress report 1993

    1994-01-01

    The Kernforschungszentrum Karlsruhe progress report is the 1993 issue of the scientific reports the institution is bound to submitt each year according to para. 13.4 of its articles of partnership. The points of main effort which are discussed reflect the institution's R and D scheme. The summaries submitted by the different institutes and departments are compiled by the topics and fields they deal with. The report gives an account of the progress under each of the KfK R and D projects. This correlation facilitates comparisons between the targets and actual achievements and elucidates the general relation between the individual tasks which often are in the care of several institutes at a time. The departments and institutes and their respective tasks are introduced, and a comprehensive appendix is attached which lists the 1993 publications. (orig.) [de

  18. Radioecological studies on plutonium and iodine-129 in the surroundings of the Karlsruhe reprocessing plant

    Schuettelkopf, H.; Pimpl, M.

    1982-01-01

    Plutonium and 129 I are emitted from the Karlsruhe Reprocessing Plant (WAK) together with exhaust air and liquid effluents. Plutonium dispersion in the environment was used to calculate the dispersion factors, to determine the rates of deposition on grass and of the total deposition rates, to measure the distribution at depth of plutonium in the soil and to evaluate the contamination of plants and animals in the environment of the Karlsruhe Reprocessing Plant. The plutonium emissions with the liquid effluents were studied to deepen understanding of the process of sedimentation in a river system. Sediments, water samples, aerosols and living organisms from the Altrhein were examined. Factors of transfer to various organisms living in the Altrhein were measured. Most of the 129 I release from WAK goes via the exhaust air: this even applies after installation of an iodine filter into the exhaust air stack. The 129 I contamination of the environmental air, the soil, thyroids and milk was measured. Regarding the milk/air concentration ratio, a mean value of 210 was determined with a scattering range of 50 to 1480. Soil contamination was studied very thoroughly. Iodine-129 is transported into lower soil layers at a very slow rate only, if at all. The contamination of the soil with 129 I remained largely constant during the three years of investigations. The low rates of deposition of 0.02 to 0.05 cm/s indicate that 129 I is released to the environmental air again from plants undergoing the process of rotting. (author)

  19. Developement of technologies for nuclear fusion at the Karlsruhe Research Center. Pt. 1

    Bahm, W.; Dammertz, G.; Glugla, M.; Janeschitz, G.; Komarek, P.; Mack, A.

    2002-01-01

    The planned ITER plant needs plasma heating powers of approx. 70-150 MW. Work performed at the Karlsruhe Research Center under this heading mainly comprises the development of microwave oscillators (gyrotrons) and their use for an electron cyclotron resonance heating system and for non-inductive plasma current operation. The plasma, which is approx. 100 million C hot, is confined in a 'magnetic cage' so as to avoid any contact with the wall structures of the vacuum vessel. Building up a magnetic field of this magnitude requires field strengths of at least 2-5 tesla in the plasma; field strengths of 11-13 tesla at the magnet coils are required for future fusion plants, such as ITER. Consequently, the development of the required future superconducting magnet coils enjoys high priority. The blanket, i.e. the enclosure around the combustion chamber of a fusion reactor, plays a major role in the design of a future fusion power plant. Blanket concepts meeting technical requirements are being developed and studied. A blanket must meet three requirements: It must convert the neutron energy into heat, breed the tritium fuel by nuclear reactions, and shield the magnets from neutron and gamma radiations. The fuel cycle of fusion reactors is determined by the gaseous phase of the two hydrogen isotopes, deuterium and tritium. In general, hydrogen handling technologies have been developed to a high level, but can be transferred to the handling of deuterium and radioactive tritium only to a very limited extent. Consequently, the necessary development work is carried out. The state of the plasma, also with respect to its purity, is a factor of special importance, as impurities will cause the plasma to dissolve and thus the fusion reaction to break down. Primary vacuum pumps, another area of activity of the Karlsruhe Research Center, first must evacuate the reactor vessel and then, during operation, maintain the necessary atmosphere. (orig.) [de

  20. Scientists from all over the world attend the 2005 Frederic Joliot/Otto Hahn summer school at Karlsruhe; Wissenschaftler aus aller Welt bei der ''Frederic Joliot/Otto Hahn Summer School 2005'' in Karlsruhe

    Sanchez, V.H.; Fischer, U. [Forschungszentrum Karlsruhe, Inst. fuer Reaktorsicherheit, Eggenstein-Leopoldshafen (Germany)

    2005-10-01

    The Frederic Joliot/Otto Hahn Summer School annually organized alternately by the Karlsruhe Research Center and the Commissariat a l'Energie Atomique (CEA), Cadarche, France, this year was held at the Karlsruhe Congress Center. In line with the mission of the School to disseminate nuclear competence an a broad basis among young scientists from all over the world, lectures covered reactor physics, nuclear fuels, and nuclear systems. Speakers from leading international research institutions presented introductions to their respective fields, outlined the current state of the art, and also highlighted areas in need of further development and, thus, likely to offer challenges to young scientists. Next year's Frederic Joliot/Otto Hahn Summer School will be organized by CEA and held at Cadarache, France. (orig.)

  1. Scientists from all over the world attend the 2005 Frederic Joliot/Otto Hahn summer school at Karlsruhe

    Sanchez, V.H.; Fischer, U.

    2005-01-01

    The Frederic Joliot/Otto Hahn Summer School annually organized alternately by the Karlsruhe Research Center and the Commissariat a l'Energie Atomique (CEA), Cadarche, France, this year was held at the Karlsruhe Congress Center. In line with the mission of the School to disseminate nuclear competence an a broad basis among young scientists from all over the world, lectures covered reactor physics, nuclear fuels, and nuclear systems. Speakers from leading international research institutions presented introductions to their respective fields, outlined the current state of the art, and also highlighted areas in need of further development and, thus, likely to offer challenges to young scientists. Next year's Frederic Joliot/Otto Hahn Summer School will be organized by CEA and held at Cadarache, France. (orig.)

  2. IAEA fast reactor knowledge preservation initiative. Project focus: KNK-II reactor, Karlsruhe, Germany

    2004-08-01

    This Working Material (including the attached CD-ROM) documents progress made in the IAEA's initiative to preserve knowledge in the fast reactor domain. The brochure describes briefly the context of the initiative and gives an introduction to the contents of the CD-ROM. In 2003/2004 a first focus of activity was concentrated on the preservation of knowledge related to the KNK-II experimental fast reactor in Karlsruhe, Germany. The urgency of this project was given by the impending physical destruction of the installation, including the office buildings. Important KNK-II documentation was brought to safety and preserved just in time. The CD-ROM contains the full texts of 264 technical and scientific documents describing research, development and operating experience gained with the KNK-II installation over a period of time from 1965 to 2002, extending through initial investigations, 17 years of rich operating experience, and final shutdown and decommissioning. The index to the documents on the CD-ROM is printed at the end of this booklet in chronological order and is accessible on the CD by subject index and chronological index. The CD-ROM contains in its root directory also the document 'fr c lassification.pdf' which describes the classification system used for the present collection of documents on the fast reactor KNK-II

  3. Investigation of the tritium level in the environment of the Karlsruhe Nuclear Research Center

    Koenig, L.A.; Winter, M.; Schueler, H.; Tachlinski, W.

    1976-06-01

    Under an IAEA sponsored measurement program the tritium level is investigated in the immediate and more distant environment of the Karlsruhe Nuclear Research Center. The tritium concentration in precipitations, surface, ground and drinking water is measured within a long-term program. In addition, relationships existing between the tritium concentration of plants and the concentrations of ground water, precipitation, soil and air humidities are investigated at three points in special series of measurement. A summary report is presented on recent measured results. According to these results, the annual mean values for precipitations and surface water tend to rise. In 1975 the annual mean values amounted to 0.89 nCi/l of tritium concentration in precipitations in the more distant environment of the Nuclear Research Center and to 0.68 nCi/l in the Rhine river. In plants tritium concentrations were observed which correspond to that measured in the humidity of the air. The radiation exposure of people living in large towns is calculated to be about 50 μrem/a in the region monitored, due to the presence of tritium in the drinking water. A little group of the population takes up as much as 110 μrem/a. (orig.) [de

  4. In-situ testing of HEPA filters in the nuclear Karlsruhe filter system

    Ohlmeyer, M.; Stotz, W.

    1977-01-01

    Nuclear plant operators and filter manufacturers are endeavouring to improve environmental protection by intensifying process control and/or improving filter quality. In-situ testing is an important element in these efforts since it represents a direct means of checking the success or otherwise of a particular development. The arrangements for in-situ testing should satisfy the following minimum requirements: the staff should not be exposed to risk during the test; the test method should be objective and reproducible as well as being as sensitive as possible; the test method should permit detection of individual leaks in the filter system so that they can be remedied as efficiently as possible; the test equipment should not necessitate modifications to the extract systems or plant construction; the test should be simple and capable of being carried out with a minimum of effort and equipment. GfK has developed the 'Nuclear-Karlsruhe' filter housing in accordance with these principles. This housing permits in-situ testing similar to the DIN 24184 visual oil-fog test or the DOP test. External visual checks on the general condition of the filter is also possible. A safe system of filter changing with a specially designed plastic bag attachment at an accessible height considerably increases the degree of protection of operating personnel

  5. Incineration plant for radioactive waste at the Nuclear Research Center Karlsruhe

    Baehr, W.; Hempelmann, W.; Krause, H.

    1977-02-01

    In 1971 a large incineration plant started operation in the Nuclear Research Center Karlsruhe. This plant is serving for routine incineration of up to 100 kg of combustible radioactive solids or 40 l of contaminated organic liquids and oils per hour. A dry off-gas cleaning system has been developed for this installation in which the flue gases are cleaned by ceramic filter candles. After passing the filtering system and cooling the off-gas is discharged directly through a stack. The activity concentration in the off-gas is measured by a continuous monitoring system. The ashes arising from the incineration are mixed with cement grout and filled into 200 ldrums. By this way approximately one drum of fixed ashes results from 100 drums of combustible wastes. During the first four years of operation, more than 4,000 m 3 of combustible solids and about 60 m 3 organic solvents have been incinerated in the plant. The operating experiences are presented. (orig.) [de

  6. List of the scientific publications of the Karlsruhe Nuclear Research Center in 1989

    1990-05-01

    The scientific and technological-scientific publications of the Kernforschungszentrum Karlsruhe appear as books, ar original articles in scientific or technological periodicals, as postdoctoral theses, theses, dissertations, patents and KfK reports and are given as lectures at scientific conferences. The report KfK 4625 contains the titles of all publications from 1989. In the case of patents, all rights established or published during 1989 are indicated: patents, information sheets (DE-OS). The list of publications is ordered according to institutes. Under projects, only published project reports and publications by staff working on the particular projects are listed. Also included are publications printed in the Kernforschungszentrum from research and development plans within the Production Technology Project (PFT) and the project called 'European Research Center for the Control of Air Pollution' (PEF), which were carried out by the Kernforschungszentrum as project sponsor in cooperation with firms and institutes. The list also includes publications of the branch of the Federal Research Institute for Nutrition based at the Kernforschungszentrum. (orig./HK) [de

  7. List of the scientific publications of the Karlsruhe Nuclear Research Center in 1987

    1988-05-01

    The scientific and technological-scientific publications of the Kernforschungszentrum Karlsruhe appear as books, as original articles in scientific or technological periodicals, as postdoctoral theses, theses, dissertations, patents and KfK reports and are given as lectures at scientific conferences. The report KfK 4425 contains the titles of all publications from 1987. In the case of patents, all rights established or published during 1987 are indicated: patents, information sheets (DE-OS). The list of publications is ordered according to institutes. Under projects, only published project reports and publications by staff working on the particular projects are listed. Also included are publications printed in the Kernforschungszentrum from research and development plans within the Production Technology Project (PFT) and the project called 'European Research Center for the Control of Air Pollution' (PEF), which were carried out by the Kernforschungszentrum as project sponsor in cooperation with firms and institutes. The list also includes publications of the Federal Research Institute for Nutrition based at the Kernforschungszentrum. (orig./HK) [de

  8. Water detritiation processing of JET purified waste water using the TRENTA facility at Tritium Laboratory Karlsruhe

    Michling, R., E-mail: robert.michling@kit.edu; Bekris, N.; Cristescu, I.; Lohr, N.; Plusczyk, C.; Welte, S.; Wendel, J.

    2013-10-15

    Highlights: • Operation of a water detritiation facility under optimized conditions for high detritiation performances. • Improvement of operational procedures to process tritiated waste water. • Handling and reduction of tritiated waste water to achieve enriched low volume tritiated water for sufficient storage. • Demonstration of the efficient availability of the TRENTA WDS facility for technical scale operation. -- Abstract: A Water Detritiation System (WDS) is required for any Fusion machine in order to process tritiated waste water, which is accumulated in various subsystems during operation and maintenance. Regarding the European procurement packages for the ITER tritium fuel cycle, the WDS test facility TRENTA applying the Combined Electrolysis Catalytic Exchange (CECE) process was developed, installed and is currently in operation at the Tritium Laboratory Karlsruhe (TLK). Besides the on-going R and D work for the design of ITER WDS, the current status of the TRENTA facility provides the option to utilize the WDS for processing tritiated water. Therefore, in the framework of the EFDA JET Fusion Technology Work Programme 2011, the TLK was able to offer the capability on a representative scale to process tritiated water, which was produced during normal operation at JET. The task should demonstrate the availability of the CECE process to handle and detritiate the water in terms of tritium enrichment and volume reduction. The operational program comprised the processing of purified tritiated water from JET, with a total volume of 180 l and an activity of 74 GBq. The paper will give an introduction to the TRENTA WDS facility and an overview of the operational procedure regarding tritiated water reduction. Data concerning required operation time, decontamination and enrichment performances and different operating procedures will be presented as well. Finally, a preliminary study on a technical implementation of processing the entire stock of JET

  9. Water detritiation processing of JET purified waste water using the TRENTA facility at Tritium Laboratory Karlsruhe

    Michling, R.; Bekris, N.; Cristescu, I.; Lohr, N.; Plusczyk, C.; Welte, S.; Wendel, J.

    2013-01-01

    Highlights: • Operation of a water detritiation facility under optimized conditions for high detritiation performances. • Improvement of operational procedures to process tritiated waste water. • Handling and reduction of tritiated waste water to achieve enriched low volume tritiated water for sufficient storage. • Demonstration of the efficient availability of the TRENTA WDS facility for technical scale operation. -- Abstract: A Water Detritiation System (WDS) is required for any Fusion machine in order to process tritiated waste water, which is accumulated in various subsystems during operation and maintenance. Regarding the European procurement packages for the ITER tritium fuel cycle, the WDS test facility TRENTA applying the Combined Electrolysis Catalytic Exchange (CECE) process was developed, installed and is currently in operation at the Tritium Laboratory Karlsruhe (TLK). Besides the on-going R and D work for the design of ITER WDS, the current status of the TRENTA facility provides the option to utilize the WDS for processing tritiated water. Therefore, in the framework of the EFDA JET Fusion Technology Work Programme 2011, the TLK was able to offer the capability on a representative scale to process tritiated water, which was produced during normal operation at JET. The task should demonstrate the availability of the CECE process to handle and detritiate the water in terms of tritium enrichment and volume reduction. The operational program comprised the processing of purified tritiated water from JET, with a total volume of 180 l and an activity of 74 GBq. The paper will give an introduction to the TRENTA WDS facility and an overview of the operational procedure regarding tritiated water reduction. Data concerning required operation time, decontamination and enrichment performances and different operating procedures will be presented as well. Finally, a preliminary study on a technical implementation of processing the entire stock of JET

  10. Range of applications of modern superconducting synchrotron radiation sources using the source planned at Karlsruhe (KSSQ) as an example

    Moser, H.O.

    1989-06-01

    The performance of the Karlsruhe synchrotron radiation source which was designed originally for X-ray deep-etch lithography comes close to that of first and second generation synchrotron radiation sources. The range of applications spanned by KSSQ is therefore quite similar to that of those machines. The present report displays a first collection of topics from the fields of surface analysis, solid state and materials research, and biology which could be investigated using KSSQ by interested groups coming from KfK and its surroundings. (orig.) [de

  11. Public relations activities of the Karlsruhe Nuclear Research Center - a national research center contributes to opinion forming

    Koerting, K.

    1988-01-01

    At the Karlsruhe Nuclear Research Center, the Public Relations Department directly reports to the Chief Executive Officer. The head of the Public Relation Department acts as spokesman of the center in the public, which requires him to be fully informed of the work of all units and of the policy goals of the executive board. The key tools used by the Public Relations Department are KfK-Hausmitteilungen, accident information, the scientific journal KfK-Nachrichten, press releases, exhibitions, fairs, guided tours, and nuclear energy information staff. (DG)

  12. 9th PEF status colloquium from March 9-11, 1993 at the Nuclear Research Center Karlsruhe

    Horsch, F.; Filby, W.G.; Fund, N.; Gross, S.; Kaendler, G.; Reinhardt, W.

    1993-04-01

    During the 9-11th of March 1993 the ninth status report of the project ''European Research Centre for Air Pollution Prevention Measures'' (PEF) took place at the Nuclear Research Center Karlsruhe. Progress reports on the following topics were presented: investigation into damage and elucidation of the causes and effects of forest decline (task 1A); research into atmospheric dispersion, conversion and deposition of airborne pollutants (task 2); development and optimization of industrial-technical processes to reduce or avoid emissions (task 3); and providing instruments and making recommendations to the industrial and political sectors (task 4). (orig./BBR) [de

  13. Generallandesarchiv Karlsruhe. Inventory 69, Karlruhe Nuclear Research Center. Records of the management of Kernreaktor Bau- und Betriebsgesellschaft mbH and of Gesellschaft fuer Kernforschung mbH, Karlsruhe (1956-1974)

    Gleitsmann, R.J.; Hochstuhl, K.; Wagner, H.; Miller, A.; Cramer, D.; Oetzel, G.

    1995-01-01

    The Karlsruhe Research Center is Germany's largest multidisciplinary research establishment in the fields of natural sciences and technology. In its relatively short period of existence, the Research Center has experienced vivid evolution and modification of original research goals, and even a profound change of the major tasks and goals laid down at the time of its foundation, which most obviously expresses itself in the change of name from Nuclear Research Center into Research Center, effective since January 1995. The wealth of important material accumulated in the archives of the Center throughout the almost 40 years of existence is a treasure for the historian and offered the tempting and useful task to process the material into a historical survey offering the many facettes of the history: in the end, the result combines an important piece of history of technology with the history of the Land of Baden-Wuerttemberg, the region, and the neighbouring city of Karlsruhe. In addition, the publication in hand also offers insight into the sociological aspects of the research work performed in the Center, and the interactive impetus of research and development in the interest of society at large. (orig./HP) [de

  14. Development of a regional concept for energy management for the region of Karlsruhe. Final report; Entwicklung eines regionalen Energiemanagement-Konzeptes und Anwendung auf die TechnologieRegion Karlsruhe. Endbericht

    Rentz, O.; Fichtner, W.; Frank, M. [Karlsruhe Univ. (T.H.) (Germany). Inst. fuer Industriebetriebslehre und Industrielle Produktion; Wolf, M.A.; Rejman, M.; Eyerer, P. [Fraunhofer-Institut fuer Chemische Technologie (ICT) (Germany); Reimert, R.; Schulz, A.; Buren, V. v. [Karlsruhe Univ. (T.H.) (Germany). Engler-Bunte-Institut Bereich 1 - Gas, Erdoel und Kohle; Schaefers, B.; Bernart, Y. [Karlsruhe Univ. (T.H.) (DE). Institut fuer Soziologie (IfSoz) (Germany)

    2002-09-01

    Major objectives of this project are: to prepare a cross-disciplinary analysis of all characteristic aspects of the energy supply and demand patterns of a group of selected energy-intensive companies in the Karlsruhe and Rhine harbour area (5 industrial power consumers, 1 utility), to identify practical approaches for optimization and integration of energy and material flows, (networking), and to develop optimised investment and energy supply options within the framework of given conditions. The basis of the optimal solution and energy network presented and explained in detail is a new combined-cycle power plant running as a gas-fired CHP plant, substituting about 50% of the systems formerly used. (orig./CB) [German] Fragestellungen der Effizienzsteigerung und der Verwertung von Abfaellen und Abwaerme gewinnen an Relevanz vor dem Hintergrund der begrenzten Aufnahmekapazitaet der Umweltmedien fuer Schadstoffe. Im Rahmen des Projektes wurde am Beispiel der Region Karlsruhe (5 Industrieunternehmen und 1 EVU) die Entwicklung betriebsuebergreifender Energieversorgungssysteme (Netzwerke) interdisziplinaer analysiert und beschrieben. Zielsetzungen des Projekts waren unter anderem: Bestimmung von zukunftsfaehigen Optionen, intelligente Vernetzung von Energiestroemen, wirtschaftliche Optimierung betriebsuebergreifender Energiemanagement-Loesungen. Die optimale vorgestellte Loesung ist charakterisiert durch den Neubau einer zentralen, gasgefeuerten GuD-Anlage, die etwa die Haelfte der bisherigen Anlagen ersetzt und zusammen mit den weiterhin genutzten Anlagen die Energieversorgung der Unternehmen sicherstellt. (orig./CB)

  15. Karlsruhe Nuclear Research Center, Institute for Meteorology and Climate Research. Progress report on research and development work in 1993

    1994-03-01

    The Institute for Meteorology and Climate Research is operated by Karlsruhe Nuclear Research Centre in cooperation with Karlsruhe University. It investigates mesoscale and global atmospheric processes. Work on mesoscale processes focuses on interactions between atmosphere, soil and vegetation via the exchange of momentum, energy, water, and materials. Another field of primary interest are the flow processes and turbulent exchange processes in the lower troposphere. Parallel to the experiments, numerical simulation models for describing and predicting mesospheric climate-relevant processes and atmospheric exchange processes were used and improved upon. For remote processing of atmospheric parameters, a satellite-based data processing system was used for recording land surface parameters and vertical profiles and meteorological variables that are applicable for climatological studies and for the validation of numerical models. For recording and interpretation of the spatial and time-dependent distribution of trace elements, measuring instruments in the field of air chemistry were newly developed or improved upon, especially with a view towards high time resolution of the measured data. Ozone research is a key issue of the remote measurements. Contributions were made primarily in the framework of international research programmes (e.g. EASOE) on the degradation of the atmospheric ozone layer in the higher latitudes of the northern hemisphere. In addition to the experimental investigations, the transport of stratospheric trace elements was simulated numerically. (orig./KW) [de

  16. The determination of Pu-241 by liquid scintillation counting in liquid effluents of the Karlsruhe Nuclear Research Center

    Godoy, J.M.; Schuettelkopf, H.; Pimpl, M.

    1983-04-01

    A procedure was developed to measure Pu-241 by liquid scintillation counting. Sample preparation was performed by electroplating of plutonium on stainless steel planchets. To correct the selfabsorption, the linear dependence of counting efficiency in the liquid scintillation counter from the resolution in the alpha spectrometer was used. Pu-238, Pu-239+240 and Pu-241 were measured in the liquid effluents of the Karlsruhe Nuclear Research Center (KfK). The concentrations in monthly mixed samples ranged from 0.07 until 46 nCi Pu-238/m 3 , from 0.13 until 2.1 nCi Pu-239+240/m 3 and from 25 until 190 nCi Pu-241/m 3 . Between 5.4% and 41% of the plutonium content of the KfK waste water are released to the River Old Rhine. The values for the activity ratio Pu-238/Pu-239+240 are between 0.39 and 1.1 and for Pu-241/Pu-239+240 are between 11 and 300. The mean value for Pu-241/Pu-239+240 is 61. The dose exposure of the environmental population of the Karlsruhe Nuclear Research Center caused by released Pu-241 is negligible low. (orig./HP) [de

  17. Design of electronic measurement and quench detection equipment for the Current Lead Test facility Karlsruhe (CuLTKa)

    Hollik, Markus; Fietz, Walter H.; Fink, Stefan; Gehrlein, Mirko; Heller, Reinhard; Lange, Christian; Möhring, Tobias

    2013-01-01

    The Current Lead Test facility Karlsruhe (CuLTKa) is under construction at the Karlsruhe Institute of Technology (KIT) to perform acceptance tests of high temperature superconductor (HTS) current leads (CL). CuLTKa is in progress and present planning expects the completion in 2013. The data acquisition system is based on a modular design with electronic measurement and monitoring equipment covering a test voltage of 50 kV DC against ground. It provides plug-in units which enable temperature and voltage measurement at high voltage potential and in addition quench detection units which detect a loss of superconductivity reliably and quickly to avoid damage of the superconducting device under test. Prototype units for quench detection, temperature and voltage measurement have been successfully tested. Six temperature measurement units are already in use in the KIT test facility TOSKA and operated reliably during the acceptance tests of the HTS current leads for Wendelstein 7-X (W7-X) in 2011/2012. CuLTKa will be used first for 26 current leads which will be built in KIT for the fusion experiment JT-60SA. The present paper gives an overview of the design of the electronic measurement and quench detection equipment

  18. Vom Klangrausch des Nordwinds und der leeren Tafel der Seele. Lepo Sumeras vierte Symphonie "Serena Borealis" in Karlsruhe uraufgeführt: Eri Klas dirigierte im Konzert der Badischen Staatskapelle zu den Kulturtagen auch Musik von Arvo Pärt und Edua

    Hartmann, Ulrich

    1992-01-01

    Lepo Sumera neljanda sümfoonia "Serena Borealis" esiettekanne Karlsruhes: Eri Klas dirigeeris kontserdil kultuuripäevade raames ka Arvo Pärdi ja Eduard Tubina muusikat. Eesti muusikute esinemisest Karlsruhe kultuuripäevadel

  19. Report on the first two IAEA-courses on nuclear power project planning and implementation in Karlsruhe

    Reuter, H.H.

    1977-01-01

    There is no more doubt about the necessity of utilizing nuclear energy to cover the world energy requirements. A growing number of developing countries find themselves compelled to use nuclear energy in order to meet their rising energy demands and, hence, to improve their conditions of life. On the other hand, the lack of suitable experts having gathered experience is particularly perceptible in these countries. For this reason, IAEA has organized training courses on an international level, which are held in Karlsruhe (Federal Republic of Germany), Saclay (France), and Argonne (USA). Taking into account the situation in the respective developing country, independent courses are being offered on ''Nuclear Power Project Planning and Implementation'' and on ''Construction and Operation Management.'' The first course of this type was held at the Karlsruhe Nuclear Research Center from September 8 until December 17, 1975. It was attended by 35 participants from 20 countries. In cooperation with industry and national as well as international authorities the syllabus proposed by IAEA was translated into a training program including all essential questions on the introduction of nuclear energy in developing countries. The next course will take place from September 6 until November 30, 1976. A detailed analysis is presented of the extent to which the expectations of participants have been fulfilled. The status of nuclear technology and the number of candidates having sufficient knowledge is of particular importance in this context. A very significant aspect consists in teaching not only theoretical knowledge but integrating practical application in such training courses, which is demonstrated by examples

  20. Scientists from all over the world attended the 'Frederic Joliot/Otto Hahn Summer School 2011' at the Karlsruhe Institute of Technology (KIT)

    Sanchez, Victor H.; Fischer, Ulrich

    2011-01-01

    The Karlsruhe Institute of Technology (KIT) and the Commissariat r leEnergie Atomique et Aux Energies Alternatives (CEA), Cadarache, alternate in organizing the annual 'Frederic Joliot/Otto Hahn Summer School.' This year's event, the 17th since its inception, was held in Karlsruhe, Germany on August 25 to September 3. Its topic was 'High-fidelity Modeling for Nuclear Reactors: Challenges and Prospects.' Here is a list of the subjects covered: - Status and perspectives of modeling and its role in design, operation, and safety. - Thermal hydraulics of nuclear reactors and simulation of 2 phase flows. - Structural mechanics, structure? fluid interaction, and seismic safety. - Advanced simulation in neutronics and reactor physics. - Progress in simulating fuel and materials behavior. - Multiphysics and uncertainty analysis methods. Experts from eight leading international research institutions and universities presented, and discussed with the 59 participants from 19 countries, the current state of the art and most recent development trends in the subjects listed above. (orig.)

  1. Removal efficiency of silver impregnated filter materials and performance of iodie filters in the off-gas of the Karlsruhe reprocessing plant WAK

    Herrmann, F.J.; Herrmann, B.; Hoeflich, V.

    1997-01-01

    An almost quantitative retention of iodine is required in reprocessing plants. For the iodine removal in the off-gas streams of a reprocessing plant various sorption materials had been tested under realistic conditions in the Karlsruhe reprocessing plant WAK in cooperation with the Karlsruhe research center FZK. The laboratory results achieved with different iodine sorption materials justified long time performance tests in the WAK Plant. Technical iodine filters and sorption materials for measurements of iodine had been tested from 1972 through 1992. This paper gives an overview over the most important results, Extended laboratory, pilot plant, hot cell and plant experiences have been performed concerning the behavior and the distribution of iodine-129 in chemical processing plants. In a conventional reprocessing plant for power reactor fuel, the bulk of iodine-129 and iodine-127 is evolved into the dissolver off-gas. The remainder is dispersed over many aqueous, organic and gaseous process and waste streams of the plant. Iodine filters with silver nitrate impregnated silica were installed in the dissolver off-gas of the Karlsruhe reprocessing plant WAK in 1975 and in two vessel vent systems in 1988. The aim of the Karlsruhe iodine research program was an almost quantitative evolution of the iodine during the dissolution process to remove as much iodine with the solid bed filters as possible. After shut down of the WAK plant in December 1990 the removal efficiency of the iodine filters at low iodine concentrations had been investigated during the following years. 12 refs., 2 figs., 2 tabs

  2. Removal efficiency of silver impregnated filter materials and performance of iodie filters in the off-gas of the Karlsruhe reprocessing plant WAK

    Herrmann, F.J.; Herrmann, B.; Hoeflich, V. [Wiederaufarbeitungsanlage Karlsruhe (Germany)] [and others

    1997-08-01

    An almost quantitative retention of iodine is required in reprocessing plants. For the iodine removal in the off-gas streams of a reprocessing plant various sorption materials had been tested under realistic conditions in the Karlsruhe reprocessing plant WAK in cooperation with the Karlsruhe research center FZK. The laboratory results achieved with different iodine sorption materials justified long time performance tests in the WAK Plant. Technical iodine filters and sorption materials for measurements of iodine had been tested from 1972 through 1992. This paper gives an overview over the most important results, Extended laboratory, pilot plant, hot cell and plant experiences have been performed concerning the behavior and the distribution of iodine-129 in chemical processing plants. In a conventional reprocessing plant for power reactor fuel, the bulk of iodine-129 and iodine-127 is evolved into the dissolver off-gas. The remainder is dispersed over many aqueous, organic and gaseous process and waste streams of the plant. Iodine filters with silver nitrate impregnated silica were installed in the dissolver off-gas of the Karlsruhe reprocessing plant WAK in 1975 and in two vessel vent systems in 1988. The aim of the Karlsruhe iodine research program was an almost quantitative evolution of the iodine during the dissolution process to remove as much iodine with the solid bed filters as possible. After shut down of the WAK plant in December 1990 the removal efficiency of the iodine filters at low iodine concentrations had been investigated during the following years. 12 refs., 2 figs., 2 tabs.

  3. Determination and behaviour of plutonium emitted with liquid effluents and exhaust air into the environment of the Nuclear Research Centre Karlsruhe

    Schuettelkopf, H.; Pimpl, M.

    1986-01-01

    The plutonium concentrations in the surroundings of the Karlsruhe Nuclear Research Centre (KfK) are in the range of variation of the global plutonium contamination caused by fallout of atmospheric nuclear tests. Exclusively in the sediments of the Old River Rhine, which serves as main canal for the liquid effluents, higher plutonium concentrations could be detected. The dose exposure of the population living in the environment of the KfK caused by the measured plutonium concentrations is negligible low. From the Karlsruhe Reprocessing Plant (WAK) and the facilities needed to decontaminate radioactive wastes 0.48 GBq (13 mCi) plutonium alpha activity has been emitted within 11 years of operation until 1982 - 1/3 with the liquid effluents and 2/3 with the exhaust air. Following the pathway with the exhaust air, plutonium concentrations in the environment of the Karlsruhe Reprocessing Plant were measured in groundlevel air, in soil, in plants, in food and in animal tissues. Radioecological parameters like dispersion factors, deposition velocities, migration velocities in soil and transfer soil-to-plant were investigated. Following the pathway with the liquid effluents, plutonium concentrations were measured in surface waters, sediments, water plants, plankton and animals. Dilution and sedimentation behaviour were studied as well as the transfer water-to-plant and water-to-animals. (orig.) [de

  4. XAS and XRF investigation of an actual HAWC glass fragment obtained from the Karlsruhe vitrification plant (VEK)

    Dardenne, K.; González-Robles, E.; Rothe, J.; Müller, N.; Christill, G.; Lemmer, D.; Praetorius, R.; Kienzler, B.; Metz, V.; Roth, G.; Geckeis, H.

    2015-05-01

    Several sections of HAWC glass rods remaining at the end of glass pouring at the Karlsruhe Vitrification Plant (VEK) were retained during vitrification operation in 2009-2010 and transferred to the KIT-INE shielded box line for later glass product characterization. A mm sized fragment with a contact dose rate of ∼590 μSv/h was selected for pilot XAS/XRF investigations at the INE-Beamline for actinide science at the ANKA synchrotron radiation source. The experiment was aimed at elucidating the potential of direct radionuclide speciation with an emphasis on the fission products Se and Tc in highly active nuclear materials and at assessing the possible influence of the γ-radiation field surrounding highly active samples on the beamline instrumentation. While the influence of γ-radiation turned out to be negligible, initial radionuclide speciation studies by XAFS were most promising. In addition to Se and Tc speciation, the focus of these initial investigations was on the possibility for direct actinide speciation by recording corresponding L3-edge XAFS data. The registration of high quality XANES data was possible for the actinide elements U, Np, Pu and Am, as well as for Zr.

  5. Forschungszentrum Juelich. Annual report 2012; Forschungszentrum Juelich. Jahresbericht 2012

    Frick, Frank; Roegener, Wiebke

    2013-07-15

    This annual report is structured as follows: 1 Highlight Energy Research (Next-generation batteries. Innovative material for the fuel cell. Smart material for solar cells. Store from midnight - Study on electromobility. Fuels from renewable electricity, carbon dioxide and water.). 2. Knowledge management (Create knowledge, pass knowledge, share knowledge and apply knowledge), and 3. Appendix (finance, boards and committees, organizational chart). [German] Dieser Jahresbericht ist wie folgt strukturiert: 1. Highlight Energieforschung (Batterien der naechsten Generation. Innovativer Werkstoff fuer die Brennstoffzelle. Smartes Material fuer Solarzellen. Laden ab Mitternacht - Studie zur Elektromobilitaet. Kraftstoffe aus Oekostrom, Kohlendioxid und Wasser). 2. Wissensmanagement (Wissen schaffen, Wissen weitergeben, Wissen teilen und Wissen anwenden) und 3. Anhang (Finanzen, Organe und Gremien, Organigramm).

  6. Forschungszentrum Juelich. Annual report 2011; Forschungszentrum Juelich. Jahresbericht 2011

    Frick, Frank; Roegener, Wiebke

    2012-07-15

    The annual report presents ten primary scientific reports selected for information of the general reader, representing the research priorities, a survey of the research and development programmes, a list of research institutes, cooperation agreements for technology transfer, facts and figures showing the organizational structure, personnel employed, financing aspects, and aspects of the service departments.

  7. Forschungszentrum Juelich. Annual report 2008; Forschungszentrum Juelich. Jahresbericht 2008

    Frick, Frank; Roegener, Wiebke

    2009-07-15

    The following topics are dealt with: The precise lattice QCD mass calculation of protons and neutrons by means of the JUGENE supercomputer, the early diagnosis of morbus Alzheimer, the fabrication of vertebra-column implants consisting of porus titanium, software for the improvement of the spatial resolution in electron microscopy by means of aberration corrections. (HSI)

  8. Forschungszentrum Juelich. Annual report 2009; Forschungszentrum Juelich. Jahresbericht 2009

    Frick, Frank; Roegener, Wiebke; Stahl-Busse, Brigitte

    2010-07-15

    The annual report presents ten primary scientific reports selected for information of the general reader, representing the research priorities, a survey of the research and development programmes, a list of research institutes, cooperation agreements for technology transfer, facts and figures showing the organizational structure, personnel employed, financing aspects, and aspects of the service departments.

  9. Forschungszentrum Juelich. Annual report 2008

    Frick, Frank; Roegener, Wiebke

    2009-07-01

    The following topics are dealt with: The precise lattice QCD mass calculation of protons and neutrons by means of the JUGENE supercomputer, the early diagnosis of morbus Alzheimer, the fabrication of vertebra-column implants consisting of porus titanium, software for the improvement of the spatial resolution in electron microscopy by means of aberration corrections. (HSI)

  10. On-the-job training as new element in RP training: experiences from the ENETRAP pilot module in Karlsruhe

    Moebius, Siegurd; Bickel, Angela; Schmitt-Hannig, Annemarie; Coeck, Michele

    2008-01-01

    A suitable qualification for responsible personnel in Radiation Protection (RP) must be in general a combination of theoretical knowledge, and the ability (competency) to practice RP. While the theoretical knowledge is acquired by suitable education and by attending training courses, competency and skills can only be obtained by appropriate on-the-job training (OJT) followed by a period of work experience. From the feedback of questionnaires from 30 EU countries within the framework of the EU supported ENETRAP project it can be concluded that OJT provides better chances for future job opportunities and increases international flexibility. As result we recommend covering OJT together with education and training in the Basic Safety Standards and their guidelines for implementation. OJT should be specified by its content (syllabus, learning objectives), availability of necessary facilities and infrastructures as precondition for OJT, assessment of the competence of the participant, format of certificate, recognition of OJT, and responsibilities of host organisation and trainees. OJT should remain a key element in the remodelled 'European RP Training'. Based on these recommendations a two weeks training module on 'Occupational RP: Specificities of Waste Management and Decommissioning' designed for radiation protection professionals has been compiled at the Karlsruhe Training Centre FTU. While the first week of the pilot course focuses on the theoretical knowledge ranging from waste classification to decontamination techniques and transport of radioactive materials, the second week is addressed to practical training as OJT from clearance of radioactive waste, operative RP in the Decontamination Department to RP work in a Research Reactor under decommissioning. Special emphasis is devoted to RP aspects and active involvement of the participants in workshops and case studies. The results of the pilot run with participants from 8 different European countries are reported

  11. Coordinated and government-sponsored research in the Federal Republic of Germany. The Karlsruhe Nuclear Research Centre: Baking a new cake with the old mixture

    Mock, W.

    1986-01-01

    This article in the series gives an outline of the main research projects of the Karlsruhe Nuclear Research Centre, reviewing the formerly purely nuclear research tasks and going over to the new projects which increasingly encompass non-nuclear research subjects. Still, about 50% of the KfK research activities will be devoted in future to projects such as the fast breeder reactor, nuclear fuel reprocessing, and thermonuclear fusion. The programme modifications have been made paying due attention to a best possible utilization of existing equipment and manpower. (UA) [de

  12. Coordinated and government-sponsored research in the Federal Republic of Germany. The Karlsruhe Nuclear Research Centre: Baking a new cake with the old mixture

    Mock, W.

    1986-12-12

    This article in the series gives an outline of the main research projects of the Karlsruhe Nuclear Research Centre, reviewing the formerly purely nuclear research tasks and going over to the new projects which increasingly encompass non-nuclear research subjects. Still, about 50% of the KfK research activities will be devoted in future to projects such as the fast breeder reactor, nuclear fuel reprocessing, and thermonuclear fusion. The programme modifications have been made paying due attention to a best possible utilization of existing equipment and manpower.

  13. Compilation of papers presented to the KTG conference on 'Advanced LWR fuel elements: Design, performance and reprocessing', 17-18 November 1988, Karlsruhe Nuclear Research Center

    Bahm, W.

    1989-05-01

    The two expert groups of the Nuclear Society (KTG), 'chemistry and waste disposal' and 'fuel elements' discussed interdisciplinary problems concerning the development and reprocessing of advanced fuel elements. The 10 lectures deal with waste disposal, mechanical layout, operating behaviour, operating experiences and new developments of fuel elements for water moderated reactors as well as operational experiences of the Karlsruhe reprocessing plant (WAK) with reprocessing of high burnup LWR and MOX fuel elements, the distribution of fission products, the condition of the fission products during dissolution and with the effects of the higher burnup of fuel elements on the PUREX process. (DG) [de

  14. Releases of radioiodine from the Karlsruhe nuclear fuel reprocessing plant as a result of spontaneous fission of actinides

    Schuettelkopf, H.

    1977-02-01

    Fro, 23,7,1976 to 28.7.76 and from 8.3.76 to 9.16.76 50 pCi 131 I/m 3 , 116 pCi 133 I/m 3 und 195 pCi 135 I/m 3 were measured on an average in 11 samples of waste air from the Karlsruhe Nuclear Fuel Reprocessing Plant (WAK). During these time intervals no dissolution of fuel material was performed. From 16.9.76 to 27.10.76 18 charges of nuclear fuel were dissolved. During this period 3.3 pCi 131 I/m 3 and 7.9 pCi 133 I/m 3 were obtained as mean waste air concentrations which were higher than the lower detection limit of the method of measurement used. 244 Cm, 242 Cm, 242 Pu, 240 Pu and 238 Pu are responsible for the production of radioiodine in nuclear fuel by spontaneous fission. 244 Cm is the most important nuclide in highly active waste solutions (HAL). The cumulative fission yield is well approximated by 3% for 13 I and by 6% for 133 I. The radioiodine is set free during fuel dissolution by venting of tanks and HAL pipes and during the vritification of such solutions. The radioiodine produced by spontaneous fission is released from WAK only by venting of tanks and HAL pipes. Corresponding to the conditions of venting, air concentrations as high as 4.4 pCi 131 I/m 3 and 8.2 pCi 133 I/m 3 are expected. These concentrations agree well with air concentrations measured during the period of fuel dissolution. Based on plausible assumptions the 131 I and 133 I waste air concentrations for the period of outage are calculated from an evaporated volume of HAL in the pipes corresponding to about 10 g of 244 Cm and with 40% equilibrium between I 2 in evaporated HAL and in waste air. In the worst case 131 I-concentrations in the waste air of WAK result in an annual release of 0.2 mCi 131 I. This value is less than 1% of the authorized annual releases of 1976. For a reprocessing plant of 1,400 t/a capacity the annual expected release of 131 I lies in the mCi range. (orig.) [de

  15. Mehrzweckforschungsreaktor Karlsruhe (MZFR)

    1976-01-01

    The RSK is of the opinion that the proposed additional emergency cooling system can present an improvement in safety. Furthermore, the RSK starts from the fact that the measures required for the present system - improvements in the accident instrumentation, fitting control devices, annual in-service inspections - are already adequately catered for in the design. (orig.) [de

  16. Scientists and professionals from all around the world in Karlsruhe. Frederic Joliot/Otto Hahn summer school 2013 on nuclear reactors 'Physics, Fuels and Systems'

    Sanchez-Espinoza, V.H.; Fischer, U. [Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen (Germany). Scientific Secretariat FJOHSS

    2014-02-15

    Every 2 years the Karlsruhe Institute of Technology (KIT) organizes the Frederic Joliot/Otto Hahn (FJOH) Summer School together with the Commissariat a l'-Energie Atomique (CEA) since 1999. In 2013, the FJOH Summer School took place in Karlsruhe from 21 to 30 August. The topic of this year's school was 'Advanced Nuclear Systems with Transuranium Fuels'. Experts from internationally well recognized research institutions and Universities from USA, Japan, Asia and Europe gave lectures about the current status and trends on the related fields. (orig.)

  17. Current Status of Experimental and Theoretical Work on Sodium/Fuel Interaction (SFI) at Karlsruhe 'Code Developments'

    Beutel, H.; Bojarsky, E.; Reiser, H.; Caldarola, L.; Jacobs, H.; Zyszkowski, W.

    1976-01-01

    presence of non condensable gases. For the heat transfer process an effective thermal conductivity of the liquid/vapour mixture accounts for partial vapour blanketing of the fuel particles. Numerical results are in general consistent with those obtainable from the first code. A survey of the various fragmentation mechanisms of UO 2 in sodium was done. It was concluded that 'vapour bubble and collapse' seems to be the most probable fragmentation mechanism in the case of UO 2 /sodium systems. For this reason work was focussed on modelling this mechanism. A preliminary model was given. Work is progressing. It is planned to couple the FCI theoretical model No. 1 developed at Karlsruhe to the american REXCO code which is available at Ispra. Work is being completed. The FCI subroutine is already available

  18. Scientists from all over the world attend the ''Frederic Joliot/Otto Hahn Summer School 2009'' at the Karlsruhe Institute of Technology (KIT)

    Sanchez Espinoza, Victor Hugo; Fischer, Ulrich

    2009-01-01

    The ''Frederic Joliot/Otto Hahn Summer School'' is organized each year alternately by the Karlsruhe Institute of Technology and the Commissariat a l'Energie Atomique (CEA), Cadarache. This year's Summer School, the 15th since its foundation, was run at the Advanced Training Center (FTU) of KIT Campus Nord on August 26 to September 4. The key topic this year was ''The Challenges in Implementing Fast Reactor Technology.'' These are the items discussed: Principles and challenges of future fast reactor designs, Fuels, fuel cycle, and recycling of minor actinides, Innovative cladding tube and structural materials, Special aspects of coolants and the challenges they pose, Fast reactor safety. Experts from 8 leading international research establishments and universities presented and discussed with the 58 participants from 16 countries the current state of the art and the latest development trends in the topics listed above. (orig.)

  19. Experimental determination of the atmospheric dispersion at the Karlsruhe Nuclear Research Center for 160 m and 195 m emission heights. Pt. 1

    Thomas, P.; Huebschmann, W.; Schuettelkopf, H.; Vogt, S.

    1983-03-01

    Diffusion experiments have been carried out at the Karlsruhe Nuclear Research Center in order to investigate the atmospheric diffusion of pollutants and to determine specifically the influence on atmospheric diffusion of topographic conditions specific to the site. For this purpose, halogenated hydrocarbons are emitted at 160 m and 195 m height, their local concentration distribution is measured at ground level downwind of the source. Part 1 of the report describes the diffusion experiments performed and presents the detailed data of measurements. These include the coordinates of the sampling positions, the measured concentrations and the relevant meteorological data recorded during the experiments. The stability classes prevailing during the experiments are derived from these data and are indicated. (orig.) [de

  20. Experimental determination of the atmospheric dispersion parameters at the Karlsruhe Nuclear Research Center for 60 m and 100 m emission heights. Pt. 1

    Thomas, P.; Dilger, H.; Huebschmann, W.; Schuettelkopf, H.; Vogt, S.; Kernforschungszentrum Karlsruhe G.m.b.H.

    1981-09-01

    Experiments have been carried out at the Karlsruhe Nuclear Research Center in order to investigate the atmospheric diffusion of pollutants. The influence on atmospheric diffusion of topographic conditions specific to the site is to be determined. For this purpose, halogenated hydrocarbons are emitted at 60 m and 100 m height; their local concentration distribution is measured at ground level downwind of the source. Part 1 of the report describes the diffusion experiments performed and presents the measured data in a detailed manner. The data include the coordinates of the sampling positions, the measured concentrations and the relevant meteorological data recorded during the experiments. The stability classes prevailing during the experiments are derived from these data and are indicated. (orig./HP) [de

  1. Manufacturing of microcomponents in a research institute under DIN EN ISO 9001

    Maas, Dieter; Karl, Bernhard; Saile, Volker; Schulz, Joachim

    2000-08-01

    The Institute for Microstructure Technology at Forschungszentrum Karlsruhe has implemented a rigorous quality management system and was certified according to the DIN ISO EN 9001 standard in January 2000.

  2. Scientists from all over the world attended the 'Frederic Joliot/Otto Hahn Summer School 2011' at the Karlsruhe Institute of Technology (KIT); Wissenschaftler aus aller Welt bei der 'Frederic Joliot/Otto Hahn Summer School 2011' am Karlsruhe Institute of Technology (KIT)

    Sanchez, Victor H.; Fischer, Ulrich [Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen (DE). Inst. for Neutron Physics and Reactor Technology (INR)

    2011-12-15

    The Karlsruhe Institute of Technology (KIT) and the Commissariat r leEnergie Atomique et Aux Energies Alternatives (CEA), Cadarache, alternate in organizing the annual 'Frederic Joliot/Otto Hahn Summer School.' This year's event, the 17th since its inception, was held in Karlsruhe, Germany on August 25 to September 3. Its topic was 'High-fidelity Modeling for Nuclear Reactors: Challenges and Prospects.' Here is a list of the subjects covered: - Status and perspectives of modeling and its role in design, operation, and safety. - Thermal hydraulics of nuclear reactors and simulation of 2 phase flows. - Structural mechanics, structure? fluid interaction, and seismic safety. - Advanced simulation in neutronics and reactor physics. - Progress in simulating fuel and materials behavior. - Multiphysics and uncertainty analysis methods. Experts from eight leading international research institutions and universities presented, and discussed with the 59 participants from 19 countries, the current state of the art and most recent development trends in the subjects listed above. (orig.)

  3. Establishing a Research Information System as Part of an Integrated Approach to Information Management: Best Practice at the Karlsruhe Institute of Technology (KIT

    Frank Scholze

    2012-01-01

    Full Text Available The Karlsruhe Institute of Technology (KIT is one of the largest research and higher education organisations in the world focusing on engineering and natural sciences. At present KIT, under the chairmanship of its executive board, is installing an extensive current research information system (CRIS covering all institutes and facilities of the organisation. The assumption underlying the project is that a consistent overview of research performance has become fundamental for the international competitiveness of research institutions and is increasingly important for strategic decisions at the executive level. Ultimately, it also leads to better data and control in rankings at higher education assessments. The new research information system systematically maps all of KIT’s processes and instruments to obtain, connect, present and utilise the research metadata of active researchers. This reduces the documentation workload for researchers, for the executive level and central units such as the library, and at the same time allows for and facilitates an overall view and the aggregation and visualisation of research metadata. Our vision is to build a federally structured network of systems that gathers information on KIT’s publications, research competence, research projects, patents and technological offers by retrieving data from external and internal sources as well as directly from the researchers. The network facilitates linking and aggregating of data and provides unique identifiers for individual researchers and organizational units. With its consistent data model the research information system also fosters the organisational development of KIT, which was formed in 2009 by the merger of a university and a national research centre. The researchers and their activities are at the core of the research information system. The system substantially reduces their administrative burden in documenting project information and publications. Automatic

  4. Deformation integrity monitoring for GNSS positioning services including local, regional and large scale hazard monitoring - the Karlsruhe approach and software(MONIKA)

    Jaeger, R.

    2007-05-01

    GNSS-positioning services like SAPOS/ascos in Germany and many others in Europe, America and worldwide, usually yield in a short time their interdisciplinary and country-wide use for precise geo-referencing, replacing traditional low order geodetic networks. So it becomes necessary that possible changes of the reference stations' coordinates are detected ad hoc. The GNSS-reference-station MONitoring by the KArlsruhe approach and software (MONIKA) are designed for that task. The developments at Karlsruhe University of Applied Sciences in cooperation with the State Survey of Baden-Württemberg are further motivated by a the official resolution of the German state survey departments' association (Arbeitsgemeinschaft der Vermessungsverwaltungen Deutschland (AdV)) 2006 on coordinate monitoring as a quality-control duty of the GNSS-positioning service provider. The presented approach can - besides the coordinate control of GNSS-positioning services - also be used to set up any GNSS-service for the tasks of an area-wide geodynamical and natural disaster-prevention service. The mathematical model of approach, which enables a multivariate and multi-epochal design approach, is based on the GNSS-observations input of the RINEX-data of the GNSS service, followed by fully automatic processing of baselines and/or session, and a near-online setting up of epoch-state vectors and their covariance-matrices in a rigorous 3D network adjustment. In case of large scale and long-term monitoring situations, geodynamical standard trends (datum-drift, plate-movements etc.) are accordingly considered and included in the mathematical model of MONIKA. The coordinate-based deformation monitoring approach, as third step of the stepwise adjustments, is based on the above epoch-state vectors, and - splitting off geodynamics trends - hereby on a multivariate and multi-epochal congruency testing. So far, that no other information exists, all points are assumed as being stable and congruent reference

  5. Scientists from all over the world attend the ''Frederic Joliot/Otto Hahn Summer School 2009'' at the Karlsruhe Institute of Technology (KIT); Wissenschaftler aus aller Welt bei der ''Frederic Joliot/Otto Hahn Summer School 2009'' am Karlsruhe Institute of Technologie (KIT)

    Sanchez Espinoza, Victor Hugo; Fischer, Ulrich [Karlsruhe Inst. of Tech. (KIT), Campus Nord/Inst. for Neutron Physics and Reactor Tech. (INR), Eggenstein-Leopoldshafen (Germany)

    2009-11-15

    The ''Frederic Joliot/Otto Hahn Summer School'' is organized each year alternately by the Karlsruhe Institute of Technology and the Commissariat a l'Energie Atomique (CEA), Cadarache. This year's Summer School, the 15th since its foundation, was run at the Advanced Training Center (FTU) of KIT Campus Nord on August 26 to September 4. The key topic this year was ''The Challenges in Implementing Fast Reactor Technology.'' These are the items discussed: Principles and challenges of future fast reactor designs, Fuels, fuel cycle, and recycling of minor actinides, Innovative cladding tube and structural materials, Special aspects of coolants and the challenges they pose, Fast reactor safety. Experts from 8 leading international research establishments and universities presented and discussed with the 58 participants from 16 countries the current state of the art and the latest development trends in the topics listed above. (orig.)

  6. Build up of radon, /sup 218/Po and /sup 214/Po in a Karlsruhe diffusion chamber as a function of time

    Fazal-ur-Rehman; Jamil, K.; Ali, S.; Khan, H.A.

    1996-01-01

    Passive radon /sup 222/Rn dosimeters employing particle detectors are widely used in concentration (p Ci/l) measurement in houses, mines and other areas of activity. These dosimeters yield track density which is needed to be converted into physically meaningful parameter of radon concentration in either p Ci/l or Bq m/sup -3/. Therefore, it is required to know the separate contributions of /sup 222/Rn and its progeny. In the present study we have measured the concentration of /sup 222/Rn and its daughters (/sup 218/Po and /sup 214/Po) separately in the Karlsruhe diffusion chamber radon dosimeter, with and without a filter, as a function of time by an active method using a surface barrier detector. The build up behavior of radon and its two daughters (/sup 218/Po and /sup 214/Po) as a function of time was studied by plotting the area under each peak versus collection time. The differential curves and the relative concentration of radon daughters as a function of time were also studied. The concentration of radon and its daughters shows a somewhat linear build up as a function of time for the presently studied time periods. The results of this experiment are expected to be useful in converting the integrated alpha track density as measured by a particle track detector, (used in passive radon dosimetry) to radon concentration levels and for determination of equilibrium factor. (author)

  7. Conceptual design of a First Wall mock-up experiment in preparation for the qualification of breeding blanket technologies in the Helium Loop Karlsruhe (HELOKA) facility

    Zeile, C., E-mail: christian.zeile@kit.edu [Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Abou-Sena, A.; Boccaccini, L.V.; Ghidersa, B.E.; Kang, Q.; Kunze, A. [Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Lamberti, L. [Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Dipartimento Energia, Politecnico di Torino (Italy); Maione, I.A.; Rey, J.; Weth, A. von der [Karlsruhe Institute of Technology (KIT), Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany)

    2016-11-01

    Highlights: • Experiment in preparation for the qualification of Breeding Blanket technologies in HELOKA facility is proposed. • Experimental capabilities, instrumentation of the mock-up and experimental program are presented. • Design and manufacturing of the mock-up is described. • Design of modular attachment system to obtain different stress levels and distributions on the mock-up is discussed. - Abstract: An experimental program based on a First Wall mock-up is presented as preparation for the qualification of breeding blanket mock-ups at high heat flux in the Helium Loop Karlsruhe (HELOKA) facility. Two objectives of the experimental program have been defined: testing of the experimental setup and a first validation of FE models. The design and manufacturing of mock-up representing about 1/3 of the heated zone of an ITER Test Blanket Module (TBM) First Wall is discussed. A modular attachment system concept has been developed for the fixation of the mock-up in order to be able to generate different stress distributions and levels on the plate, which is confirmed by thermo-mechanical analyses. The HELOKA facility is able to provide a TBM relevant helium cooling system and to generate the required surface heat flux by an electron beam gun. An installed IR camera can be used to measure the temperature distribution on the surface.

  8. ANITA-IEAF activation code package - updating of the decay and cross section data libraries and validation on the experimental data from the Karlsruhe Isochronous Cyclotron

    Frisoni, Manuela

    2017-09-01

    ANITA-IEAF is an activation package (code and libraries) developed in the past in ENEA-Bologna in order to assess the activation of materials exposed to neutrons with energies greater than 20 MeV. An updated version of the ANITA-IEAF activation code package has been developed. It is suitable to be applied to the study of the irradiation effects on materials in facilities like the International Fusion Materials Irradiation Facility (IFMIF) and the DEMO Oriented Neutron Source (DONES), in which a considerable amount of neutrons with energies above 20 MeV is produced. The present paper summarizes the main characteristics of the updated version of ANITA-IEAF, able to use decay and cross section data based on more recent evaluated nuclear data libraries, i.e. the JEFF-3.1.1 Radioactive Decay Data Library and the EAF-2010 neutron activation cross section library. In this paper the validation effort related to the comparison between the code predictions and the activity measurements obtained from the Karlsruhe Isochronous Cyclotron is presented. In this integral experiment samples of two different steels, SS-316 and F82H, pure vanadium and a vanadium alloy, structural materials of interest in fusion technology, were activated in a neutron spectrum similar to the IFMIF neutron field.

  9. Experimental studies of the break-up of 156 MeV 6Li-ions at extreme forward angles using the Karlsruhe magnetic spectrograph 'Little John'

    Jelitto, H.

    1987-05-01

    6 Li-induced break-up reactions have been investigated at reaction angles in extreme forward direction including O 0 with the Karlsruhe Magnetic Spectrograph 'Little John'. The experiments were characterized by the minimization of the high experimental background that dominates at small emission angles. Inclusive alpha-particle and deuteron spectra from the bombardement of 12 C- and 208 Pb-targets with 156 MeV 6 Li-ions have been measured. Below the grazing angle the Coulomb interaction shows a distinct influence on the angular distributions of the fragments. A simple spectator-model and a more realistic description within the DWBA-formalism largely allows a reproduction of the data. In the light of the reverse reaction α + d → 6 Li + γ at small α-d-relative energies, which is of considerable interest for astrophysics, a particle-particle-coincidence measurement with θ α = 5 0 and θ d = -2 0 has been performed. The result could be reproduced reasonably well by a simple Monte-Carlo-simulation. Beside the treatment of a physical problem this work deals with the start-up of the magnetic spectrograph and the clarification of spectrograph specific questions concerning the data reduction. (orig.) [de

  10. Activities at the Institute of Materials and Solid State Research of the Karlsruhe Nuclear Research Centre in the field of fuel pin modelling

    Elbel, H.

    1979-01-01

    Fuel pin modelling has been pursued at the Institute of Materials and Solid State Research (IMF) of the Karlsruhe Nuclear Research Centre (KfK) with the main objective to provide a detailed quantitative analysis of the fuel pin behaviour in a LMFBR under normal and off-normal operation conditions. The computer programs and models developed at the IMF serve the purpose to aid effectively in the development of an optimized fuel pin concept for a LMFBR. What extent of clad deformation can be tolerated without running into clad failure? What is the influence of neutron dose, temperature, corrosion attack, arid cyclic forces on the state of the clad? What may be the reasons for clad failure? In answering these questions computer programs can play an important role. The activities at the IMF in the field of fuel pin modelling cover the following topics: development of computer programs and models; validation of these programs and models, application to the design of fuel pins for irradiation experiments; assistance in the evaluation of operation data and post- irradiation results, and parametric studies on the influence of design parameters, operation conditions and certain material phenomena on the in-pile behaviour of the fuel pin

  11. The calculated radiological impact on the environment of the Karlsruhe Nuclear Research Center due to radioactive emissions to the atmosphere in the years 1975 and 1976

    Huebschmann, W.; Nagel, D.; Papadopoulos, D.

    1976-08-01

    The radiological impact by radioactive offgas and exhaust air on the environment of the Karlsruhe Nuclear Research Center (KNRC) is calculated every year and compared with the permissible equivalent doses. This report includes both the forecasted maximum doses from maximum releases scheduled for the year 1976 and the actual doses of 1975 based on the measured releases in 1975. According to the various irradiation mechanisms of the nuclides emitted, the following doses are indicated, each calculated for an adult person: whole body dose by γ-irradiation and tritium inhalation, skin dose by external β-irradiation, lung dose by aerosol inhalation, bone dose by plutonium inhalation, and effective integral dose. The maximum infant thyroid dose due to iodine ingestion via the pasture-cow-milk-pathway is also calculated. The respective maximum doses indicate that the dose limits of 30 mrem/a whole body dose (adult) and 90 mrem/a thyroid dose (Infant) which are to be observed by the KNRC since the year 1975 are not exceeded at any point, provided the emissions remain below the scheduled maximum level. The doses in 1975 were markedly below the dose limits mentioned above. This is even true when partial body and organ doses are integrated in an 'effective dose'. (orig.) [de

  12. Methods for registration and mapping of waste heat emissions and their application to the regions of Rastatt, Baden-Baden and Karlsruhe-City (Federal Republic of Germany)

    Bartholomaei, G.; Kinzelbach, W.

    1978-05-01

    Methods are developed that allow the registration and mapping of waste heat emissions on a grid of 2 x 2 km 2 . They are directly applicable in the Federal Republik of Germany and may be extended to neighbouring countries. Such a mapping provides the distribution of anthropogeneous waste heat emissions in space and time and serves in the case of the upper Rhine Valley as a basis for the numerical evaluation of climate modification by man. In a close approximation the distribution of waste heat is equal to the distribution of energy consumption. Therefore, the first step is the registration and mapping of energy consumption. Data about the consumption of the most important types of energy such as coal, fuel oil, gas, electricity etc. are available only partially and on the level of administrative units which are considerably larger than the grid size. Therefore, models were developed which allow to determine energy consumption on the commune and grid level with the help of local structural data like the distribution of population, households, traffic etc. The second step to be taken is the transformation of energy of energy consumption into waste heat emissions categorized in terms of the components convection, radiation, latent heat and discharge of heated water. Energy consumption and waste heat were determined separately for the various sectors of economy. Large sources in the industrial and energy supply sectors were analyzed individually by questionnaires. The results obtained with foresaid methods in the districts of Rastatt and Baden-Baden and in the township of Karlsruhe are presented. (orig.) 891 HP [de

  13. Experiences gained in the conditioning of radioactive wastes from regional depots by example of Kernforschungszentrum Karlsruhe, and recommendations for the establishment of regional depots in the new Federal States of unified Germany

    Pfeifer, W.

    1992-01-01

    Details are given about radioactive waste management and radioactive waste management fundamentals as well as about the respective methods applied by the Baden-Wuerttemberg radioacive waste depot. The waste treatment, quality assurance and internal inspection methods applied by Hauptabteilung Dekontaminationsbetriebe (HDB), Kernforschungszentrum Karlsruhe (KfK) are described, and recommendations are given for the establishment of regional depots in the new provinces of the Federal Republic of Germany. These recommendations which are based on Western German standards before unification suggest regional depots with combined administrative systems which watch over the depot use and charges, the foundation of a waste management association responsible for the disposal, transport, intermediate storage and conditioning of radioactive wastes in the new provinces, and the establishment of a facility to be run by the proposed waste management association for the intermediate storage of conditioned waste packages intended for final disposal. (orig.) [de

  14. Research in Europe. Forschungszentrum Juelich. Annual report 2010; Forschen in Europa. Forschungszentrum Juelich. Jahresbericht 2010

    Frick, Frank; Roegener, Wiebke; Stahl-Busse, Brigitte

    2010-07-15

    Following the newest chronicle from April 2010 to March 2011, the annual report presents four highlights as well as a lot of contributions on the knowledge management. The annex of this annual report shows the organizational structure, personnel employed, financial aspects, and the contact information.

  15. Development of new auxiliary basis functions of the Karlsruhe segmented contracted basis sets including diffuse basis functions (def2-SVPD, def2-TZVPPD, and def2-QVPPD) for RI-MP2 and RI-CC calculations.

    Hellweg, Arnim; Rappoport, Dmitrij

    2015-01-14

    We report optimized auxiliary basis sets for use with the Karlsruhe segmented contracted basis sets including moderately diffuse basis functions (Rappoport and Furche, J. Chem. Phys., 2010, 133, 134105) in resolution-of-the-identity (RI) post-self-consistent field (post-SCF) computations for the elements H-Rn (except lanthanides). The errors of the RI approximation using optimized auxiliary basis sets are analyzed on a comprehensive test set of molecules containing the most common oxidation states of each element and do not exceed those of the corresponding unaugmented basis sets. During these studies an unsatisfying performance of the def2-SVP and def2-QZVPP auxiliary basis sets for Barium was found and improved sets are provided. We establish the versatility of the def2-SVPD, def2-TZVPPD, and def2-QZVPPD basis sets for RI-MP2 and RI-CC (coupled-cluster) energy and property calculations. The influence of diffuse basis functions on correlation energy, basis set superposition error, atomic electron affinity, dipole moments, and computational timings is evaluated at different levels of theory using benchmark sets and showcase examples.

  16. GASFLOW computer code (physical models and input data)

    Muehlbauer, Petr

    2007-11-01

    The GASFLOW computer code was developed jointly by the Los Alamos National Laboratory, USA, and Forschungszentrum Karlsruhe, Germany. The code is primarily intended for calculations of the transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containments and in other facilities. The physical models and the input data are described, and a commented simple calculation is presented

  17. Micro powder-injection moulding of metals and ceramics

    Development of micro-MIM/-CIM was started at Forschungszentrum Karlsruhe with the aim of creating a process suitable for a wide range of materials as well as for medium-scale and large-scale production of micro components. Using enhanced machine technology and special tempering procedures, this process enables ...

  18. Scientific publications of Kernforschungszentrum Karlsruhe in 1980

    1981-04-01

    The report gives the titles of the publications that appeared in 1980. It is the first time that such reports are not available in print yet are separated from the bibliography. As regards the patents all patent rights granted and published in 1980 are mentioned: patents, patent applications, and patent specifications for public inspection. The publications list is classified according to institutes. As to the projects only the published project reports and publications from collaborators of the respective project staff are specified. The list also contains the publications printed in the Kernforschungszentrum and concerning the following research- and development projects: Prozesslenkung mit DV-Anlagen (PDV), Rechenunterstuetztes Entwickeln, Konstruieren und Fertigen (CAD), and Fertigungstechnik (PFT) ; the Kernforschungszentrum is effecting these projects in co-operation with other firms and institutes with the Kernforschungszentrum being project manager. Moreover, the list contains the publications from the branch office of the Bundesforschungsanstalt fuer Ernaehrung (federal research institute for alimentation) situated in the KFK-area. The last section of the list gives publications on guest experiments carried out in the Kernforschungszentrum. The list is provided with an alphabetic author register referring to page- and recording-numbers. (orig./HP) [de

  19. Karlsruhe Nuclear Research Centre. Programme budget 1988

    1987-01-01

    Following a general survey of tasks, planned activities and developmental trends of the nuclear research centre, the report gives an account of the activities to be performed in the subject fields of main interest, showing the budgeting figures for annual expenditure (for personnel, investments, operating costs) up to the year 1991. Further information explains the infrastructure of the centre and the distribution of overall expenditure as well as the budgetary planning. (UA) [de

  20. Forschungszentrum Juelich, Institut fuer Kernphysik/COSY. Annual report 2009

    Buescher, Markus; Hanhart, Christoph; Krewald, Siegfried; Machner, Hartmut; Maier, Rudolf; Meissner, Ulf G.; Ritman, James; Stockhorst, Hans; Stroeher, Hans (eds.)

    2010-05-15

    The following topics were dealt with: Physics at COSY, COSY operation and developments, further experimental activities, theoretical investigations, preparation of the HESR, the PANDA experiment. (HSI)

  1. Forschungszentrum Rossendorf, Institute of Radiochemistry. Annual report 1995

    Nitsche, H.

    1996-02-01

    The activities of the institute in the year 1995 are described by short communications. The themes of the chapters are: Speciation and migration of radionuclides; behaviour of colloids and aerosols; organic matter and their interaction with radionuclides; application of x-ray absorption spectroscopy; chemistry of heaviest elements. (SR)

  2. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 1997

    Weiss, F P; Rindelhardt, U [eds.

    1998-10-01

    The research work of the institute aims at the assessment and increase of the safety of technical facilities. Subject of the investigation are equally nuclear plants and installations of process industries. To analyse thermo-fluiddynamic phenomena of accident scenarios physical models and computer codes are developed as well for multi-phase and multi-component flows as for the time and space dependent power release (neutron kinetics in light water reactors, reaction kinetics of exothermic chemical reactions). Emphasis is put on the description of spatial flows and the transient evolution of flow patterns. (orig.)

  3. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2003

    NONE

    2004-07-01

    The work of the institute is directed to the assessment and enhancement of the safety of technical plants and to the increase of the efficiency and environmental sustainability of those facilities. Subjects of investigation are equally nuclear plants and installations of process industries. To achieve the goals mentioned, the institute is mainly engaged in the scientific fields of thermal fluid dynamics including magneto-hydrodynamics (MHD) and materials sciences. In 2003, the ISR worked on the following main scientific projects. Sub-programme: Plant and Rector Safety. Project: accident analysis of nuclear reactors, safety of materials and components, particle and radiation transport, safety and efficiency of chemical processes. Sub-programme: Thermal Fluid Dynamics. Project: magneto-hydrodynamics, thermal fluid dynamics of multiphase systems. Considerable progress could also be achieved in the CFD simulation of two-phase flows. New approaches for the forces acting on steam bubbles in a water flow could be developed and implemented into the CFX code in close cooperation with the CFX developer ANSYS/CFX. The qualified models allow to simulate the evolution of bubble size specific radial void distribution profiles along the flow path. These theoretical studies and the related experiments at the Rossendorf TOPFLOW test facility represent an important part of the German CFD network that aims at the improvement of thermal hydraulic calculation methods in reactor safety. (orig.)

  4. Forschungszentrum Juelich, Institut fuer Kernphysik. Annual report 1993

    Baur, G.; Filges, D.; Kilian, K.; Maier, R.; Rossen, P. v.; Schult, O.; Seyfarth, H.; Speth, J.; Turek, P.

    1994-02-01

    The annual report contains extended abstracts about the work performed in the named research center in 1993 together with a list of talks and publications. The work concerns experimental and theoretical studies on medium and high energy physics, nuclear spectroscopy, nuclear structure and reaction mechanisms, developments of the cooler synchrotron COSY, isochronous cyclotron and ion sources, the magnetic spectrometer BIG KARL, as well as technical developments on data acquisition and processing, electronics, detector and targets, and ESS. (DG)

  5. Forschungszentrum Juelich, Institut fuer Kernphysik/COSY. Annual report 2010

    Buescher, Markus; Grzonka, Dieter; Hanhart, Christoph; Krewald, Siegfried; Maier, Rudolf; Meissner, Ulf G.; Ritman, James; Stockhorst, Hans; Stroeher, Hans (eds.)

    2011-04-15

    The following topics are dealt with: Physics at COSY, COSY operation and developments, further experimental activities, theoretical investigations, preparation of the HESR, the PANDA experiments. (HSI)

  6. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 1996

    Weiss, F P; Rindelhardt, U [eds.

    1997-08-01

    The research of the institute aims at the safety assessment of the design of nuclear and chemical facilities, the development of accident management procedures, and the increase of operational safety by improved plant surveillance. Physical models and computer codes are developed for multiphase/multicomponent flows and for the space and time dependent power release in nuclear and chemical reactors to be able to analyse the thermo-fluiddynamic phenomena during assumed accident scenarios. Emphasis is particulary focussed on spatial flow phenomena and the time dependent change of flow patterns. Sustainable void fraction probes and tomographic systems are developed to measure those parameters of two phase flows that characterize the exchange of pulse, energy and mass between the phases and components. The research related to materials safety is directed to the behaviour of components exposed to neutron and gamma radiation. The susceptibility to irradiation induced embrittlement and the behaviour of annealed material during reirradiation are investigated by fracture mechanical methods in dependence on the materials composition. The work on process and plant diagnostics makes available basic methods for early failure detection and operational monitoring which are important means of accident prevention. Recent initiatives of the institute are concerned with the transport of pollutants in the geosphere. Particularly, codes are developed for the simulation of physical and chemical processes during the transport of pollutants in unsaturated zones of the soil. (orig.)

  7. GSF-Forschungszentrum fuer Umwelt und Gesundheit. Annual report '95

    Haury, H.J.

    1996-01-01

    As a center for environmental sciences, the major field of work of the GSF is research into and performance of complex and multidisciplinary problems and tasks. The annual report of the year 1995 presents compact surveys of the activities and results achieved in the three major research areas of ecology and biology (investigation of effects and response), environmental engineering, and human health (epidemiology a.o.). The various reports of the institutes, departments and project groups cover annual surveys as well as topical information, (ecosystems in agriculture), and information on the development of the infrastructure. (DG) [de

  8. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2003

    2004-01-01

    The work of the institute is directed to the assessment and enhancement of the safety of technical plants and to the increase of the efficiency and environmental sustainability of those facilities. Subjects of investigation are equally nuclear plants and installations of process industries. To achieve the goals mentioned, the institute is mainly engaged in the scientific fields of thermal fluid dynamics including magneto-hydrodynamics (MHD) and materials sciences. In 2003, the ISR worked on the following main scientific projects. Sub-programme: Plant and Rector Safety. Project: accident analysis of nuclear reactors, safety of materials and components, particle and radiation transport, safety and efficiency of chemical processes. Sub-programme: Thermal Fluid Dynamics. Project: magneto-hydrodynamics, thermal fluid dynamics of multiphase systems. Considerable progress could also be achieved in the CFD simulation of two-phase flows. New approaches for the forces acting on steam bubbles in a water flow could be developed and implemented into the CFX code in close cooperation with the CFX developer ANSYS/CFX. The qualified models allow to simulate the evolution of bubble size specific radial void distribution profiles along the flow path. These theoretical studies and the related experiments at the Rossendorf TOPFLOW test facility represent an important part of the German CFD network that aims at the improvement of thermal hydraulic calculation methods in reactor safety. (orig.)

  9. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 1999

    Weiss, F.P.; Rindelhardt, U.

    2000-02-01

    The work of the institute is directed to the assessment and enhancement of the safety of large technical plants and to the increase of the effectiveness and environmental sustainability of those facilities. Subjects of investigations are equally nuclear plants and installations of process industries. To achieve the above mentioned goals, the institute is engaged in two scientific fields, i.e. thermo-fluiddynamics including magneto-hydrodynamics (MHD) and materials/components safety. (orig.)

  10. 1-cycle SANEX process development studies performed at Forschungszentrum Juelich

    Wilden, Andreas; Sypula, Michal; Schreinemachers, Christian; Kluxen, Paul; Modolo, Giuseppe

    2010-01-01

    In the framework of our research activities related to the partitioning of spent nuclear fuel solutions, the direct selective extraction of trivalent actinides from a simulated PUREX raffinate solution (1-cycle SANEX) was studied using a mixture of CyMe 4 BTBP and TODGA. The solvent showed a high selectivity for trivalent actinides with a high lanthanide separation factor. However the co-extraction of some fission products, such as Cu, Ni, Zr, Mo, Pd, Ag and Cd was observed. The extraction of Zr and Mo could be suppressed using oxalic acid but the use of the well-known Pd complexant HEDTA was unsuccessful. During screening experiments with different amino acids, the sulphur-bearing amino acid L-Cysteine showed good complexation of Pd and prevented its extraction into the organic phase without influencing the extraction of trivalent actinides. A strategy for a single-cycle process is proposed within this paper. (authors)

  11. Forschungszentrum Juelich, Institut fuer Kernphysik/COSY. Annual report 2009

    Buescher, Markus; Hanhart, Christoph; Krewald, Siegfried; Machner, Hartmut; Maier, Rudolf; Meissner, Ulf G.; Ritman, James; Stockhorst, Hans; Stroeher, Hans

    2010-05-01

    The following topics were dealt with: Physics at COSY, COSY operation and developments, further experimental activities, theoretical investigations, preparation of the HESR, the PANDA experiment. (HSI)

  12. GSF - Forschungszentrum fuer Umwelt und Gesundheit. Annual report 2001

    Haury, H.J.; Wiedemann, M.; Goedde, M.; Guldner, H.; Kettembeil, S.; Meyer-Streng, O.; Weiner, M.

    2002-01-01

    Nothing has moved the GSF in recent years as much as the structural change that has taken place within the Helmholtz Association, and the associated introduction of a system of programme-oriented support. The members of the Scientific-Technical Board and the staff of the Scientific-Technical Department have been and still are particularly strongly involved in the process. We also wish the new President of the Helmholtz Association, Professor Kroell, the skills and good fortune needed to lead our mother organisation in a future that is determined by scientific competition and remarkable scientific achievement, and not marked by administration and new bureaucratic impediments. While these discussions, so important for the future of the GSF, have been proceeding, scientific research has of course continued successfully. One good example is genome research. The GSF not only contributes a decisive part of the research within the Helmholtz Association, it also makes an important contribution at both the national and international scales. The GSF has paid particular attention for years to the question of technology transfer. (orig.)

  13. GSF - Forschungszentrum fuer Umwelt und Gesundheit. Annual report 2003

    Wiedemann, M.; Haury, H.J.; Goedde, M.; Guldner, H.; Kettembeil, S.; Leser, B.; Meyer-Streng, O.

    2004-01-01

    The GSF develops scientific principles that provide the basis for protecting human health and the natural basis of life for the future. GSF health research focuses on the genetic and immunological basis of molecular protection and define and their dysfunction during disease development, and the identification of new factors that contribute to sickness or health. (orig.)

  14. The Hot Cell Radioactive Waste Concept of Forschungszentrum Juelich

    Pott, G.; Halaszovich, St.

    1999-01-01

    During the last 30 years extensive scientific examinations on radioactive metals,ceramics and fuel elements have been carried out, so that a high volume of waste has resulted. Also from the dismantling of irradiated facilities metallics waste has o be handed. Prior for equipment repair the hot cell involved has to be decontaminated and a large amount of lower active waste is produced. The waste is collected for conditioning and storing. There are different categories as: low active liquid waste, low active burnable waste, fuel waste, low and high active metallic waste. For each waste category special transport container are used. For the volume reduction our Waste Department is equipped with special facilities e.g.: furnace for burning, drying, liquids evaporators, hydraulic press for pelletizing, decontamination box for the dismantling ad cleaning of components. After conditioning the waste will be stored on site or transported to final storage in a salt mine (ERAM) . Special documentation has to be done for the acceptance of this waste

  15. Forschungszentrum Juelich, Institut fuer Kernphysik/COSY. Annual report 2010

    Buescher, Markus; Grzonka, Dieter; Hanhart, Christoph; Krewald, Siegfried; Maier, Rudolf; Meissner, Ulf G.; Ritman, James; Stockhorst, Hans; Stroeher, Hans

    2011-04-01

    The following topics are dealt with: Physics at COSY, COSY operation and developments, further experimental activities, theoretical investigations, preparation of the HESR, the PANDA experiments. (HSI)

  16. GSF - Forschungszentrum fuer Umwelt und Gesundheit. Annual report 2005

    Wiedemann, M.; Haury, H.J.; Guldner, H.; Kettembeil, S.; Leser, B.; Offenberger, M.; Weiner, M.

    2006-01-01

    The report for the year 2005 falls at a time of change in both the Scientific and Administrative Managing Directors of the GSF. Thus securing continuity of the projects was a priority for the sound development of the research centre. In recent years, research at the GSF has focused on the health of humans in their environment - recognition of risks for human health from environmental factors, elucidation of mechanisms of disease development, and development of concepts - in order to protect human health and the natural basis of life. Substantial resources were invested in genome research, including in the German Mouse Clinic, biomedical translational approaches were initiated, programme-oriented funding was introduced, and new pathways were established for the transfer of results into practice. The 'mid term' review confirmed both the direction and excellence. The scientific achievements of the GSF are presented in detail in the following report, which, as in previous years, is arranged according to the reports of the institutes. Further, GSF scientists ensure that the most recent research results can flow into guidelines and new legislation by participating in national and international advisory commissions. GSF scientists are members of the Commission on Radiological Protection of the Federal Environment Ministry, in the MAK commission of the German Research Foundation, and in the ICRP (International Commission on Radiological Protection), to name but a few, and also act as scientific advisors for policy in the areas of medicine and data processing. (orig.)

  17. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2001

    Weiss, F.P.; Rindelhardt, U.

    2002-06-01

    In the reporting period, the ISR performed 9 meetings and workshops with international participation. It is especially worth mentioning the workshop on 'Process Control and Condition Monitoring in Chemical Plants' that was conducted for the first time, and the concluding conference of the DFG Innovationskolleg 'Magneto-Hydrodynamics of Electrically Conducting Fluids'. At the ROCOM test facility (Rossendorf Coolant Mixing facility), a large series of experiments was performed dedicated to coolant mixing phenomena in PWRs during boron dilution and cold water transients. CFD models were validated against those experiments and a so called semi-analytical mixing model was developed. By coupling that semi-analytical model with the DYN3D reactor dynamics code it could be shown that a shut down reactor gets re-critical when a plug of 36 m 3 deionated water enters the core after switching on the first main coolant pump. However, that deionated plug does not lead to non-allowed high coolant pressure or fuel temperatures. The behavior of a RPV lower callotte during a severe accident with melt slumping into the lower plenum is studied in 1:10 test at Royal Institute of Technology Stockholm. At the ISR computational methods were developed for pre- and post-test calculations of those experiments in order to predict the time and mode of RPV failure. The temperature, as well as location, and time of the RPV failure were found in good agreement with the experiment. Two patents resulted from those studies. One of them proposes a creep stool to mechanically support the RPV deformed by creeping, and the flooding of the reactor pit for ex vessel cooling of the melt inside the vessel. Such measures extend the time till RPV failure and offer the possibility for additional accident management procedures that can prevent the RPV meltthrough. The MHD department of ISR was especially successful in 2001. In the framework of the Bundesministerium fuer Bildung und Forschung (BMBF) initiative 'Innovative Gruenderlabore' they were granted an amount of 750,000 DM to be able permanently to create the conditions for applied and market relevant developments that allow young scientists to found their own private technology business. (orig.)

  18. Forschungszentrum Juelich, Institut fuer Kernphysik/COSY. Annual report 2007

    Buescher, M.; Hanhart, C.; Krewald, S.; Machner, H.; Maier, R.; Meissner, U.G.; Ritman, J.; Stockhorst, H.; Stroeher, H. (eds.)

    2008-03-15

    The following topics are dealt with, Physics at COSY, external experiments, theoretical investigations. COSY operation and developments, preparation for FAIR. See hints under the relevant topics. (HSI)

  19. Forschungszentrum Rossendorf, Institute of Radiochemistry. Annual report 1993

    Nitsche, H.; Bernhard, G.

    1994-06-01

    Since the founding of the Institute, a reorientation of the scientific direction was initiated: From the production and application of radioisotopes during the period before 1992 toward the new focus of radioecological research for risk assessment and remediation of radionuclide contaminations. The research relates to contamination problems from uranium mining in the German states of Saxony and Thuringia and in the neighboring Czech Republic, and from nuclear weapons production, testing, and accidents in the former Soviet Union. The new research direction of the Institute covers the essential aspects of radionuclide transport in the geo- and biosphere. It includes the distribution of radioactivity in ground- and surface waters and in air. We are studying the interaction of radioactive materials (a) at the interface between aqueous phase and rocks, minerals and soils, (b) the formation and distribution of colloids and aerosols, and (c) the mobilization and retardation of radionuclides through the interaction with organic contaminants and biological decay products. Our studies are essential for the successful development of environmental decontamination and remediation strategies. This report reflects the scientific transition of the Institute. The contributions to the section on ''Ecological Research'' are already focused toward the new challenge. The research that is summarized as ''General Research'' and ''Chemistry of the Heavy Elements'' clearly bear the elements of aerosol science. (orig.)

  20. Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 1996

    Weiss, F.P.; Rindelhardt, U.

    1997-08-01

    The research of the institute aims at the safety assessment of the design of nuclear and chemical facilities, the development of accident management procedures, and the increase of operational safety by improved plant surveillance. Physical models and computer codes are developed for multiphase/multicomponent flows and for the space and time dependent power release in nuclear and chemical reactors to be able to analyse the thermo-fluiddynamic phenomena during assumed accident scenarios. Emphasis is particularly focussed on spatial flow phenomena and the time dependent change of flow patterns. Sustainable void fraction probes and tomographic systems are developed to measure those parameters of two phase flows that characterize the exchange of pulse, energy and mass between the phases and components. The research related to materials safety is directed to the behaviour of components exposed to neutron and gamma radiation. The susceptibility to irradiation induced embrittlement and the behaviour of annealed material during reirradiation are investigated by fracture mechanical methods in dependence on the materials composition. The work on process and plant diagnostics makes available basic methods for early failure detection and operational monitoring which are important means of accident prevention. Recent initiatives of the institute are concerned with the transport of pollutants in the geosphere. Particularly, codes are developed for the simulation of physical and chemical processes during the transport of pollutants in unsaturated zones of the soil. (orig.)

  1. Forschungszentrum Rossendorf, Institute for Safety Research. Annual report 1994

    Weiss, F.P.; Rindelhardt, U.

    1995-06-01

    Striving for the assessment and enhancement of design based safety, for improving operational safety, and for risk management IFS is engaged in the following methodical fields: - Experimental and theoretical thermo-fluiddynamics, - 3-dimensional neutron kinetics, - characterization of the mechanical behaviour of aged materials and microstructural analysis, -transport calculations of particle and radiation fields, - early failure diagnostics of processes and plants, - hazard ranking of non-nuclear waste deposits and support of the selection of appropriate remediation procedures by means of decision analysis. In 1994, special efforts were directed to the extension of experimental facilities needed for radioactive materials testing and for two phase flow investigations. Moreover, first research projects on the safety of VVER reactors could successfully be finished. (orig./HP)

  2. Forschungszentrum Rossendorf, Institute for Safety Research. Annual report 1995

    Weiss, F.P.; Rindelhardt, U.

    1996-09-01

    The scientific work of the Institute of Safety Research covers a wide range of safety related investigations. During 1995 important results on thermo-fluid dynamic single effects, thermalhydraulics and neutron kinetics for accident analysis, materials safety, simulation of radiation and particle transport, mechanical integrity of technical systems and process monitoring, risk management for waste deposits, magneto-hydrodynamics of conductive fluids, and of renewable energies were reached. The annual report presents also lists of publications, conference contributions, meetings, and workshops. (DG)

  3. Forschungszentrum Juelich, Institut fuer Kernphysik/COSY. Annual report 2007

    Buescher, M.; Hanhart, C.; Krewald, S.; Machner, H.; Maier, R.; Meissner, U.G.; Ritman, J.; Stockhorst, H.; Stroeher, H.

    2008-03-01

    The following topics are dealt with, Physics at COSY, external experiments, theoretical investigations. COSY operation and developments, preparation for FAIR. See hints under the relevant topics. (HSI)

  4. Forschungszentrum Rossendorf, Institute for Safety Research. Annual report 1993

    Weiss, F.P.; Rindelhardt, U.

    1994-06-01

    Seven of the 10 selected reports describe computer codes for the analysis of accident scenarios at the Russian VVER type reactors, irradiation induced defect structures, neutron fluence calculations, acoustic leak detection using neural networks, diagnostics and modelling of component vibration of VVER reactors, and a specification of a technical system to improve the operational monitoring of Zaporoche-5 reactor. The other 3 reports show a computer simulation of a plasma source, an decision analysis for the assessment of risks with conventional and radioactive wastes, and investigations on renewable energy systems. (DG)

  5. Forschungszentrum Rossendorf, Institut fuer Ionenstrahlphysik und Materialforschung. Annual report 1993

    Moeller, W.; Wieser, E.; Kirch, S.

    1994-04-01

    Highlights were: Ion beam induced epitaxial crystallization of 6H-SiC -Band gap engineering in Co alloyed β-FeSi 2 formed by ion beam synthesis -Formation of CoSi 2 wires by maskless implantation with the focused ion beam -Phosphorus implanted n + -layers for HPGe - Development of a fluidic ISFET microsystem for chemical analysis - Depth selective Moessbauer spectroscopy of Al-implanted iron - Plasma source ion implantation - Simultaneous light element analysis by HIERD for plasma-wall interaction studies in fusion research -Paint layer studies using PIXE on air - Texture investigation on geological three phase samples - status of the Rossendorf 7.25 GHz ECR ion source -Formation of double-height Si(001) steps by sputtering with Xe ions - a computer simulation - Self-organisation during Ostwald ripening in ion beam synthesis of buried compound layers - Modification of metals and other materials - Modification of semiconductors and patterning by focused ion beam -Application of ion beams to sensors - Ion beam analysis, fundamentals of ion-solid-interaction and accelerator technique - Structural research. (orig./HP)

  6. GSF - Forschungszentrum fuer Umwelt und Gesundheit. Annual report 1998

    Haury, H.J.; Wiedemann, M.; Grill, A.; Guldner, H.; Kettembeil, S.; Knauer, R.; Meyer-Streng, O.; Weiner, M.

    1999-01-01

    The research fields of the GSF in 1998 were as follows. Behaviour and fate of foreign compounds in the environment, biogeochemical cycles and signalling in terrestrial and aquatic systems, risk assessment and management in ecosystems, biological effects of chemicals and radiation on the cellular level, genome analysis and genetic predisposition, influence of the environment on differentiation, development and carcinogenesis, health risk resulting from internal and external exposure, basic research on the improvement of diagnostic and therapeutical methods, clinical-experimental research on diagnosis and therapy, improvement of efficacy and cost effectiveness in public health care. Separate abstracts were prepared for seven sections of this report [de

  7. GSF - Forschungszentrum fuer Umwelt und Gesundheit. Annual report 2005; GSF - Forschungszentrum fuer Umwelt und Gesundheit. Jahresbericht 2005

    Wiedemann, M.; Haury, H.J.; Guldner, H.; Kettembeil, S.; Leser, B.; Offenberger, M.; Weiner, M. (eds.)

    2006-07-01

    The report for the year 2005 falls at a time of change in both the Scientific and Administrative Managing Directors of the GSF. Thus securing continuity of the projects was a priority for the sound development of the research centre. In recent years, research at the GSF has focused on the health of humans in their environment - recognition of risks for human health from environmental factors, elucidation of mechanisms of disease development, and development of concepts - in order to protect human health and the natural basis of life. Substantial resources were invested in genome research, including in the German Mouse Clinic, biomedical translational approaches were initiated, programme-oriented funding was introduced, and new pathways were established for the transfer of results into practice. The 'mid term' review confirmed both the direction and excellence. The scientific achievements of the GSF are presented in detail in the following report, which, as in previous years, is arranged according to the reports of the institutes. Further, GSF scientists ensure that the most recent research results can flow into guidelines and new legislation by participating in national and international advisory commissions. GSF scientists are members of the Commission on Radiological Protection of the Federal Environment Ministry, in the MAK commission of the German Research Foundation, and in the ICRP (International Commission on Radiological Protection), to name but a few, and also act as scientific advisors for policy in the areas of medicine and data processing. (orig.)

  8. GSF - Forschungszentrum fuer Umwelt und Gesundheit. Annual report 2004; GSF - Forschungszentrum fuer Umwelt und Gesundheit. Jahresbericht 2004

    Wiedemann, M.; Haury, H.J.; Goedde, M.; Guldner, H.; Kettembeil, S.; Leser, B.; Meyer-Streng, O. (eds.)

    2005-07-01

    Recent years have been shaped by the introduction of programme-oriented funding. In 2004, we were able once again to focus on the real goal of the GSF, the performance of excellent research. The effects of fine particles, for example, are at the centre of public interest. This topic is not only of great importance for health, it also has a wide-reaching economic significance; we have only to think of filters for diesel engines. The GSF was involved in many scientific successes. For example, the results on the economic costs of smoking received considerable attention from both the general public and the scientific world. GSF scientists were involved in the decoding of the chicken genome and the discovery of a Parkinson gene. Together with university and other research organisations, they founded a Virtual Institute on Biotic Interactions, and took part in an international project on the development of combination vaccines against HIV. The setting up of the GSF 'glass laboratory', which was created with substantial support form the Helmholtz Association, is particularly worthy of mention. GSF scientists have been awarded various prizes, for example the Felix Wankel Prize awarded to Professor Jean-Marie Buerstedde. The Bavarian Advancement of Women Prize 2004, which distinguished exemplary initiatives in the area of family and women's advancement, was a special honour. Professor Magdalena Goetz was appointed Director of the Institute for Stem Cell Research. (orig.)

  9. GSF - Forschungszentrum fuer Umwelt und Gesundheit. Annual report 2003; GSF - Forschungszentrum fuer Umwelt und Gesundheit. Jahresbericht 2003

    Wiedemann, M; Haury, H J; Goedde, M; Guldner, H; Kettembeil, S; Leser, B; Meyer-Streng, O [eds.

    2004-07-01

    The GSF develops scientific principles that provide the basis for protecting human health and the natural basis of life for the future. GSF health research focuses on the genetic and immunological basis of molecular protection and define and their dysfunction during disease development, and the identification of new factors that contribute to sickness or health. (orig.)

  10. GSF - Forschungszentrum fuer Umwelt und Gesundheit. Annual report 2005; GSF - Forschungszentrum fuer Umwelt und Gesundheit. Jahresbericht 2005

    Wiedemann, M; Haury, H J; Guldner, H; Kettembeil, S; Leser, B; Offenberger, M; Weiner, M [eds.

    2006-07-01

    The report for the year 2005 falls at a time of change in both the Scientific and Administrative Managing Directors of the GSF. Thus securing continuity of the projects was a priority for the sound development of the research centre. In recent years, research at the GSF has focused on the health of humans in their environment - recognition of risks for human health from environmental factors, elucidation of mechanisms of disease development, and development of concepts - in order to protect human health and the natural basis of life. Substantial resources were invested in genome research, including in the German Mouse Clinic, biomedical translational approaches were initiated, programme-oriented funding was introduced, and new pathways were established for the transfer of results into practice. The 'mid term' review confirmed both the direction and excellence. The scientific achievements of the GSF are presented in detail in the following report, which, as in previous years, is arranged according to the reports of the institutes. Further, GSF scientists ensure that the most recent research results can flow into guidelines and new legislation by participating in national and international advisory commissions. GSF scientists are members of the Commission on Radiological Protection of the Federal Environment Ministry, in the MAK commission of the German Research Foundation, and in the ICRP (International Commission on Radiological Protection), to name but a few, and also act as scientific advisors for policy in the areas of medicine and data processing. (orig.)

  11. List of publications of the University of Karlsruhe and the Karlsruhe Nuclear Research Centre

    1985-01-01

    This list covers books and periodicals, articles in periodicals and collective publications, scientific reports, theses and habilitations composed or edited by institutions, their organs and institutes as well as their teaching staff and scientific collaborators, and indicates moreover patents. (orig./PW) [de

  12. The Karlsruhe Atmospheric Mesoscale Model KAMM; Das Karlsruher Atmosphaerische Mesoskalige Modell KAMM

    Adrian, G. [Forschungszentrum Karlsruhe GmbH Umwelt und Technik (Germany). Inst. fuer Meteorologie und Klimaforschung]|[Karlsruhe Univ. (T.H.). (Germany). Inst. fuer Meteorologie und Klimaforschung

    1998-01-01

    The applications of the KAMM model range from real-time simulations over the analysis of mesoscale phenomena and the development of parametrizations to describing climatology. In the course of time, wishes emerged to change essential parts of the original model concept, calling for substantial reprogramming; so it was decided to entirely redraft the dynamic core of KAMM and to program it from the beginning including the parallelization of the code. The paper describes the basics of the new model core. (orig./KW) [Deutsch] Der Anwendungsbereich des KAMM-Modells erstreckt sich von Echtzeitsimulationen, ueber Analyse mesoskaliger Phaenomene, Entwicklung von Parametrisierungen bis hin zur beschreibenden Klimatologie. Weil im Laufe der Entstehungszeit wesentliche Aenderungswuensche des urspruenglichen Konzeptes entstanden sind, die eine Neuprogrammierung in wesentlichen Teilen erforderlich erscheinen lassen, wurde entschieden, den dynamischen Kern von KAMM voellig neu zu gestalten und bei der Programmierung eine Parallelisierung des Codes von Anfang an mit einzubeziehen. Die Grundlagen dieses neuen Modellkernes werden vorgestellt. (orig./KW)

  13. IAEA consultants' meeting on benchmark validation of FENDL-1. Summary report

    Pashchenko, A.B.

    1996-01-01

    The present report contains the Summary of the IAEA Consultants' Meeting on ''Benchmark Validation of FENDL-1'', held at Karlsruhe, Germany, from 17 to 19 October 1995. This meeting was organized by the IAEA Nuclear Data Section (NDS) with the co-operation and assistance of local organizers of the Forschungszentrum Karlsruhe, Germany. Summarized are the conclusions and the main results of extensive benchmarking of FENDL-1 by comparing experimental data from numerous number of fusion integral experiments, to analytical predictions based on discrete ordinates as well as Monte Carlo calculations. (author). 4 refs

  14. Comparison of ASTECV1.3.2 and ASTECV2 results for QUENCH 12 test

    Stefanova, A.

    2010-01-01

    This paper presents a comparison of QUENCH 12 test calculated results with ASTECv1.3R2 and ASTECv2 computer codes. The test was performed to investigate the behavior of VVER fuel assemblies. This investigation is a part of the 6th and 7th framework programs of the EC supported ISTC program. The test facility is located at Forschungszentrum in Karlsruhe. The structure of the test facility allows experimental studies under transient and accident conditions. The ASTEC1.3R2 and ASTECv2 computer codes have been used to simulate the investigated test. The base line input model for ASTEC was provided from Forschungszentrum, Karlsruhe. During the preparation of QUENCH - 12 experiment, the input deck was adapted to new initial and boundary conditions. The comparison show good agreement between measured data and ASTEC calculated results. (author)

  15. Data on research and technology marketing in 2000; Daten zum Forschungs- und Technologiemarketing 2000

    Friehmelt, R.; Oberdorf, R.

    2001-04-01

    At Forschungszentrum Karlsruhe all ideas suited for cooperations or licenses or for the raising of third-party funds are stored in a know-how database run by the Technology Transfer and Marketing Department (TTM). At trade fairs, current licenses and cooperations desired and offered are pinned up on a board. In addition, approx. 6300 interested persons are informed about wishes and offers of licenses and cooperations five times per year. In the present report, the ideas of Forschungszentrum Karlsruhe are split up in accordance with the type of partner wanted, the technical field covered, their age, and the institutes involved. The numbers of contacts made on trade fairs are indicated. Inquiries regarding the TT information sheets have been counted and the contacts are evaluated. Furthermore, it is reported about the presence of technology offers in databases. Strategic actions, in particular market studies, were carried out for attractive topics in cooperation with partner companies. Finally, proposals for improvement shall be discussed. (orig.) [German] Von der Stabsabteilung Technologietransfer und Marketing (TTM) werden alle Ideen aus dem Forschungszentrum Karlsruhe, die fuer Kooperationen, Lizenzen oder zur Drittmitteleinwerbung geeignet sind, in einer Know-how-Datenbank gefuehrt. Die aktuellen Technologieangebote werden auf Messen ausgehaengt. Ausserdem werden fuenfmal jaehrlich Technologieangebote an einen Kreis von etwa 6300 Interessenten verschickt. Der Bericht schluesselt die Ideen des Forschungszentrums nach Art der gesuchten Partner, Fachgebieten, Alter und nach Instituten auf. Es werden die Zahlen der Messekontake angegeben. Zu den Technologieangeboten wurden die Ruecklaeufer gezaehlt und die Kontakte bewertet. Es folgen Angaben zur Praesenz der Technologieangebote des Forschungszentrums in Datenbanken. Zu attraktiven Themenbereichen wurden mit Unterstuetzung von Partnerfirmen strategische Aktionen durchgefuehrt, insbesondere Marktuntersuchungen. In

  16. Experiments on the quench behavior of fuel rods

    Hofmann, P.; Noack, V.; Burbach, J.; Metzger, H.

    1995-01-01

    Because of the importance of the observed reflood phenomena for safety of current and future LWRs, the Forschungszentrum Karlsruhe (FZKA) started a program to investigate the mechanisms of quench-induced oxidation of Zircaloy. A small scale test-rig was designed and built in which it is possible to quench single Zircaloy rods by water and steam. The report describes the status of this work in May 1995. Some experimental results are presented. (orig./HP)

  17. Experiments on the quench behavior of fuel rods

    Hofmann, P.; Noack, V.; Burbach, J.; Metzger, H.

    1995-08-01

    Because of the importance of the observed reflood phenomena for safety of current and future LWRs, the Forschungszentrum Karlsruhe (FZKA) started a program to investigate the mechanisms of quench-induced oxidation of Zircaloy. A small scale test-rig was designed and built in which it is possible to quench single Zircaloy rods by water and steam. The report describes the status of this work in May 1995. Some experimental results are presented. (orig./HP)

  18. International Conference (4th) on Nanostructured Materials Held in Stockholm, Sweden on 14-19 June 1998. Book of Abstracts

    1998-06-19

    de Fisica de Sistemas, Spain Forschungszentrum Karlsruhe, Germany Univ. of Delaware, USA EPFL, Switzerland Tohoku University, Japan Virginia...Dominguez2, E.Roldan2, J.Campora3, P. Palma3 and A. Fernandez! institute de Ciencia de Materiales de Sevilla, Centra de Investigaciones Cintificas...34Isk de la Cartuja", Avda. Americo Vespucio s/n, 41092-Sevilla, SPAIN <asuncion@cica.es: 2Depto. de Qufmica- Fisica , Universidad de Sevilla,

  19. Beryllium irradiation embrittlement test programme. Material and specimen specification, manufacture and qualification

    Harries, D.R.; Dalle Donne, M.

    1996-06-01

    The report presents the specification, manufacture and qualification of the beryllium specimens to be irradiated in the BR2 reactor in Mol to investigate the effect of the neutron irradiation on the embrittlement as a function of temperature and beryllium oxide content. This work was been performed in the framework of the Nuclear Fusion Project of the Forschungszentrum Karlsruhe and is supported by the European Union within the European Fusion Technology Program. (orig.)

  20. Ion diode diagnostics to resolve beam quality issues

    Bluhm, H; Buth, L; Hoppe, P [Forschungszentrum Karlsruhe (Germany). Institut fuer Neutronenphysik und Reaktortechnik; and others

    1997-12-31

    Various diagnostic methods and instruments are under development at the Forschungszentrum Karlsruhe to measure important physical quantities in the accelerating gap of high power diodes on KALIF with a high spatial and temporal resolution. The methods include optical spectroscopy, refractive index measurements, dispersion interferometry, and high resolution energy analysis. The setup of these diagnostic tools and the first results obtained for applied and self-magnetically insulated diodes are presented. (author). 6 figs., 5 refs.

  1. Availability measurement of grid services from the perspective of a scientific computing centre

    Marten, H; Koenig, T

    2011-01-01

    The Karlsruhe Institute of Technology (KIT) is the merger of Forschungszentrum Karlsruhe and the Technical University Karlsruhe. The Steinbuch Centre for Computing (SCC) was one of the first new organizational units of KIT, combining the former Institute for Scientific Computing of Forschungszentrum Karlsruhe and the Computing Centre of the University. IT service management according to the worldwide de-facto-standard 'IT Infrastructure Library (ITIL)' was chosen by SCC as a strategic element to support the merging of the two existing computing centres located at a distance of about 10 km. The availability and reliability of IT services directly influence the customer satisfaction as well as the reputation of the service provider, and unscheduled loss of availability due to hardware or software failures may even result in severe consequences like data loss. Fault tolerant and error correcting design features are reducing the risk of IT component failures and help to improve the delivered availability. The ITIL process controlling the respective design is called Availability Management. This paper discusses Availability Management regarding grid services delivered to WLCG and provides a few elementary guidelines for availability measurements and calculations of services consisting of arbitrary numbers of components.

  2. Karlsruhe Nuclear Research Center. Research and development program 1992

    1991-01-01

    The KfK R and D activities are classified by ten point-of-main-effort projects: 1) low-pollution/low-waste methods, 2) environmental energy and mass transfers, 3) nuclear fusion, 4) nuclear saftey research, 5) radioactive waste management, 6) superconduction, 7) microtechnics, 8) materials handling, 9) materials and interfaces, 10) basic physical research. (orig.) [de

  3. Bundesforschungsanstalt fuer Ernaehrung (BFE), Karlsruhe - annual report 1986

    1987-01-01

    The annual report of the BFE informs about the tasks of the institution, the organisational structure, and the actual staff. The scientific activities of the various institutes and the research results achieved are reported in brief, together with activities within the framework of international cooperation agreements. A list of publications issued in 1986 is added. The BFE's activities currently concentrate on the following research subjects: Storage, shipping, processing, and quality of food. Fertilizing and food quality. Sensory, toxicologic, nutritional and economic evaluation of food. Food characterization by means of objective methods. Important components, foreign matter, and radionuclides in food. Development of analytic methods for food research. Hygenic improvement of food. Evaluation of catering systems of importance to communal provisions. Nutritional requirements and behaviour of the population. Quality and cost of food. Information of the consumer about wholesome food and nutrition. Documentation and information activities. (orig./MG) [de

  4. 1991 annual report of the Karlsruhe Federal Food Research Institute

    1992-01-01

    The Federal Food Research Institute does research in the field of nutrition, food and household sciences as well as in related special fields. Among its working priorities are the determination of foreign matter and radionuclides in food as well as food preservation by means of irradiation including dosimetry. The results of those priorities are represented. (orig./MG) [de

  5. The meteorological measurement system of the Karlsruhe Nuclear Research Center

    Dilger, H.

    1976-08-01

    The system mainly serves to record the parameters which are important for the diffusion of offgas plume. The system includes 47 instruments in total which are used to measure the wind velocity, the wind direction, the wind vector, the temperature, the dew point, the solar and heat radiation, the precipitations and the atmospheric pressure, most of them mounted at the 200 m high meteorological tower. (orig./HP) [de

  6. Karlsruhe Nuclear Research Center. Research and development program 1991

    1990-01-01

    The R and D activities of the KfK are classified in 8 main research activities: 1) project nuclear fusion; 2) project pollutant mitigation in the environment; 3) solid state and materials research; 4) nuclear and elementary particle physics; 5) microtechnics e.g. X-ray lithography; 6) materials handling; 7) project nuclear safety research; 8) radioactive waste management. (orig.) [de

  7. Fast neutron capture in actinide isotopes: recent results from Karlsruhe

    Wisshak, K.; Kaeppeler, F.; Reffo, G.; Fabbri, F.

    1982-01-01

    Capture gamma-ray spectra of 241 Am, 240 Pu, 242 Pu 238 U and 197 Au were calculated in the framework of the spherical optical model and the statistical model. These spectra were used to correct experimental data for the capture cross sections of 240 242 Pu and 241 Am from relative measurements using a Moxon Rae-detector with graphite converter and 197 Au as well as 238 U as standards. This correction is required to take into account that the detector efficiency is not exactly proportional to gamma-ray energy. The resulting correction factors proved to be negligible for measurements relative to 238 U, whereas they are approx. 3% if gold is used as a standard. The capture cross section of 243 Am has been measured in the energy range 10 to 250 keV using kinematically collimated neutrons from the 7 Li(p,n) and T(p,n) reaction. The samples are positioned at flight paths of 5 to 7 cm and gold was used as a standard. Capture events were detected by two Moxon-Rae detectors with graphite and bismuth-graphite converters shielded by 0.5 to 2 cm of lead. Fission events were detected by a NE213 liquid scintillator. The present status of the experiment and some preliminary results will be presented

  8. The vacuum system of the Karlsruhe magnetic spectrograph 'Little John'

    Buschmann, J.; Gils, H.J.; Jelitto, H.; Krisch, J.; Ludwig, G.; Manger, D.; Rebel, H.; Seith, W.; Zagromski, S.

    1985-02-01

    The vacuum equipment of the magnetic spectrograph Little John is described. The system is characterized by the following special features: The sliding exit flange of the target chamber can be moved to the desired angle of observation without affecting the high vacuum. The pressure maintained is less by a factor of ten than the pressure in the incoming beam tubing. The vacuum system is divided into several separate pumping sections. Ground loops are strictly avoided. All actual states of relevance are fed back to the control panels. The vacuum installation is protected by hardware interlocking systems as well as by a real time program written in FORTRAN in cooperation with CAMAC interfacing. (orig.) [de

  9. Heavy liquid metal technologies at KArlsruhe Lead LAboratory KALLA

    Knebel, J.U.; Mueller, G.; Konys, J.

    2002-01-01

    The objectives of the research cover: lead-bismuth technologies; corrosion mechanism and corrosion protection; thermal hydraulics; kinetics of oxygen control systems. Detailed experimental results are presented

  10. The meterological information system of the Karlsruhe Nuclear Research Center

    Holleuffer-Kypke, R. von; Huebschmann, W.G.; Thomas, P.; Suess, F.

    1984-01-01

    The Meteorological Information System (MIS) comprising the meteorological instruments, the computers, and the software for data processing and recording, is part of the KfK safety and control system. In 1982 is was equipped with an independent data processing system. The report explains the arrangement and the operation of the sensors and thw two process computers. For selected meteorological situations the ability of the system is demonstrated, i.e., the presentation of the vertical profiles of wind, temperature and turbulence in the lower atmospheric boundary layer as well as the calculation and graphical representation of the transport and dispersion into the KfK environment of radioactive pollutants being released by the nuclear installations of the KfK into the atmosphere. (orig.) [de

  11. The European Institute for Transuranium Elements (EURATOM) Karlsruhe

    1975-01-01

    The objectives of the Institute, its historical and geographical background, its structure, and its operation are described in the first part of this booklet. In the second part, a more detailed account of the scientific and technological work carried out at the Institute is given: fuel science and technology (mainly plutonium) and basic actinide research (mainly transplutonium elements)

  12. List of scientific publications of the Kernforschungszentrum Karlsruhe in 1976

    1977-03-01

    The report KFK 2425 contains the titles of all publications printed in 1976. Lectures are included if the Central Library has the written text at its disposal. With regard to patents, only 'Ersterteilungen', 'Auslegeschriften' (DAS) or 'Offenlegungsschriften' (OS) are listed. The list of publications is arranged according to institutes. Under projects, only published project reports and publications by members of the project staff in question are named. Included, too, are publications, printed on the premises, concerning R+D activities within the projects 'Process control by data processing systems' (PDV)' and 'Computer-aided design and development' (CAD), projects which are carried out under the auspices of the Gesellschaft fuer Kernforschung in cooperation with firms and institutes. (orig./HK) [de

  13. Decommissioning and dismantling of the reprocessing plant Karlsruhe

    Eiben, K.; Fritz, P.

    1995-01-01

    Reprocessing activities were discontinued in late 1990. The facility was drained and rinsed, and 80 m3 of HLWC have since been stored in special tanks, awaiting vitrification. Decommissioning work is scheduled to proceed in six phases. The reprocessing areas of the facility will be prepared for release from radiological control and dismantled in the first phase. The remaining facilities can be deregulated, and storage tanks dismantled, only after termination of phase 1. The goal of the following phase is clearance from radiological control of all controlled areas, and the last phase is to cover dismantling of all buildings and restoration of a green field site. The overall costs of these activities are estimated to amount to DM 1.657 million. The article explains the contents of the first permits for decommissioning as well as the documents prepared for planning of work and licence application. (orig./HP) [de

  14. Institute for transuranium elements Karlsruhe Annual Report 1988

    1989-01-01

    The present report summarizes the results of the work which has been performed in 1988 at the Institute for Transuranium Elements of the Joint Research Centre of the Commission of the European Communities. While, as in the past, major efforts were devoted to the Programme on Nuclear Fuels and Actinide Research, important contributions were made to other JRC Specific Programmes, i.e. Reactor Safety, Radioactive Waste Management, and Safeguards and Fissile Materials Control. In addition, The Institute has carried out analytical work for the EURATOM Safeguards Directorate and executed research tasks in the safeguards context, both, for the Commission of the European Communities and for the International Atomic Energy Agency in Vienna. Exploratory Research, finally, dealt with an investigation of possibilities of acoustic aerosol scavenging

  15. Annual report 1980 of the 'Bundesforschungsanstalt fuer Ernaehrung' in Karlsruhe

    1981-01-01

    Food irradiation for preservation is investigated in two research programs by the mutagenicity of irradiated onion powder, dates, mangoes, beans, onions, cocoa, extracts of meat, potatoes, salad, apples, joghurt. Besides that, the environmental uptake of radioisotopes in food was investigated. (AJ) [de

  16. Karlsruhe Nuclear Research Center. Research and development programme 1989

    1988-01-01

    The R and D activities of the KfK are classified in 10 main research activities: 1) Project fast breeder; 2) separation nozzle method; 3) project nuclear fusion; 4) project reprocessing and waste processing; 5) ultimate storage; 6) environment and safety; 7) solid-state and materials research; 8) nuclear and elementary particle physics; 9) microtechnics e.g. X-ray lithography; 10) materials handling. (HP) [de

  17. Second Karlsruhe international conference on analytical chemistry in nuclear technology

    1989-01-01

    Around 180 abstracts of invited lectures and poster presentations of the international analytical conference are presented in this book. They cover analytical applications throughout the fuel cycle and radioanalysis of manifold materials. Most of the abstracts are prepared separately for input in INIS and EDB. (RB)

  18. Institute for transuranium elements Karlsruhe. Annual report 1989

    1990-01-01

    Transient-tested high burn-up fuel samples were investigated by electron microscopy to study the effect of strain on fission product distribution, and the concentration of (U,Pu)O 2 agglomerates in irradiated MOX fuel was examined by electron microprobe analysis. Conclusions on maximum temperatures to which the core of the Three Mile Island reactor was exposed could be drawn from an examination of TMI fuel debris. Equipment to measure thermophysical fuel properties for reactor safety studies was further developed. An improved version (slice version) of the TRANSURANUS fuel pin code was tested and released for external use. Safety Aspects of Fuel Operation and Handling were dealt with by improving preparation methods of (U,Pu)N. Release and resuspension of radioactive dust particles in fires was studied. The principal objective of the Actinide Determination and Recycling activity was the reduction of long-term hazards of alpha-bearing nuclear waste. The long-term storage behaviour of UO 2 and MOX spent fuel samples as well as of vitrified waste forms was further investigated by studying the effect of leaching. The electronic structure of the transuranium elements is the central objective of basic Actinide Research. A large number of ternary alloys containing Np or Pu and Si or Ge, together with a transition metal was prepared for basic experimental studies. New high-pressure phases were discovered in PuSe, UPS, ThO 2 , and PuO 2 . Analytical techniques were evaluated and automated for safeguards. A multiwavelength pyrometer was adapted for industrial use. Major contracts with Third Parties were dealing with the development of minor actinide alloys, and the post-irradiation examination of high burn-up UO 2 and MOX fuel from LWR power stations

  19. Karlsruhe Nuclear Research Center. Research and development programme 1988

    1987-01-01

    A general survey of planned activities and developmental trends of the nuclear research centre is followed by a more detailed account of projects and goals. The various institutes and laboratories are presented together with their specific task schedules. (UA) [de

  20. Karlsruhe international conference on analytical chemistry in nuclear technology

    1985-01-01

    This volume presents 218 abstracts of contributions by researchers working in the analytical chemistry field of nuclear technology. The majority of the papers deal with analysis with respect to process control in fuel reprocessing plants, fission and corrosion product characterization throughout the fuel cycle as well as studies of the chemical composition of radioactive wastes. Great interest is taken in the development and optimization of methods and instrumentation especially for in-line process control. About 3/4 of the papers have been entered into the data base separately. (RB)

  1. The FORTRAN-77 version of the Karlsruhe program system KAPROS

    Moritz, N.

    1985-02-01

    The FORTRAN-77 KAPROS-kernel includes some major changes compared with the version, which is described in the KfK-report 2254. The changes are documented in this report from the point of view of the system-programmer. This report is meant to be a supplement to the KfK-report 2254, assuming that the reader of this report is familiar with the KfK-report 2254. He also should be familiar with the IBM operating system MVS SP1.3.2 and the usual terms of data processing. (orig.) [de

  2. HelmholtzZentrum Muenchen Deutsches Forschungszentrum fuer Gesundheit und Umwelt. Annual report 2011; HelmholtzZentrum Muenchen Deutsches Forschungszentrum fuer Gesundheit und Umwelt. Jahresbericht 2011

    NONE

    2012-11-01

    The contribution under consideration is the annual report 2011 of the German Research Centre for Environmental Health (HelmholtzZentrum Munich, Federal Republic of Germany). The most important component of this annual report are the scientific highlights according to the following topics: (1) Systems researches for the health (M. Hrabe de Angelis); (2) Mechanisms of the interaction between genes and environment (M. Goetz); (3) Research of the metabolism (M. Tschoep); (4) Research of lungs and allergies (O. Eickelberg); (5) Technologies for the bio medicine (V. Ntziachristos); (6) Natural basis of existence (J. Durner).

  3. Institute for Nuclear Waste Disposal. Annual Report 2009

    Geckeis, H.; Stumpf, T.

    2010-01-01

    On October 01, 2009, the Karlsruhe Institute of Technology (KIT) was founded by a merger of Forschungszentrum Karlsruhe and Universitaet Karlsruhe (TH). KIT bundles the missions of both precursory institutions: a university of the state of Baden- Wuerttemberg with teaching and research tasks and a large-scale research institution of the Helmholtz Association conducting program-oriented provident research on behalf of the Federal Republic of Germany. Within these missions, KIT is operating along the three strategic fields of action, research, teaching, and innovation. With about 8000 employees and an annual budget of about EUR 700 million, KIT is one of the largest research and teaching institutions worldwide. It has the potential to assume a top position worldwide in selected fields of research. The objective: KIT will become an institution of excellent research and scientific education, as well as a prominent location of academic life, life-long learning, comprehensive advanced training, unrestricted exchange of know-how and sustainable innovation culture. The largest organizational units of KIT are the KIT Centers. They focus on problems of fundamental importance to the existence and further development of our society or on key issues of basic science. KIT Centers are characterized by the uniqueness of their scientific approach, their strategic objective and mission and by a long-term perspective. The Institut fuer Nukleare Entsorgung, INE, (Institute for Nuclear Waste Disposal) belongs to the KIT Energy Center. The KIT Energy Center comprises some 40 institutes of the Universitaet Karlsruhe (TH) and 18 large institutes of the Forschungszentrum Karlsruhe with, at present, a total of approx. 1100 staff members. The participating institutes and research groups are the operating research units. An interdisciplinary KIT School of Energy establishes ideal framework conditions for teaching. For external partners from industry, the KIT Center develops solutions in

  4. First Ph.D. Student Workshop of the Hermann von Helmholtz Association of National Research Centers (HGF) on ''Nuclear Safety Research''

    Knebel, J.U.; Sanchez Espinoza, V.H.

    2006-03-01

    The First Ph.D. Student Workshop ''Nuclear Safety Research'' of the Helmholtz Association of National Research Centers (HGF)'' was jointly organized by the Research Center Karlsruhe GmbH and the Energie Baden-Wuerttemberg AG (EnBW) from Wednesday 9th to Friday 11th March 2005. The workshop was opened with welcome greetings by Dr. Peter Fritz, Forschungszentrum Karlsruhe. Subsequently Dr. Joachim U. Knebel explained the main goals and the content of the workshop. The young scientists reported in 28 high-level presentations about their research work which covered a wide spectrum from reactor safety, partitions and transmutation, and innovative reactor systems, to safety research for nuclear waste disposal. The junior researchs showed excellent professional competence and demonstrated presentation qualities at the highest level. The successful funding of two Virtual Institutes, namely: the ''Competence in Nuclear Technologies'' and ''Functional Characteristics of Aquatic Interfaces both co-ordinated by Forschungszentrum Karlsruhe'', by the President of the Helmholtz Association Prof. Walter Kroell was the motivation for the organization of this first Ph.D. Student Workshop. Thanks to these two Virtual Institutes, the Reseach Center Karlsruhe and Juelich together with several univer-sities i.e. RWTH Aachen, Heidelberg, Karlsruhe, Muenster, and Stuttgart, have successfully financed eight Ph.D. and two post-doctoral students. Moreover, young scientists of the European Institute for Transuranium Elements (ITU) and additional seven Ph.D. Students, who are sponsored by the German nuclear industry (Framatome ANP, RWE Power, EnBW) in the frame of the Alliance Competence in on Nuclear Technology, and who are trained at Forschungszentrum Karlsruhe, actively contributed to this workshop. The EnBW-Award was handed over by Dr. Hans-Josef Zimmer, member of the board of directors of the EnBW-Kraftwerksgesellschaft, to Mrs. Ayelet Walter from the University of Stuttgart for the best

  5. Forschungszentrum Rossendorf, Institute of Ion Beam Physics and Materials Research. Annual report 2004

    Borany, J. von; Heera, V.; Helm, M.; Jaeger, H.U.; Moeller, W.

    2005-01-01

    The following topics are dealt with: Silicon based electrically driven microcavity LED, ultraviolet electroluminescence from a Gd-implanted Si-metal-oxide-semiconductor device, semiconductor quantum-cascade lasers, ion beam synthesis and morphology of semiconductor memories, ion implantation, films, sputtering, ion-beam induced destabilization of nanoparticles. (HSI)

  6. Recent developments in solid oxide fuel cells at Forschungszentrum Juelich and in Europe

    Steinberger-Wilckens, Robert; Blum, L.; Buchkremer, H.P.; Haart, L.J.G. de; Malzbender, J. [Forschungszentrum Juelich GmbH (DE). Inst. fuer Energieforschung (IEF); Pap, M.; Gross, S.M. [Forschungszentrum Juelich GmbH (DE). Zentralabteilung Technologie (ZAT)

    2010-07-01

    The SOFC group at FZJ has assembled and tested more than 350 SOFC stacks rated between 100 W and 15 kW during the last 15 years. The research topics cover the whole SOFC development area from materials over stack design, manufacturing of cells, stacks and components, mechanical and electrochemical characterisation, up to system design and demonstration. Use of improved steels, cathodes and materials processing has resulted in reduced degradation rates around 4 mV (<0.50%) per 1000 hours at 800 C and 500 mA/cm{sup 2} over tested stack lifetimes of over 15 000 hours. Other stacks operating at 700 C have already reached over 22.000 hours of lifetime. However, the target of development is directed at even further lowered degradation for commercial operation in stationary applications. All stack tests are accompanied by disassembly and post-operative examinations investigating such phenomena as cathode degradation, corrosion, and other ageing phenomena. These analyses give a deep insight into the interaction of the stack materials and supply vital data on assessing the possibilities for prolonged stack operation over some 10's of thousand hours. This paper gives an overview and summary of achievements of Juelich developments. It also discusses the European perspectives in SOFC commercialisation. European manufacturers are holding a leading edge on the planar SOFC technology with new activities developing rapidly. (orig.)

  7. Forschungszentrum Juelich GmbH, Institut fuer Kernphysik. Annual report 1991

    1992-03-01

    During the year 1991 the work concentrated on building the Cooler Synchrotron COSY-Juelich. The experimental activity was accompanied by theoretical studies in the field of medium energy nuclear physics. The preparation of COSY experiments concerned the realization of multipurpose facilities and other experiments. Work going on in the field of theoretical nuclear physics was strongly connected with research projects at COSY and processes induced in the proton-antiproton interaction. Through nuclear spectroscopy two-phonon octupole excitation had been identified in Gd-148. The ISIS ECR source has been used for the production of ion beams for atomic physics research. (DG)

  8. Forschungszentrum Rossendorf, Institute of Ion Beam Physics and Materials Research. Annual report 2004

    Borany, J. von; Heera, V.; Helm, M.; Jaeger, H.U.; Moeller, W. (eds.)

    2005-07-01

    The following topics are dealt with: Silicon based electrically driven microcavity LED, ultraviolet electroluminescence from a Gd-implanted Si-metal-oxide-semiconductor device, semiconductor quantum-cascade lasers, ion beam synthesis and morphology of semiconductor memories, ion implantation, films, sputtering, ion-beam induced destabilization of nanoparticles. (HSI)

  9. Forschungszentrum Rossendorf, Institute of Nuclear and Hadronic Physics. Annual report 1993

    Doenau, F.; Prade, H.

    1994-03-01

    The theoretical investigations performed in 1993 dealt with the study of nuclear and subnuclear degrees of freedom, high-spin phenomena and the dynamics of open quantum systems. The results of the research and developments are presented in numerous publications, conference contributions and talks. Experimental data are obtained from in-beam spectroscopic studies, medium energy physics and heavy ion physics. The participation in national or international research projects has been continued. (orig.)

  10. Forschungszentrum Rossendorf, Institute of Bioinorganic and Radiopharmaceutical Chemistry. Annual report 1995

    Johannsen, B.

    1996-02-01

    Research at the Institute of Bioinorganic and Radiopharmaceutical Chemistry of the Research Center Rossendorf is focused on radiotracers as molecular probes for diagnosis of disease. The research effort has two main components: -Positron emission tomography (PET) - technetium chemistry and radiopharmacology. The research activities of the Institute have been performed in three administratively classified groups. A PET tracer group is engaged in the chemistry and radiopharmacy of 11 C and 18 F compounds and in the setup of the PET center. A SPECT tracer group deals with the design, synthesis and chemical characterization of metal coordination compounds, primarily rhenium and technetium complexes. A biochemical group is working on SPECT and PET-relevant biochemical and biological projects. This includes the characterization and assessment of new compounds developed in the two synthetically oriented groups. The annual report presented here covers the research activities of the Institute of Bioinorganic and Radiopharmaceutical Chemistry in 1995. (orig.)

  11. On the operating experience of the Doppler Sodar system at the Forschungszentrum Juelich

    Adiga, B.B.; Zeuner, G.

    1990-04-01

    In this report the description and the operating principles of the Doppler Sodar at the KFA are briefly described and outputs from the routine operation of the Sodar are compared with the concurrently measured data on the 120 m high KFA meteorological tower. Three sets of data, varying from periods of ten days to 18 days, are used for the comparison. (orig.)

  12. Decommissioning of the reactor tank and the activated structures within the containment of the sodium cooled nuclear reactor facility (KNK) regulated by the permission step 9; Kompakte Natriumgekuehlte Kernreaktoranlage (KNK). Beseitigung des Reaktortanks und der aktivierten Strukturen im Sicherheitsbehaelter der KNK im Zuge der 9. Stilllegungsgenehmigung

    Zuefle, E.M. [Westinghouse Electric Germany GmbH (Germany)

    2006-07-01

    Westinghouse was assigned with the decommissioning of the KNK plant by th Forschungszentrum Karlsruhe. One very substantial subject such as the decommissioning of the reactor vessel, is currently performed under specific boundary conditions as residual sodium in the vessel on nitrogen environment. An enclosure in hot-cell technology with wall thickness of 350 mm and total weight of around 500 Mg has been erected above the reactor vessel. All operations are done remote controlled. The paper describes the main boundary conditions, weights and dose rates, cutting technology and installed infrastructure. (orig.)

  13. Computational methods, tools and data for nuclear analyses of fusion technology systems

    Fischer, U.

    2006-01-01

    An overview is presented of the Research and Development work conducted at Forschungszentrum Karlsruhe in co-operation with other associations in the framework of the European Fusion Technology Programme on the development and qualification of computational tools and data for nuclear analyses of Fusion Technology systems. The focus is on the development of advanced methods and tools based on the Monte Carlo technique for particle transport simulations, and the evaluation and qualification of dedicated nuclear data to satisfy the needs of the ITER and the IFMIF projects. (author)

  14. Applications of moisture monitoring using TAUPE-sensors

    Koeniger, F.

    2007-01-01

    TAUPE as a moisture sensor has been developed in cooperation with Technology Transfer Division in Forschungszentrum Karlsruhe since 1996. These sensors can be used to monitor moisture in a variety of materials, using time domain or frequency domain techniques. Major applications are large area supervision of landfill sealings, determination of the snow water equivalent, e.g. in the project SNOWPOWER for the forecasting of the amount of water for energy production in storage lakes and, as a new project, continuous monitoring of groundwater level in the flood plane of river Rhine. (orig.)

  15. Modelling of QUENCH-03 and QUENCH-06 Experiments Using RELAP/SCDAPSIM and ASTEC Codes

    Tadas Kaliatka

    2014-01-01

    Full Text Available To prevent total meltdown of the uncovered and overheated core, the reflooding with water is a necessary accident management measure. Because these actions lead to the generation of hydrogen, which can cause further problems, the related phenomena are investigated performing experiments and computer simulations. In this paper, for the experiments of loss of coolant accidents, performed in Forschungszentrum Karlsruhe, QUENCH-03 and QUENCH-06 are modelled using RELAP5/SCDAPSIM and ASTEC codes. The performed benchmark allowed analysing different modelling features. The recommendations for the model development are presented.

  16. Results of the ITER toroidal field model coil project

    Salpietro, E.; Maix, R.

    2001-01-01

    In the scope of the ITER EDA one of the seven largest projects was devoted to the development, manufacture and testing of a Toroidal Field Model Coil (TFMC). The industry consortium AGAN manufactured the TFMC based on on a conceptual design developed by the ITER EDA EU Home Team. The TFMC was completed and assembled in the test facility TOSKA of the Forschungszentrum Karlsruhe in the first half of 2001. The first testing phase started in June 2001 and lasted till October 2001. The first results have shown that the main goals of the project have been achieved

  17. IAEA consultants' meeting on selection of basic evaluations for the FENDL-2 library. Summary report

    Pashchenko, A.B.

    1996-09-01

    FENDL-1 is the international reference nuclear data library for fusion design applications, available from the IAEA Nuclear Data Section. FENDL/E is the sublibrary for evaluated neutron reaction data. An updated version, FENDL-2, is being developed. The present report contains the Summary of the IAEA Consultants' Meeting on ''Selection of Basic Evaluations for the FENDL-2 Library'', held at Karlsruhe, Germany, from 24 to 28 June 1996. This meeting was organized by the IAEA Nuclear Data Section (NDS) with the co-operation and assistance of local organizers of the Forschungszentrum Karlsruhe, Germany. Summarized are the conclusions and recommendations for the selection of basic evaluations from candidates submitted by five national projects (JENDL-FF, BROND, EFF, ENDF/B-VI and CENDL) for FENDL/E-2.0 international reference data library. (author). 1 tab

  18. IFMIF High Flux Test Module-Recent progress in design and manufacturing

    Leichtle, D. [Association FZK-EURATOM, Forschungszentrum Karlsruhe, Institut fuer Reaktorsicherheit, Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen (Germany)], E-mail: leichtle@irs.fzk.de; Arbeiter, F.; Dolensky, B.; Fischer, U.; Gordeev, S.; Heinzel, V.; Ihli, T.; Lang, K.-H. [Association FZK-EURATOM, Forschungszentrum Karlsruhe, Institut fuer Reaktorsicherheit, Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen (Germany); Moeslang, A. [Association FZK-EURATOM, Forschungszentrum Karlsruhe, Institut fuer Materialforschung, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Simakov, S.P.; Slobodchuk, V.; Stratmanns, E. [Association FZK-EURATOM, Forschungszentrum Karlsruhe, Institut fuer Reaktorsicherheit, Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen (Germany)

    2008-12-15

    The International Fusion Material Irradiation Facility (IFMIF) is an accelerator driven neutron source for irradiation tests of candidate fusion reactor materials. Within the High Flux Test Module (HFTM) a testing volume of 0.5 l filled by qualified small scale specimens will be irradiated at displacement rates of 20-50 dpa/fpy in structural materials. The Forschungszentrum Karlsruhe (FZK) has developed a HFTM design which closely follows the design premise of maximising the space available for irradiation specimens in the IFMIF high flux zone and in addition allows keeping the temperature nearly constant in the rigs containing the specimen. Complementary analyses on nuclear, thermo-hydraulics and mechanical performance of the HFTM were performed to optimize the design. The present paper highlights the main design characteristics as well as recent progress achieved in this area. The contribution also includes (i) recommendations for the use of container, rig and capsule materials, and (ii) a description of the fabrication routes for the entire HFTM including brazing and filling procedures which are currently under development at the Forschungszentrum Karlsruhe.

  19. IFMIF High Flux Test Module-Recent progress in design and manufacturing

    Leichtle, D.; Arbeiter, F.; Dolensky, B.; Fischer, U.; Gordeev, S.; Heinzel, V.; Ihli, T.; Lang, K.-H.; Moeslang, A.; Simakov, S.P.; Slobodchuk, V.; Stratmanns, E.

    2008-01-01

    The International Fusion Material Irradiation Facility (IFMIF) is an accelerator driven neutron source for irradiation tests of candidate fusion reactor materials. Within the High Flux Test Module (HFTM) a testing volume of 0.5 l filled by qualified small scale specimens will be irradiated at displacement rates of 20-50 dpa/fpy in structural materials. The Forschungszentrum Karlsruhe (FZK) has developed a HFTM design which closely follows the design premise of maximising the space available for irradiation specimens in the IFMIF high flux zone and in addition allows keeping the temperature nearly constant in the rigs containing the specimen. Complementary analyses on nuclear, thermo-hydraulics and mechanical performance of the HFTM were performed to optimize the design. The present paper highlights the main design characteristics as well as recent progress achieved in this area. The contribution also includes (i) recommendations for the use of container, rig and capsule materials, and (ii) a description of the fabrication routes for the entire HFTM including brazing and filling procedures which are currently under development at the Forschungszentrum Karlsruhe

  20. Analytical support for the preparation of bundle test QUENCH-10 on air ingress

    Birchley, J.; Haste, T.; Homann, C.; Hering, W.

    2005-07-01

    Bundle test QUENCH-10 is dedicated to study air ingress with subsequent water quench during a supposed accident in a spent fuel storage tank. It was proposed by AEKI, Budapest, Hungary and was performed on 21 July 2004 in the QUENCH facility at Forschungszentrum Karlsruhe. Preparation of the test is based on common analytical work at Forschungszentrum Karlsruhe and Paul Scherrer Institut, Villigen, Switzerland, mainly with the severe accident codes SCDAP/RELAP5 and MELCOR, to derive the protocol for the essential test phases, namely pre-oxidation, air ingress and quench phase. For issues that could not be tackled by this computational work, suggestions for the test conduct were made and applied during the test. Improvements of the experimental set-up and the test conduct were suggested and largely applied. In SCDAP/RELAP5, an error was found: for thick oxide scales, the output value of the oxide scale is sensibly underestimated. For the aims of the test preparation, its consequences could be taken into account. Together with the related computational and other analytical support by the engaged institutions the test is co-financed as test QUENCH-L1 by the European Community under the Euratom Fifth Framework Programme on Nuclear Fission Safety 1998 - 2002 (LACOMERA Project, contract No. FIR1-CT2002-40158). (orig.)

  1. Thermalhydraulic and material specific investigations into the realization of an Accelerator Driven System (ADS) to transmute minor actinides. 1999 Status report

    Knebel, J.U.; Cheng, X.; Mueller, G.; Schumacher, G.; Konys, J.; Wedemeyer, O.; Groetzbach, G.; Carteciano, L.

    2000-10-01

    At Forschungszentrum Karlsruhe an HGF Strategy Fund Project entitled ''Thermalhydraulic and Material Specific Investigations into the Realization of an accelerator-driven system (ADS) to Transmute Minor Actinides'' is performed which is funded by the Hermann von Helmholtz-Gemeinschaft Deutscher Forschungszentren (HGF) in the section ''Energy Research and Energy Technology'' over a time period from 07/1999 to 06/2002 with a financial support of 7.0 million DM (35 man years). The objective of this HGF Strategy Fund Project is the development of new methods and technologies to design and manufacture thin-walled thermally highly-loaded surfaces (e.g. beam window) which are cooled by a corrosive heavy liquid metal (lead-bismuth eutectic). The beam window is a vital component of an ADS spallation target. The results of this project will provide the scientific-technical basis which allows the conception and the design of an ADS spallation target and later on a European Demonstrator of an ADS system. The work performed at Forschungszentrum Karlsruhe is embedded in a broad European research and development programme on ADS systems. (orig.)

  2. Radiation Safety Report 2003, Forschungszentrum Rossendorf e.V. and Verein fuer Kernverfahrenstechnik und Analytik Rossendorf e.V.; Jahresbericht Strahlenschutz 2003 des Forschungszentrums Rossendorf e.V. und des Vereins fuer Kernverfahrenstechnik und Analytik Rossendorf e.V.

    Sahre, P. (comp.)

    2004-03-01

    The annual report contains information and measured data obtained with the routine monitoring and measuring activities performed in 2003 at the VKTA and the nuclear research center, FZR, referring to health physics measurements and individual dosimetry of internal and external personnel, and ambient radioactivity monitoring in the area of the two facilities. [German] Der Jahresbericht informiert ueber die Taetigkeiten und die Messwerte des Jahres 2003, die im VKTA und FZR routinemaessig durchgefuehrt und gemessen wurden in den Bereichen: 1. Personenueberwachung, berufliche Strahlenexposition von internen Mitarbeitern oder externem Personal von Fremdfirmen. 2. Strahlenschutzumgebungsueberwachung. (orig./AJ)

  3. Radiation Safety Report 2003, Forschungszentrum Rossendorf e.V. and Verein fuer Kernverfahrenstechnik und Analytik Rossendorf e.V

    Sahre, P.

    2004-03-01

    The annual report contains information and measured data obtained with the routine monitoring and measuring activities performed in 2003 at the VKTA and the nuclear research center, FZR, referring to health physics measurements and individual dosimetry of internal and external personnel, and ambient radioactivity monitoring in the area of the two facilities [de

  4. Experience with cleaning of sodium-wetted components and decontamination at Nuclear Research Centre Karlsruhe

    Menzenhauer, P; Borgstedt, U; Stamm, H H; Dippel, Th; Kunze, S; Hentschel, D [Kernforschungszentrum Karlsruhe, Karlsruhe (Germany)

    1978-08-01

    Within the framework of the Fast Breeder Project various institutes of the KarIsruhe Nuclear Research Center operate sodium loops for corrosion studies and component tests under sodium. The operation of these loops has led to extensive experience in cleaning sodium-wetted components. This experience relates to the alcohol method, the removal of sodium by melting, storage in air, and to cleaning by means of steam. Deposition samples from radioactive sodium loops were used for decontamination experiments employing various decontaminating agents. The department concerned with the treatment of radioactive waste studied the use of molten salts and paste type cleansers for components unsuitable for mechanical decontamination, primarily with the objective to reduce the amount of radioactive waste. (author)

  5. Current status of modeling fission gas behaviour in the Karlsruhe code LANGZEIT/KURZZEIT

    Vaeth, L.

    1980-12-01

    The programme LANGZEIT/KURZZEIT has been recently extended to describe intragranular bubble coalescence and volume equilibration, to model intergranular gas behaviour and transient release from closed porosity. The model is described and the results of some comparisons with transient experiments are discussed. Further necessary refinements of the model are outlined. (orig.) [de

  6. Putting teeth in the nuclear non-proliferation and disarmament regime. 25 March 2006, Karlsruhe, Germany

    ElBaradei, M.

    2006-01-01

    The factors, contributing to the world's changes in respect to peace, security and non-proliferation of nuclear weapons are presented in the document. Five necessary and urgent measures are proposed in order to meet the current challenges: 1)tighten control for assess to nuclear fuel cycle technology; 2)accelerate global efforts tp protect nuclear material; 3)support effective nuclear verification; 4) reinvigorate disarmament efforts; 5) increase the effectiveness of the UN Security Council. The importance and necessity to place nuclear operations under multinational control is outlined

  7. Decommissioning of the MZFR nuclear power plant at the Karlsruhe Nuclear Research Center

    Demant, W.; Engelhardt, G.

    1991-01-01

    The MZFR multipurpose research reactor was permanently shut down on May 3, 1984. The envisaged decommissioning concept provides for disposal in five steps. The first two steps are devoted to preparatory work on dismantling and simplification of the systems needed for dismantling. In the third step the reactor auxiliary systems in the auxiliary building and in the fourth step the reactor systems in the reactor building will be dismantled. In the fifth step remote dismantling of the reactor pressure vessel and demolition of the building will take place. The scheduled date of completion is the year 2001. (author)

  8. 9. PEF status colloquium, Nuclear Research Center Karlsruhe, March 9-11, 1993

    1993-04-01

    This report compiles the summarizing reviews of the program management at the PEF Statuskolloquium of March 1993. Seven papers, which are not individually recorded, deal with the four subject areas of the project: Monitoring and analysis of the effect of air pollutants on forest ecosystems and delimitation against possible other causes of novel forest damage; research into the atmospheric propagation, conversion and deposition of air pollutants; development and optimization of technic-economic methods for cutting down or avoiding emissions; provision of instruments and recommendations for the economic and political sector. (UWa) [de

  9. Research and development projects in the frame of the technology transfer program of the Kernforschungszentrum Karlsruhe

    Wuest, J.

    1984-01-01

    Within the framework of the Technology Transfer Programme carried through by kfk for some years now, a specific technology transfer model has been developed for the purpose of efficient utilization of the spin-off. This model showing means and methods of ensuring a continuous, purposeful and controllable organization of the transfer of know-how, is accompanied by experience in the appropriate contractual activities adjusted to the various conditions encountered, as e.g. cooperation and licence agreements, services, consultative agreements, personnel transfer, selling agreements, committed research agreements, and development contracts. Consuming about 2 p.c. of the annual overall expenses of the kfk, the Technology Transfer Programme belongs to the minor projects of the research centre. (DG) [de

  10. List of scientific publications of the Karlsruhe Nuclear Reseach Centre for the year 1986

    1987-05-01

    This report contains the titles of the publications which appeared during the year 1986. Lectures which have not been printed yet are listed separately from the literature. All the patents awarded or published in 1986 are given; i.e. patents and publications of patents. Summarising lectures and practical instructions from the courses at the College for Nuclear Technology are not included in the list. The list of publications is arranged according to Institutes. Among the projects, only the published project reports and publications by members of the staff of the project are listed. The publications printed at the Nuclear Research Centre from the research and development projects of the Manufacturing Technique Project (PFT) and the project on the 'European Research Centre for Measures for Keeping the Air Clean' (PEF), which are being carried out by the Nuclear Research Centre in collaboration with firms and institutions, are also included in the list. The list also contains publications by the external office of the West German Institute of Food resident in the Nuclear Research Centre. The last chapter of the list contains publications on guest experiments at the Nuclear Research Centre. The list has an alphabetical index, which gives page and registry numbers. (orig./GG) [de

  11. Radiochemistry Institute of Karlsruhe Nuclear Research Centre. Progress report on R and D work in 1985

    1986-02-01

    The Radiochemistry Institute carried out R and D work within the framework of the following projects: Project PWA, Reprocessing and Waste Treatment; project PSB, Fast Breeder Reactor; project PKF, Nuclear Fusion. Basic and applied problems in the field of surface chemistry and surface analysis were studied under the working programme 'Solids and Materials Research', and 'Technology - Man - Environment' was a point of main interest that gathered a number of working programmes in the field of water chemistry. (orig./RB) [de

  12. Report on the 3rd status colloquium, Karlsruhe, February 18-19, 1992

    1992-06-01

    The 1992 status seminar in a final report on the project water-waste-soil (PWAB), whose first phase terminated in 1992. The second phase will last through 1998. Findings of the project have been summarized in separate chapters under the following headings: Water and soil waste treatment leachates, and long-standing pollution. (orig.) [de

  13. 25 years of financing and accountancy of the Karlsruhe Nuclear Research Center

    Neck, E.

    1980-11-01

    It will be first described how the system of financing has progressed since the establishment of the Center. A distinction will be made between four different financing models in succession. The presentation of these financing models will be accompanied by a description of building up and development of the Center, mainly under financial aspects. The second part will show the development of accountancy and balance striking. Particular courses will be indicated which are typical of large research establishments funded by the government, thus providing the picture of an accountancy system specifically adapted to research establishments. It differs from classical business accounting by laying a bridge to the cameralistic accountancy of public authorities. Besides, the organization and tools of KfK cost accounting will be described. Finally, the third part will present statistical time series (1956 to 1979) including both the annual balances, annual expenditures and some average numbers (per capita numbers). These time series will be supplemented each by short comments. (orig./HP) [de

  14. Radioactivity levels in mushrooms collected in the area of Karlsruhe during 1987 and 1988

    Rueckert, G.; Diehl, J.F.; Heilgeist, M.

    1990-01-01

    Radioactive contamination of wild-growing mushrooms collected in the Northern Black Forest and neighbouring Rhine Valley area has been monitored since the Chernobyl reactor accident. Cs-134, Cs-137, Ag-110m and the natural nuclide K-40 were determined by gamma-spectrometry. Pooled data from all species and all locations showed a decrease in the radio-caesium levels from 1986 to 1988, both in mean values and maximum values. Samples of the same species collected at the same location exhibited large differences, although mixed samples rather than individual mushrooms were measured. Accumulation of caesium was observed particularly in Laccaria amethystina, Xerocomus badius, Xerocomus chrysenteron, Cantharellus tubaeformis, Laccaria laccata, and Russula ochroleuca, with maximum values of 3600 (1986), 2000 (1987), and 1200 (1988) Bq/kg of radio-caesium. A large number of species, among them Calocybe gambosa and Coprinus comatus, showed very small accumulations or no caesium. An accumulation of silver was found in Macrolepiota rhacodes and Agaricus arvensis, which contained a maximum of 11 Bq/kg Ag-110m. (orig.) [de

  15. Karlsruhe Nuclear Research Centre. Report on the results of research and development 1985

    1986-01-01

    The report contains a description of the research projects, a list of the institutes and departments of the scientific-technical range with short articles concerning the results of the institutional work, and a bibliography of all publications of 1985. The main aspects of the projects and research programs are fast breeder, separation nozzle process, nuclear fusion, waste recycling and reprocessing, final storage, nuclear safety, the range of technique-man-environment, solid state and materials research, nuclear and elementary particle physics, and research programs of different institutes. (HK)

  16. List of scientific publications of the Karlsruhe Nuclear Research Center in 1993

    1994-03-01

    The report contains the titles of all publications from 1993. In the case of patents, all rights established or published during 1993 are indicated: patents, information sheets (DE-OS). The list of publications is ordered according to institutes. Under projects, only published project reports and publications by staff working on the particular projects are listed. Also included are publications printed in the Kernforschungszentrum from research and development plans within the production Technology Project (PFT) and the project called 'European Research Center for the Control of Air Pollution' (PEF), which were carried out by the Kernforschungszentrum as project sponsor in cooperation with firms and institutes. The list also includes publications of the branch of the Federal Research Institute for Nutrition based at the Kernforschungszentrum. (orig.) [de

  17. Karlsruhe Nuclear Research Center. Progress report on research and development work in 1987

    1988-01-01

    This summary of R and D work is the scientific annual report to be prepared by the research center in compliance with its statutes. The material is arranged by items of main activities, as given in the overall R and D programme set up for the research center. The various reports prepared by the individual institutes and principal departments are presented under their relevant subject headings. The annual report is intended to demonstrate the progress achieved in the tasks and activities assigned by the R and D programme of the research center, by referring to the purposes and goals stated in the programme, showing the joint or separate efforts and achievements of the institutes. Details and results of activities are found in the scientific-technical publications given in the bibliographical survey, and in the internal primary surveys. The main activities of the research center include the following: Fast Breeder Project (PSB), Nuclear Fusion Project (PKF), Separation Nozzle Project (TDV), and Reprocessing and Waste Treatment Project (PWA), Ultimate Disposal of Radioactive Waste (ELA), Environment and Safety (U and S), Solids and Materials (FM), Nuclear and Particle Physics (KTP), Microtechniques (MT), Materials Handling (HT), Other Research Activities (SF). Organisational aspects and institutes and the list of publications conclude the report. (orig./HK) [de

  18. Developments in the area of high-current-superconductivity in the Kernforschungszentrum Karlsruhe

    Maurer, W.; Arendt, F.; Bruenner, N.; Erb, J.; Fessler, N.; Hartwig, G.; Heinz, W.; Hofmann, A.; Juengst, K.P.; Katheder, H.

    1976-05-01

    In this report the development work is presented which has been done from 1971 to 1975 on High-Current-Superconducticity at the institute IEKP III. The report deals with the development, construction and operation of superconducting magnets, with material investigations and with the pursued applications of superconducting Magnettechnology in research and industry. (orig.) [de

  19. List of scientific and technical publications of the Karlsruhe Nuclear Research Centre, 1985

    1986-05-01

    The report lists the titles and other bibliographic data of the publications released in 1985. Lectures not yet available in printed form are listed separately. The patent section gives information on patent rights granted or published in 1985. Technical lectures or material prepared for courses held by the SKT (Nuclear Engineering School) are not part of the list. The data are arranged by institutes, information on project activities is given referring to published project reports and other publications prepared by project staff. The list also presents R and D reports printed by KfK for informationn on the PFT project, fabrication technologies, which is a joint enterprise by KfK, several other institutes, and industry. Publications of the branch institute of the Federal Food Research Institute are also given, followed by a list of publications prepared by guest scientists of the KfK. (orig./PW) [de

  20. List of scientific publications issued in 1991 by Karlsruhe Nuclear Research Center

    1992-05-01

    This report KfK 5025 presents the titles of scientific publications issued in 1991. Conference papers or other papers not yet available in printed from are listed separately. Patent documents of the year 1991 are listed in two categories: patent specifications and unexamined laid-open patent applications (DE-OS). Reviews on specific subjects or training documents prepared for courses in the KfK's Center for Advanced Training are not included in this report. (orig.) [de

  1. List of the scientific publications of the Karlsruhe Nuclear Research Center in 1990

    1991-05-01

    The report contains the titles of all publications from 1990. In the case of patents, all rights established or published during 1990 are indicated: patents, information sheets (DE-OS). The list of publications is ordered according to institutes. Under projects, only published project reports and publications by staff working on the particular projects are listed. Also included are publications printed in the Kernforschungszentrum from research and development plans within the Production Technology Project (PFT) and the project called 'European Research Center for the Control of Air Pollution' (PEF), which were carried out by the Kernforschungszentrum as project sponsor in cooperation with firms and institutes. The list also includes publications of the branch of the Federal Research Institute for Nutrition based at the Kernforschungszentrum. (orig./HP) [de

  2. List of scientific publications of the Karlsruhe Nuclear Research Center in 1992

    1993-05-01

    The report contains the titles of all publications from 1992. In the case of patents, all rights established or published during 1992 are indicated: patents, information sheets (DE-OS). The list of publications is ordered according to institutes. Under projects, only published project reports and publications by staff working on the particular projects are listed. Also included are publications printed in the Kernforschungszentrum from research and development plans within the Production Technology Project (PFT) and the project called 'European Research Center for the Control of Air Pollution' (PEF), which were carried out by the Kernforschungszentrum as project sponsor in cooperation with firms and institutes. The list also includes publications of the branch of the Federal Research Institute for Nutrition based at the Kernforschungszentrum. (orig.) [de

  3. The scientific publications of the Karlsruhe Nuclear Research Centre in the year 1974

    1975-04-01

    Report KFK 2125 contains all the titles of those publications which were printed in 1974. Lectures are included then when the written version is available in the Central Library. Concerning patents, only those specified in a certain way (Ersterteilung, Auslegeschrift, Offenlegungsschrift) are listed. The list of publications is arranged according to institutes. Under the heading 'Projekt' there are only project reports and publications of project staff members. The list also includes those publications printed in the Kernforschungszentrum concerned with the research and development projects' Prozesslenkung mit DV-Anlagen (PDV)' und 'Rechnerunterstuetztes Entwickeln und Konstruieren (CAD)' which are carried out by the Gesellschaft fuer Kernforschung in cooperation with other firms and organizations. In addition, the publications of the Institut fuer Strahlentechnologie der Bundesforschungsanstalt fuer Lebensmittelfrischhaltung, situated on the premises of the Kernforschungszentrum, are given. (orig./HK) [de

  4. Modeling steady state and transient fission gas behaviour with the Karlsruhe code LAKU

    Vaeth, L.

    1984-08-01

    The programme LAKU models the behaviour of gaseous fission products in reactor fuel under steady state and transient conditions, including molten fuel. A presentation of the full model is given, starting with gas behaviour in the grains and on grain faces and including the treatment of release from porosity. The results of some recent calculations are presented. (orig.) [de

  5. Experience with cleaning of sodium-wetted components and decontamination at Nuclear Research Centre Karlsruhe

    Menzenhauer, P.; Borgstedt, U.; Stamm, H.H.; Dippel, Th.; Kunze, S.; Hentschel, D.

    1978-01-01

    Within the framework of the Fast Breeder Project various institutes of the KarIsruhe Nuclear Research Center operate sodium loops for corrosion studies and component tests under sodium. The operation of these loops has led to extensive experience in cleaning sodium-wetted components. This experience relates to the alcohol method, the removal of sodium by melting, storage in air, and to cleaning by means of steam. Deposition samples from radioactive sodium loops were used for decontamination experiments employing various decontaminating agents. The department concerned with the treatment of radioactive waste studied the use of molten salts and paste type cleansers for components unsuitable for mechanical decontamination, primarily with the objective to reduce the amount of radioactive waste. (author)

  6. Karlsruhe Nuclear Research Center, Institute of Radiochemistry. Progress report on research and development work in 1993

    1994-03-01

    The IRCH microsystems technology activities are dedicated to the development of chemical sensors and probes which meet the practical sensitivity, selectivity or specificity and stability requirements. The devices are miniaturized for integration into microsystems technology solutions and are designed for a wide range of process management, process control and process analysis uses including, e.g. pollution monitoring and medical diagnosis. The nuclear fusion project focuses on investigations into chemical and technical tritium technology problems which may occur, e.g. during tritium recovery from tritiated compounds in the internal and external fusion reactor fuel cycles. Additional efforts go into the physico-ceramic characterization of ceramic breeder materials, the extraction of bred tritium from the blanket, and the development of the necessary process analysis methods. (orig.) [de

  7. Deep X-ray lithography for the fabrication of microstructures at ELSA

    Pantenburg, F.J. E-mail: pantenburg@imt.fzk.de; Mohr, J

    2001-07-21

    Two beamlines at the Electron Stretcher Accelerator (ELSA) of Bonn University are dedicated for the production of microstructures by deep X-ray lithography with synchrotron radiation. They are equipped with state-of-the-art X-ray scanners, maintained and used by Forschungszentrum Karlsruhe. Polymer microstructure heights between 30 and 3000 {mu}m are manufactured regularly for research and industrial projects. This requires different characteristic energies. Therefore, ELSA operates routinely at 1.6, 2.3 and 2.7 GeV, for high-resolution X-ray mask fabrication, deep and ultra-deep X-ray lithography, respectively. The experimental setup, as well as the structure quality of deep and ultra deep X-ray lithographic microstructures are described.

  8. Structural materials for innovative nuclear systems (SMINS)

    2008-01-01

    Structural materials research is a field of growing relevance in the nuclear sector, especially for the different innovative reactor systems being developed within the Generation IV International Forum (GIF), for critical and subcritical transmutation systems, and of interest to the Global Nuclear Energy Partnership (GNEP). Under the auspices of the NEA Nuclear Science Committee (NSC) the Workshop on Structural Materials for Innovative Nuclear Systems (SMINS) was organised in collaboration with the Forschungszentrum Karlsruhe in Germany. The objectives of the workshop were to exchange information on structural materials research issues and to discuss ongoing programmes, both experimental and in the field of advanced modelling. These proceedings include the papers and the poster session materials presented at the workshop, representing the international state of the art in this domain. (author)

  9. ECO steam explosion experiments on the conversion of thermal into mechanical energy

    Cherdron, W.; Kaiser, A.; Schuetz, W.; Will, H.

    2001-01-01

    In case of a steam explosion, e.g. as a consequence of a severe reactor accident, part of the thermal energy of the melt is transferred into mechanical energy. At Forschungszentrum Karlsruhe, so-called ECO experiments, are being directed to measure the conversion factor under well-defined conditions. In ECO, alumina from a thermite reaction is used as a simulating material instead of corium. Dimensions of the test facility as well as major test conditions, e.g. temperature and release mode of the melt, water inventory and test procedure, are based on the former PREMIX experimental series. In the paper, results of the first test, ECO 01, are given. (orig.)

  10. The hydrogen generated as a gas and storage in Zircaloy during water quenching

    Garcia, Eduardo A.

    1999-01-01

    A simple one-dimensional diffusion model has been developed for the complex process of Zircaloy oxidation during water quenching, calculating the hydrogen liberated as a gas and the hydrogen stored in the metal. The model was developed on the basis of small-scale separate-effects quench experiments performed at Forschungszentrum Karlsruhe. The new oxide surface and the new metallic surface produced by cracking of the oxide during quenching are calculated for each experiment performed at 1200 , 1400 and 1600 C degrees using as-received Zircaloy-4 (no pre oxidation) and with Zircaloy specimens pre oxidised to give oxide thicknesses of 100μm and 300μm. The results are relevant to accident management in light water reactors. (author)

  11. Simulation of the Quench-06 experiment with Scdapsim; Simulacion del experimento Quench-06 con Scdapsim

    Angel M, E. del; Nunez C, A.; Amador G, R. [CNSNS, Dr. Barragan No. 779, 03020 Mexico D.F. (Mexico)]. e-mail: edangelm@cnsns.gob.mx

    2003-07-01

    The present work describes the pattern of the called Quench installation developed and used by the National Commission of Nuclear Security and Safeguards (CNSNS) for their participation in the International Standard Problem 45 (ISP), organized by the Nuclear Energy Agency (NEA). The exercise consisted on the simulation of the denominated experiment Quench-06 carried out in the experimental installation Quench located in the Forschungszentrum laboratory in Karlsruhe, Germany. The experiment Quench-06 consisted on simulating the sudden and late injection of water in a fuel assemble for a pressurized reactor (PWR). The CNSNS uses the version bd of the SCDAPSIM code developed by the company Innovative Software Systems (ISS) to simulate this experiment. The obtained results showed that the code is able to predict the experiment partially when overestimating the hydrogen production and of the partial fused of some fuel pellets, but predicting correctly the damage in the shroud. (Author)

  12. The second advanced lead lithium blanket concept using ODS steel as structural material and SiCf/SiC flow channel inserts as electrical and thermal insulators (Task PPA 2.5). Final report

    Norajitra, P.; Buehler, L.; Fischer, U.

    1999-12-01

    Preparatory work on the advanced dual coolant (A-DCL) blanket concept using SiC f /SiC flow channel inserts as electrical and thermal insulators has been carried out at the Forschungszentrum Karlsruhe in co-operation with CEA as a conceptual design proposal to the EU fusion power plant study planned to be launched in 2000 within the framework of the EU fusion programme with the main objective of specifying the characteristics of an attractive and viable commercial D-T fusion power plant. The basic principles and design characteristics of this A-DCL blanket concept are presented and its potential with regard to performance (neutron wall load, lifetime, availability) is discussed in this report. The results of this study show that the A-DCL blanket concept has a high potential for further development due to its high thermal efficiency and its simple concept solution. (orig.) [de

  13. Technical meeting to 'Review of national programmes on fast reactors and accelerator driven systems (ADS)'. Working material

    2002-01-01

    The 35th Annual Meeting of the Technical Working Group on Fast Reactors TWG-FR, previously International Working Group on Fast Reactors (IWG-FR, created in 1967), was hosted by the Forschungszentrum Karlsruhe (FZK) and was attended by TWG-FR members and advisers from the following Member States: Brazil, China, France, Germany, India, Japan, the Republic of Kazakhstan, the Republic of Korea, the Russian Federation, and the United States of America. The objectives of the meeting were: to exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); to review the progress since the 34th TWG-FR Annual Meeting, including the status of the actions; to consider meeting arrangements for 2002 and 2003; to review the Agency's co-ordinated research activities in the field of FRs and ADS, as well as co-ordination of the TWG-FR's activities with other organizations

  14. Determination of appropriate models and parameters for premixing calculations

    Park, Ik-Kyu; Kim, Jong-Hwan; Min, Beong-Tae; Hong, Seong-Wan

    2008-03-15

    The purpose of the present work is to use experiments that have been performed at Forschungszentrum Karlsruhe during about the last ten years for determining the most appropriate models and parameters for premixing calculations. The results of a QUEOS experiment are used to fix the parameters concerning heat transfer. The QUEOS experiments are especially suited for this purpose as they have been performed with small hot solid spheres. Therefore the area of heat exchange is known. With the heat transfer parameters fixed in this way, a PREMIX experiment is recalculated. These experiments have been performed with molten alumina (Al{sub 2}O{sub 3}) as a simulant of corium. Its initial temperature is 2600 K. With these experiments the models and parameters for jet and drop break-up are tested.

  15. The German DEMO working group. Perspectives of a fusion power plant

    Hesch, Klaus

    2013-01-01

    Fusion development has many different challenges in the areas of plasma physics, fusion technologies, materials development and plasma wall interaction. For making fusion power a reality, a coherent approach is necessary, interlinking the different areas of work. To this end, the German fusion program started in 2010 the German DEMO Working Group, bringing together high-level experts from all the different fields, from the 3 German fusion centers Max-Planck-Institut fuer Plasmaphysik (IPP), Karlsruher Institut fuer Technologie (KIT) and Forschungszentrum Juelich (FZJ). An encompassing view of what will be needed with high priority, in plasma physics, in fusion technology and in the interrelation of the fields, to make fusion energy real, has been elaborated, and is presented here in a condensed way. On this basis, the 3 German fusion centers now are composing their work program, towards a fusion demonstration reactor DEMO. (orig.)

  16. He-cooled divertor for DEMO: Experimental verification of the conceptual modular design

    Norajitra, P.; Gervash, A.; Giniyatulin, R.; Ihli, T.; Krauss, W.; Kruessmann, R.; Kuznetsov, V.; Makhankov, A.; Mazul, I.; Ovchinnikov, I.

    2006-01-01

    A modular He-cooled divertor concept is being developed at the Forschungszentrum Karlsruhe. The design goal is to withstand a high heat flux of 10 MW/m 2 at least. The work programme of 2004 focused on experiments to verify the design and thermohydraulics layout. In cooperation with the Efremov Institute, experimental investigations were performed for the joining of tungsten parts and/or tungsten parts with steel and the fabrication of divertor components from tungsten. Moreover, gas puffing experiments were carried out with a stationary approach to measuring pressure loss and heat transfer for the purpose of screening the design options and verifying the computational fluid dynamics (CFD) calculations. The status and results of the technological and helium experiments shall be outlined in this report

  17. Progress of the 10 MW ECRH System for W7-X

    Michel, G.; Brand, P.; Dammertz, G.

    2003-01-01

    The electron cyclotron resonance heating system for the W7-X stellarator is a joint effort of the Max-Planck-Institut fuer Plasmaphysik in Greifswald, the Institut fuer Plasmaforschung Stuttgart and the Forschungszentrum Karlsruhe under the supervision of the latter. Currently it is being constructed at the Greifswald branch of IPP. It will consist of 10 gyrotrons (each with 1 MW 140 GHz in the CW regime) and a quasi optical multi-beam transmission line. W7-X gyrotron candidates are being developed separately in Western Europe and the USA. The prototype phase of the gyrotrons is almost over and significant results have been achieved. The manufacturing of the transmission line is ongoing. An overview over the system including data acquisition and control issues will be given and the current status of the construction will be presented. (authors)

  18. Determination of appropriate models and parameters for premixing calculations

    Park, Ik-Kyu; Kim, Jong-Hwan; Min, Beong-Tae; Hong, Seong-Wan

    2008-03-01

    The purpose of the present work is to use experiments that have been performed at Forschungszentrum Karlsruhe during about the last ten years for determining the most appropriate models and parameters for premixing calculations. The results of a QUEOS experiment are used to fix the parameters concerning heat transfer. The QUEOS experiments are especially suited for this purpose as they have been performed with small hot solid spheres. Therefore the area of heat exchange is known. With the heat transfer parameters fixed in this way, a PREMIX experiment is recalculated. These experiments have been performed with molten alumina (Al 2 O 3 ) as a simulant of corium. Its initial temperature is 2600 K. With these experiments the models and parameters for jet and drop break-up are tested

  19. Analysis of RELAP/SCDAPSIM/MOD3.2 Computer Code using QUENCH Experiments

    Honaiser, Eduardo; Anghaie, Samim

    2004-01-01

    The experiments QUENCH-01/06 were modelled using RELAP5/SCDAPSIM MOD3.2(bd) computer code. The results obtained from these models were compared to the experimental data to evaluate the code performance. The experiments were performed in the Forschungszentrum Karlsruhe (FZK), Germany. The objective of the experimental program was the investigation of the core behaviour during a severe accident, focusing on rod claddings overheat due to zirconium oxidation at high temperatures and due to the strong thermal gradient developed when the nuclear reactor core is flooded as part of an accident management measure. Temperatures histories and hydrogen production were compared. Molecular hydrogen is a product of the oxidation reaction, serving as a parameter to measure the oxidation reaction. After some model adjustments, good predictions were possible. The temperatures and the hydrogen production parameters stayed, most of the transient time, inside the uncertainty envelop. (authors)

  20. Investigations on sump cooling after core melt down

    Knebel, J.U. [Forschungeszentrum Karlsruhe - Technik und Umwelt Institut fuer Angewandte Thermo- und Fluiddynamik, Karlsruhe (Germany)

    1995-09-01

    This article presents the basic physical phenomena and scaling criteria of decay heat removal from a large coolant pool by single-phase and two-phase natural circulation flow. The physical significance of the dimensionless similarity groups derived is evaluated. The above results are applied to the SUCO program that is performed at the Forschungszentrum Karlsruhe. The SUCO program is a three-step series of scaled model experiments investigating the possibility of an optional sump cooling concept for the European Pressurized Water Reactor EPR. This concept is entirely based on passive safety features within the containment. The work is supported by the German utilities and the Siemens dimensional SUCOS-2D test facility. The experimental results of the model geometry are transformed to prototypic conditions.

  1. VESPA. Behaviour of long-lived fission and activation products in the nearfield of a nuclear waste repository and the possibilities of their retention

    Bischofer, Barbara; Hagemann, Sven [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Koeln (Germany); Altmaier, Marcus [Karlsruher Institut fuer Technologie (KIT) (Germany); and others

    2016-06-15

    The present document is the final report of the Joint Research Project VESPA (Behaviour of Long-lived Fission and Activation Products in the Near Field of a Nuclear Waste Repository and the Possibilities of Their Retention), started in July 2010 with a duration of four years. The following four institutions were collaborative Partners in VESPA: - Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH - Institut fuer Energie- und Klimaforschung, IEK-6: Nukleare Entsorgung und Reaktorsicherheit, Forschungszentrum Juelich (FZJ) - Institut fuer Ressourcenoekologie (IRE), Helmholtz-Zentrum Dresden-Rossendorf (HZDR) - Institut fuer Nukleare Entsorgung (INE), Karlsruher Institut fuer Technologie (KIT) VESPA was funded by the German Federal Ministry of Economics and Energy (BMWi) under the contract numbers 02 E 10770 (GRS), 02 E 10780 (FZJ-IEF-6), 02 E 10790 (HZDR-IRE), 02 E 10800 (KIT-INE).

  2. Technical meeting to 'Review of national programmes on fast reactors and accelerator driven systems (ADS)'. Working material

    NONE

    2002-07-01

    The 35th Annual Meeting of the Technical Working Group on Fast Reactors TWG-FR, previously International Working Group on Fast Reactors (IWG-FR, created in 1967), was hosted by the Forschungszentrum Karlsruhe (FZK) and was attended by TWG-FR members and advisers from the following Member States: Brazil, China, France, Germany, India, Japan, the Republic of Kazakhstan, the Republic of Korea, the Russian Federation, and the United States of America. The objectives of the meeting were: to exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); to review the progress since the 34th TWG-FR Annual Meeting, including the status of the actions; to consider meeting arrangements for 2002 and 2003; to review the Agency's co-ordinated research activities in the field of FRs and ADS, as well as co-ordination of the TWG-FR's activities with other organizations.

  3. Measurement of the thermal conductivity and heat transfer coefficient of a binary bed of beryllium pebbles

    Donne, M.D.; Piazza, G. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reaktortechnik; Goraieb, A.; Sordon, G.

    1998-01-01

    The four ITER partners propose to use binary beryllium pebble bed as neutron multiplier. Recently this solution has been adopted for the ITER blanket as well. In order to study the heat transfer in the blanket the effective thermal conductivity and the wall heat transfer coefficient of the bed have to be known. Therefore at Forschungszentrum Karlsruhe heat transfer experiments have been performed with a binary bed of beryllium pebbles and the results have been correlated expressing thermal conductivity and wall heat transfer coefficients as a function of temperature in the bed and of the difference between the thermal expansion of the bed and of that of the confinement walls. The comparison of the obtained correlations with the data available from the literature show a quite good agreement. (author)

  4. Determination of neutron spectra formed by 40-MeV deuteron bombardment of a lithium target with multi-foil activation technique

    Maekawa, F; Wada, M; Wilson, P P H; Ikeda, Y

    2000-01-01

    Neutron flux spectra at an irradiation field produced by a 40-MeV deuteron bombardment on a thick lithium-target at Forschungszentrum Karlsruhe, Germany, have been determined by the multi-foil activation technique. Twenty-seven dosimetry reactions having a wide energy range of threshold energies up to 38 MeV were employed as detectors for the neutron flux spectra extending to 55 MeV. The spectra were adjusted with the SAND-II code with the experimental reaction rates based on an iterative method. The adjusted spectra validated quantitatively the Monte Carlo deuteron-lithium (d-Li) neutron source model code (M sup C DeLi) which was used to calculate initial guess spectra and also has been used for IFMIF nuclear designs. Accuracy of the adjusted spectra was approx 10% that was suitable for successive integral tests of activation cross section data.

  5. MEGAPIE, a 1 MW pilot experiment for a liquid metal spallation target

    Bauer, G.S.; Salvatores, M.; Heusener, G.

    2001-01-01

    MEGAPIE (Megawatt Pilot Target Experiment) is an initiative launched by Commissariat a l'Energie Atomique, Cadarache (France) and Forschungszentrum Karlsruhe (Germany) in collaboration with Paul Scherrer Institut (Switzerland), to demonstrate, in an international collaboration, the feasibility of a liquid lead bismuth target for spallation facilities at a beam power level of 1 MW. Such a target is under consideration for various concepts of accelerator driven systems (ADS) to be used in transmutation of nuclear waste and other applications world-wide. It also has the potential of increasing significantly the thermal neutron flux available at the spallation neutron source (SINQ) for neutron scattering. SINQ's beam power being close to 1 MW already, this facility offers a unique opportunity to realize such an experiment with a reasonably small number of new ancillary systems. The paper describes the basic features of the experiment and its boundary conditions, the technical concept of the target and underlying research carried out at participating laboratories. (author)

  6. Deep X-ray lithography for the fabrication of microstructures at ELSA

    Pantenburg, F. J.; Mohr, J.

    2001-07-01

    Two beamlines at the Electron Stretcher Accelerator (ELSA) of Bonn University are dedicated for the production of microstructures by deep X-ray lithography with synchrotron radiation. They are equipped with state-of-the-art X-ray scanners, maintained and used by Forschungszentrum Karlsruhe. Polymer microstructure heights between 30 and 3000 μm are manufactured regularly for research and industrial projects. This requires different characteristic energies. Therefore, ELSA operates routinely at 1.6, 2.3 and 2.7 GeV, for high-resolution X-ray mask fabrication, deep and ultra-deep X-ray lithography, respectively. The experimental setup, as well as the structure quality of deep and ultra deep X-ray lithographic microstructures are described.

  7. Deep X-ray lithography for the fabrication of microstructures at ELSA

    Pantenburg, F.J.; Mohr, J.

    2001-01-01

    Two beamlines at the Electron Stretcher Accelerator (ELSA) of Bonn University are dedicated for the production of microstructures by deep X-ray lithography with synchrotron radiation. They are equipped with state-of-the-art X-ray scanners, maintained and used by Forschungszentrum Karlsruhe. Polymer microstructure heights between 30 and 3000 μm are manufactured regularly for research and industrial projects. This requires different characteristic energies. Therefore, ELSA operates routinely at 1.6, 2.3 and 2.7 GeV, for high-resolution X-ray mask fabrication, deep and ultra-deep X-ray lithography, respectively. The experimental setup, as well as the structure quality of deep and ultra deep X-ray lithographic microstructures are described

  8. Deep X-ray lithography for the fabrication of microstructures at ELSA

    Pantenburg, F J

    2001-01-01

    Two beamlines at the Electron Stretcher Accelerator (ELSA) of Bonn University are dedicated for the production of microstructures by deep X-ray lithography with synchrotron radiation. They are equipped with state-of-the-art X-ray scanners, maintained and used by Forschungszentrum Karlsruhe. Polymer microstructure heights between 30 and 3000 mu m are manufactured regularly for research and industrial projects. This requires different characteristic energies. Therefore, ELSA operates routinely at 1.6, 2.3 and 2.7 GeV, for high-resolution X-ray mask fabrication, deep and ultra-deep X-ray lithography, respectively. The experimental setup, as well as the structure quality of deep and ultra deep X-ray lithographic microstructures are described.

  9. Simulation of the Quench-06 experiment with Scdapsim

    Angel M, E. del; Nunez C, A.; Amador G, R.

    2003-01-01

    The present work describes the pattern of the called Quench installation developed and used by the National Commission of Nuclear Security and Safeguards (CNSNS) for their participation in the International Standard Problem 45 (ISP), organized by the Nuclear Energy Agency (NEA). The exercise consisted on the simulation of the denominated experiment Quench-06 carried out in the experimental installation Quench located in the Forschungszentrum laboratory in Karlsruhe, Germany. The experiment Quench-06 consisted on simulating the sudden and late injection of water in a fuel assemble for a pressurized reactor (PWR). The CNSNS uses the version bd of the SCDAPSIM code developed by the company Innovative Software Systems (ISS) to simulate this experiment. The obtained results showed that the code is able to predict the experiment partially when overestimating the hydrogen production and of the partial fused of some fuel pellets, but predicting correctly the damage in the shroud. (Author)

  10. The hydrogen generated as a gas and storage in Zircaloy during steam quenching

    Garcia, Eduardo A.

    2000-01-01

    A simple one-dimensional diffusion model has been developed for the complex process of Zircaloy oxidation during steam quenching, calculating the hydrogen liberated as a gas and the hydrogen stored in the metal. The model was developed on the basis of small-scale separate-effects quench experiments performed at Forschungszentrum Karlsruhe. The new oxide surface and the new metallic surface produced by cracking of the oxide during quenching are calculated for each experiment performed at 1200 centigrade, 1400 centigrade and 1600 centigrade using as-received Zircaloy-4 (no pre-oxidation) and with Zircaloy specimens pre-oxidized to give oxide thickness of 100μm and 300μm. The results are relevant to accident management in nuclear power plants. (author)

  11. Passive decay heat removal by sump cooling after core meltdown

    Knebel, J.U.; Mueller, U.

    1996-01-01

    This article presents the basic physical phenomena and scaling criteria of decay heat removal from a large coolant pool by single-phase and two-phase natural circulation flow. The physical significance of the dimensionless similarity groups derived is evaluated. The above results are applied to the SUCO program that is performed at the Forschungszentrum Karlsruhe. The SUCO program is a three-step series of scaled model experiments investigating the possibility of a sump cooling concept for future light water reactors. The sump cooling concept is based on passive safety features within the containment. The work is supported by the German utilities and the Siemens AG. The article gives first measurement results of the 1:20 linearly scaled plane two-dimensional SUCOS-2D test facility. The experimental results of the model geometry are transformed to prototype conditions

  12. Investigations on sump cooling after core melt down

    Knebel, J.U.

    1995-01-01

    This article presents the basic physical phenomena and scaling criteria of decay heat removal from a large coolant pool by single-phase and two-phase natural circulation flow. The physical significance of the dimensionless similarity groups derived is evaluated. The above results are applied to the SUCO program that is performed at the Forschungszentrum Karlsruhe. The SUCO program is a three-step series of scaled model experiments investigating the possibility of an optional sump cooling concept for the European Pressurized Water Reactor EPR. This concept is entirely based on passive safety features within the containment. The work is supported by the German utilities and the Siemens dimensional SUCOS-2D test facility. The experimental results of the model geometry are transformed to prototypic conditions

  13. Validated design of the ITER main vacuum pumping systems

    Day, Chr.; Antipenkov, A.; Dremel, M.; Haas, H.; Hauer, V.; Mack, A.; Boissin, J.-C.; Class, G.; Murdoch, D.K.; Wykes, M.

    2005-01-01

    Forschungszentrum Karlsruhe is developing the ITER high vacuum cryogenic pumping systems (torus, cryostat, NBI) as well as the corresponding mechanical roughing pump trains. All force-cooled big cryopumps incorporate similar design of charcoal coated cryopanels cooled to 5 K with supercritical helium. A model of the torus exhaust cryopump was comprehensively characterised in the TIMO testbed at Forschungszentrum. This paper discusses the vacuum performance results of the model pump and outlines how these data were incorporated in a sound design of the whole ITER torus exhaust pumping system. To do this, the dedicated software package ITERVAC was developed which is able to describe gas flow in viscous, transitional and molecular flow regimes as needed for the gas coming through the divertor slots and along the pump ducts into the cryopumps. The entrance section between the divertor cassettes and each pumping duct was identified to be the bottleneck of the gas flow. The interrelation of achievable throughputs as a function of the divertor pressure and the cryopump pumping speed is discussed. The system design is completed by assessment of the NBI cryopump system and integrating performance curves for the roughing pump trains needed during the regeneration phases of the cryopumps. (author)

  14. Nuclear Legislation in OECD and NEA Countries. Regulatory and Institutional Framework for Nuclear Activities - Germany

    2011-01-01

    Committee - KTA); 3. Public and semi-public agencies (Technological Surveillance Association - Technische Ueberwachungsvereine-TUV; Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS)mbH; Karlsruhe Research Centre - Forschungszentrum Karlsruhe; Juelich Research Centre - Forschungszentrum Juelich GmbH; GKSS Research Centre Geesthacht - Forschungszentrum Geesthacht GmbH; Helmholtz Zentrum Berlin for Materials and Energy; The Electron-Synchrotron in Hamburg - Deutsches Elektronen-Synchrotron-DESY; Max-Planck Institute for Plasma Physics at Garching/Munich - Max-Planck-Institut fuer Plasmaphysik-IPP; Company for Heavy Ion Research - Gesellschaft fuer Schwerionenforschung mbH-GSI; Rossendorf Association for Nuclear Technology and Analysis - Verein fuer Kernverfahrenstechnik und Anlaytik)

  15. Department of Cosmic Radiation Physics: Overview

    Gawin, J.

    1999-01-01

    Full text: The Department of Cosmic Ray Physics in Lodz is involved in basic research in the area of high energy physics and cosmic ray physics related to: - Studies of asymptotic properties of hadronic interactions based on the analysis of cosmic ray propagation in the atmosphere. - Experimental and phenomenological studies of Extensive Air Showers induced by cosmic ray particles. - Search for point sources of high energy cosmic rays. - Studies of cosmic ray propagation in the Galaxy and mechanisms of particle acceleration. - Studies of mass composition of cosmic rays in the energy range 10 15 - 10 17 eV. Theoretical and experimental studies of Extensive Air Shower properties are performed mostly based on the results obtained by the Lodz Extensive Air Shower Array. We analysed nearly 100,000 events of energies above 10 15 eV registered by the Lodz hodoscope. We have developed the method of data analysis which allows us to verify different models of cosmic ray mass composition. In our research in high energy cosmic rays we also used experimental data from other collaborating experiments in Karlsruhe, Baksan and THEMISTOCLE. The Lodz group collaborates with many foreign institutes and laboratories in construction and data interpretation of cosmic ray experiments. Our most important partners are: Forschungszentrum in Karlsruhe (Germany), College de France, Institute for Nuclear Studies of the Russian Academy of Science, University of Perpignan and Uppsala University (Sweden). (author)

  16. Fast power measurement on a 30 GHz/15 kW gyrotron

    Saala, G.

    2004-09-01

    This work has been developed in the scope of a study-thesis at the Universitaet Karlsruhe (TH). The realization took place at the Institut fuer Hochleistungsimpuls- und Mikrowellentechnik (IHM) at the Forschungszentrum Karlsruhe (FZK). The aim was to investigate the possibilities of a fast power measurement at a compact, industrial gyrotron-system. To measure the output-power a small fraction of the gyrotron microwave radiation is coupled out and analyzed using a diode-detector. At the beginning of the work a mirror of the quasi-optical transmission line with a built in λ/4-coupler was available. This built-in coupler and other coupling structures which have been set up during this work have been characterized. To be able to perform reproduceable measurements several computer programs have been developed. Using these programs the gyrotron-system can be remote-controlled from a PC. The diode-detector signal has been analyzed under different conditions of gyrotron operation with respect to its short-term- and long-term-stability. After that the dependency of the calorimetrically measured output-power of the gyrotron has been used to calibrate the diode-voltage. (orig.)

  17. Comparison of actinides and fission products recycling scheme with the normal plutonium recycling scheme in fast reactors

    Salahuddin Asif

    2013-01-01

    Full Text Available Multiple recycling of actinides and non-volatile fission products in fast reactors through the dry re-fabrication/reprocessing atomics international reduction oxidation process has been studied as a possible way to reduce the long-term potential hazard of nuclear waste compared to that resulting from reprocessing in a wet PUREX process. Calculations have been made to compare the actinides and fission products recycling scheme with the normal plutonium recycling scheme in a fast reactor. For this purpose, the Karlsruhe version of isotope generation and depletion code, KORIGEN, has been modified accordingly. An entirely novel fission product yields library for fast reactors has been created which has replaced the old KORIGEN fission products library. For the purposes of this study, the standard 26 groups data set, KFKINR, developed at Forschungszentrum Karlsruhe, Germany, has been extended by the addition of the cross-sections of 13 important actinides and 68 most important fission products. It has been confirmed that these 68 fission products constitute about 95% of the total fission products yield and about 99.5% of the total absorption due to fission products in fast reactors. The amount of fissile material required to guarantee the criticality of the reactor during recycling schemes has also been investigated. Cumulative high active waste per ton of initial heavy metal is also calculated. Results show that the recycling of actinides and fission products in fast reactors through the atomics international reduction oxidation process results in a reduction of the potential hazard of radioactive waste.

  18. Old waste products - new requirements. Preparations for the later repository

    Graf, A.; Merx, H.

    2003-01-01

    For more than 30 years now, the Hauptabteilung Dekontaminationsbetriebe (HDB, Central Decontamination Department) of the Forschungszentrum Karlsruhe has been engaged in the management of radioactive wastes produced by the operation and decommissioning of research reactors and institutes of the Research Center, the Karlsruhe reprocessing plant, the European Institute for Transuranium Elements, and the Baden-Wuerttemberg state collection center. For this purpose, the wastes delivered to HDB have been conditioned at various facilities according to the requirements specified. These conditioning requirements, however, have changed in the course of time. In the past, only minimum declaration and conditioning requirements had to be fulfilled for the ASSE repository storage facility. Since 1994, the KONRAD repository storage conditions have been adopted. They comprise a variety of quality criteria. Judging from today, duration of interim storage until transfer to a repository storage facility will take another 30 years at least. In addition to the documentary qualification of the waste products, it is therefore required to take measures to ensure long-term safety of both the waste packages and their storage. This is why the HDB, in agreement with the supervisory authority, i.e. the Federal Radiation Protection Authority, and its experts, has decided to put the waste products into KONRAD containers in certified compliance with the repository storage conditions and to backfill these containers with concrete in accordance with approved procedures. Thus, waste packages suited for repository storage will be produced and corrosion processes and the possible release of radioactivity will be prevented. (orig.)

  19. Old waste products - new requirements. Preparations for the later repository

    Graf, A.; Merx, H. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Hauptabteilung Dekontaminationsbetriebe

    2003-07-01

    For more than 30 years now, the Hauptabteilung Dekontaminationsbetriebe (HDB, Central Decontamination Department) of the Forschungszentrum Karlsruhe has been engaged in the management of radioactive wastes produced by the operation and decommissioning of research reactors and institutes of the Research Center, the Karlsruhe reprocessing plant, the European Institute for Transuranium Elements, and the Baden-Wuerttemberg state collection center. For this purpose, the wastes delivered to HDB have been conditioned at various facilities according to the requirements specified. These conditioning requirements, however, have changed in the course of time. In the past, only minimum declaration and conditioning requirements had to be fulfilled for the ASSE repository storage facility. Since 1994, the KONRAD repository storage conditions have been adopted. They comprise a variety of quality criteria. Judging from today, duration of interim storage until transfer to a repository storage facility will take another 30 years at least. In addition to the documentary qualification of the waste products, it is therefore required to take measures to ensure long-term safety of both the waste packages and their storage. This is why the HDB, in agreement with the supervisory authority, i.e. the Federal Radiation Protection Authority, and its experts, has decided to put the waste products into KONRAD containers in certified compliance with the repository storage conditions and to backfill these containers with concrete in accordance with approved procedures. Thus, waste packages suited for repository storage will be produced and corrosion processes and the possible release of radioactivity will be prevented. (orig.)

  20. The HGF strategy project

    Knebel, J.U.; Fellmoser, F.; Lefhalm, C.; Mack, K.; Pettan, C.; Piecha, H.; Konys, J.; Adelhelm, C.; Glasbrenner, H.; Muscher, H.; Novotny, J.; Voss, Z.; Wedemeyer, O.; Mueller, G.; Heinzel, A.; Schumacher, G.; Huber, R.; Zimmermann, F.; Groetzbach, G.; Dorr, B.; Carteciano, L.N.

    2000-01-01

    Within the Hermann von Helmholtz-Gemeinschaft Deutscher Forschungszentren (HGF) an HGF-Strategy Fund Project entitled 'Innovative Technologies to Reduce Radiotoxicity' is funded since October 1999. The objectives of this HGF-Strategy Fund Project is the development of new methods and technologies to design and manufacture thin-walled and highly thermally-loaded surfaces which are cooled by a corrosive heavy liquid metal (lead-bismuth eutectic). The result of this project will be the basic scientific-technical tool which allows the conception and the design of a European Demonstrator of an ADS system (cf. 32.23.05). The work performed at Forschungszentrum Karlsruhe is embedded in a broad European research and development programme on ADS systems. The project is divided in three sub-projects: Sub-Project 1: Thermalhydraulic Investigations, Sub-Project 2: Material Specific Investigations, Sub-Project 3: Oxygen Control System. This progress report gives a general description of the project and its envisaged objectives. As a selection of the results achieved, first, FLUTAN calculations for the COULI beam window design and, second, the oxygen control system for the KArlsruhe Lead LAboratory KALLA are described in detail. Finally, the design and status of KALLA is given. (orig.)

  1. PREFACE: International Conference on Magnetism (ICM 2009)

    Goll, Gernot; Löhneysen, Hilbert v.; Loidl, Alois; Pruschke, Thomas; Richter, Manuel; Schultz, Ludwig; Sürgers, Christoph; Wosnitza, Jochen

    2010-11-01

    The International Conference on Magnetism 2009 (ICM 2009) was held in Karlsruhe, Germany, from 26-31 July 2009. Previous conferences in this series were organized in Edingburgh, United Kingdom (1991), Warsaw, Poland (1994), Cairns, Australia (1997), Recife, Brazil (2000), Rome, Italy (2003) and Kyoto, Japan (2006). As with previous ICM conferences, the annual Conference on Strongly Correlated Electron Systems (SCES) was integrated into ICM 2009. Conference photograph Participants of ICM 2009 in front of the Stadthalle Karlsruhe. Topics of ICM 2009 were: Strongly Correlated Electron Systems; Quantum and Classical Spin Systems; Magnetic Structures and Interactions; Magnetization Dynamics and Micromagnetics; Spin-Dependent Transport; Spin Electronics; Magnetic Thin Films, Particles, and Nanostructures; Soft and Hard Magnetic Materials and their Applications; Novel Materials and Device Applications; Magnetic Recording and Memories; Measuring Techniques and Instrumentation, as well as Interdisciplinary Topics. We are grateful to the International Advisory Committee for their help in putting up an attractive program encompassing practically all aspects of magnetism, both experimentally and theoretically. The program committee comprised A Loidl, Germany (Chair), M A Continentino, Brazil, D E Dahlberg, USA, D Givord, France, G Güntherodt, Germany, H Mikeska, Germany, D Kaczorowski, Poland, Ching-Ray Chang, South Korea, I Mertig, Germany, D Vollhardt, Germany and E F Wassermann, Germany was also head of the National Organizing Committee. His help is gratefully acknowledged. Photographs Left: Poster session in the Stadthalle Karlsruhe. Upper right: H v Löhneysen (Conference Chairman), Nobel Laureates A Fert and P. Grünberg, E Umbach (Chairman of the Executive Board of Forschungszentrum Karlsruhe) (left to right). Lower right: Nobel Laureate P W Anderson. The scientific program started on Monday 27 July 2009 with opening addresses by the Conference Chairman, the deputy

  2. GSF- Research Centre for Environment and Health. Institute for Hydrology. Annual report 2000; GSF - Forschungszentrum fuer Umwelt und Gesundheit. Inst. fuer Hydrologie. Jahresbericht 2000

    NONE

    2001-11-01

    The main areas of activities in the period under review are the migration of microorganisms in aquifers, ground water and sediments, transport mechanisms, influence of biofilms on hydraulic properties of sediments, analytical and numerical modelling of nitrate reduction in a bioreactor, migration of copper and antimony in aquifers, isotope identification and quantification in ground water and in neve of an antarctic region. (UKE)

  3. Neutron scattering. Lectures of the JCNS laboratory course held at Forschungszentrum Juelich and the research reactor FRM II of TU Munich

    Brueckel, T.; Heger, G.; Richter, D.; Zorn, R.

    2007-01-01

    The following topics are dealt with: Fourier transform, basic assumptions of quantum mechanics and the Born approximation, symmtery in crystals, neutron sources, neutron elastic scattering and properties, polarized neutron scattering, correlation functions measured by scattering experiments, grazing incidence neutron scattering, neutron diffractometers, small-angle scattewring inelastic crystal spectrometers, time-of-flight spectrometers using NSE, structure determination, inelastic neutron scattering with phonon and magnon excitations, structure of complex fluids and macromolecules, polymer dynamics, magnetism. (HSI)

  4. Setup and commissioning of a combined water detritiation and isotope separation experiment at the Tritium Laboratory Karlsruhe

    Welte, S., E-mail: stefan.welte@kit.edu; Cristescu, I.; Dittrich, H.; Lohr, N.; Melzer, C.; Michling, R.; Plusczyk, C.; Schaefer, P.

    2013-10-15

    Highlights: • Technical scale, tritium compatible liquid phase catalytic exchange (LPCE). • Technical scale, tritium compatible cryogenic distillation. • Combines processing option for tritiated water and isotope separation. -- Abstract: The European union in kind supply for the ITER fuel cycle development consists, among others, of the water detritiation system (WDS) and the isotope separation system (ISS). In order to mitigate the release of tritium to the environment, these systems are combined by feeding hydrogen exhaust from the ISS into the WDS for final processing. Therefore, the WDS is the final tritium barrier before releasing hydrogen (H{sub 2}) exhaust to the environment. The TRENTA 4 scaled prototype facility at TLK is based on combination of the combined electrolysis and catalytic exchange (CECE) process and a cryogenic distillation (CD) process. All components are fully tritium compatible and controlled using a state of the art control system for process automation, backed up by an additional dedicated safety system. The paper will give a detailed overview of the current experimental facility including all process components. Furthermore the paper will present the results of the functional test of the WDS/ISS combination using protium and deuterium, as well the results of the first commissioning runs using HTO of approximately 5 × 10{sup 9} Bq kg{sup −1} activity concentration.

  5. Het EDTA-gehalte van 20 monsters gesteriliseerde peulvruchten, in september 1984 gekocht te Karlsruhe en Emmerich

    Westerling, F.J.

    1984-01-01

    In tegenstelling tot Nederland is in Duitsland de toevoeging van EDTA (ethyleendiaminetetra-azijnzuur) aan geconserveerde peulvruchten niet toegestaan. Bij export van deze produkten naar Duitsland dient de nederlandse producent hier rekening mee te houden. In verband hiermee is een onderzoek

  6. Karlsruhe Nuclear Research Center, Institute of Nuclear Solid State Physics. Progress report on research and development work in 1993

    1994-03-01

    The Institute for Nuclear Solids Physics carried out about 90% of its work in the year of the report, 1993, on the main point of superconductivity. The work on high temperature superconductors on a cuprate basis was continued on a large scale. The availability of better samples (eg: non-twinned single crystals) make it possible to clear up a series of important detailed questions regarding the structure, grid dynamics and electronic structure. The activities closely related to applications of superconducting films were concentrated on the growth of a-axis and c-axis orientated films on technically relevant substrates (above all on sapphire, including suitable buffer layers and the examination of these films regarding their high frequency behaviour. Considerable progress was achieved in the manufacture of wafers coated on both sides. The work on Fullerene (carbon molecules C 60 , C 70 etc) and Fullerene compounds was continued. The Institute quickly succeeded not only in preparing these systems, but also in making a considerable contribution to a physical understanding of them. Among the Institute's activities, which are not directly connected to superconductivity (about 10%), one should mention above all, the experimental and theoretical work on the physics of surfaces and boundary surfaces, on polymer physics and on the physics of mesoscopic systems. (orig.) [de

  7. Karlsruhe Nuclear Research Center, Institute of Materials Research. Progress report on research and development work in 1993

    1994-03-01

    The Institute consists of three parts IMF I, IMF II and IMF III. The tasks are divided into applied material physics (IMF I), material and structural mechanics (IMF II) and material process technology (IMF III). IMF I works preferably on the development of metallic, non-metallic and compound materials and on questions of the structure and properties of boundary surfaces and surface protection coatings. The main work of IMF II is the reliability of components, failure mechanics and the science of damage. IMF III examines process technology questions in the context of the manufacture of ceramic materials and fusion materials and the design of nuclear components. The Institute works on various main points of the Kernforschungszentrum in its research work, particularly in nuclear fusion, micro-system technique, nuclear safety research, superconductivity and in processes with little harmful substances and waste. Material and strength problems for future fusion reactors and fission reactors, in powerful micro systems and safety-related questions of nuclear technology are examined. Also, research not bound to projects in the field of metallic, ceramic and polymer materials for high stresses is carried out. (orig.) [de

  8. Kernforschungszentrum Karlsruhe. Institut fuer Datenverarbeitung in der Technik: Progress report on research and development works in 1984

    1985-02-01

    The Institut fuer Datenverarbeitung in der Technik (Institute for Data Processing in Engineering) works in the field of applied computer and systems analysis. The present report describes the activities of this Institute within the following KfK-projects: Reprocessing, Fusion Technology, Nuclear Material Safeguards, Nuclear Safety, and the Fast Breeder Project. (WB) [de

  9. Ten years statistics of wind direction and wind velocity measurements performed at the Karlsruhe Nuclear Research Center

    Becker, M.; Dilger, H.

    1979-06-01

    The measurements of wind direction and wind velocity performed at 60 m and 200 m height were evaluated for one year each and frequency distributions of the measured values were established. The velocity was divided into 1 m/s steps and the direction into 10 0 sectors. The frequency distribution of the wind direction reveals three maxima located in the southwest, northeast and north, respectively. The maximum of the frequency distribution of the wind velocity occurs between 4 and 5 m/s at 200 m height and between 3 and 4 m/s at 60 m height. (orig.) [de

  10. The FR 2 reactor at Karlsruhe, F.R. Germany and associated hot cell facilities. Information sheets

    Hardt, P. von der; Roettger, H.

    1981-01-01

    Technical information is given on the FR 2 reactor and associated hot cell facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

  11. Destruction of the BETA experimental facility for core meltdown experiments in the Karlsruhe Nuclear Research Center on 21 March 1992

    Feige, K.D.

    1992-01-01

    The BETA experiment V 6.2 was intended to yield information on the processes involved in a lateral containment meltdown starting in a concrete wall with external water cooling. The unexpected overpressure that caused the explosion occurred 1896 seconds after the melt had been fed into the crucible, inducing the melt-water interaction. The explosion destroyed only the inner space of the facility. (orig.) [de

  12. Progress report on research and development work 1991 of the Department for Applied Systems Analysis, Karlsruhe Nuclear Research Center

    1991-03-01

    The following technology-oriented studies were conducted in the time period of the report: Technology assesment regarding 'Renewable Resources'; Environmental and health impact of the manufacturing and application and waste management of components and integrated circuits of micro- and optoelectronics; studies on product-oriented reduction of pollution, an innovative electronic form of presenting results of scientific projects: developing an electronic book prototype; expert systems and application of knowledge. (orig.) [de

  13. The Karlsruhe Neutron Transmission Experiment (KANT): Spherical shell transmission measurements with 14 MeV neutrons on beryllium

    Moellendorff, U. von; Fischer, U.; Giese, H.; Kappler, F.; Tayama, R.; Wiegner, E.; Klein, H.; Alevra, A.

    1996-01-01

    This is a set of viewgraphs (no additional text) of a presentation on spherical shell transmission measurements with 14 MeV neutrons on beryllium; the cross for 9 Be(n,2n)2α for the energy range between threshold (1.85 MeV) and 20 MeV neutron energy is measured and the measurement is compared with the literature. Also, neutron leakage multiplication in spherical Be shells with various thicknesses are presented. Figs, tabs

  14. The importance of on-line monitoring systems within the environmental monitoring program of the Karlsruhe Nuclear Research Center

    Koenig, L.A.; Winter, M.; Schmitt, A.

    1980-10-01

    The two on-line monitoring systems used in KfK environmental monitoring should be taken as measures of accident precaution and they are restricted to measurement of gamma local dose rates and of the (β + γ)-radiation levels. One of the systems serves to monitor the KfK operational area, the second serves to monitor the surrounding communities up to a radius of 8 km. By use of two different types of detectors the first system covers a range of measurement of 10 μrem/h to 1000 rem/h. By the second system only increases in the radiation level can be detected. It allows to record accidents in which countermeasures must be taken very urgently. The two monitoring systems are described which have been operated and partly been developed at the KfK. The possibilities and limits of using them for environmental monitoring are discussed. (orig./HP) [de

  15. 13. status report of the project HDR safety program of Kernforschungszentrum Karlsruhe. Working report 05.46/89

    Katzenmeier, G.

    1989-01-01

    The programme phase III, which extends to the end of 1991, is divided into the part projects containment behaviour in extreme accidents, long-term damage and monitoring the components in operation, behaviour of damaged components in dynamic accidents and large fires of actual materials. The main aims, state of the HDR safety programme, main points of the programme for 1990 and 8 technical reports on phase II and III are documented. There is a survey of costs. (DG) [de

  16. Progress report on research and development work 1991 of the Department of Hot Chemistry, Karlsruhe Nuclear Research Center

    1991-03-01

    In the year under review, the Institute of Hot Chemistry (IHCH) was in the midst of a thematic reorientation process. The priority of future chemical-technical work will be in the field of the development of supercriticality processes. The objective of such work consists in seeking new ways for getting rid of resistant chemical pollutants (halogenated organic compounds). The following projects are presented in detail: 1) Waste control in the environment (communal waste management; water and soil; emission-reducing processes; highly polluted soils); 2) Solid state and materials research (chemistry of materials research); basic physical research (neutrino and particle physics); 3) Nuclear waste management (concluding work on reprocessing technology), and 4) Other research projects (Institute-related research). The Annex lists the publications made by the IHCH staff. (BBR) [de

  17. Example of End States of Decommissioning Phases from the Decommissioning of the Multipurpose Research Reactor MZFR, Karlsruhe, Germany

    NONE

    2013-06-15

    The multipurpose reactor MZFR was a pressurized water reactor, cooled and moderated with heavy water. It was built from 1961 to 1966, and went critical for the first time on 29 September 1965. After 19 years of successful operation, the reactor was shut down on 3 May 1984. The reactor had a thermal output of 200 MW, and an electrical output of 50 MW. In addition to generating electricity, the MZFR had the following functions: - Testing fuel assemblies and various materials for reactor construction; - Gaining experience in the design, erection and operation of heavy water reactor systems; - Training scientific and technical reactor personnel; - Providing heat (first nuclear combined heat and power system (1979-1984)). In 1989, it was decided to dismantle the reactor completely, step by step. The decommissioning concept for the plant, down to a greenfield site, provides for eight distinct decommissioning steps (phases). A separate decommissioning licence was required for each step. The decommissioning work was carried out according to pre-approved work schedules. About 72 000 t of concrete and 7200 t of metal were to be removed. About 1000 t of concrete (500 t biological shield) and 1680 t of metal were to be classified as radioactive waste.

  18. Symposium on Turbulent Shear Flows (4th) Held at Karlsruhe University (Germany, F.R.), 12-14 September 1983.

    1983-09-01

    investigations in ducts of constant surfaces to a rectangle (40a0 lx60+0 1mm) at the exit cross-sectional area (Humphrey et al. 1977. 1981. Enayet at after 45...k___ to the thinner inlet boundary layers. Enayet et a1(1982) (1982a). The C-shaped diffuser was assembled with the measured the developing flow in a...about 0 25 Vb measured at the 450 smaller radial velocities In the turbulent case (cf plane of the constant area duct of Enayet et al (1982) of figures

  19. Karlsruhe Nuclear Research Center, Institute of Neutron Physics and Reactor Engineering. Progress report on research and development work in 1993

    1994-03-01

    The Institute of Neutron Physics and Reactor Engineering is concerned with research work in the field of nuclear engineering related to the safety of thermal reactors as well as with specific problems of fusion reactor technology. Under the project of nuclear safety research, the Institute works on concepts designed to drastically improve reactor safety. Apart from that, methods to estimate and minimize the radiological consequences of reactor accidents are developed. Under the fusion technology project, the Institute deals with neutron physics and technological questions of the breeding blanket. Basic research covers technico-physical questions of the interaction between light ion radiation of a high energy density and matter. In addition and to a small extent, questions of employing hydrogen in the transport area are studied. (orig.) [de

  20. Receiver system for radio observation of high-energy cosmic ray air showers and its behaviour in self trigger mode

    Kroemer, Oliver

    2008-04-01

    on the site of the cosmic ray air shower experiment KASCADE-Grande at the Forschungszentrum Karlsruhe. They are receiving radio signals which are clearly in coincidence with cosmic ray air showers. Due to the calibration spanning the whole signal path and the polarization analysis it is possible to investigate radio emission from cosmic ray air showers and underlying emission models. An autonomous operation of the receiver stations requires a self trigger which identifies the cosmic ray air shower by its own radio signal only. Due to the superposition of noise and radio frequency interference an increasing false trigger rate is expected with decreasing trigger threshold. The self trigger conceived within this work allows suitably low thresholds at technically manageable false trigger rates. The behaviour and limitations of this self trigger concept are derived theoretically but also confirmed by measurements under real environmental conditions. On the radio-loud site of the Forschungszentrum Karlsruhe, the electric field strength threshold is only a factor of 3 above the theoretical minimum which is given by the omnipresent galactic noise in an unpopulated environment. The resulting detection limits for cosmic rays are expected to be above 5.10 17 eV for the primary particle energies in an unpopulated environment and above 10 18 eV on the site of the Forschungszentrum Karlsruhe. (orig.)

  1. Redox stability of neptunium(V) in the presence of humic substances of varying functionality

    Schmeide, K.; Geipel, G.; Bernhard, G. [Forschungszentrum Rossendorf e.V., Institute of Radiochemistry, P.O. Box 510 119, D-01314 Dresden (Germany)

    2005-07-01

    be stabilized in lower oxidation states, e.g. in complexation and sorption studies. [1] Sachs, S., Schmeide, K., Brendler, V., Krepelova, A., Mibus, J., Geipel, G., Heise, K.H., Bernhard, G.: Investigation of the Complexation and the Migration of Actinides and Nonradioactive Substances with Humic Acids under Geo-genic Conditions. Complexation of Humic Acids with Actinides in the Oxidation State IV Th, U, Np. FZR-399, Wissenschaftlich- Technische Berichte, Forschungszentrum Rossendorf, Dresden 2004. [2] Schmeide, K., Geipel, G., Bernhard, G.: Study of the Neptunium(V) Reduction by Various Natural and Synthetic Humic Substances. In: FZKA 7070, Wissenschaftliche Berichte (G. Buckau, ed.). Forschungszentrum Karlsruhe, Karlsruhe 2005, in press. (authors)

  2. IFMIF high flux test module - recent progress in design and manufacturing

    Leichtle, D.; Arbeiter, F.; Dolensky, B.

    2007-01-01

    The International Fusion Material Irradiation Facility (IFMIF) is an accelerator driven neutron source for irradiation tests of candidate fusion reactor materials. Two 40 MeV deuterium beams with 125 mA each strike a liquid lithium jet target, producing a high intensity neutron flux up to 55 MeV, which penetrates the adjacent test modules. Within the High Flux Test Module (HFTM) a testing volume of 0.5 litres filled by qualified small scale specimens will be irradiated at displacement rates of 20-50 dpa/fpy in structural materials. The HFTM will also provide helium and hydrogen production to dpa ratios that reflect within the uncertainties the values expected in a DEMO fusion reactor The Forschungszentrum Karlsruhe (FZK) has developed a HFTM design which closely follows the design premise of maximising the space available for irradiation specimens in the IFMIF high flux zone and in addition allows keeping the temperature nearly constant in the rigs containing the specimen. Within the entire specimen stack the temperature deviation will be below about 15 K. The main design principles applied are (i) filling the gaps between the specimens with liquid metal, (ii) winding three separately controlled heater sections on the inner capsules and (iii) dividing the test rigs in a hot inner and a cold outer zone, which a separated by a gap filled with stagnant helium that serves as a thermal insulator. Channels between the outer covers (the cold parts) are cooled by helium gas at moderate pressure (3 bars at inlet) and temperature (50 C). 12 identical rigs holding the specimen capsules which are heated by segmented helically wound electrical heaters ensure a flexible loading scheme during IFMIF operation. Complementary analyses on nuclear, thermo-hydraulics and mechanical performance of the HFTM were performed to optimize the design. The present paper highlights the main design characteristics as well as recent progress achieved in this area. This includes the stiffening of

  3. 20 years of cosmic muons research performed in IFIN-HH

    Mitrica, Bogdan

    2012-01-01

    During the last two decades a modern direction in particle physics research has been developed in IFIN-HH Bucharest, Romania. The history started with the WILLI detector built in IFIN-HH Bucharest in collaboration with KIT Karlsruhe (formerly Forschungszentrum Karlsruhe). The detector was designed for measurements of the low energy muon charge ratio ( 0.4GeV, show a diurnal modulation of the muon flux. The analysis of the muon events for energies 15 eV. Simulation studies and preliminary experimental tests, regarding the performances of the mini-array, have been performed using H and Fe primaries, with energies in a range 10 13 eV - 10 15 eV. The results show detailed effects of the direction of EAS incidence relative to the geomagnetic field, depending, in particular, of the primary mass. Based on the results, we can say that WILLI-EAS experiment could be used for testing the hadronic interaction models. Measurements of the high energy muon flux in underground of the salt mine from Slanic Prahova, Romania was performed using a new mobile detector developed in IFIN-HH, Bucharest. Consisting of 2 scintillator plates measuring in coincidence, the detector is installed on a van which facilitates measurements on different positions at surface or in underground. The detector was used to measure muon fluxes in different locations at surface or in underground. The detector was used to measure muon fluxes at different sites of Romania and in the underground of the salt mines from Slanic Prahova, Romania where IFIN-HH has a modern underground laboratory. New methods for the detection of cosmic ray muons are investigated in our institute based on scintillator techniques using optical fiber and MPPC photodyodes.

  4. Kinetic of the Oxygen Control System (OCS) for stagnant lead-bismuth systems

    Lefhalm, C.H.; Knebel, J.U.; Mack, K.J.

    2001-09-01

    Within the framework of the HGF strategy fund project 99/16 ''Thermalhydraulic and Material Specific Investigations into the Realization of an accelerator driven system (ADS) to Transmute Minor Actinides'' at the institute for nuclear and energy technology (IKET) investigations on the cooling of thermally high-loaded surfaces with liquid lead bismuth (Pb-Bi) are carried out. To operate a Pb-Bi loop safety, for example in order to cool a spallation target or a blanket of an accelerator driven system (ADS), the control of the oxygen concentration within the liquid metal is an inalienable prerequisite to prevent or minimize corrosion at the structure material. In this report the kinetic behaviour of the oxygen control system (OCS), which was developed at Forschungszentrum Karlsruhe, is examined. The OCS controls the chemical potential of oxygen in the liquid metal by regulating the oxygen content in the gas phase which flows over the free surface of the liquid metal. In this work the experimental facility KOCOS (kinetics of oxygen control system) in the karlsruhe lead laboratory (KALLA) was built. A physical diffusion model was utilised and extended to describe the exchange of oxygen between the gas and the liquid metal. The theoretical calculations are in very good agreement to the experimental findings. The OCS allows to control reversibly the oxygen concentration in the liquid metal. According to the observed kinetics of the process one can extrapolate that the control of large volumes, as they are necessary to operate an ADS demonstrator, is possible. Therefore, further experiments in liquid metal loop systems are suggested. (orig.)

  5. SMES based power modulator - status August 2001

    Juengst, K.P.; Gehring, R.; Kudymow, A.; Suess, E.

    2001-10-01

    Based on a superconducting magnetic energy storage (SMES) a long-pulse klystron modulator has been designed for use in the TESLA test facility (TTF) at DESY, Hamburg. A proto-type with an output power of 25 MW is under development at Forschungszentrum Karlsruhe in cooperation with the office of engineering lbK at Karlsruhe. Including a pulse transformer (1:13/11.5), the system will deliver pulses of 130 kV or 115 kV, 1.7 ms pulse length with a flat top of ± 0.5%, at a repetition rate up to 10 Hz. This new system's main features are a highly dynamic SMES (> 100 T/s), a high current power supply (rated 27 V/2.6 kA), a switched-mode high voltage power supply (rated 14 kV/45 A), a fast thyristor power switch for 2.6 kA approx. continuous current/ 2 ms break, an IGCT power switch rated 2.6 kA/14 kV, a protection switch unit and a system control unit. This demonstration system is to serve alternatively two klystrons of 5 MW RF output or one multibeam klystron of 10 MW RF output. A significant part of the components of the system has been built. A first set of the system components had been arranged to form a model of the modulator and 1 MW pulses were generated. The next large step in the area of the power electronic part is to increase the power of this test arrangement up to 10 MW. The SMES and its cryostat have undergone initial testing. The data acquisition and control system under development at DESY has been taken over and adjusted to our computer and experimental environment. (orig.)

  6. Reactive flow simulation in complex 3D geometries using the COM3D code

    Breitung, W.; Kotchourko, A.; Veser, A.; Scholtyssek, W.

    1999-01-01

    The COM3D code, under development at the Forschungszentrum Karlsruhe (FZK), is a 3-d CFD code to describe turbulent combustion phenomena in complex geometries. It is intended to be part of the advanced integral code system for containment analysis (INCA) which includes in addition GASFLOW for distribution calculations, V3D for slow combustion and DET3D for detonation analysis. COM3D uses a TVD-solver and optional models for turbulence, chemistry and thermodynamics. The hydrodynamic model considers mass, momentum and energy conservation. Advanced procedures were provided to facilitate grid-development for complex 3-d structures. COM3D was validated on experiments performed on different scales with generally good agreement for important physical quantities. The code was applied to combustion analysis of a large PWR. The initial conditions were obtained from a GASFLOW distribution analysis for a LOOP scenario. Results are presented concerning flame propagation and pressure evolution in the containment which clearly demonstrate the effects of internal structures, their influence on turbulence formation and consequences for local loads. (author)

  7. Models and criteria for prediction of Deflagration-to-Detonation Transition (DDT) in hydrogen-air-steam systems under severe accident conditions. Final report

    Klein, R.; Rehm, W.

    1999-01-01

    The European Commission in Brussels supported a joint project on Deflagration-to-Detonation Transition (DDT) studies for hydrogen safety within the framework programme on nuclear fission safety. The project was initiated by the Forschungszentrum Juelich based on the results of a pilot project. The following main project was coordinated by the Freie Universitaet Berlin involving seven european partners. The partners came from universities, research centers and industry, as follows: FU-Berlin, RWTH-Aachen, CNRS-Marseille, IPSN-Saclay, FZ-Juelich, FZ-Karlsruhe, and NNC-Knutsford, which worked closely together. The working period was two years (1997-1998). The aim of the project was to develop models and criteria for prediction of deflagration-to-detonation transition (DDT) in hydrogen-air-steam systems under severe accident conditions. The results obtained are documented in this final report, which was finished in 1999. The report consists of seven chapters, concerning: - Introduction - Experimental Investigations - Modelling and Numerics - Validation - Mitigation - Further Deliverables - Summary and Conclusion. The final report presents special experimental, theoretical, and computational aspects of the complex DDT phenomena for hydrogen safety studies, and it should be a solid basis for end user applications and further developments. (orig.)

  8. The Status of Beryllium Research for Fusion in the United States

    Glen R. Longhurst

    2003-01-01

    Use of beryllium in fusion reactors has been considered for neutron multiplication in breeding blankets and as an oxygen getter for plasma-facing surfaces. Previous beryllium research for fusion in the United States included issues of interest to fission (swelling and changes in mechanical and thermal properties) as well as interactions with plasmas and hydrogen isotopes and methods of fabrication. When the United States formally withdrew its participation in the International Thermonuclear Experimental Reactor (ITER) program, much of this effort was terminated. The focus in the U.S. has been mainly on toxic effects of beryllium and on industrial hygiene and health-related issues. Work continued at the INEEL and elsewhere on beryllium-containing molten salts. This activity is part of the JUPITER II Agreement. Plasma spray of ITER first wall samples at Los Alamos National Laboratory has been performed under the European Fusion Development Agreement. Effects of irradiation on beryllium structure are being studied at Oak Ridge National Laboratory. Numerical and phenomenological models are being developed and applied to better understand important processes and to assist with design. Presently, studies are underway at the University of California Los Angeles to investigate thermo-mechanical characteristics of beryllium pebble beds, similar to research being carried out at Forschungszentrum Karlsruhe and elsewhere. Additional work, not funded by the fusion program, has dealt with issues of disposal, and recycling

  9. System design development for microwave and millimeter-wave materials processing

    Feher, Lambert; Thumm, Manfred

    2002-06-01

    The most notable effect in processing dielectrics with micro- and millimeter-waves is volumetric heating of these materials, offering the opportunity of very high heating rates for the samples. In comparison to conventional heating where the heat transfer is diffusive and depends on the thermal conductivity of the material, the microwave field penetrates the sample and acts as an instantaneous heat source at each point of the sample. By this unique property, microwave heating at 2.45 GHz and 915 MHz ISM (Industrial, Medical, Scientific) frequencies is established as an important industrial technology since more than 50 years ago. Successful application of microwaves in industries has been reported e.g. by food processing systems, domestic ovens, rubber industry, vacuum drying etc. The present paper shows some outlines of microwave system development at Forschungszentrum Karlsruhe, IHM by transferring properties from the higher frequency regime (millimeter-waves) to lower frequency applications. Anyway, the need for using higher frequencies like 24 GHz (ISM frequency) for industrial applications has to be carefully verified with respect to special physical/engineering advantages or to limits the standard microwave technology meets for the specific problem.

  10. Direct containment heating integral effects tests in geometries of European nuclear power plants

    Meyer, Leonhard; Albrecht, Giancarlo; Caroli, Cataldo; Ivanov, Ivan

    2009-01-01

    The DISCO test facility at Forschungszentrum Karlsruhe (FZK) has been used to perform experiments to investigate direct containment heating (DCH) effects during a severe accident in European nuclear power plants, comprising the EPR, the French 1300 MWe plant P'4, the VVER-1000 and the German Konvoi plant. A high-temperature iron-alumina melt is ejected by steam into scaled models of the respective reactor cavities and the containment vessel. Both heat transfer from dispersed melt and combustion of hydrogen lead to containment pressurization. The main experimental findings are presented and critical parameters are identified. The consequences of DCH are limited in reactors with no direct pathway between the cavity and the containment dome (closed pit). The situation is more severe for reactors which do have a direct pathway between the cavity and the containment (open pit). The experiments showed that substantial fractions of corium may be dispersed into the containment in such cases, if the pressure in the reactor coolant system is elevated at the time of RPV failure. Primary system pressures of 1 or 2 MPa are sufficient to lead to full scale DCH effects. Combustion of the hydrogen produced by oxidation as well as the hydrogen initially present appears to be the crucial phenomenon for containment pressurization.

  11. Direct containment heating integral effects tests in geometries of European nuclear power plants

    Meyer, Leonhard [Forschungszentrum Karlsruhe (FZK), Postfach 3640, 76021 Karlsruhe (Germany)], E-mail: meyer@iket.fzk.de; Albrecht, Giancarlo [Forschungszentrum Karlsruhe (FZK), Postfach 3640, 76021 Karlsruhe (Germany); Caroli, Cataldo [Institut de Radioprotection et de Surete Nucleaire, BP 17, 92262 Fontenay-aux-Roses Cedex (France); Ivanov, Ivan [Technical University of Sofia, BG-1797 Sofia (Bulgaria)

    2009-10-15

    The DISCO test facility at Forschungszentrum Karlsruhe (FZK) has been used to perform experiments to investigate direct containment heating (DCH) effects during a severe accident in European nuclear power plants, comprising the EPR, the French 1300 MWe plant P'4, the VVER-1000 and the German Konvoi plant. A high-temperature iron-alumina melt is ejected by steam into scaled models of the respective reactor cavities and the containment vessel. Both heat transfer from dispersed melt and combustion of hydrogen lead to containment pressurization. The main experimental findings are presented and critical parameters are identified. The consequences of DCH are limited in reactors with no direct pathway between the cavity and the containment dome (closed pit). The situation is more severe for reactors which do have a direct pathway between the cavity and the containment (open pit). The experiments showed that substantial fractions of corium may be dispersed into the containment in such cases, if the pressure in the reactor coolant system is elevated at the time of RPV failure. Primary system pressures of 1 or 2 MPa are sufficient to lead to full scale DCH effects. Combustion of the hydrogen produced by oxidation as well as the hydrogen initially present appears to be the crucial phenomenon for containment pressurization.

  12. Numerical investigation of a brazed joint between W-1%La{sub 2}O{sub 3} and ODS EUROFER components

    Reiser, J. [Forschungszentrum Karlsruhe GmbH, Institute for Materials Research III, P.O. Box 3640, 76021 Karlsruhe (Germany)], E-mail: Jens.Reiser@imf.fzk.de; Norajitra, P.; Ruprecht, R. [Forschungszentrum Karlsruhe GmbH, Institute for Materials Research III, P.O. Box 3640, 76021 Karlsruhe (Germany)

    2008-12-15

    A modular helium-cooled divertor design HEMJ (helium-cooled modular divertor concept with multiple-jet cooling) for the 'post-ITER' demonstration (DEMO) fusion reactor has been developed at the Forschungszentrum Karlsruhe. The design goal is to withstand a surface heat flux of at least 10 MW/m{sup 2} at an acceptable pumping power. A conical design of a brazed joint between two structural components of the HEMJ finger module which are made of different materials has been investigated. This new transition piece design should withstand at least 1000 temperature load cycles between operating and room temperatures. Due to the large mismatch of the thermal expansion coefficients (TECs) of the different materials used, high thermal stresses caused by the thermocyclic loads could lead to the plasticization of both materials in the joint region. To demonstrate the feasibility of this transition piece design, a systematic investigation is required, which includes a numerical simulation, the choice of the brazing material, a study of the brazing technology, and thermocyclic tests of the finger mock-up. This paper shall present a method of numerical investigation as the first step of investigation. Plastic stress calculations are performed using the commercial software ANSYS taking into account thermocyclic as well as internal pressure loads. The calculation results, in particular the plastic behavior of the brazed joint, will be discussed.

  13. Program nuclear safety research: report 2000

    Muehl, B.

    2001-09-01

    The reactor safety R and D work of forschungszentrum karlsruhe (FZK) had been part of the nuclear safety research project (PSF) since 1990. In 2000, a new organisational structure was introduced and the Nuclear Safety Research Project was transferred into the nuclear safety research programme (NUKLEAR). In addition to the three traditional main topics - Light Water Reactor safety, Innovative systems, Studies related to the transmutation of actinides -, the new Programme NUKLEAR also covers Safety research related to final waste storage and Immobilisation of HAW. These new topics, however, will only be dealt with in the next annual report. Some tasks related to the traditional topics have been concluded and do no longer appear in the annual report; other tasks are new and are described for the first time. Numerous institutes of the research centre contribute to the work programme, as well as several external partners. The tasks are coordinated in agreement with internal and external working groups. The contributions to this report, which are either written in German or in English, correspond to the status of early/mid 2001. (orig.)

  14. Technical Note: A numerical test-bed for detailed ice nucleation studies in the AIDA cloud simulation chamber

    R. J. Cotton

    2007-01-01

    Full Text Available The AIDA (Aerosol Interactions and Dynamics in the Atmosphere aerosol and cloud chamber of Forschungszentrum Karlsruhe can be used to test the ice forming ability of aerosols. The AIDA chamber is extensively instrumented including pressure, temperature and humidity sensors, and optical particle counters. Expansion cooling using mechanical pumps leads to ice supersaturation conditions and possible ice formation. In order to describe the evolving chamber conditions during an expansion, a parcel model was modified to account for diabatic heat and moisture interactions with the chamber walls. Model results are shown for a series of expansions where the initial chamber temperature ranged from −20°C to −60°C and which used desert dust as ice forming nuclei. During each expansion, the initial formation of ice particles was clearly observed. For the colder expansions there were two clear ice nucleation episodes. In order to test the ability of the model to represent the changing chamber conditions and to give confidence in the observations of chamber temperature and humidity, and ice particle concentration and mean size, ice particles were simply added as a function of time so as to reproduce the observations of ice crystal concentration. The time interval and chamber conditions over which ice nucleation occurs is therefore accurately known, and enables the model to be used as a test bed for different representations of ice formation.

  15. RODOS System in the Slovak Republic - its Implementation and Adaptation

    Duranova, T.; Bohun, L; Metke, E.; Janko, K.

    2003-01-01

    With support of the European Commission's (EC) ECHO programme 'Implementation of the RODOS Decision Support System for Off-Site Emergency Preparation and response in the Emergency centres in Poland and the Slovak Republic', RODOS system version 3.13 was implemented in the Slovak Republic with main objective to accelerate the implementation of the system within national emergency preparedness arrangements. Within the ECHO project, the National Centre of RODOS was established at the Nuclear Regulatory Authority of the Slovak Republic (NRA SR). VUJE was established as technical support organization and interactive user. As a data supplier and passive user were established the Slovak Centre for Radiation Monitoring, Slovak Hydro-Meteorological Institute (SHMI), Jaslovske Bohunice and Mochovce NPP's. As RODOS could become a standard tool for emergency preparedness in the European Union and CEE region lessons learned within projects mentioned in the paper were valuable contribution to other similar international and national projects. Effective working arrangements and links have been established between some institutes having competence in various aspects of emergency preparedness and response in about 20 European countries, with Forschungszentrum Karlsruhe as main responsible institute for system development and DSSNET project co-ordination. This network contributes to the more cost-effective use of resources for the further improvement of decision support for nuclear emergencies. More importantly, it will enhance trust and confidence between people, which is essential for responding effectively and coherently to any future nuclear accident that may have implications on a European scale. (authors)

  16. Beyond grid security

    Hoeft, B; Epting, U; Koenig, T

    2008-01-01

    While many fields relevant to Grid security are already covered by existing working groups, their remit rarely goes beyond the scope of the Grid infrastructure itself. However, security issues pertaining to the internal set-up of compute centres have at least as much impact on Grid security. Thus, this talk will present briefly the EU ISSeG project (Integrated Site Security for Grids). In contrast to groups such as OSCT (Operational Security Coordination Team) and JSPG (Joint Security Policy Group), the purpose of ISSeG is to provide a holistic approach to security for Grid computer centres, from strategic considerations to an implementation plan and its deployment. The generalised methodology of Integrated Site Security (ISS) is based on the knowledge gained during its implementation at several sites as well as through security audits, and this will be briefly discussed. Several examples of ISS implementation tasks at the Forschungszentrum Karlsruhe will be presented, including segregation of the network for administration and maintenance and the implementation of Application Gateways. Furthermore, the web-based ISSeG training material will be introduced. This aims to offer ISS implementation guidance to other Grid installations in order to help avoid common pitfalls

  17. Measurements of time-dependent liquid-metal magnetohydrodynamic flows in a flat rectangular duct

    Buehler, L.; Horanyi, S.

    2009-01-01

    In the helium-cooled lead lithium (HCLL) blanket, which has been chosen as a reference concept for a liquid-metal breeding blanket to be tested in ITER, the heat is removed by helium cooled plates aligned with the strong toroidal magnetic field that confines the fusion plasma. The liquid breeder lead lithium circulates through gaps of rectangular cross-section between the cooling plates to transport the generated tritium towards external extraction facilities. Under the action of the strong magnetic field, liquid metal flows in conducting rectangular ducts exhibit jet-like velocity profiles in the thin boundary layers near the side walls, which are parallel to the magnetic field like the cooling plates in HCLL blankets. The velocity in these side layers may exceed several times the mean velocity in the duct and it is known that these layers become unstable for sufficiently high Reynolds numbers. The present paper summarizes experimental results for such unstable time-dependent flows in strong magnetic fields, which have been obtained in the MEKKA liquid metal laboratory of the Forschungszentrum Karlsruhe. In particular, spatial and temporal scales of perturbation patterns are identified. The results suggest that the flow between cooling plates in a HCLL blanket is laminar and stable. The observed time-dependent flow behavior appears at larger velocities so that the present results are more relevant for applications in dual coolant concepts where high-velocity jets have been predicted along side walls.

  18. Local velocity measurements in lead-bismuth and sodium flows using the ultrasound doppler velocimetry

    Eckert, S.; Gerbeth, G.

    2003-01-01

    We will present measurements of the velocity profiles in liquid sodium and eutectic lead-bismuth by means of the Ultrasonic Doppler Velocimetry (UDV). A sodium flow in a rectangular duct exposed to an external, transverse magnetic field has been examined. To demonstrate the capability of UDV the transformation of the well-known turbulent, piston-like profile to an M-shaped velocity profile for growing magnetic field strength was observed. The significance of artifacts such as caused by the existence of reflecting interfaces in the measuring domain will be discussed. In the sodium case, the measurements were performed through the channel wall. An integrated ultrasonic sensor with acoustic wave-guide has been developed to overcome the limitation of ultrasonic transducers to temperatures lower than 200 .deg. C. This sensor can presently be applied at maximum temperatures up to 800 .deg. C. Stable and robust measurements have been performed in various PbBi flows in our laboratory at FZR as well as at the THESYS loop of the KALLA laboratory of the ForschungsZentrum Karlsruhe (FZK). We will also present experimental results obtained in a PbBi bubbly flow at 250...300 .deg. C. Argon bubbles were injected through a single orifice in a cylindrical container filled with stagnant PbBi. Velocity profiles were measured in the bubble plume. Mean values of the liquid as well as the bubble velocity were extracted from the data and will be presented as function of the gas flow rate

  19. Conceptual design of a He-cooled divertor with integrated flow and heat transfer promoters (PPCS subtask TW3-TRP-001-D2). Pt. 1. Summary

    Norajitra, P.; Kruessmann, R.

    2004-04-01

    Within the framework of the EU power plant conceptual study (PPCS), helium-cooled modular divertor concepts with a flow promoter (HEMP as a pin array and HEMS as slot array version) have been investigated at the Forschungszentrum Karlsruhe since 2002. The design goal is to achieve a high heat flux performance of 15 MW/m 2 . In this summary of the detailed report, research areas related to the development of a helium-cooled divertor shall be addressed. Latest changes in thermohydraulic layout as well as current results of simulation calculations shall be presented exemplarily for the slot concept HEMS which has the crucial advantage of being easier to manufacture. The divertor construction resulting from the requirements as well as the design-related issues shall be discussed. Possible manufacturing processes for divertor components of tungsten are assessed. Chapters 7 and 8 have been completely revised comprising the latest results of the thermohydraulic layout and thermomechanical analyses. Calculation results have to be verified by experiments. For this purpose, a helium loop will be built at the Efremov Institute, St. Petersburg, Russia, in 2004. An outlook on an alternative multi-jet design (HEMJ) will be given at the end of this report. (orig.)

  20. Review of the sodium fire experiments including sodium-concrete-reactions and summary of the results

    Cherdron, W.

    1996-01-01

    In the technical and design concept of containment systems of sodium cooled breeder reactors it has to be considered, that leakages in sodium pipes lead to sodium fires. The temperature and pressure rise caused by sodium fires makes it indispensable to analyse these accidents to be able to assess the safety of the whole system. Generally sodium leakages may lead to three different types of fires with different consequences. The main influences are the geometry of the leakage, shape, size, location, and the sodium conditions, such as temperature, flow rate and velocity. It must be also considered the reaction of sodium with surfaces like concrete. The paper gives an overview over all the sodium fire experiments performed in the FAUNA-facility (220 m 3 ) of the Forschungszentrum Karlsruhe in the years 1979 to 1993. The experimental program started with the investigation of pool fires on burning areas between 2 and 12 m 2 with up to 500 kg of Sodium. The experiments had been continued with 3 combined fires and 40 experiments on spray fires. 7 experiments on sodium-concrete reactions completed the program. (author)

  1. Experimental investigation of homogeneous freezing of sulphuric acid particles in the aerosol chamber AIDA

    O. Möhler

    2003-01-01

    Full Text Available The homogeneous freezing of supercooled H2SO4/H2O solution droplets was investigated in the aerosol chamber AIDA (Aerosol Interactions and Dynamics in the Atmosphere of Forschungszentrum Karlsruhe. 24 freezing experiments were performed at temperatures between 189 and 235 K with aerosol particles in the diameter range 0.05 to 1 µm. Individual experiments started at homogeneous temperatures and ice saturation ratios between 0.9 and 0.95. Cloud cooling rates up to -2.8 K min-1 were simulated dynamically in the chamber by expansion cooling using a mechanical pump. Depending on the cooling rate and starting temperature, freezing threshold relative humidities were exceeded after expansion time periods between about 1 and 10 min. The onset of ice formation was measured with three independent methods showing good agreement among each other. Ice saturation ratios measured at the onset of ice formation increased from about 1.4 at 231 K  to about 1.75 at 189 K. The experimental data set including thermodynamic parameters as well as physical and chemical aerosol analysis provides a good basis for microphysical model applications.

  2. A review of the demonstration of innovative solvent extraction processes for the recovery of trivalent minor actinides from PUREX raffinate

    Modolo, G.; Wilden, A.; Geist, A.; Magnusson, D.; Malmbeck, R.

    2012-01-01

    The selective partitioning (P) of long-lived minor actinides from highly active waste solutions and their transmutation (T) to short-lived or stable isotopes by nuclear reactions will reduce the long-term hazard of the high-level waste and significantly shorten the time needed to ensure their safe confinement in a repository. The present paper summarizes the on-going research activities at Forschungszentrum Juelich (FZJ), Karlsruher Institut fuer Technologie (KIT) and Institute for Transuranium Elements (ITU) in the field of actinide partitioning using innovative solvent extraction processes. European research over the last few decades, i.e. in the NEWPART, PARTNEW and EUROPART programmes, has resulted in the development of multi-cycle processes for minor actinide partitioning. These multi-cycle processes are based on the co-separation of trivalent actinides and lanthanides (e.g. by the DIAMEX process), followed by the subsequent actinide(III)/lanthanide(III) group separation in the SANEX process. The current direction of research for the development of innovative processes within the recent European ACSEPT project is discussed additionally. This paper is focused on the development of flow-sheets for recovery of americium and curium from highly active waste solutions. The flow-sheets are verified by demonstration processes, in centrifugal contactors, using synthetic or genuine fuel solutions. The feasibility of the processes is also discussed. (orig.)

  3. Mechanical performance of irradiated beryllium pebbles

    Scaffidi-Argentina, F.; Dalle-Donne, M.; Werle, H. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reaktortechnik

    1998-01-01

    For the Helium Cooled Pebble Bed (HCPB) Blanket, which is one of the two reference concepts studied within the European Fusion Technology Programme, the neutron multiplier consists of a mixed bed of about 2 and 0.1-0.2 mm diameter beryllium pebbles. Beryllium has no structural function in the blanket, however microstructural and mechanical properties are important, as they might influence the material behavior under neutron irradiation. The EXOTIC-7 as well as the `Beryllium` experiments carried out in the HFR reactor in Petten are considered as the most detailed and significant tests for investigating it. This paper reviews the present status of beryllium post-irradiation examinations performed at the Forschungszentrum Karlsruhe with samples from these irradiation experiments, emphasizing the effects of irradiation of essential material properties and trying to elucidate the processes controlling the property changes. The microstructure, the porosity distribution, the impurity content, the behavior under compression loads and the compatibility of the beryllium pebbles with lithium orthosilicate (Li{sub 4}SiO{sub 4}) during the in-pile irradiation are presented and critically discussed. Qualitative information on ductility and creep obtained by hardness-type measurements are also supplied. (author)

  4. Tritium release from neutron irradiated beryllium pebbles

    Scaffidi-Argentina, F.; Werle, H. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reactortechnik

    1998-01-01

    One of the most important open issues related to beryllium for fusion applications refers to the kinetics of the tritium release as a function of neutron fluence and temperature. The EXOTIC-7 as well as the `Beryllium` experiments carried out in the HFR reactor in Petten are considered as the most detailed and significant tests for investigating the beryllium response under neutron irradiation. This paper reviews the present status of beryllium post-irradiation examinations performed at the Forschungszentrum Karlsruhe with samples from the above mentioned irradiation experiments, trying to elucidate the tritium release controlling processes. In agreement with previous studies it has been found that release starts at about 500-550degC and achieves a maximum at about 700-750degC. The observed release at about 500-550degC is probably due to tritium escaping from chemical traps, while the maximum release at about 700-750degC is due to tritium escaping from physical traps. The consequences of a direct contact between beryllium and ceramics during irradiation, causing tritium implanting in a surface layer of beryllium up to a depth of about 40 mm and leading to an additional inventory which is usually several times larger than the neutron-produced one, are also presented and the effects on the tritium release are discussed. (author)

  5. Analysis of a thermite experiment to study low pressure corium dispersion

    Wilhelm, D.

    2001-08-01

    The report describes the recalculation of a thermite experiment in a reduced scale which simulates the discharge of molten core materials out of the pressure vessel of a light water reactor into the open compartments and the dome of the containment. The experiment was performed in the framework of a multinational effort at the Sandia National Laboratory, U.S.A. It is being followed by the DISCO program at the Forschungszentrum Karlsruhe. A computational fluid dynamics code was supplemented with specific models to recalculate the Sandia experiment in order to identify problem areas which need to be addressed in the future. Therefore, a first attempt was undertaken to extrapolate to reactor conditions. This was done in two steps to separate geometric from material scaling relationships. The study shows that important experimental results can be extrapolated according to general scaling laws but that there are sensitivities, especially when replacing thermite by corium. The results show a considerable scatter and a dependence on geometric resolution and dynamics of energy transfer between participating components. (orig.) [de

  6. Simulation of Molten Core-Concrete Interaction in oxide/metal stratified configuration with the TOLBIAC-ICB code

    Tourniaire, B.; Spindler, B.

    2005-01-01

    The frame of this work is the validation of the TOLBIAC-ICB code which is devoted to the simulation of Molten Core-Concrete Interaction (MCCI) for reactor safety analysis. Attention focuses here on the validation of TOLBIAC-ICB in configurations expected to be representative of the long term phase of MCCI i.e. during an interaction between an oxide/metal stratified corium melt and a concrete structure. Up to now the BETA tests performed at the Forschungszentrum Karlsruhe (FzK) are the only tests available to study such kind of interaction. The BETA tests are first described and the operating conditions are reminded. The TOLBIAC-ICB code is then briefly described, with emphasis on the models used for stratified configurations. The results of the simulations are discussed. A sensitivity study is also performed with the power generated in the oxide layer instead of the metal layer as in the test. This last calculation shows that the large axial ablation observed in the tests is probably due to the peculiar configuration of the test with input power in the bottom metal layer. Since in the reactor case the residual power would be mainly concentrated in the upper oxide layer, the conclusions of the BETA tests for the reactor applications, in term of axial ablation, must be derived with caution. (author)

  7. MEGAPIE, a 1 MW pilot experiment for a liquid metal spallation target

    Bauer, G.S. [Paul Scherrer Institut, Spallation Neutron Source Division, Villigen-PSI (Switzerland); Salvatores, M. [CEA Cadarache, Direction des Reacteurs Nucleaires, Saint-Paul-lez-Durance Cedex (France); Heusener, G. [Forschungszentrum Karlsruhe, Projekt Nukleare Sicherheitsforschung, Karlsruhe (Germany)

    2001-03-01

    MEGAPIE (Megawatt Pilot Target Experiment) is an initiative launched by Commissariat a l'Energie Atomique, Cadarache (France) and Forschungszentrum Karlsruhe (Germany) in collaboration with Paul Scherrer Institut (Switzerland), to demonstrate, in an international collaboration, the feasibility of a liquid lead bismuth target for spallation facilities at a beam power level of 1 MW. Such a target is under consideration for various concepts of accelerator driven systems (ADS) to be used in transmutation of nuclear waste and other applications world-wide. It also has the potential of increasing significantly the thermal neutron flux available at the spallation neutron source (SINQ) for neutron scattering. SINQ's beam power being close to 1 MW already, this facility offers a unique opportunity to realize such an experiment with a reasonably small number of new ancillary systems. The paper describes the basic features of the experiment and its boundary conditions, the technical concept of the target and underlying research carried out at participating laboratories. (author)

  8. Neutronics and thermal hydraulics coupling scheme for design improvement of liquid metal fast systems

    Sanchez-Espinoza, V.H.; Jaeger, W.; Travleev, A.; Monti, L.; Doern, R.

    2009-01-01

    Many advanced reactor concepts are nowadays under investigations within the Generation IV international initiative as well as in European research programs including subcritical and critical fast reactor systems cooled by liquid metal, gas and supercritical water. The Institute of Neutron Physics and Reactor Technology (INR) at the Forschungszentrum Karlsruhe GmbH is involved in different European projects like IP EUROTRANS, ELSY, ESFR. The main goal of these projects is, among others, to assess the technical feasibility of proposed concepts regarding safety, economics and transmutation requirements. In view of increased computer capabilities, improved computational schemes, where the neutronic and the thermal hydraulic solution is iteratively coupled, become practicable. The codes ERANOS2.1 and TRACE are being coupled to analyze fuel assembly or core designs of lead-cooled fast reactors (LFR). The neutronic solution obtained with the coupled system for a LFR fuel assembly was compared with the MCNP5 solution. It was shown that the coupled system is predicting physically sound results. The iterative coupling scheme was realized using Perlscripts and auxiliary Fortran programs to ensure that the mapping between the neutronic and the thermal hydraulic part is consistent. The coupled scheme is very flexible and appropriate for the neutron physical and thermal hydraulic investigation of fuel assemblies and of cores of lead cooled fast reactors. The developed methods and the obtained results will be presented and discussed. (author)

  9. Air oxidation of Zircaloy-4 in the 600-1000 °C temperature range: Modeling for ASTEC code application

    Coindreau, O.; Duriez, C.; Ederli, S.

    2010-10-01

    Progress in the treatment of air oxidation of zirconium in severe accident (SA) codes are required for a reliable analysis of severe accidents involving air ingress. Air oxidation of zirconium can actually lead to accelerated core degradation and increased fission product release, especially for the highly-radiotoxic ruthenium. This paper presents a model to simulate air oxidation kinetics of Zircaloy-4 in the 600-1000 °C temperature range. It is based on available experimental data, including separate-effect experiments performed at IRSN and at Forschungszentrum Karlsruhe. The kinetic transition, named "breakaway", from a diffusion-controlled regime to an accelerated oxidation is taken into account in the modeling via a critical mass gain parameter. The progressive propagation of the locally initiated breakaway is modeled by a linear increase in oxidation rate with time. Finally, when breakaway propagation is completed, the oxidation rate stabilizes and the kinetics is modeled by a linear law. This new modeling is integrated in the severe accident code ASTEC, jointly developed by IRSN and GRS. Model predictions and experimental data from thermogravimetric results show good agreement for different air flow rates and for slow temperature transient conditions.

  10. High-accuracy mass spectrometry for fundamental studies.

    Kluge, H-Jürgen

    2010-01-01

    Mass spectrometry for fundamental studies in metrology and atomic, nuclear and particle physics requires extreme sensitivity and efficiency as well as ultimate resolving power and accuracy. An overview will be given on the global status of high-accuracy mass spectrometry for fundamental physics and metrology. Three quite different examples of modern mass spectrometric experiments in physics are presented: (i) the retardation spectrometer KATRIN at the Forschungszentrum Karlsruhe, employing electrostatic filtering in combination with magnetic-adiabatic collimation-the biggest mass spectrometer for determining the smallest mass, i.e. the mass of the electron anti-neutrino, (ii) the Experimental Cooler-Storage Ring at GSI-a mass spectrometer of medium size, relative to other accelerators, for determining medium-heavy masses and (iii) the Penning trap facility, SHIPTRAP, at GSI-the smallest mass spectrometer for determining the heaviest masses, those of super-heavy elements. Finally, a short view into the future will address the GSI project HITRAP at GSI for fundamental studies with highly-charged ions.

  11. The status of beryllium research for fusion in the United States

    Longhurst, G.R.; Snead, L.L.; Abou-Sena, A.A.

    2004-01-01

    Use of beryllium in fusion reactor has been considered for neutron multiplication in breeding blankets an as an oxygen getter for plasma - facing surface. Previous beryllium research for fusion in the United States included issues of interest to fission (swelling an changes in mechanical and thermal properties) as well as interactions with plasmas and hydrogen isotopes and methods of fabrication. When the United States formally withdrew its participation in the International Experimental Reactor (ITER) program, much of this effort was terminated. The focus in the U.S. has been mainly on toxic effects of beryllium and on industrial hygiene and health-related issues. Work continued at the INEEL (Idaho National Engineering and Environmental Laboratory) and elsewhere on beryllium-containing molten salts. This activity is part of the JUPITER II Agreement. Plasma spray of ITER first wall samples at Los Alamos National Laboratory has been performed under the European Fusion Development Agreement. Effects of irradiation on beryllium structure are being studied at Oak Ridge National Laboratory. Numerical and phenomenological models are being developed and applied at the University of California Los Angels to investigate thermo-mechanical characteristics of beryllium pebble beds, similar to research being carried out at Forschungszentrum Karlsruhe and elsewhere. Additional work, not funded by the fusion program, has dealt with issues of disposal, and recycling. (author)

  12. Temperature dependence of the mechanical properties of melt-processed Dy-Ba-Cu-O bulk superconductors evaluated by three point bending tests

    Katagiri, K; Nyilas, A; Sato, T; Hatakeyama, Y; Hokari, T; Teshima, H; Iwamoto, A; Mito, T

    2006-01-01

    Dy-Ba-Cu-O bulk superconductor has an excellent capability of trapping magnetic flux and lower heat conductivity at cryogenic temperatures as compared with Y-Ba-Cu-O bulk superconductor. The Young's modulus and the bending strength in the range from room temperature to 7 K were measured by the three-point bending tests using specimens cut from a melt-processed Dy-Ba-Cu-O bulk superconductor. They were tested in a helium gas flow type cryostat at Forschungszentrum Karlsruhe and in a liquid nitrogen bath at Iwate University. The Young's modulus was calculated by either the slope of stress-strain curve or that of the load-deflection curve of the specimen. Although the bending strength measured in the two institutes coincided well, there was a significant discrepancy in the Young's modulus. The Young's modulus and bending strength increased with decrease of temperature down to 7 K. The amount of increase in the Young's modulus and the bending strength were about 32% and 36% of those at room temperature, respectively. The scatter of data for each run was significant and did not depend on temperature. The temperature dependence of the Young's modulus coincided with that in Y-Ba-Cu-O obtained by ultrasonic velocity. The temperature dependence of the Young's modulus and the bending strength was discussed from the view point of interatomic distance of the bulk crystal

  13. Investigation of the impact of fabrication methods on the microstructure features of W-components of a He-cooled divertor

    Krauss, W.; Holstein, N.; Konys, J.; Mazul, I.

    2006-01-01

    Within the EU framework of the power plant conceptual study (PPCS), a He-cooled modular divertor concept to remove the expected heat loads of up to 15 MW/m 2 is investigated at Forschungszentrum Karlsruhe. These high loads require sufficient cooling of the divertor components, which can only be obtained by an adapted design together with a close interaction with materials issues and development of manufacturing processes. Physical aspects favor tungsten as a functional and structural material. The design work performed indicates that sufficient heat removal by He requires microstructured W-surfaces in the shape of pin or slot arrays, or else a multi-jet cooling technology. In this work, manufacturing processes (e.g. EDM, laser etching, PIM, ECM) were analyzed for their applicability and cost effectiveness for shaping of microstructured W-arrays. In a second step, their impact on the microstructure and, thus, on stability and function of the parts were investigated. First test arrays were fabricated by EDM and brazed into the designed finger-like cooling structures. However, testing showed clearly that further development of the structuring processes (e.g. PIM, ECM) for W-components and of improved W-alloys are necessary

  14. CERMET fuel behavior and properties in ADS reactors

    Haas, D.; Fernandez, A.; Staicu, D.; Somers, J.; Maschek, W.; Liu, P.; Chen, X.

    2008-01-01

    Within the EUROTRANS Integrated Project, Forschungszentrum Karlsruhe (FZK) and the Institute for Transuranium Elements (ITU) are joining their efforts to study the behavior of Mo-based CERMET non-uranium fuel for the ADS. Contributions include core safety calculations, and fuel property measurements and irradiation experiments. Safety studies for optimized EFIT core designs have concluded that, for the new low power cores of EFIT with a power class of ∼400 MWth and a fuel power density of ∼250 MW/m 3 , the CERMET-loaded cores behave favorably and the design limits of the fuels were not violated. Mo-based CERMET fuel pellets and pins loaded with Pu and Am were fabricated for irradiation programmes which will start by mid-2007 in PHENIX (France) and HFR-Petten (The Netherlands). The thermal diffusivity and specific heat of the CERMET fuels (loaded with Pu and Am) were the main properties measured, and the thermal conductivity was deduced. The results were used to prepare the safety report for the irradiation experiments

  15. Homogeneous nucleation rates of nitric acid dihydrate (NAD at simulated stratospheric conditions – Part II: Modelling

    O. Möhler

    2006-01-01

    Full Text Available Activation energies ΔGact for the nucleation of nitric acid dihydrate (NAD in supercooled binary HNO3/H2O solution droplets were calculated from volume-based nucleation rate measurements using the AIDA (Aerosol, Interactions, and Dynamics in the Atmosphere aerosol chamber of Forschungszentrum Karlsruhe. The experimental conditions covered temperatures T between 192 and 197 K, NAD saturation ratios SNAD between 7 and 10, and nitric acid molar fractions of the nucleating sub-micron sized droplets between 0.26 and 0.28. Based on classical nucleation theory, a new parameterisation for ΔGact=A×(T ln SNAD−2+B is fitted to the experimental data with A=2.5×106 kcal K2 mol−1 and B=11.2−0.1(T−192 kcal mol−1. A and B were chosen to also achieve good agreement with literature data of ΔGact. The parameter A implies, for the temperature and composition range of our analysis, a mean interface tension σsl=51 cal mol−1 cm−2 between the growing NAD germ and the supercooled solution. A slight temperature dependence of the diffusion activation energy is represented by the parameter B. Investigations with a detailed microphysical process model showed that literature formulations of volume-based (Salcedo et al., 2001 and surface-based (Tabazadeh et al., 2002 nucleation rates significantly overestimate NAD formation rates when applied to the conditions of our experiments.

  16. Evaluation of ITER design criteria applied to RAFM steels. Final report tasks - TW2-TTMS-005b, D2 and TW5-TTMS-005, D8

    Sunyk, R.; Aktaa, J.

    2006-08-01

    In the first line, the aim of the activity represented in this work is an application of two advanced material models to a simulation of the test blanket module (TBM) undergoing cyclic thermal and mechanical loadings. The first model is thereby the ABAQUS standard combined non-linear isotropic-kinematic hardening model whereas the second is a viscoplastic material model considering material damage and being newly implemented as an ABAQUS user material (UMAT). Material parameters for both models are adjusted using results of isothermal tensile and cyclic experiments performed at Forschungszentrum Karlsruhe GmbH (FZK) on EUROFER 97. As is generally known, EUROFER 97 is an important blanket material for the future fusion reactor and belongs to reduced activation ferriticmartensitic steels (RAFM), which soften under cyclic loading in contrast to austenitic steels exhibiting cyclic hardening. Moreover, the work is focused on the application of some existing design rules considered for austenitic steels and further evaluation of the rules by comparison of their predictions with results of cyclic simulations using the advanced material models mentioned above. Thereby, some important allowable stress limits are calculated under consideration of the cyclic softening of RAFM. Finally, new considerations concerning a mock-up experiment allowing to verify the advanced material models used in the present work and to assess a capability of the actual TBM design are represented here. (orig.) [de

  17. Department of Cosmic Radiation Physics - Overview

    Gawin, J.

    1997-01-01

    Full text: The Department of Cosmic Ray Physics in Lodz is involved in basic research in the area of high energy physics and cosmic ray physics related to: -Studies of the asymptotic properties of hadronic interactions from the analysis of cosmic ray propagation in the atmosphere. -Studies of structure and properties of Extensive Air Showers induced by cosmic ray particles. -Search for point sources of high energy cosmic rays. -Studies of cosmic ray propagation in the Galaxy and mechanisms of particle acceleration. -Studies of the mass composition of cosmic rays in the energy range 10 15 -10 17 eV. Theoretical and experimental studies of nuclear interactions for energies exceeding those obtained by modern particle accelerators are performed employing results obtained by the Lodz Extensive Air Shower Array. The Lodz hodoscope can register electromagnetic components of cosmic ray showers in the atmosphere as well as muons at two energy thresholds. Data collected by the Lodz array are also used to study mass composition of cosmic rays in the energy range 10 15 - 10 17 eV. The Lodz group collaborates with foreign institutes and laboratories on construction and data interpretation of cosmic ray experiments. Our most important partners are: Forschungszentrum Karlsruhe (Germany), College de France, the Institute for Nuclear Studies of the Russian Academy of Sciences, the University of Durham, and the University of Perpignan. (author)

  18. Department of Cosmic Radiation Physics: Overview

    Szabelski, J.

    2000-01-01

    Full text: Department of Cosmic Ray Physics in Lodz is involved in basic research in the area of high-energy physics and cosmic ray physics related to: -Studies of asymptotic properties of hadronic interactions based on the analysis of cosmic ray propagation through the atmosphere. -Experimental and phenomenological studies of Extensive Air Showers induced by cosmic ray particles. - Search for high-energy cosmic ray point sources. - Studies of cosmic ray propagation in the Galaxy and particle acceleration mechanisms. -Studies of mass composition of cosmic rays in the energy range 10 15 -10 17 eV. Theoretical and experimental studies of Extensive Air Shower properties are performed mainly on the basis of the results obtained by the Lodz Extensive Air Shower Array. We have analysed nearly 100,000 events of energies above 10 15 eV registered in the Lodz hodoscope. We have developed a method to verify different models of cosmic ray mass composition. The Lodz group collaborates with many foreign institutes and laboratories in construction and data interpretation of cosmic ray experiments. Our most important partners are: Forschungszentrum in Karlsruhe (Germany), College de France, Institute for Nuclear Studies of the Russian Academy of Sciences and Uppsala University (Sweden). (author)

  19. Department of Cosmic Radiation Physics: Overview

    Gawin, J.

    1998-01-01

    (full text) The Department of Cosmic Ray Physics in Lodz is involved in basic research in the area of high energy physics and cosmic ray physics related to: -Studies of asymptotic properties of hadronic interactions based on the analysis of cosmic ray propagation in the atmosphere. -Studies of the structure and properties of Extensive Air Showers induced by cosmic ray particles. - Search for point sources of high energy cosmic rays. - Studies of cosmic ray propagation in the Galaxy and mechanisms of particle acceleration. - Studies of mass composition of cosmic rays in the energy range l0 15 -10 17 eV. Theoretical and experimental studies of nuclear interactions for energies exceeding those obtained by modern particle accelerators are performed based on the results obtained by the Lodz Extensive Air Shower Array. The Lodz hodoscope can register the electromagnetic component of cosmic ray showers developing in the atmosphere as well as muons of two energy thresholds. Data collected by the Lodz array are also used to study the mass composition of cosmic rays in the energy range 10 15 -10 17 eV. The Lodz group collaborates with many foreign institutes and laboratories in construction and data interpretation of cosmic ray experiments. Our most important partners are: Forschungszentrum Karlsruhe (Germany), College de' France, the Institute for Nuclear Studies of the Russian Academy of Science, the University of Perpignan (France) and Uppsala University (Sweden). (author)

  20. Self-triggering of radio signals from cosmic ray air showers

    Asch, Thomas

    2009-02-01

    LOPES STAR is a prototype detector for future experiments on the observation of radio emission of ultra high energy cosmic rays. Absolutely calibrated measurements of the electric field strength with the LOPES STAR detector were performed in coincidence with the well-established air shower detector KASCADE-Grande. The experinmental configuration allowed a simultaneous observation of east-west and north-south polarised components of the electric field per antenna used. This thesis discusses in detail the influence of background sources on the detector configuration as well as the resulting self-trigger system. The implemented trigger suppresses strong background signals from the industrial environment on the site of the Forschungszentrum Karlsruhe (rejection >99.9 %) and is the basis for a hardware self-trigger. Therefore, the system is adequate for any other detector site. Two different calibration methods are performed and cross-checked to convert the measured raw data into an electric field strength. Both methods result in the same frequency dependent calibration values within their uncertainties. Furthermore, the probable scale parameter of d 0 =(137±18) m. The comparison of selected events with Monte Carlo simulations on an event-by-event basis points out a good correspondence within the given uncertainties and confirms the geosynchrotron model. The overall angular resolution of the arrival direction results in only a few degrees. The presented methods and algorithms are developed for the trigger system and the analysis and are now standard tools for the data analysis in the LOPES collaboration. (orig.)

  1. Boiling induced mixed convection in cooling loops

    Knebel, J.U.; Janssens-Maenhout, G.; Mueller, U.

    2000-01-01

    This article describes the SUCO program performed at the Forschungszentrum Karlsruhe. The SUCO program is a three-step series of scaled model experiments investigating the possibility of a sump cooling concept for future light water reactors. In case of a core melt accident, the sump cooling concept realises a decay heat removal system that is based on passive safety features within the containment. The article gives, first, results of the experiments in the 1:20 linearly scaled SUCOS-2D test facility. The experimental results are scaled-up to the conditions in the prototype, allowing a statement with regard to the feasibility of the sump cooling concept. Second, the real height SUCOT test facility with a volume and power scale of 1:356 that is aimed at investigating the mixed single-phase and two-phase natural circulation flow in the reactor sump, together with first measurement results, are discussed. Finally, a numerical approach to model the subcooled nucleate boiling phenomena in the test facility SUCOT is presented. Physical models describing interfacial mass, momentum and-heat transfer are developed and implemented in the commercial software package CFX4.1. The models are validated for an isothermal air-water bubbly flow experiment and a subcooled boiling experiment in vertical annular water flow. (author)

  2. Safety and environmental impact of the dual coolant blanket concept. SEAL subtask 6.2, final report

    Kleefeldt, K.; Dammel, F.; Gabel, K.; Jordan, T.; Schmuck, I.

    1996-03-01

    The European Union has been engaged since 1989 in a programme to develop tritium breeding blankets for application in a fusion power reactor. There are four concepts under development, namely two of the solid breeder type and two of the liquid breeder type. At the Forschungszentrum Karlsruhe one blanket concept of each line has been pursued so far with the so-called dual coolant type representing the liquid breeder line. In the dual coolant concept the breeder material (Pb-17Li) is circulated to external heat exchangers to carry away the bulk of the generated heat and to extract the tritium. Additionally, the heavily loaded first wall is cooled by high pressure helium gas. The safety and environmental impact of the dual coolant blanket concept has been assessed as part of the blanket concept selection excercise, a European concerted action, aiming at selecting the two most promising concepts for futher development. The topics investigated are: (a) Blanket materials and toxic materials inventory, (b) energy sources for mobilisation, (c) fault tolerance, (d) tritium and activation products release, and (e) waste generation and management. No insurmountable safety problems have been identified for the dual coolant blanket. The results of the assessment are described in this report. The information collected is also intended to serve as input to the EU 'Safety and Environmental Assessment of Fusion longterm Programme' (SEAL). The unresolved issues pertaining to the dual coolant blanket which would need further investigations in future programmes are outlined herein. (orig.) [de

  3. Surface enhanced infrared spectroscopy using interacting gold nanowires

    Neubrech, Frank; Weber, Daniel; Pucci, Annemarie [Kirchhoff-Institut fuer Physik, Heidelberg (Germany); Shen, Hong [Universite Troyes, Troyes (France); Lamy de la Chapelle, Marc [Universite Paris 13, Bobigny (France)

    2009-07-01

    We performed surface enhanced infrared spectroscopy (SEIRS) of molecules adsorbed on gold nanowires using synchrotron light of the ANKA IR-beamline at the Forschungszentrum Karlsruhe (Germany). Arrays of gold nanowires with interparticle spacings down to 30nm were prepared by electron beam lithography. The interparticle distance was reduced further by wet-chemically increasing the size of the gold nanowires. The growth of the wires was proofed using IR spectroscopy as well as scanning electron microscopy. After this preparation step, appropriate arrays of nanowires with an interparticle distance down to a few nanometers were selected to demonstrate the surface enhanced infrared spectroscopy of one monolayer octadecanthiol (ODT). As know from SEIRS studies using single gold nanowires, the spectral position of the antenna-like resonance in relation to the absorption bands of ODT (2850cm-1 and 2919cm-1) is crucial for both, the lineshape of the molecular vibration and the signal enhancement. In contrast to single nanowires studies, a further increase of the enhanced signals is expected due to the interaction of the electromagnetic fields of the close-by nanowires.

  4. A review of optical measurements at the aerosol and cloud chamber AIDA

    Wagner, Robert; Linke, Claudia; Naumann, Karl-Heinz; Schnaiter, Martin; Vragel, Marlen; Gangl, Martin; Horvath, Helmuth

    2009-01-01

    This paper provides a survey of recent studies on the optical properties of aerosol and cloud particles that have been conducted at the AIDA facility of Forschungszentrum Karlsruhe (Aerosol Interactions and Dynamics in the Atmosphere). Reflecting the broad accessible temperature range of the AIDA chamber which extends from ambient temperature down to 183 K, the investigations feature a broad diversity of research topics, such as the wavelength-dependence of the specific absorption cross sections of soot and mineral dust aerosols at room temperature, depolarization and infrared extinction measurements of ice crystal clouds generated at temperatures below 235 K, and the optical properties of polar stratospheric cloud constituents whose formation was studied in chamber experiments at temperatures well below 200 K. After reviewing the AIDA research activity of the past decade and introducing the optical instrumentation of the AIDA facility, this paper presents illustrative examples of ongoing and already published work on optical measurements of soot aerosols, mineral dust particles, and ice crystal clouds.

  5. Monte Carlo calculation of the energy deposited in the KASCADE GRANDE detectors

    Mihai, Constantin

    2004-01-01

    The energy deposited by protons, electrons and positrons in the KASCADE GRANDE detectors is calculated with a simple and fast Monte Carlo method. The KASCADE GRANDE experiment (Forschungszentrum Karlsruhe, Germany), based on an array of plastic scintillation detectors, has the aim to study the energy spectrum of the primary cosmic rays around and above the 'knee' region of the spectrum. The reconstruction of the primary spectrum is achieved by comparing the data collected by the detectors with simulations of the development of the extensive air shower initiated by the primary particle combined with detailed simulations of the detector response. The simulation of the air shower development is carried out with the CORSIKA Monte Carlo code. The output file produced by CORSIKA is further processed with a program that estimates the energy deposited in the detectors by the particles of the shower. The standard method to calculate the energy deposit in the detectors is based on the Geant package from the CERN library. A new method that calculates the energy deposit by fitting the Geant based distributions with simpler functions is proposed in this work. In comparison with the method based on the Geant package this method is substantially faster. The time saving is important because the number of particles involved is large. (author)

  6. Neutron induced displacement damage in beryllium in the blanket of a (d,t)-fusion reactor

    Hermanutz, D.

    1995-09-01

    Beryllium is a favoured candidate for a neutron multiplier in solid breeder blankets of fusion reactors. This is mainly due to its low (n, 2n)-reaction threshold and because of its good thermal and mechanical properties. Its behaviour under intense neutron irradiation, however, is a crucial issue for its use in future fusion reactors. Displacement damage in beryllium so far has been calculated both with data related and methodological deficiencies. First of all, there is a need to have accurate cross-section data in order to obtain reliable spectra of primary knock-on atoms (PKA's). Furthermore, there are principal restrictions of the NRT-model in general used to calculate secondary displacements initiated by PKA's. The underlying theory of damage-energy (part of kinetic energy of PKA transferred elastically to matrix atoms) according to Lindhard is strictly valid only for medium and heavy mass ions with moderate energies in targets of the same element. In this work improved damage cross-sections and displacement rates (dpa/s) in beryllium have been calculated based on cross-section data from ENDF/B-VI (with a significantly improved (n, 2n)-evaluation) and on an appropriate treatment of damage-energy that is suitable for fusion relevant damage of light mass materials. ''This work has been performed in the framework of the Nuclear Fusion Project of the Forschungszentrum Karlsruhe and is supported by the European Communities within the European Fusion Technology Program''. (orig.)

  7. The INE-Beamline for Actinide Research at ANKA

    Brendebach, Boris; Denecke, Melissa A.; Rothe, Jörg; Dardenne, Kathy; Römer, Jürgen

    2007-02-01

    The INE-Beamline for actinide research at the synchrotron source ANKA is now fully operational. This beamline was designed, built, and commissioned by the Institut für Nukleare Entsorgung (INE) at the Forschungszentrum Karlsruhe (FZK), Germany. It is dedicated to actinide speciation investigations related to nuclear waste disposal as well as applied and basic actinide research. Experiments on radioactive samples with activities up to 106 times the limit of exemption inside a safe and flexible double containment concept are possible. The close proximity of the beamline to INE's active laboratories is unique in Europe. Currently, experiments can be performed in an X-ray energy range from around 2.15 keV (P K edge) to 24.35 keV (Pd K edge). The INE-Beamline design is optimized for spectroscopy with emphasis on surface sensitive techniques. A microfocus option is presently being installed at the INE-Beamline. Access to the INE-Beamline is possible through cooperation with INE, through the ANKA proposal system and via the European Network of Excellence for Actinide Sciences (ACTINET).

  8. Swedish-German actinide migration experiment at ÄSPÖ hard rock laboratory

    Kienzler, B.; Vejmelka, P.; Römer, J.; Fanghänel, E.; Jansson, M.; Eriksen, T. E.; Wikberg, P.

    2003-03-01

    Within the scope of a bilateral cooperation between Svensk Kärnbränslehantering (SKB) and Forschungszentrum Karlsruhe, Institut für Nukleare Entsorgung (FZK-INE), an actinide migration experiment is currently being performed at the Äspö Hard Rock Laboratory (HRL) in Sweden. This paper covers laboratory and in situ investigations on actinide migration in single-fractured granite core samples. For the in situ experiment, the CHEMLAB 2 probe developed by SKB was used. The experimental setup as well as the breakthrough of inert tracers and of the actinides Am, Np and Pu are presented. The breakthrough curves of inert tracers were analyzed to determine hydraulic properties of the fractured samples. Postmortem analyses of the solid samples were performed to characterize the flow path and the sorbed actinides. After cutting the cores, the abraded material was analyzed with respect to sorbed actinides. The slices were scanned optically to visualize the flow path. Effective volumes and inner surface areas were measured. In the experiments, only breakthrough of Np(V) was observed. In each experiment, the recovery of Np(V) was ≤40%. Breakthrough of Am(III) and Pu(IV) as well as of Np(IV) was not observed.

  9. Investigation of transient electrical, magnetic, and mechanical phenomena in large superconducting magnet coils

    Sihler, C.

    1996-07-01

    The progress in the field of technology for superconducting magnets led to the necessity of transferring existing calculation methods from electrical power engineering, modifying these tools to satisfy the boundary conditions for superconducting magnets, and also developing new calculation methods for special purposes. In this work suitable calculation methods are elaborated. Their validity and applicability is demonstrated in employing these scientific engineering tools to actual developments of the Forschungszentrum Karlsruhe. In detail this work deals with: 1. calculating eddy current and force densities in the conducting environment of a superconducting magnet or magnet system. 2. the effects of eddy current forces in experimental engineering; 3. transient effects of electrical surges acting on new coil designs; and 4. the electrical and magnetic properties of superconducting cables. Especially, the magnetic properties can lead to an inhomogeneous current distribution in the cable and, thus, to a considerable reduction of the current carrying capacity of the whole magnet. These investigations demonstrate that a detailed analysis of electrodynamic phenomena is indispensable in order to find the optimum technical way to make use of the physical potential of superconductivity. (orig./MM) [de

  10. Rupture tests with reactor pressure vessel head models

    Talja, H.; Keinaenen, H.; Hosio, E.; Pankakoski, P.H.; Rahka, K.

    2003-01-01

    In the LISSAC project (LImit Strains in Severe ACcidents), partly funded by the EC Nuclear Fission and Safety Programme within the 5th Framework programme, an extensive experimental and computational research programme is conducted to study the stress state and size dependence of ultimate failure strains. The results are aimed especially to make the assessment of severe accident cases more realistic. For the experiments in the LISSAC project a block of material of the German Biblis C reactor pressure vessel was available. As part of the project, eight reactor pressure vessel head models from this material (22 NiMoCr 3 7) were tested up to rupture at VTT. The specimens were provided by Forschungszentrum Karlsruhe (FzK). These tests were performed under quasistatic pressure load at room temperature. Two specimens sizes were tested and in half of the tests the specimens contain holes describing the control rod penetrations of an actual reactor pressure vessel head. These specimens were equipped with an aluminium liner. All six tests with the smaller specimen size were conducted successfully. In the test with the large specimen with holes, the behaviour of the aluminium liner material proved to differ from those of the smaller ones. As a consequence the experiment ended at the failure of the liner. The specimen without holes yielded results that were in very good agreement with those from the small specimens. (author)

  11. Design update, thermal and fluid dynamic analyses of the EU-HCPB TBM in vertical arrangement

    Cismondi, F.; Kecskes, S.; Ilic, M.; Legradi, G.; Kiss, B.; Bitz, O.; Dolensky, B.; Neuberger, H.; Boccaccini, L.V.; Ihli, T.

    2009-01-01

    In the frame of the activities of the EU Breeder Blanket Programme and of the Test Blanket Working Group of ITER, the Helium Cooled Pebble Bed Test Blanket Module (HCPB TBM) is developed in Forschungszentrum Karlsruhe (FZK) to investigate DEMO relevant concepts for blanket modules. The three main functions of a blanket module (removing heat, breeding tritium and shielding sensitive components from radiation) will be tested in ITER using a series of four TBMs, which are irradiated successively during different test campaigns. Each HCPB TBM will be installed, with a vertical orientation, into the vacuum vessel connected to one equatorial port. As the studies performed up to 2006 in FZK concerned a horizontal orientation of the HCPB TBM, a global review of the design is necessary to match with the new ITER specifications. A preliminary version of the new vertical design is proposed extrapolating the neutronic analysis performed for the horizontal HCPB TBM. An overview of the new HCPB TBM vertical designs, as well as the preliminary thermal and fluid dynamic analyses performed for the validation of the design, are presented in this paper. A critical review of the results obtained allows us, in the conclusion, to prepare a plan for the future detailed analyses of the vertical HCPB TBM.

  12. Experimental and numerical simulation of passive decay heat removal by sump cooling after cool melt down

    Knebel, J.U.; Kuhn, D.; Mueller, U.

    1997-01-01

    This article presents the basic physical phenomena and scaling criteria of passive decay heat removal from a large coolant pool by single-phase and two-phase natural circulation. The physical significance of the dimensionless similarity groups derived is evaluated. The above results are applied to the SUCO program that is performed at the Forschungszentrum Karlsruhe. The SUCO program is a three-step series of scaled model experiments investigating the possibility of a sump cooling concept for future light water reactors. The sump cooling concept is based on passive safety features within the containment. The work is supported by the German utilities and the Siemens AG. The article gives results of temperature and velocity measurements in the 1:20 linearly scaled SUCOS-2D test facility. The experiments are backed up by numerical calculations using the commercial software package Fluent. Finally, using the similarity analysis from above, the experimental results of the model geometry are scaled-up to the conditions in the prototype, allowing a first statement with regard to the feasibility of the sump cooling concept. 11 refs., 9 figs., 3 tabs

  13. Quasi-optical mode converter for a coaxial cavity gyrotron

    Jin, J.

    2007-03-01

    This work concentrates on the synthesis of the quasioptical mode converter for the 170 GHz, TE 34,19 -mode, 2MW, CW coaxial-cavity gyrotron at Forschungszentrum Karlsruhe (FZK). The improvement of the general method for the design of so-call dimpled-wall launcher to provide a good Gaussian mode content is described. This method is verified through the design of a launcher operating in the TE 22,6 mode at 118 GHz. A phase rule is proposed as a quality criterion for monitoring the optimization and the choices of parameters of the quasi-optical mode converter. High-order harmonics introduced to the launcher wall deformations are proposed for this gyrotron. The launcher is numerically optimized, the fields on the cut edges are suppressed. The fields in the launcher are well approximated by the waveguide modes, the radiated fields are calculated using the scalar diffraction integral. The procedure for the numerical optimization of the mirror system is improved, the tolerance conditions of the phase correcting mirrors are investigated. A conversion efficiency of 95.8% to the circular fundamental Gaussian distribution with 20mm beam waist and power transmission of 90% are achieved in the window plane using the optimized quasi-optical mode converter. The methods to ameliorate the initial conditions of the phase correcting mirrors are explored. (orig.)

  14. European development of He-cooled divertors for fusion power plants

    Norajitra, P.; Giniyatulin, R.; Kuznetsov, V.; Mazul, I.; Ovchinnikov, I.; Ihli, T.; Janeschitz, G.; Krauss, W.; Kruessmann, R.; Karditsas, P.; Maisonnier, D.; Sardain, P.; Nardi, C.; Papastergiou, S.; Pizzuto, A.

    2005-01-01

    Helium-cooled divertor concepts are considered suitable for use in fusion power plants for safety reasons, as they enable the use of a coolant compatible with any blanket concept, since water would not be acceptable e.g. in connection with ceramic breeder blankets using large amounts of beryllium. Moreover, they allow for a high coolant exit temperature for increasing the efficiency of the power conversion system. Within the framework of the European power plant conceptual study (PPCS), different helium-cooled divertor concepts based on different heat transfer mechanisms are being investigated at ENEA Frascati, Italy, and Forschungszentrum Karlsruhe, Germany. They are based on a modular design which helps reduce thermal stresses. The design goal is to withstand a high heat flux of about 10-15 MW/m 2 , a value which is considered relevant to future fusion power plants to be built after ITER. The development and optimisation of the divertor concepts require an iterative design approach with analyses, studies of materials and fabrication technologies, and the execution of experiments. These issues and the state of the art of divertor development shall be the subject of this report. (author)

  15. ESE a 2D compressible multiphase flow code developed for MFCI analysis - code validation

    Leskovar, M.; Mavko, B.

    1998-01-01

    ESE (Evaluation of Steam Explosions) is a general second order accurate two-dimensional compressible multiphase flow computer code. It has been developed to model the interaction of molten core debris with water during the first premixing stage of a steam explosion. A steam explosion is a physical event, which may occur during a severe reactor accident following core meltdown when the molten fuel comes into contact with the coolant water. Since the exchanges of mass, momentum and energy are regime dependent, different exchange laws have been incorporated in ESE for the major flow regimes. With ESE a number of premixing experiments performed at the Oxford University and at the QUEOS facility at Forschungszentrum Karlsruhe has been simulated. In these premixing experiments different jets of spheres were injected in a water poll. The ESE validation plan was carefully chosen, starting from very simple, well-defined problems, and gradually working up to more complicated ones. The results of ESE simulations, which were compared to experimental data and also to first order accurate calculations, are presented in form graphs. Most of the ESE results agree qualitatively as quantitatively reasonably well with experimental data and in general better than the results obtained with the first order accurate calculation.(author)

  16. German contributions to the CMS computing infrastructure

    Scheurer, A

    2010-01-01

    The CMS computing model anticipates various hierarchically linked tier centres to counter the challenges provided by the enormous amounts of data which will be collected by the CMS detector at the Large Hadron Collider, LHC, at CERN. During the past years, various computing exercises were performed to test the readiness of the computing infrastructure, the Grid middleware and the experiment's software for the startup of the LHC which took place in September 2008. In Germany, several tier sites are set up to allow for an efficient and reliable way to simulate possible physics processes as well as to reprocess, analyse and interpret the numerous stored collision events of the experiment. It will be shown that the German computing sites played an important role during the experiment's preparation phase and during data-taking of CMS and, therefore, scientific groups in Germany will be ready to compete for discoveries in this new era of particle physics. This presentation focuses on the German Tier-1 centre GridKa, located at Forschungszentrum Karlsruhe, the German CMS Tier-2 federation DESY/RWTH with installations at the University of Aachen and the research centre DESY. In addition, various local computing resources in Aachen, Hamburg and Karlsruhe are briefly introduced as well. It will be shown that an excellent cooperation between the different German institutions and physicists led to well established computing sites which cover all parts of the CMS computing model. Therefore, the following topics are discussed and the achieved goals and the gained knowledge are depicted: data management and distribution among the different tier sites, Grid-based Monte Carlo production at the Tier-2 as well as Grid-based and locally submitted inhomogeneous user analyses at the Tier-3s. Another important task is to ensure a proper and reliable operation 24 hours a day, especially during the time of data-taking. For this purpose, the meta-monitoring tool 'HappyFace', which was

  17. Application of high temperature superconductors for fusion

    Fietz, W.H.; Heller, R.; Schlachter, S.I.; Goldacker, W.

    2011-01-01

    The use of High Temperature Superconductor (HTS) materials in future fusion machines can increase the efficiency drastically. For ITER, W7-X and JT-60SA the economic benefit of HTS current leads was recognized after a 70 kA HTS current lead demonstrator was designed, fabricated and successfully tested by Karlsruhe Institute of Technology (KIT, which is a merge of former Forschungszentrum Karlsruhe and University of Karlsruhe). For ITER, the Chinese Domestic Agency will provide the current leads as a part of the superconducting feeder system. KIT is in charge of design, construction and test of HTS current leads for W7-X and JT-60SA. For W7-X 14 current leads with a maximum current of 18.2 kA are required that are oriented with the room temperature end at the bottom. JT60-SA will need 26 current leads (20 leads - 20 kA and 6 leads - 25.7 kA) which are mounted in vertical, normal position. These current leads are based on BiSCCO HTS superconductors, demonstrating that HTS material is now state of the art for highly efficient current leads. With respect to future fusion reactors, it would be very promising to use HTS material not only in current leads but also in coils. This would allow a large increase of efficiency if the coils could be operated at temperatures ≥65 K. With such a high temperature it would be possible to omit the radiation shield of the coils, resulting in a less complex cryostat and a size reduction of the machine. In addition less refrigeration power is needed saving investment and operating costs. However, to come to an HTS fusion coil it is necessary to develop low ac loss HTS cables for currents well above 20 kA at high fields well above 10 T. The high field rules BiSCCO superconductors out at temperatures above 50 K, but RE-123 superconductors are promising. The development of a high current, high field RE-123 HTS fusion cable will not be targeted outside fusion community and has to be in the frame of a long term development programme for

  18. Problems with the disposal of run-out high-activity fission product solution in the Hot Cells of Karlsruhe Nuclear Research Center

    Schreibmaier, J.

    1979-05-01

    During decanting of 50 l high-level radioactive waste (120 Ci/l) from a transport container about 1 l HAW leaked to the floor of the transfer chamber. The causes for the incident and the removal of the consequences are described. The costs incurred and the losses resulting from the cell facility not having been used are said to amount to 6-8 million DM. Decontamination and repair work took more than 18 months, sometimes more than 80 persons were occupied. The radiation exposure of all persons involved amounted to 80 man-rem. (HP) [de

  19. Institute of Genetics and Toxicology of Fission Products (IGT) of Karlsruhe Nuclear Research Centre. Progress report on R and D work in 1985

    1986-02-01

    The main research activities of the IGT in 1985 according to the R and D programme set up for that year have been carried out under the roof of eight different projects or programmes: Gene repair; gene regulation; biological cancerogenesis; molecular genetics of eukaryotes; radiotoxicology of actinides; biochemistry of actinides and other heavy metals; biophysics of organometallic compounds; biochemical principles of decorporation therapy. (orig./MG) [de

  20. Papers presented as part of the status report of the Nuclear Safety Research Project of the Karlsruhe Nuclear Center on 23 March 1994

    Hueper, R.

    1994-05-01

    The ten papers deal with the state of safety requirements on future LWR plants and with nuclear safety research with regard to fast reactors and future PWR plants. In particular, passive after-heat removal, core disruptive accidents, and actinide burning in fast reactors are analysed. For PWR type plants the fuel element behaviour in the event of accidents, hydrogen distribution and hydrogen fires, and the origin and effects of steam explosions on the reactor pressure vessel and the containment are examined. Core meltdown cooling systems are suggested. (DG) [de

  1. Fusion, energy of the future - we take part. The German ITER Industry Forum e.V. (dIIF) was founded in Karlsruhe

    Ebbinghaus, K.; Grill, K.D.

    2007-01-01

    In the interest of worldwide scientific and technical cooperation in implementing the ITER project, Europe was the first member to sign the ITER Agreement in September 2006. Construction and operation of ITER are to demonstrate the feasibility of the peaceful use of fusion energy. The activities of the newly founded 'German ITER Industry Forum e.V.' (dIIF) are to ensure that optimum participation allows German research and industry to contribute jointly to the continued development and construction of ITER. Opportunities and capabilities for international cooperation are to be exploited and expanded in an effort also to create jobs and adding intellectual and material value for Germany as an objective of research policy over the past few years. dIIF's work will focus on these activities and topics: - Acting as a centralized source of information and consultancy to German companies interested in ITER. - Lobbying at the locations of the future ITER experiment (Cadarache, France) and the European Agency for Contributions to ITER (Barcelona, Spain). - Establishment of an exchange for cooperation between interested suitable industries and national research establishments. Present members of dIIF are BDI (the German Federation of Industries) and firms; the Federal Ministry for Education and Research supports dIIF in the startup phase. (orig.)

  2. The determination of Pu-241 by liquid scintillation counting in gaseous effluents of an incineration facility, FERAB, and the Karlsruhe Nuclear Reprocessing Plant, WAK

    Godoy, J.M.; Schuettelkopf, H.

    1983-03-01

    Although the concentration of Pu-241 in nuclear fuel to be reprocessed is high, there are only few results published about the emission of Pu-241 with gaseous and liquid effluents. Nearly no information is available, too, about the environmental contamination of nuclear installations by Pu-241. Therefore a procedure was developed to measure Pu-241 by liquid scintillation counting. Sample preparation was performed by electroplating of plutonium on stainless steel planchets. To correct the selfabsorption the linear dependence of counting efficiency in the liquid scintillation counter and the resolution in the α-spectrometer was used. (orig./HP) [de

  3. List of reports and conference papers on the Fast Breeder Project published by the Nuclear Research Center Karlsruhe from 1972 to 1975

    Hueper, R.

    1976-12-01

    This list is a continuation of the list of publications contained in the final report on work completed by GfK during Phase IIa of the Fast Breeder Project (KFK-Ext. 25/72-1). In addition, short accounts of the results of the research work done in the framework of the Fast Breeder Project of GfK have been published in the quarterly reports KFK 1972/1 through 1975/4. These reports have not been included in the present list. (orig.) [de

  4. Programming Environments for High Level Scientific Problem Solving. IFIP WG 2.5 Working Conference 6 Held in Karlsruhe, Germany on September 23 - 27, 1991

    1991-09-27

    Springer Verlag (1989). (13] Hulshof , B.J.A. and van Hulzen, J.A.: "Automatic error cumulation control", Proceedir EUROSAM 󈨘 (J. Fitch. ed.), Springer...User’s Manual", Dept of Comp. Science. Univ. of Twente (In preparation). 268 [15] van Hulzen, J.A., Hulshof , B.J.A.. Gates, B.L. and van Heerwaarden, M.C

  5. Current development of Green IPPs: experiences, challenges, and strategies. Workshop of the EC-ASEAN Green Independent Power Producers Network, 15th of Sept., 2005 in Karlsruhe

    Rentz, Otto; Möst, Dominik; Eßer, Anke [Hrsg.

    2005-01-01

    Due to growing environmental issues, a strong political will to increase the use of renewable energy sources exists in many countries of the world. Mainly in the EU, measures to promote renewable energies have been taken. In Asia, the use of renewable energy is being promoted, too. However, policies as well as markets are still rather in the fledging stages. Therefore, a network on Green Independent Power Producers (GrIPPs) was set up, to exchange experiences between Europe and Southeast Asia...

  6. Contact arc metal cutting (CAMC), a young cutting technique has matured. Successful use under water in the demolition of the Karlsruhe multipurpose research reactor (MFZR)

    Stanke, D.; Bienia, H.; Loeb, A.; Thoma, M.; Eisenmann, B.; Prechtl, E.; Suessdorf, W.; Kremer, G.; Ruemenapp, T.

    2006-01-01

    Dismantling radiologically burdened large components is among the most complex and difficult jobs in the demolition of nuclear installations. The technologies used and their safe operation play a key role in demolition. Dismantling highly activated components as a rule requires shielding by water. As a consequence, the techniques employed must be designed for use under water. A variety of technologies are available for these applications. One established mechanical cutting method is water abrasive suspension jet cutting (WASS). Because of the small cutting nozzle employed, this highly flexible cutting technique can be used nearly anywhere together with different guiding systems. In the course of disassembly under water of the MZFR, plasma cutting has been found to be a reliable and efficient technique for remote operation. Contact arc metal cutting is a thermal cutting technique allowing all electrically conducting materials, including those with claddings, to be cut nearly irrespective of their component geometries. The methods, technology, possible uses, and practical operation of contact arc metal cutting in the demolition of the MZFR are covered in this article. (orig.)

  7. Radiation exposure of the personnel during dismantling and cutting of the primary system of the Karlsruhe Multi-purpose Research Reactor (MZFR)

    Hesse, H.; Demant, W.; Reichert, A.; Willmann, F.

    2000-10-01

    The heavy water (D 2 O) cooled and moderated pressurized water reactor MZFR with a thermal power of 200 MW will be dismantled step-by-step within the framework of sectional decommissioning licenses. The past decommissioning step (6 th sectional license) in general covered the removal of the primary systems and of all reactor support systems inside the reactor building. The measures for radiation protection during dismantling and handling of the large components of the primary system, such as the fuel element loading machine, fuel element transfer system, steam generator and pressurizer shall be pointed out. The measures taken for the reduction of the dose rate during dismantling and cutting of the components for the purpose of conditioning or unrestricted reuse at the central decontamination department (HDB) shall be described. Chemical decontamination of the primary circuit and its components, which had to be executed in order to reduce the dose rates for subsequent manual dismantling, shall be presented. The efforts undertaken for the protection of individuals in view of the difficult radiological boundary conditions (high concentrations of tritium in all systems as well as very high alpha contamination) will be explained. Moreover, dose-minimizing measures during cutting of the primary circuit and its components at HDB shall be described by the example of the cutting of a steam generator. It shall be demonstrated that cutting and dismantling of highly contaminated and activated parts with high dose rates can be executed safely in terms of both the radiation exposure of the personnel and the technical, financial and time expenditure. (orig.)

  8. Elaboration and experimental study of the Borosilicate glass GP 98/12 for the vitrification of the radioactive wastes of KfKarlsruhe Centre (R.F.A.)

    Ghezal, A.

    1987-09-01

    The transformation into a vitrified block of highly radioactive liquid wastes is actually the best solution for the storage in long run. In West Germany, the research institute in the field of nuclear energy (KfK) has been oriented in this way by developing industrial processes of vitrification and by following studies on the behaviour of the final products. For the fission products, the chosen glasses present good stability characteristics and are used as a first barrier during confinement. Our work, which is part of the research program on radioactive waste vitrification, consists of preparing borosilicate glass GP 98/12 and studying physical and chemical characteristics. We have also contributed to the development and the realization of glass blocks sampling system prepared at pilot scale

  9. Progress report on research and development work 1991 of the Institute of Genetics and Toxicology of Fissionable Materials, Karlsruhe Nuclear Research Center

    1991-03-01

    The present annual report describes the results of research work done by the Institute of Genetics and Toxicology of Fissionable Materials (IGT) in 1991. The following eight subjects were dealt with: genetic repair; genetic regulation; biological carcinogenesis; molecular genetics of eukaryontic genes; genetic mouse models for human illnesses; radiation toxicology of actinides; molecular and cellular environmental toxicology, and in vivo fractionation and speciation of actinides. (MG) [de

  10. International Annual Conference (29th) of ICT Held in Karlsruhe, Federal Republic of Germany on June 30-July 3, 1998. Energetic Materials; Production, Processing and Characterization

    1998-06-26

    QCPE 464, M. Dewar Group, University of Texas, Austin, Texas, 78712. 10. Allen F.H., Brice M.D., Cartwright B.A., Doubleday A., Higgs T., Hummelink T...steel and fusions of Fe- C-Ni. The usage of the materials smelted with addition of ultra-dispersive powders of boson carbide, vanadium carbide and

  11. Annual report 1991 on R and D work by the Institute for Materials and Solid State Research (IMF), Karlsruhe Nuclear Research Center

    1992-03-01

    The annual report summarises the activities of the IMF in the following subject areas: 1) Contributions to the PKF (fusion technology project (refewing to structural materials, superconducting magnets, blanket development); 2) PSU, project for the management of pollutants in the environment (treatment and recycling of hazardous waste); 3) solid state and materials research (high-temperature materials, ceramic materials as protective coatings, polymer materials, high-performance ceramics, high-TC superconducting materials; biomechanics, laser technology); 4) microtechnology (development and testing of compact or layered materials in microtechnology); 5) PSF project, nuclear safety, research (safety and materials aspects of fast breeder reactors, transient behaviour of fuel elements in fact breeder reactors, LWR-specific safety research, containment design concepts for the next generation of PWR-type reactors); 6) NE project, nuclear waste management (analysis of solid wastes from the dissolution of spent LWR fuels, materials testing in nitric acid). The primary reports and other publications of the Institute issued in 1991 are listed in an annex. (orig./MM) [de

  12. Safety problems encountered in construction and operation of the sodium test facilities of the Institute of Reactor Development (IRD) at the Karlsruhe Nuclear Research Center

    Schleisiek, K.

    1971-01-01

    In this report the safety aspects of the design and construction of a sodium boiling loop and a sodium tank test facility are discussed. Subsequently two experiments concerning the safety of the facilities are described: the testing of a drip basin to collect the sodium and to limit the rate of burning in the case of a leak, and the investigation of the chemical reaction of sodium with the insulating materials. Finally some general emergency procedures in the case of sodium incidents are discussed. A 16 mm-film demonstrating sodium fires and fire fighting methods will be shown. (author)

  13. Fusion, energy of the future - we take part. The German ITER Industry Forum e.V. (dIIF) was founded in Karlsruhe; Fusion, die Energie der Zukunft - wir sind dabei. Das deutsche ITER Industrie Forum e.V. (dIIF) wurde in Karlsruhe gegruendet

    Ebbinghaus, K. [Babcock Noell GmbH (Germany); Grill, K.D. [Deutsche ITER Industrie Forum e.V. (dIIF), Berlin (Germany)

    2007-08-15

    In the interest of worldwide scientific and technical cooperation in implementing the ITER project, Europe was the first member to sign the ITER Agreement in September 2006. Construction and operation of ITER are to demonstrate the feasibility of the peaceful use of fusion energy. The activities of the newly founded 'German ITER Industry Forum e.V.' (dIIF) are to ensure that optimum participation allows German research and industry to contribute jointly to the continued development and construction of ITER. Opportunities and capabilities for international cooperation are to be exploited and expanded in an effort also to create jobs and adding intellectual and material value for Germany as an objective of research policy over the past few years. dIIF's work will focus on these activities and topics: - Acting as a centralized source of information and consultancy to German companies interested in ITER. - Lobbying at the locations of the future ITER experiment (Cadarache, France) and the European Agency for Contributions to ITER (Barcelona, Spain). - Establishment of an exchange for cooperation between interested suitable industries and national research establishments. Present members of dIIF are BDI (the German Federation of Industries) and firms; the Federal Ministry for Education and Research supports dIIF in the startup phase. (orig.)

  14. HELOKA facility: thermo-hydrodynamic model and control

    Ghidersa, B.E.; Ihli, T.; Marchese, V.; Ionescu-Bujor, M.

    2007-01-01

    This paper presents the thermo-hydrodynamic model used to simulate the behaviour of the HELOKA (Helium Loop Karlsruhe) facility and describes the mechanism used to control various loop parameters. This test facility, which is under construction at the Forschungszentrum Karlsruhe (FZK), is designed for testing of various components for nuclear fusion such as the Helium-Cooled Pebble Bed blanket (HCPB) and the heliumcooled- divertor for the DEMO power reactor. Besides the individual testing of the blanket and divertor modules, the understanding of the behaviour of their cooling systems in conditions relevant for ITER operation is mandatory. An important aspect in the operation of these cooling loops is the accurate control, via feedback, of the flow parameters at the inlet of the test module. Understanding heat transfer and fluid flow phenomena during normal and transient operation of HELOKA is essential to ensure the adequacy of safety features. Systems analysis codes, such as RELAP5-3D, are suited to this task. However, the application of these models to HELOKA design must be later validated by experimental measurements, while the basic physical models have been proven for light water reactors. The control of the test section inlet parameters is one of the most important issues. In particular, the start-up phase, when the test section temperature is increased from ambient temperature up to 300 C, requires special attention. As a first step, the HELOKA open loop thermal transient was computed using the RELAP model. The data obtained have been used for the identification of the power-temperature transfer function needed to compute the parameters of the feedback controller (PID) using MATLAB and SIMULINK. An accurate control of the temperature during the start-up and flat top phases is achieved solely by controlling the heater power. The adopted solution reduces the harmonic distortions when operating at reduced power while keeping the investment cost low. This

  15. Transient dynamic finite element analysis of hydrogen distribution test chamber structure for hydrogen combustion loads

    Singh, R.K.; Redlinger, R.; Breitung, W.

    2005-09-01

    Design and analysis of blast resistant structures is an important area of safety research in nuclear, aerospace, chemical process and vehicle industries. Institute for Nuclear and Energy Technologies (IKET) of Research Centre- Karlsruhe (Forschungszentrum Karlsruhe or FZK) in Germany is pursuing active research on the entire spectrum of safety evaluation for efficient hydrogen management in case of the postulated design basis and beyond the design basis severe accidents for nuclear and non-nuclear applications. This report concentrates on the consequence analysis of hydrogen combustion accidents with emphasis on the structural safety assessment. The transient finite element simulation results obtained for 2gm, 4gm, 8gm and 16gm hydrogen combustion experiments concluded recently on the test-cell structure are described. The frequencies and damping of the test-cell observed during the hammer tests and the combustion experiments are used for the present three dimensional finite element model qualification. For the numerical transient dynamic evaluation of the test-cell structure, the pressure time history data computed with CFD code COM-3D is used for the four combustion experiments. Detail comparisons of the present numerical results for the four combustion experiments with the observed time signals are carried out to evaluate the structural connection behavior. For all the combustion experiments excellent agreement is noted for the computed accelerations and displacements at the standard transducer locations, where the measurements were made during the different combustion tests. In addition inelastic analysis is also presented for the test-cell structure to evaluate the limiting impulsive and quasi-static pressure loads. These results are used to evaluate the response of the test cell structure for the postulated over pressurization of the test-cell due to the blast load generated in case of 64 gm hydrogen ignition for which additional sets of computations were

  16. Theoretical and experimental studies of heavy liquid metal thermal hydraulics. Proceedings of a technical meeting

    2006-10-01

    Heavy Liquid Metal Thermal Hydraulics (28-31 October 2003). The TM was hosted by the Forschungszentrum Karlsruhe, Germany. The scope of the TM was to provide a global forum for information exchange on the most recent theoretical and experimental studies of HLM thermal hydraulics. The main objective of the TM was to assess the shortcomings of the present CFD codes used for HLM simulation and to identify future research needs, in both the numerical and experimental area

  17. Technology images and concepts of technology in transition. An analysis in the philosophy of technology and general technology; Technikbilder und Technikkonzepte im Wandel. Eine technikphilosophische und allgemeintechnische Analyse

    Banse, G. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (DE). Inst. fuer Technikfolgen-Abschaetzung und Systemanalyse (ITAS); Meier, B. [Potsdam Univ. (Germany). Inst. fuer Arbeitslehre/Technik; Wolffgramm, H. (eds.)

    2002-02-01

    This volume contains contributions resulting from an expert discussion on 'Technology Images and Concepts of Technology in Transition - an analysis in the philosophy of technology and general technology. This expert discussion took place on 6 October 2000 at the State Pedagogical Institute Brandenburg in Ludwigsfelde-Struveshof and was conceived and organized co-operatively by the Forschungszentrum Karlsruhe, Institute for Technology Assessment and Systems Analysis, the University of Potsdam, Institute for the Theory of Work/Technology and Professor Horst Wolffgramm, Frankfurt (Oder). It was the aim of the expert discussion to compile, compare and relate the various positions in the philosophy of technology, general technology science, the history of technology and the didactics of technology of the 'conceptualisation' of technology as a basis for generally understanding technology or for a scientifically based 'image of technology' to each other, and then to make them accessible for curricula within a framework of conceiving general technical education at all school levels. The contributions are grouped according to the two main foci of the event: On the one hand they are concerned with determining a contemporary concept of technology ('Image of technology'). One of the aims is to characterize technological change from the historical-genetic perspective and in this way to access technology as a work of mankind, as an important element of our culture. At the same time it is necessary to forecast future developments or to make future paths of development visible to enable the indication of change by basic innovations. Second, on this basis and supported by educational theory, conclusions are drawn for future-oriented technical general education for all students. The main focus in this is on the linkage between goals, content and subject-specific methods. In order to enable the determination of competence of any individual

  18. Gradient Measurements of Nitrous Acid (hono)

    Kleffmann, J.; Kurtenbach, R.; Lörzer, J.; Wiesen, P.; Kalthoff, N.; Vogel, B.; Vogel, H.

    Nitrous acid (HONO) plays an important role in photochemical air pollution due to its photodissociation by solar UV radiation into hydroxyl radicals and thus significantly enhances photooxidation processes. Furthermore, HONO is an important indoor pol- lutant, which can react with amines leading to nitrosamines, which are known to be carcinogenic. Despite its importance in atmospheric chemistry the mechanisms lead- ing to HONO formation are still not completely understood at present. Although it is commonly proposed that HONO is formed by heterogeneous processes, i.e. by the conversion of NO2 on wet surfaces, it is still under discussion whether HONO produc- tion is dominated by the surface of particles or by the ground surface. Simultaneous vertical profile measurements of HONO, the precursor NO2 and the aerosol surface area, which could answer this question are not available at present. Accordingly, in the present study night-time HONO, NO2 and particle surface area gradients in the altitude range 10-190 m were measured on the meteorological tower at the Forschungszentrum Karlsruhe/Germany using a new, very sensitive HONO in- strument (LOPAP), a commercial NOx monitor and a SMPS system. For all gradient measurements during the campaign it was observed that the [HONO]/[NO2] ratio decreased with increasing altitude. In contrast, the particle sur- face area was found to be more or less constant. Accordingly, no correlation between the [HONO]/[NO2] ratio and the particle surface area was observed showing that HONO formation was dominated by processes on ground surfaces and that signifi- cant HONO formation on particle surfaces could be excluded for the measurement site.

  19. 100G Ethernet in the wild-first experiences

    Hoeft, Bruno; Reymund, Aurelie; Stoy, Robert; Schröder, Frank; Niederberger, Ralf; Mextorf, Olaf; Werner, Sabine

    2011-01-01

    A 100 Gigabit Testbed was established in a collaboration of 6 partners. Three industry partners have contributed the fiber infrastructure, the DWDM equipment, as well as the required routers. 447 kilometer was the distance of the wide area testbed established in collaboration with the German NREN DFN between Karlsruhe Institute of Technology and Forschungszentrum Julich Before starting, DFN assured the quality of the fiber infrastructure, the operation of the DWDM systems at both locations, as well as the connection of the routers to this WAN link with a bandwidth of 100GE. 12*10GE interfaces were available at each site for connecting the local testnodes to the routers. A monitoring and measurement framework was installed for recording the most important IP network performance metrics, among them the One Way Delay (OWD) and its Variation, Packet Loss and Packet Reordering. The delay measurements were conducted between the GPS time synchronized Hades [1] measurement nodes at each location. Additionally all relevant counters at the routers have been recorded using a SNMP based Network Manangement Station and supplemented special command line interface output gathering and parsing scripts. The interfaces statistics were stored in 60 second intervals. The aim of the testbed was to demonstrate a failure-free transmission of one or more IP datastreams over 100GE during the whole period of 4 weeks.This included the evaluation of the 100 Gbit/s optical transmission system, the 100GE interfaces between the routers and the optical system, and the evaluation of a sustained 100GE transmission as well as the evaluation of the use of 100GE in a production like environment. The evaluation included a circulated (in a routing loop) tunable load between 1 and 100 Gbit/s, measurement of transmission quality of TCP and UDP datastreams between the endsystems, measurements of one way latency, a ramping up data transmission from approx. 8 Gbit/s up to 96 Gbit/s.

  20. The effect of organic coating on the heterogeneous ice nucleation efficiency of mineral dust aerosols

    Moehler, O; Benz, S; Saathoff, H; Schnaiter, M; Wagner, R [Forschungszentrum Karlsruhe, Institute for Meteorology and Climate Research, 76021 Karlsruhe (Germany); Schneider, J; Walter, S [Max Planck Institute for Chemistry, 55128 Mainz (Germany); Ebert, V; Wagner, S [University of Heidelberg, Institute for Physical Chemistry, 69120 Heidelberg (Germany)], E-mail: Ottmar.Moehler@imk.fzk.de

    2008-04-15

    The effect of organic coating on the heterogeneous ice nucleation (IN) efficiency of dust particles was investigated at simulated cirrus cloud conditions in the AIDA cloud chamber of Forschungszentrum Karlsruhe. Arizona test dust (ATD) and the clay mineral illite were used as surrogates for atmospheric dust aerosols. The dry dust samples were dispersed into a 3.7 m{sup 3} aerosol vessel and either directly transferred into the 84 m{sup 3} cloud simulation chamber or coated before with the semi-volatile products from the reaction of {alpha}-pinene with ozone in order to mimic the coating of atmospheric dust particles with secondary organic aerosol (SOA) substances. The ice-active fraction was measured in AIDA expansion cooling experiments as a function of the relative humidity with respect to ice, RHi, in the temperature range from 205 to 210 K. Almost all uncoated dust particles with diameters between 0.1 and 1.0 {mu}m acted as efficient deposition mode ice nuclei at RHi between 105 and 120%. This high ice nucleation efficiency was markedly suppressed by coating with SOA. About 20% of the ATD particles coated with a SOA mass fraction of 17 wt% were ice-active at RHi between 115 and 130%, and only 10% of the illite particles coated with an SOA mass fraction of 41 wt% were ice-active at RHi between 160 and 170%. Only a minor fraction of pure SOA particles were ice-active at RHi between 150 and 190%. Strong IN activation of SOA particles was observed only at RHi above 200%, which is clearly above water saturation at the given temperature. The IN suppression and the shift of the heterogeneous IN onset to higher RHi seem to depend on the coating thickness or the fractional surface coverage of the mineral particles. The results indicate that the heterogeneous ice nucleation potential of atmospheric mineral particles may also be suppressed if they are coated with secondary organics.

  1. The effect of organic coating on the heterogeneous ice nucleation efficiency of mineral dust aerosols

    Moehler, O; Benz, S; Saathoff, H; Schnaiter, M; Wagner, R; Schneider, J; Walter, S; Ebert, V; Wagner, S

    2008-01-01

    The effect of organic coating on the heterogeneous ice nucleation (IN) efficiency of dust particles was investigated at simulated cirrus cloud conditions in the AIDA cloud chamber of Forschungszentrum Karlsruhe. Arizona test dust (ATD) and the clay mineral illite were used as surrogates for atmospheric dust aerosols. The dry dust samples were dispersed into a 3.7 m 3 aerosol vessel and either directly transferred into the 84 m 3 cloud simulation chamber or coated before with the semi-volatile products from the reaction of α-pinene with ozone in order to mimic the coating of atmospheric dust particles with secondary organic aerosol (SOA) substances. The ice-active fraction was measured in AIDA expansion cooling experiments as a function of the relative humidity with respect to ice, RHi, in the temperature range from 205 to 210 K. Almost all uncoated dust particles with diameters between 0.1 and 1.0 μm acted as efficient deposition mode ice nuclei at RHi between 105 and 120%. This high ice nucleation efficiency was markedly suppressed by coating with SOA. About 20% of the ATD particles coated with a SOA mass fraction of 17 wt% were ice-active at RHi between 115 and 130%, and only 10% of the illite particles coated with an SOA mass fraction of 41 wt% were ice-active at RHi between 160 and 170%. Only a minor fraction of pure SOA particles were ice-active at RHi between 150 and 190%. Strong IN activation of SOA particles was observed only at RHi above 200%, which is clearly above water saturation at the given temperature. The IN suppression and the shift of the heterogeneous IN onset to higher RHi seem to depend on the coating thickness or the fractional surface coverage of the mineral particles. The results indicate that the heterogeneous ice nucleation potential of atmospheric mineral particles may also be suppressed if they are coated with secondary organics

  2. Heterogeneous ice nucleation activity of bacteria: new laboratory experiments at simulated cloud conditions

    O. Möhler

    2008-10-01

    Full Text Available The ice nucleation activities of five different Pseudomonas syringae, Pseudomonas viridiflava and Erwinia herbicola bacterial species and of Snomax™ were investigated in the temperature range between −5 and −15°C. Water suspensions of these bacteria were directly sprayed into the cloud chamber of the AIDA facility of Forschungszentrum Karlsruhe at a temperature of −5.7°C. At this temperature, about 1% of the Snomax™ cells induced immersion freezing of the spray droplets before the droplets evaporated in the cloud chamber. The living cells didn't induce any detectable immersion freezing in the spray droplets at −5.7°C. After evaporation of the spray droplets the bacterial cells remained as aerosol particles in the cloud chamber and were exposed to typical cloud formation conditions in experiments with expansion cooling to about −11°C. During these experiments, the bacterial cells first acted as cloud condensation nuclei to form cloud droplets. Then, only a minor fraction of the cells acted as heterogeneous ice nuclei either in the condensation or the immersion mode. The results indicate that the bacteria investigated in the present study are mainly ice active in the temperature range between −7 and −11°C with an ice nucleation (IN active fraction of the order of 10−4. In agreement to previous literature results, the ice nucleation efficiency of Snomax™ cells was much larger with an IN active fraction of 0.2 at temperatures around −8°C.

  3. International standard problem ISP36. Cora-W2 experiment on severe fuel damage for a Russian type PWR

    1996-01-01

    An OECD/NEA-CSNI International Standard Problem (ISP) has been performed on the experimental comparison basis of the severe fuel damage experiment CORA-W2. The out-of-pile experiment CORA-W2 was executed in February 1993 at he Forschungszentrum Karlsruhe. The objective of this experiment was the investigation of the behavior of a Russian type PWR fuel element (VVER-1000) during early core degradation. The main difference between a Western type and a Russian type PWR bundle is the B 4 C absorber rod instead of AgInCd. Measured quantities ar boundary conditions, bundle temperature, hydrogen generation and the final bundle configurations after cooldown. The ISP was conducted as a blind exercise. Boundary conditions were estimated using ATHLET-CD. Six different severe accident codes were used. The comparisons between experimental and analytical results were grouped by codes and examined separately. The thermal behavior up to significant oxidation has been predicted quite well. Larger deviations have been observed for the oxidation-induced temperature escalation, both time of onset and maximum temperature as well. The bundle behavior is greatly influenced by chemical interactions involving B 4 C absorber rod material, which failed relatively early at low temperature due to eutectic interaction between B 4 C and SS cladding as well as the SS guide tube. Regarding the complex material interaction larger differences can be recognized between calculated and measured results because of inappropriate models for material relocation and solidification processes and the lack of models describing the interactions of absorber rod materials with the fuel rods. For the total amount of H 2 generated, acceptable agreement could be achieved, if the total of oxidized zirconium was calculated correctly. The oxidation of stainless steel components and B 4 C were not treated. In general the confidence in code predictions decreases with processing core damage. (N.T.)

  4. The MEGAPIE Initiative

    Salvatores, M.; Bauer, G.S.; Heusener, G.

    2000-10-01

    MEGAPIE (Megawatt Pilot Experiment) is a joint initiative by Commissariat a l'Energie Atomique (CEA), France, Forschungszentrum Karlsruhe (FZK), Germany, and Paul Scherrer Institut (PSI), Switzerland, to design, build, operate and explore a liquid lead-bismuth spallation target for 1MW of beam power, taking advantage of the existing spallation neutron facility SINQ at PSI. Such a target based on an eutectic mixture with a melting point as low as 125 o C and a boiling point as high as 1670 o C is the preferred concept in several studies aiming at utilising accelerators to drive subcritical assemblies in order to transmute long lived nuclear waste into shorter lived isotopes in an effort to ease problems of long term storage and final disposal. MEGAPIE will be an essential step towards demonstrating the feasibility of the coupling of a high power accelerator, a spallation target and a subcritical assembly. It will specifically address one of the most critical issues, namely the behaviour of a liquid metal target under realistic operating conditions. As an intensely instrumented pilot experiment it will provide valuable data for benchmarking of frequently used computer codes and will allow to gain important experience in the safe handling of components that have been irradiated with PbBi. It will be installed at the ring cyclotron at PSI with 590 MeV proton energy and a continuous current of 1.8 mA. The basic concept of the MEGAPIE target as well as the definition of the project phases and of the supporting research and development activities at the participating laboratories are described in the present report

  5. 100G Ethernet in the wild - first experiences

    Hoeft, Bruno; Stoy, Robert; Schröder, Frank; Reymund, Aurelie; Niederberger, Ralf; Mextorf, Olaf; Werner, Sabine

    2011-12-01

    A 100 Gigabit Testbed was established in a collaboration of 6 partners. Three industry partners have contributed the fiber infrastructure, the DWDM equipment, as well as the required routers. 447 kilometer was the distance of the wide area testbed established in collaboration with the German NREN DFN between Karlsruhe Institute of Technology and Forschungszentrum Jülich Before starting, DFN assured the quality of the fiber infrastructure, the operation of the DWDM systems at both locations, as well as the connection of the routers to this WAN link with a bandwidth of 100GE. 12*10GE interfaces were available at each site for connecting the local testnodes to the routers. A monitoring and measurement framework was installed for recording the most important IP network performance metrics, among them the One Way Delay (OWD) and its Variation, Packet Loss and Packet Reordering. The delay measurements were conducted between the GPS time synchronized Hades[1]measurement nodes at each location. Additionally all relevant counters at the routers have been recorded using a SNMP based Network Manangement Station and supplemented special command line interface output gathering and parsing scripts. The interfaces statistics were stored in 60 second intervals. The aim of the testbed was to demonstrate a failure-free transmission of one or more IP datastreams over 100GE during the whole period of 4 weeks.This included the evaluation of the 100 Gbit/s optical transmission system, the 100GE interfaces between the routers and the optical system, and the evaluation of a sustained 100GE transmission as well as the evaluation of the use of 100GE in a production like environment. The evaluation included a circulated (in a routing loop) tunable load between 1 and 100 Gbit/s, measurement of transmission quality of TCP and UDP datastreams between the endsystems, measurements of one way latency, a ramping up data transmission from approx. 8 Gbit/s up to 96 Gbit/s.

  6. Department of Cosmic Ray Physics: Overview

    Szabelski, J.

    2001-01-01

    Full text: The Department of Cosmic Ray Physics in Lodz is involved in basic research in the area of high-energy physics and cosmic ray physics related to: Experimental and phenomenological studies of Extensive Air Showers induced by cosmic ray particles. Studies of ultra-high energy (above 10 19 eV) cosmic rays: determination of energy and primary particle mass composition. Studies of asymptotic properties of hadronic interactions based on the analysis of cosmic ray propagation through the atmosphere. Studies of mass composition of cosmic rays in the energy range 10 15 -10 17 eV. Registration of cosmic ray intensity variation correlated with solar activity. Theoretical and experimental studies of Extensive Air Shower properties are performed mostly based on the results obtained by the Lodz Extensive Air Shower Array. We have noticed unexplainable delayed signals registered about 500-900 microseconds after the main EAS pulse. We prepared hardware for further experimental study of this effect. In September we have started registration of 5 GeV muon flux with the underground muon telescope. We registered 3 decreases of muon intensity correlated with Forbush decreases registered at lower energies. Variations of primary cosmic ray of energies up to about 100 GeV were responsible for our registrations. These set the upper limits for geometrical size of geomagnetic disturbances in interplanetary space. In construction and data interpretation of cosmic ray experiments, the Lodz group collaborates with many foreign institutes and laboratories: Forschungszentrum in Karlsruhe (Germany), College de France, Institute for Nuclear Studies of the Russian Academy of Sciences and Uppsala University (Sweden). We have organised (together with the Physics Department of the University of Lodz) the 17 th European Cosmic Ray Symposium (24-?8 July 2000) in which about 150 physicists participated (about 100 from abroad). (author)

  7. Thermo-mechanical Modelling of Pebble Beds in Fusion Blankets and its Implementation by a Return-Mapping Algorithm

    Gan, Yixiang; Kamlah, Marc

    2008-01-01

    In this investigation, a thermo-mechanical model of pebble beds is adopted and developed based on experiments by Dr. Reimann at Forschungszentrum Karlsruhe (FZK). The framework of the present material model is composed of a non-linear elastic law, the Drucker-Prager-Cap theory, and a modified creep law. Furthermore, the volumetric inelastic strain dependent thermal conductivity of beryllium pebble beds is taken into account and full thermo-mechanical coupling is considered. Investigation showed that the Drucker-Prager-Cap model implemented in ABAQUS can not fulfill the requirements of both the prediction of large creep strains and the hardening behaviour caused by creep, which are of importance with respect to the application of pebble beds in fusion blankets. Therefore, UMAT (user defined material's mechanical behaviour) and UMATHT (user defined material's thermal behaviour) routines are used to re-implement the present thermo-mechanical model in ABAQUS. An elastic predictor radial return mapping algorithm is used to solve the non-associated plasticity iteratively, and a proper tangent stiffness matrix is obtained for cost-efficiency in the calculation. An explicit creep mechanism is adopted for the prediction of time-dependent behaviour in order to represent large creep strains in high temperature. Finally, the thermo-mechanical interactions are implemented in a UMATHT routine for the coupled analysis. The oedometric compression tests and creep tests of pebble beds at different temperatures are simulated with the help of the present UMAT and UMATHT routines, and the comparison between the simulation and the experiments is made. (authors)

  8. Safety and environmental impact of the BOT helium cooled solid breeder blanket for DEMO. SEAL subtask 6.2, final report

    Kleefeldt, K.; Dammel, F.; Gabel, K.

    1996-03-01

    The European Union has been engaged since 1989 in a programme to develop tritium breeding blankets for application in a fusion power reactor. There are four concepts under development, namely two of the solid breeder type and two of the liquid breeder type. At the Forschungszentrum Karlsruhe one blanket concept of each line has been pursued so far with the so-called breeder outside tube (BOT) type representing the solid breeder line. In the BOT concept, Li 4 SiO 4 is used as ceramic breeding material in the form of pebble beds in combination with beryllium pebbles serving as neutron multiplier. Breeder and multiplier materials are arranged in radial-toroidal layers, separated by cooling plates. The coolant is high pressure helium which is circulated in series, at first through the first wall structure and subsequently through the cooling plates. The safety and environmental impact of the BOT blanket concept has been assessed as part of the blanket concept selection exercise, a European concerted action aiming at selecting the two most promising concepts for further development. The topics investigated are: (a) Blanket materials and toxic materials inventory, (b) energy sources for mobilisation, (c) fault tolerance, (d) tritium and activation product release, and (e) waste generation. No insurmountable safety problems have been identified for the BOT concept. The results of the assessment are described in this report. The information collected is also intended to serve as input to the EU 'Safety and Environmental Assessment of Fusion long-term Programme' (SEAL). The unresolved issues pertaining to the BOT blanket which need further investigations in future programmes are outlined herein. (orig.) [de

  9. International standard problem ISP36. Cora-W2 experiment on severe fuel damage for a Russian type PWR

    NONE

    1997-12-31

    An OECD/NEA-CSNI International Standard Problem (ISP) has been performed on the experimental comparison basis of the severe fuel damage experiment CORA-W2. The out-of-pile experiment CORA-W2 was executed in February 1993 at he Forschungszentrum Karlsruhe. The objective of this experiment was the investigation of the behavior of a Russian type PWR fuel element (VVER-1000) during early core degradation. The main difference between a Western type and a Russian type PWR bundle is the B{sub 4}C absorber rod instead of AgInCd. Measured quantities ar boundary conditions, bundle temperature, hydrogen generation and the final bundle configurations after cooldown. The ISP was conducted as a blind exercise. Boundary conditions were estimated using ATHLET-CD. Six different severe accident codes were used. The comparisons between experimental and analytical results were grouped by codes and examined separately. The thermal behavior up to significant oxidation has been predicted quite well. Larger deviations have been observed for the oxidation-induced temperature escalation, both time of onset and maximum temperature as well. The bundle behavior is greatly influenced by chemical interactions involving B{sub 4}C absorber rod material, which failed relatively early at low temperature due to eutectic interaction between B{sub 4}C and SS cladding as well as the SS guide tube. Regarding the complex material interaction larger differences can be recognized between calculated and measured results because of inappropriate models for material relocation and solidification processes and the lack of models describing the interactions of absorber rod materials with the fuel rods. For the total amount of H{sub 2} generated, acceptable agreement could be achieved, if the total of oxidized zirconium was calculated correctly. The oxidation of stainless steel components and B{sub 4}C were not treated. In general the confidence in code predictions decreases with processing core damage. 36 refs.

  10. GASFLOW: A Computational Fluid Dynamics Code for Gases, Aerosols, and Combustion, Volume 2: User's Manual

    Nichols, B. D.; Mueller, C.; Necker, G. A.; Travis, J. R.; Spore, J. W.; Lam, K. L.; Royl, P.; Wilson, T. L.

    1998-10-01

    Los Alamos National Laboratory (LANL) and Forschungszentrum Karlsruhe (FzK) are developing GASFLOW, a three-dimensional (3D) fluid dynamics field code as a best-estimate tool to characterize local phenomena within a flow field. Examples of 3D phenomena include circulation patterns; flow stratification; hydrogen distribution mixing and stratification; combustion and flame propagation; effects of noncondensable gas distribution on local condensation and evaporation; and aerosol entrainment, transport, and deposition. An analysis with GASFLOW will result in a prediction of the gas composition and discrete particle distribution in space and time throughout the facility and the resulting pressure and temperature loadings on the walls and internal structures with or without combustion. A major application of GASFLOW is for predicting the transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containment and other facilities. It has been applied to situations involving transporting and distributing combustible gas mixtures. It has been used to study gas dynamic behavior in low-speed, buoyancy-driven flows, as well as sonic flows or diffusion dominated flows; and during chemically reacting flows, including deflagrations. The effects of controlling such mixtures by safety systems can be analyzed. The code version described in this manual is designated GASFLOW 2.1, which combines previous versions of the United States Nuclear Regulatory Commission code HMS (for Hydrogen Mixing Studies) and the Department of Energy and FzK versions of GASFLOW. The code was written in standard Fortran 90. This manual comprises three volumes. Volume I describes the governing physical equations and computational model. Volume II describes how to use the code to set up a model geometry, specify gas species and material properties, define initial and boundary conditions, and specify different outputs, especially graphical displays. Sample problems are included. Volume III

  11. Thermohydraulics design and thermomechanics analysis of two European breeder blanket concepts for DEMO. Pt. 1 and Pt. 2. Pt. 1: BOT helium cooled solid breeding blanket. Pt. 2: Dual coolant self-cooled liquid metal blanket

    Norajitra, P.

    1995-06-01

    Two different breeding blanket concepts are being elaborated at Forschungszentrum Karlsruhe within the framework of the DEMO breeding blanket development, the concept of a helium cooled solid breeding blanket and the concept of a self-cooled liquid metal blanket. The breeder material used in the first concept is Li 4 SiO 4 as a pebble bed arranged separate from the beryllium pebble bed, which serves as multiplier. The breeder material zone is cooled by several toroidally-radially configurated helium cooling plates which, at the same time, act as reinforcements of the blanket structures. In the liquid metal blanket concept lead-lithium is used both as the breeder material and the coolant. It flows at low velocity in poloidal direction downwards and back in the blanket front zone. In both concepts the First Wall is cooled by helium gas. This report deals with the thermohydraulics design and thermomechanics analysis of the two blanket concepts. The performance data derived from the Monte-Carlo computations serve as a basis for the design calculations. The coolant inlet and outlet temperatures are chosen with the design criteria and the economics aspects taken into account. Uniform temperature distribution in the blanket structures can be achieved by suitable branching and routing of the coolant flows which contributes to reducing decisively the thermal stress. The computations were made using the ABAQUS computer code. The results obtained of the stresses have been evaluated using the ASME code. It can be demonstrated that all maximum values of temperature and stress are below the admissible limit. (orig.) [de

  12. New developments at the INE-Beamline for actinide research at ANKA

    Dardenne, K.; Brendebach, B.; Denecke, M. A.; Liu, X.; Rothe, J.; Vitova, T.

    2009-11-01

    The INE-Beamline for actinide research at the synchrotron source ANKA is operated by the Institut für Nukleare Entsorgung (INE) at the Forschungszentrum Karlsruhe. Experiments on radioactive samples with activities up to 106 times the limit of exemption inside a safe and flexible double containment concept are possible. One great advantage of the beamline is its close proximity to INE's active laboratories with its equipment for manipulation of actinide materials and state-of-the-art spectroscopic, analytical, and microscopic instrumentation. This constellation is unique in Europe. The INE-Beamline is built primarily to serve INE in-house research associated with safe disposal of high level nuclear waste such as actinide speciation or coordination-, redox-, and geo-chemistry of actinides. A wide energy range from around 2.1 keV to 25 keV covering the K-edges from P to Pd and the L3, L2, and L1 edges for actinides from Th to Cm can be used. The INE-Beamline is optimized for X-ray absorption spectroscopy techniques (XANES/EXAFS), but x-ray fluorescence (XRF) analysis and powder diffraction (XRD) are also possible, as well as surface sensitive measurements in grazing incidence geometry (GI-XAFS). Upgrades of instrumentation and extension of experimental capabilities at the INE-Beamline are driven by user needs. Two of the recent upgrades are presented: 1) installation of a microfocus option for spatially resolved studies (μ-XRF, μ-XANES, μ-XRD) and investigations of small volumes (e.g., heterogeneous natural samples and diamond anvil high pressure cells); 2) construction, and commissioning of a high resolution x-ray emission spectrometer (HRXES); 3) availability of an electrochemical cell for investigation of redox sensitive systems.

  13. ITER toroidal field model coil (TFMC). Test and analysis summary report (testing handbook) chapter 3 TOSKA FACILITY

    Ulbricht, A.

    2001-05-01

    In the frame of a contract between the ITER (International Thermonuclear Experimental Reactor) Director and the European Home Team Director was concluded the extension of the TOSKA facility of the Forschungszentrum Karlsruhe as test bed for the ITER toroidal field model coil (TFMC), one of the 7 large research and development projects of the ITER EDA (Engineering Design Activity). The report describes the work and development, which were performed together with industry to extend the existing components and add new components. In this frame a new 2 kW refrigerator was added to the TOSKA facility including the cold lines to the Helium dewar in the TOSKA experimental area. The measuring and control system as well as data acquisition was renewed according to the state-of-the-art. Two power supplies (30 kA, 50 kA) were switched in parallel across an Al bus bar system and combined with an 80 kA dump circuit. For the test of the TFMC in the background field of the EURATOM LCT coil a new 20 kA power supply was taken into operation with the existing 20 kA discharge circuit. Two forced flow cooled 80 kA current leads for the TFMC were developed. The total lifting capacity for loads in the TOSKA building was increased by an ordered new 80 t crane with a suitable cross head (125 t lifting capacity +5 t net mass) to 130 t for assembling and installation of the test arrangement. Numerous pre-tests and development and adaptation work was required to make the components suitable for application. The 1.8 K test of the EURATOM LCT coil and the test of the W 7-X prototype coil count to these tests as overall pre-tests. (orig.)

  14. CFD studies on thermal hydraulics of spallation targets

    Tak, N.I.; Batta, A.; Cheng, X.

    2005-01-01

    Full text of publication follows: Due to the fast advances in computer hardware as well as software in recent years, more and more interests have been aroused to use computational fluid dynamics (CFD) technology in nuclear engineering and designs. During recent many years, Forschungszentrum Karlsruhe (FZK) has been actively involved in the thermal hydraulic analysis and design of spallation targets. To understand the thermal hydraulic behaviors of spallation targets very detailed simulations are necessary because of their complex geometries, complicated boundary conditions such as spallation heat distributions, and very strict design limits. A CFD simulation is believed to be the best for this purpose even though the validation of CFD codes are not perfectly completed yet in specific topics like liquid metal heat transfer. The research activities on three spallation targets (i.e., MEGAPIE, TRADE, and XADS targets) are currently very active in Europe in order to consolidate the European ADS road-map. In the thermal hydraulics point of view, two kinds of the research activities, i.e., (1) numerical design and (2) experimental work, are required to achieve the objectives of these targets. It should be noted that CFD studies play important role on both kinds of two activities. A preliminary design of a target can be achieved by sophisticated CFD analysis and pre-and-post analyses of an experimental work using a CFD code help the design of the test section of the experiment as well as the analysis of the experimental results. The present paper gives an overview about the recent CFD studies relating to thermal hydraulics of the spallation targets recently involved in FZK. It covers numerical design studies as well as CFD studies to support experimental works. The CFX code has been adopted for the studies. Main recent results for the selected examples performed by FZK are presented and discussed with their specific lessons learned. (authors)

  15. Investigations on flow reversal in stratified horizontal flow

    Staebler, T.; Meyer, L.; Schulenberg, T.; Laurien, E.

    2005-01-01

    The phenomena of flow reversal in stratified flows are investigated in a horizontal channel with application to the Emergency Core Cooling System (ECCS) in Pressurized Water Reactors (PWR). In case of a Loss-of-Coolant-Accident (LOCA), coolant can be injected through a secondary pipe within the feeding line of the primary circuit, the so called hot leg, counter-currently to the steam flow. It is essential that the coolant reaches the reactor core to prevent overheating. Due to high temperatures in such accident scenarios, steam is generated in the core, which escapes from the reactor vessel through the hot leg. In case of sufficiently high steam flow rates, only a reduced amount of coolant or even no coolant will be delivered to the reactor core. The WENKA test facility at the Institute for Nuclear and Energy Technologies (IKET) at Forschungszentrum Karlsruhe is capable to investigate the fluid dynamics of two-phase flows in such scenarios. Water and air flow counter-currently in a horizontal channel made of clear acrylic glass to allow full optical access. Flow rates of water and air can be varied independently within a wide range. Once flow reversal sets in, a strong hysteresis effect must be taken into account. This was quantified during the present investigations. Local experimental data are needed to expand appropriate models on flow reversal in horizontal two-phase flow and to include them into numerical codes. Investigations are carried out by means of Particle Image Velocimetry (PIV) to obtain local flow velocities without disturbing the flow. Due to the wavy character of the flow, strong reflections at the interfacial area must be taken into account. Using fluorescent particles and an optical filter allows eliminating the reflections and recording only the signals of the particles. The challenges in conducting local investigations in stratified wavy flows by applying optical measurement techniques are discussed. Results are presented and discussed allowing

  16. Simulation of the QUENCH-06 experiment with MELCOR 1.8.5

    Stanojevic, M.; Leskovar, M.

    2001-01-01

    The MELCOR 1.8.5 code input model and simulation results of the OECD/NEA international standard problem No. 45 (ISP-45) are presented. ISP-45 was performed as QUENCH-06 experiment at Forschungszentrum Karlsruhe. The objectives of the QUENCH program are the analysis of the heat-up, oxidation and delayed reflood phases of a PWR type fuel rod bundle in the QUENCH facility and investigation of the thermal, mechanical, physical and chemical behavior of fuel rod claddings under transient cool-down conditions. The objectives of the OECD/NEA ISP program are the extension of the reflood database to identify key phenomena occurring during accident management measure procedures and code validation, i.e., reliability and accuracy of severe accident codes especially during the quench phase. The QUENCH test bundle is made up of 21 fuel rod simulators approximately 2.5 m long. The Zircaloy-4 rod cladding is identical to that used in pressurized water reactors with respect to material and dimensions. The bundle is heated electrically. The QUENCH-06 experiment had three phases: the pre-oxidation phase, the power transient phase and the reflood-quench phase. According to the ISP-45 specification, the MELCOR 1.8.5 simulation includes the events from the beginning of the pre-oxidation phase until the end of the reflood-quench phase and shut-off of electric power, steam and cooling water. Calculated results are discussed with respect to accuracy, plausibility and completeness. Shortcomings and limitations of the input model are described.(author)

  17. Program and Abstracts of the International Symposium on Detection of Subsurface Flow Phenomena by Self-Potential/Geoelectrical and Thermical Methods Held in Karlsruhe, Federal Republic of Germany on March 14-18, 1988

    1988-03-18

    The tests were carried out at Le Mayet-de-Montagne (Allier). This test site is used by I.N.A.G. (Institut National d’Astronomie et de Geophysique ...study. Dep. Geophysique , Bureau de Recherches Geologiques et Minieres, B.P. 6009, 45060 Orleans Cedex 2, France 41 - THE USE OF INFRARED THERMOGRAPHY

  18. Review on transactinium isotope build-up and decay in reactor fuel and related sensitivities to cross section changes and results and main conclusions of the IAEA-Advisory Group Meeting on Transactinium Nuclear Data, held at Karlsruhe, November 1975

    Kuesters, H.; Lalovic, M.

    1976-04-01

    In this report a review is given on the actinium isotope build-up and decay in LWRs, LMFBRs and HTRs. The dependence of the corresponding physical aspects on reactor type, fuel cycle strategy, calculational methods and cross section uncertainties is discussed. Results from postirradiation analyses and from integral experiments in fast zero power assemblies are compared with theoretical predictions. Some sensitivity studies about the influence of actinium nuclear data uncertainties on the isotopic concentration, decay heat, and the radiation out-put in fuel and waste are presented. In a second part, the main results of the IAEA-Advisory Group Meeting on Transactinium Nuclear Data are summarized and discussed. (orig.) [de

  19. Research on aerosol formation, aerosol behaviour, aerosol filtration, aerosol measurement techniques and sodium fires at the Laboratory for Aerosol Physics and Filter Technology at the Nuclear Research Center Karlsruhe

    Jordan, S; Schikarski, W; Schoeck, W [Gesellschaft fuer Kernforschung mbH, Karlsruhe (Germany)

    1977-01-01

    The behaviour of aerosols in LMFBR plant systems is of great importance for a number of problems, both normal operational and accident kind. This paper covers the following: aerosol modelling for LMFBR containment systems; aerosol size spectrometry by laser light scattering; experimental facilities and experimental results concerned with aerosol release under accident conditions; filtration of sodium oxide aerosols by multilayer sand bed filters.

  20. Cost/effectiveness aspects of road lighting : contribution to CIE TC 4.6 Symposium on Measures of Road Lighting Effectiveness, Karlsruhe, 5-6 July, 1977. Session II - Road lighting and accidents.

    Flury, F.C.

    1977-01-01

    The common method to determine the effect of road lighting on traffic safety, is to compare accident numbers during daylight and darkness, before and after the measure is taken. This approach ignores the possibility of increased risk of collisions with road side obstacles due to the erection of

  1. Chemical operational experience with the water/steam-circuit at KNK II; Presentation at the meeting on Experience exchange on operational experience of fast breeder reactors, Karlsruhe/Bensberg/Kalkar, June 18. - 22. 1990

    Grumer, U.

    1990-06-01

    The availability of sodium cooled reactors depends essentially from the safety and reliability of the sodium heated steam generator. The transition from experimental plants with 12-20 MW electrical power to larger plants with 600 MW (BN-600) or 1200 MW (Superphenix) required the change from modular components to larger and compact steam generators with up to 800 MW. Defects of these large components cause extreme losses in availability of the plant and have to be avoided. In view of this request, a comprehensive test program has been performed at KNK II in addition to the normal control of the water/steam-circuit to compile all operational data on the water and steam side of the sodium heated steam generator. This paper describes the plant and the water/steam-circuit with its mode of operation. The experience with the surveillance and different methods of the conditioning are discussed in detail in this presentation

  2. Consoil '98 ; 6th international FZK/TNO conference on contaminated soil, organized by Research Centre Karlsruhe (KZK, D), TNO, in cooperation with Scottish enterprise, May 17-21, 1998, EICC Edinburgh; vol. 1 en 2.

    Harder, W.; Ahrendt, F.; Hart, I.

    1998-01-01

    These volumes present the proceedings of ConSoil '98, the sixth international FZK/TNO conference on contaminated soil. This series of conferences focuses on policies, research and development, regulation, practical implementation and experience related to contaminated sites. Legal, financial and

  3. Consoil 2000 : 7th international FZK/TNO conference on contaminated soil, organized by Research Centre Karlsruhe (KZK, D), TNO, in cooperation with UFZ Leipzig, 18-22 Sept 2000. Vol. 1 en 2

    2000-01-01

    These volumes present the proceedings of ConSoil 2000, the 7th international FZK/TNO conference on contaminated soil (in cooperation with UFZ Leipzig-Halle). This series of conferences focuses on policies, research and development, regulations, practical implementation and experiences related to

  4. Removing of the fuel element storage basin by explosive technique in the course of decommissioning of the Nuclear research reactor FR 2 in the research center Karlsruhe. Permission and technical execution

    Jehle, P.; Freund, H.U.

    1999-01-01

    The fuel element storage basin was removed by explosive technique in the course of the decommissioning of the nuclear research reactor FR 2. This basin consisted of 6.800 tons of heavily reinforced concrete with 25 tons of stainless steel lining. The reactor building including residual radioactive inventory was constructionally connected to the basin and had to stay undamaged. For this reason and due to the fact that the storage basin as operational part of the nuclear facility was subject to the German nuclear law the dismantling had to follow stringent licensing and control requirements. Special restrictions concerned the tolerable reactor building vibrations and the direct blast loadings which could affect the structural integrity of the building enclosing the basin. The explosive dismantling operations which also included the final removal of the building foundation were successfully performed in 90 separate blasts employing 490 kg of commercial explosives. (orig.) [de

  5. Research on aerosol formation, aerosol behaviour, aerosol filtration, aerosol measurement techniques and sodium fires at the Laboratory for Aerosol Physics and Filter Technology at the Nuclear Research Center Karlsruhe

    Jordan, S.; Schikarski, W.; Schoeck, W.

    1977-01-01

    The behaviour of aerosols in LMFBR plant systems is of great importance for a number of problems, both normal operational and accident kind. This paper covers the following: aerosol modelling for LMFBR containment systems; aerosol size spectrometry by laser light scattering; experimental facilities and experimental results concerned with aerosol release under accident conditions; filtration of sodium oxide aerosols by multilayer sand bed filters

  6. Association EURATOM-FZJ. Annual progress report 2012. SC-FZJ 90(13)/4.1.2

    2012-01-01

    The Helmholtz Association's (HGF) fusion activities are in line with the European fusion re-search programme. The following Helmholtz Centres are involved: Max Planck Institute of Plasma Physics (IPP, Garching and Greifswald), Karlsruhe Institute of Technology (KIT), and Forschungszentrum Juelich (FZJ). This report presents results having been achieved by FZJ in the year 2012. Forschungszentrum Juelich as a EURATOM Association coordinates its fusion research activities within the Nuclear Fusion Project (KFS). The programme is based on several institutes and is well embedded into the European fusion research structure. The major part of the Juelich research activities is located within the Institute of Energy and Climate Research (IEK). This is organized along a number of institute parts, among which fusion research is concentrated within IEK-4 Plasma Physics and IEK-2 Microstructure and Properties of Materials. The IEK-4 Plasma Physics has the largest share of scientific staff in physics and technology for fusion, operates the TEXTOR tokamak, performs scientific work on JET and DIII-D, supports the Wendelstein 7-X construction and takes up significant projects related to the development of ITER. With the recent appointment of a new second director at IEK-4 (Prof. Linsmeier) it is intended to enhance the materials science expertise within the Juelich fusion programme and in particular in IEK-4: This will complement the activities in IEK-2, which operates the high heat flux test facilities JUDITH 1 and 2. They are installed inside a Hot Cell and in a controlled area which is licensed to operate with toxic and radiating materials. The Central Technology Division (ZEA1) provides engineering expertise and specialised workshop capacities. The Juelich Supercomputing Centre (JSC) operates various types of super-computer systems, among which one device (HPC-FF) is dedicated exclusively to fusion research within EFDA. The Association EURATOM-FZJ has very close contacts

  7. Association EURATOM-FZJ. Annual progress report 2013. SC-FZJ-92-(14)-4.1.3

    2013-01-01

    The Helmholtz Association's (HGF) fusion activities are in line with the European fusion re-search programme. The following Helmholtz Centres are involved: Max Planck Institute of Plasma Physics (IPP, Garching and Greifswald), Karlsruhe Institute of Technology (KIT), and Forschungszentrum Juelich (FZJ). This report presents results having been achieved by FZJ during the final year of the Association (2013). Forschungszentrum Juelich coordinates its fusion research activities within several institutes and is well embedded into the European fusion research structures, the work programme of which is oriented along the European Road Map for the Realization of Fusion Electricity. The major part of the Juelich research activities is located within the Institute of Energy and Climate Research (IEK). This is organized along a number of institute parts, among which fusion research is concentrated within IEK-Plasma Physics and IEK-Microstructure and Properties of Materials. The IEK-Plasma Physics has the largest share of scientific staff in physics and technology for fusion, operated the TEXTOR tokamak, performs scientific work on JET and DIII-D, supports the Wendelstein 7-X construction and takes up significant projects related to the development of ITER. The appointment in 2012 of a new second director at IEK-4 (Prof. Linsmeier) strengthens in particular the materials science expertise within the Juelich fusion programme. This will complement the activities which are based on the operation of the high heat flux test facilities JUDITH 1 and 2. They are installed inside a Hot Cell and in a controlled area which are licensed for operating with toxic and radiating materials. The Association EURATOM-FZJ has very close contacts to the neighbouring EURATOM associations in Belgium and The Netherlands. In 1996 together they have founded the Trilateral Euregio Cluster (TEC) which provides a clustering of resources in order to perform a co-ordinated R and D programme, to operate

  8. Association EURATOM-FZJ. Annual progress report 2013. SC-FZJ-92-(14)-4.1.3

    NONE

    2013-07-01

    The Helmholtz Association's (HGF) fusion activities are in line with the European fusion re-search programme. The following Helmholtz Centres are involved: Max Planck Institute of Plasma Physics (IPP, Garching and Greifswald), Karlsruhe Institute of Technology (KIT), and Forschungszentrum Juelich (FZJ). This report presents results having been achieved by FZJ during the final year of the Association (2013). Forschungszentrum Juelich coordinates its fusion research activities within several institutes and is well embedded into the European fusion research structures, the work programme of which is oriented along the European Road Map for the Realization of Fusion Electricity. The major part of the Juelich research activities is located within the Institute of Energy and Climate Research (IEK). This is organized along a number of institute parts, among which fusion research is concentrated within IEK-Plasma Physics and IEK-Microstructure and Properties of Materials. The IEK-Plasma Physics has the largest share of scientific staff in physics and technology for fusion, operated the TEXTOR tokamak, performs scientific work on JET and DIII-D, supports the Wendelstein 7-X construction and takes up significant projects related to the development of ITER. The appointment in 2012 of a new second director at IEK-4 (Prof. Linsmeier) strengthens in particular the materials science expertise within the Juelich fusion programme. This will complement the activities which are based on the operation of the high heat flux test facilities JUDITH 1 and 2. They are installed inside a Hot Cell and in a controlled area which are licensed for operating with toxic and radiating materials. The Association EURATOM-FZJ has very close contacts to the neighbouring EURATOM associations in Belgium and The Netherlands. In 1996 together they have founded the Trilateral Euregio Cluster (TEC) which provides a clustering of resources in order to perform a co-ordinated R and D programme, to operate

  9. Nuclear safety research in HGF 2012

    Anon.

    2013-01-01

    Nuclear Competence Association. The Forschungszentrum Juelich GmbH, HZDR Helmholtz-Zentrum Dresden-Rossendorf and the KIT Karlsruhe Institute of Technology are involved in the Nuclear Safety Research Program within the Helmholtz Association. The work and results in 2012 are presented. (orig.)

  10. He-cooled divertor for DEMO. Fabrication technology for tungsten cooling fingers

    Reiser, J.; Norajitra, P.; Widak, V.; Krauss, W. [Forschungszentrum Karlsruhe GmbH (Germany)

    2008-07-01

    A modular helium-cooled divertor design based on the multi-jet impingement concept (HEMJ) has been developed for the ''post-ITER'' demonstration reactor (DEMO) at the Forschungszentrum Karlsruhe [1, 2]. The main function of the divertor is to keep the plasma free from impurities by catching particles, such as fusion ash and eroded particles from the first wall. From the divertor surface, a maximum heat load of 10 MW/m{sup 2} at least has to be removed. The whole divertor is split up into a number of cassettes (48 according to the latest design studies [3]). Each cassette is cooled separately. The target plates are provided with several cooling fingers to keep the thermal stresses low. Each cooling finger consists of a tungsten tile which is brazed to a thimble-like cap made of a tungsten alloy W-1%La2O3 (WL10) underneath. The thimble has to be connected to the ODS EUROFER steel structure, which is accomplished by brazing again. The tungsten/tungsten brazing is exposed to 1200 C operation temperature while the tungsten/steel brazing joint must withstand 700 C operating temperature. Cooling of the finger is achieved by multi-jet impingement with helium. The inlet temperature of helium is 600 C and rises up to 700 C at the outlet. With this kind of cooling, a mean heat transfer coefficient of 35.000 W/(m{sup 2*}K) can be reached. This compact report will focus on the manufacturing of such a cooling finger unit at FZK. It will cover the machining of the tungsten tile as well as of the thimble and, the brazing of the parts. The major aim of this activity is, on the one hand, to obtain functioning mock-ups with high quality and high reliability, in particular in terms of minimising the surface roughness, cracks, and micro-cracks. On the other hand, effort should also be laid on realising the mass production from economic point of view. (orig.)

  11. Neutronics Experiment on A HCPB Breeder Blanket Mock-Up

    Paola Batistoni, P.; Angelone, M.; Bettinali, L.

    2006-01-01

    A neutronics experiment has been performed in the frame of European Fusion Technology Program on a mock-up of the EU Test Blanket Module (TBM), Helium Cooled Pebble Bed (HCPB) concept, with the objective to validate the capability of nuclear data to predict nuclear responses, such as the tritium production rate (TPR), with qualified uncertainties. The experiment has been carried out at the FNG 14-MeV neutron source in collaboration between ENEA, Technische Universitaet Dresden, Forschungszentrum Karlsruhe, J. Stefan Institute Ljubljana and with the participation of JAEA. The mock-up, designed in such a way to replicate all relevant nuclear features of the TBM-HCPB, consisted of a steel box containing beryllium block and two intermediate steel cassettes, filled with of Li 2 CO 3 powder, replicating the breeder insert main characteristics: radial thickness, distance between ceramic layers, thickness of ceramic layers and of steel walls. In the experiment, the TPR has been measured using Li 2 CO 3 pellets at various depths at two symmetrical positions at each depth, one in the upper and one in the lower cassette. Twelve pellets were used at each position to determine the TPR profile through the cassette. Three independent measurements were performed by ENEA, TUD/VKTA and JAEA. The neutron flux in the beryllium layer was measured as well using activation foils. The measured tritium production in the TBM (E) was compared with the same quantity (C) calculated by the MCNP.4c using a very detailed model of the experimental set up, and using neutron cross sections from the European Fusion File (EFF ver.3.1) and from the Fusion Evaluated Nuclear Data Library (FENDL ver. 2.1, ITER reference neutron library). C/E ratios were obtained with a total uncertainty on the C/E comparison less than 9% (2 s). A sensitivity and uncertainty analysis has also been performed to evaluate the calculation uncertainty due to the uncertainty on neutron cross sections. The results of such

  12. Boomerang - the Australian light source

    Boldeman, J.W.; Garrett, R.F.

    2000-01-01

    Full text: The Australian Synchrotron Research Program (ASRP) was one of seven major national research facilities funded by the Federal Government in December 1995. The program provides guaranteed access and travel funds for Australian scientists to conduct synchrotron radiation-based research at two overseas facilities - the Photon Factory at Tsukuba in Japan and the Advanced Photon Source at the Argonne National Laboratory in the US. The Federal Government also provided funding of $100K to carry out a Feasibility Study for an Australian-based facility. This has been completed and included a mission to a number of laboratories overseas that were or had recently constructed a facility that could be considered for Australia. Following the mission, consensus was achieved within the community for the specifications of a proposed Australian facility. The proposed facility, Boomerang, has an energy of 3 GeV, an emittance of 16 nm rad and will be equipped in the first phase with 9 instrument stations. Boomerang will be competitive in performance with other facilities currently under construction overseas. A detailed proposal has been submitted to the Federal Government for funding. No site has been specified in the proposal. The proposal was prepared within the Australian Synchrotron Research Program (ASRP) following extensive consultation with industrial and scientific groups in all Australian states. Valuable contributions have been made by members of all the committees of the ASRP, the Australian synchrotron research community that works through the ASRP and the National Synchrotron Steering Committee. Important contributions have also been made by many industrial groups including consortia in Victoria, Queensland and New South Wales. The input from the ANKA staff at Forschungszentrum Karlsruhe and, in particular. Professor Einfeld has been a critical component. The estimated capital cost of a no frills laboratory has been estimated to be $100M in 1999 dollars. The

  13. Study on partitioning and transmutation (P and T) of high-level waste. Status of R and D. Final report

    Merk, Bruno; Glivici-Cotruta, Varvara

    2014-01-01

    The main project, where this sub project contributed to, has been structured into two modules: module A (funded by the federal ministry of economics, managed by KIT) and module B (funded by the federal ministry of education and research, managed by acatech). Partners in module A were DBE TECHNOLOGY GmbH, the Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), the Helmholtz-Zentrum Dresden-Rossendorf (HZDR), the Karlsruher Institute of Technology (KIT) and the Rheinisch-Westfaelische Technische Hochschule (RWTH) Aachen, in co-operation with the Forschungszentrum Juelich (FZJ). Modul B has been executed by the Zentrum fuer Interdisziplinaere Risiko- und Innovationsforschung der Universitaet Stuttgart (ZIRIUS). The overall coordination has been carried out by the Deutsche Akademie der Technikwissenschaften (acatech). The social implications have been evaluated in module B based on the analysis of the scientific and technological aspects in module A. Recommendations for communication and actions to be taken for the future positioning of P and T have been developed. In the project part, coordinated by HZDR - status of R and D - an overview on the whole topic P and T is given. The topic is opened by a short description of reactor systems possible for transmutation. In the following the R and D status of separation technologies, safety technology, accelerator technology, liquid metal technology, spallation target development, transmutation fuel and structural material development, as well as waste conditioning is described. The topic is completed by the specifics of transmutation systems, the basic physics and core designs, the reactor physics, the simulation tools and the development of Safety Approaches. Additionally, the status of existing irradiation facilities with fast neutron spectrum is described. Based on the current R and D status, the research and technology gaps in the topics: separation and conditioning, accelerator and spallation target, and reactor

  14. Investigation of an overheated PWR-type fuel rod simulator bundle cooled down by steam. Pt. 1: experimental and calculational results of the QUENCH-04 test. Pt. 2: application of the SVECHA/QUENCH code to the analysis of the QUENCH-01 and QUENCH-04 bundle tests

    Sepold, L.; Hofmann, P.; Homann, C.

    2002-04-01

    The QUENCH experiments are to investigate the hydrogen source term that results from the water injection into an uncovered core of a light-water reactor (LWR). The test bundle is made of 21 fuel rod simulators with a length of approximately 2.5 m. 20 fuel rod simulators are heated over a length of 1024 mm, the one unheated fuel rod simulator is located in the center of the test bundle. Heating is carried out electrically using 6-mm-diameter tungsten heating elements installed in the center of the rods and surrounded by annular ZrO 2 pellets. The rod cladding is identical to that used in LWRs: Zircaloy-4, 10.75 mm outside diameter, 0.725 mm wall thickness. The test bundle is instrumented with thermocouples attached to the cladding and the shroud at 17 different elevations with an axial distance between the thermocouples of 100 mm. During the entire test up to the cooldown phase, superheated steam together with the argon as carrier gas enters the test bundle at the bottom end and leaves the test section at the top together with the hydrogen that is produced in the zirconium-steam reaction. The hydrogen is analyzed by three different instruments: two mass spectrometers and a ''Caldos 7 G'' hydrogen measuring device (based on the principle of heat conductivity). Part I of this report describes the results of test QUENCH-04 performed in the QUENCH test facility at the Forschungszentrum Karlsruhe on June 30, 1999. The objective of the experiment QUENCH-04 was to investigate the reaction of the non-preoxidized rod cladding on cooldown by steam rather than quenching by water. Part II of the present report deals with the results of the SVECHA/QUENCH (S/Q) code application to the FZK QUENCH bundle tests. The adaptation of the S/Q code to such kind of calculations is described. The numerical procedure of the recalculation of the temperature test data, and the preparation for the S/Q code input is presented. In particular, the results of the QUENCH-01 and QUENCH-04 test

  15. Department of Cosmic Ray Physics; Overview

    Szabelski, J.

    2003-01-01

    Full text: Department of Cosmic Ray Physics in Lodz is involved in basic research in the area of high-energy physics and cosmic ray physics related to: - Experimental and phenomenological studies of Extensive Air Showers induced by cosmic ray particles. - Studies of ultra-high energy (above 10 19 eV) cosmic rays: determination of energy spectrum and mass composition of primary particles - Studies of asymptotic properties of hadronic interactions based on the analysis of cosmic ray propagation through the atmosphere. - Studies of mass composition of cosmic rays in the energy range 10 15 - 10 17 eV. - Registration of cosmic ray intensity variation correlated with solar activity. Theoretical and experimental studies of Extensive Air Shower properties are performed mostly basing on the results obtained by the Lodz Extensive Air Shower Array. We have noticed unexplainable delayed signals registered about 500-900 microseconds after the main EAS pulse. Neutron transport simulations were performed in collaboration with JINR in Dubna. We prepared hardware for further experimental study of this effect. Continuous registrations of 5 GeV muon flux with the underground muon telescope have been carried on over the year 2001. We have detected several changes of muon intensity correlated with Forbush decreases registered at lower energies. We have also started registrations of muon counting rate in the on-surface scintillation detectors. These measurements will be included to the analysis of the disturbed energy spectrum of primary cosmic rays and its dependence on interplanetary disturbances related to the solar activity. In construction and data interpretation of cosmic ray experiments the Lodz group collaborates with many foreign institutes and laboratories: Forschungszentrum in Karlsruhe (Germany), College de France, Institute for Nuclear Studies of the Russian Academy of Sciences, JINR in Dubna (Russia), Uppsala University (Sweden) and DESY (Germany). We have prepared a

  16. Department of Cosmic Ray Physics: Overview

    Szabelski, J.

    2002-01-01

    Full text:The Department of Cosmic Ray Physics in Lodz is involved in basic research in the area of high-energy physics and cosmic ray physics related to: * Experimental and phenomenological studies of Extensive Air Showers induced by cosmic ray particles. * Studies of ultra-high energy (above 10 19 eV) cosmic rays: determination of energy spectrum and mass composition of primary particles * Studies of asymptotic properties of hadronic interactions based on the analysis of cosmic ray propagation through the atmosphere. * Studies of mass composition of cosmic rays in the energy range 10 15 -10 17 eV. * Registration of cosmic ray intensity variation correlated with solar activity. Theoretical and experimental studies of Extensive Air Shower properties are performed mostly based on the results obtained by the Lodz Extensive Air Shower Array. We have noticed unexplainable delayed signals registered about 500-900 microseconds after the main EAS pulse. We prepared hardware for further experimental study of this effect. Continuous registrations of 5 GeV muon flux with the underground muon telescope have been carried on during 2001. We detected several changes of muon intensity correlated with Forbush decreases registered at lower energies. We have also started registration of the muon counting rate in on-surface scintillation detectors. These measurements will be included to the analysis of the disturbed energy spectrum of primary cosmic rays and its dependence on interplanetary disturbances related to solar activity. In construction and data interpretation of cosmic ray experiments the Lodz group collaborates with many foreign institutes and laboratories: Forschungszentrum in Karlsruhe (Germany), College de France, Institute for Nuclear Studies of the Russian Academy of Sciences, Uppsala University (Sweden) and DESY (Germany). We have prepared a project of large air shower array for studies of cosmic rays up to 10 20 eV. Detectors would be placed on the roofs of high

  17. Magnesium Diboride Current Leads

    Panek, John

    2010-01-01

    A recently discovered superconductor, magnesium diboride (MgB2), can be used to fabricate conducting leads used in cryogenic applications. Dis covered to be superconducting in 2001, MgB2 has the advantage of remaining superconducting at higher temperatures than the previously used material, NbTi. The purpose of these leads is to provide 2 A of electricity to motors located in a 1.3 K environment. The providing environment is a relatively warm 17 K. Requirements for these leads are to survive temperature fluctuations in the 5 K and 11 K heat sinks, and not conduct excessive heat into the 1.3 K environment. Test data showed that each lead in the assembly could conduct 5 A at 4 K, which, when scaled to 17 K, still provided more than the required 2 A. The lead assembly consists of 12 steelclad MgB2 wires, a tensioned Kevlar support, a thermal heat sink interface at 4 K, and base plates. The wires are soldered to heavy copper leads at the 17 K end, and to thin copper-clad NbTi leads at the 1.3 K end. The leads were designed, fabricated, and tested at the Forschungszentrum Karlsruhe - Institut foer Technische Physik before inclusion in Goddard's XRS (X-Ray Spectrometer) instrument onboard the Astro-E2 spacecraft. A key factor is that MgB2 remains superconducting up to 30 K, which means that it does not introduce joule heating as a resistive wire would. Because the required temperature ranges are 1.3-17 K, this provides a large margin of safety. Previous designs lost superconductivity at around 8 K. The disadvantage to MgB2 is that it is a brittle ceramic, and making thin wires from it is challenging. The solution was to encase the leads in thin steel tubes for strength. Previous designs were so brittle as to risk instrument survival. MgB2 leads can be used in any cryogenic application where small currents need to be conducted at below 30 K. Because previous designs would superconduct only at up to 8 K, this new design would be ideal for the 8-30 K range.

  18. Nuclear safety research in HGF 2012; Fortschrittsbericht 2012. Programm 'Nukleare Sicherheitsforschung' Helmholtz-Gemeinschaft

    Anon.

    2013-06-15

    in the Nuclear Competence Association. The Forschungszentrum Juelich GmbH, HZDR Helmholtz-Zentrum Dresden-Rossendorf and the KIT Karlsruhe Institute of Technology are involved in the Nuclear Safety Research Program within the Helmholtz Association. The work and results in 2012 are presented. (orig.)

  19. Department of Nuclear Reactions: Overview

    Rusek, K.

    1998-01-01

    (full text) During the last year our activities were spread over the three major domains: nuclear, atomic and material physics. The nuclear physics experimental programme covered a broad range of nuclear reactions induced by light and heavy ions. New experiments were performed at the compact C-30 cyclotron at Swierk, at University of Jyvaeskylae, GSI Darmstadt, LN Saturne. Prospects for future experiments on nucleon structure at Forschungszentrum Juelich were open. The collaboration with INR Kiev was tightened and work was done in order to prepare experiments at the C-200 heavy ion cyclotron in Warsaw. An effort to install the ion guide isotope separator on line (IGISOL) at the C-200 cyclotron has also to be mentioned A half a year stay of Dr. Nicholas Keeley in the Department, who received The Royal Society/Polish Academy of Science grant, resulted in many interesting results on breakup of light nuclei. Details can be found in the short abstracts presented in this report. As far as atomic physics is concerned, the activity of a group lead by Prof. Marian Jaskola yielded various new results. The experiments were performed at the University of Erlangen, in close collaboration with the Pedagogical University in Kielce and the University of Basel. Fast neutrons generated in the 3 H(d,n) 4 He reaction induced by the 2 MeV deuteron beam from the Van der Graaff accelerator at the Department were used to calibrate solid state-nuclear-track detectors. This was a very good year for material physics research: Jan Kaczanowski and Slawomir Kwiatkawski received Ph.D. degrees based on dissertation research performed in the material physics research programme, while Pawel Kolodziej completed his MSc. thesis in collaboration with the Institute of Electronic Materials Technology in Warsaw, Research Center Karlsruhe, University of Jena and CSNSM Orsay many results were obtained. Lech Nowicki and Prof. Andrzej Turos were awarded by the Director of the IPJ prizes for their scientific

  20. Community-oriented support and research structures

    Attig, Norbert; Eickermann, Thomas; Gibbon, Paul; Lippert, Thomas, E-mail: th.lippert@fz-juelich.d [Institute for Advanced Simulation, Juelich Supercomputing Centre, Forschungszentrum Juelich, 52425 Juelich (Germany)

    2009-07-01

    Coordinated by the Partnership for Advanced Computing in Europe (PRACE) Europe is restructuring and strengthening its high-performance computing infrastructure with the aim to create a model HPC ecosystem. At the tip of the pyramid, up to six centres are envisaged that will operate systems of the highest performance class. The HPC Research Infrastructure (HPC-RI) will comprise European, national and regional centres. Science communities are integral partners, strong links will include Grid and Cloud users. The HPC-RI strives at providing scientists all over Europe, on the one hand, with unlimited and independent access to state-of-the-art computer resources in all performance classes and, on the other hand, with a world-class pan-European competence and support network. While the hardware-oriented buildup of the infrastructure is making progress, high-quality user support and software development in the upcoming era of unprecedented parallelism and exascale on the horizon have become the imminent challenges. This has been clearly recognized by the European Commission, who will issue calls for proposals to fund petascale software development in summer 2009. Although traditional support structures are well established in Europe's major supercomputing centres, it is questionable if these structures are able to meet the challenges of the future: in general, support structures are based on cross-disciplinary computer science and mathematics teams; disciplinary computational science support usually is given in an ad-hoc, project-oriented manner. In this paper, we describe our approach to establish a suitable support structure-Simulation Laboratories (SL). SLs are currently being established at the Juelich Supercomputing Centre of the Forschungszentrum Juelich (FZJ) and at the Steinbuch Centre for Computing (SCC) of the Karlsruhe Institute for Technology (KIT) in Germany. While SLs are community-oriented, i.e. each SL focusses on a specific community, they are

  1. Study on partitioning and transmutation (P and T) of high-level waste. Status of R and D. Final report; Studie zur Partitionierung und Transmutation (P and T) hochradioaktiver Abfaelle. Stand der Grundlagen- und technologischen Forschung. Abschlussbericht

    Merk, Bruno; Glivici-Cotruta, Varvara

    2014-07-01

    The main project, where this sub project contributed to, has been structured into two modules: module A (funded by the federal ministry of economics, managed by KIT) and module B (funded by the federal ministry of education and research, managed by acatech). Partners in module A were DBE TECHNOLOGY GmbH, the Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), the Helmholtz-Zentrum Dresden-Rossendorf (HZDR), the Karlsruher Institute of Technology (KIT) and the Rheinisch-Westfaelische Technische Hochschule (RWTH) Aachen, in co-operation with the Forschungszentrum Juelich (FZJ). Modul B has been executed by the Zentrum fuer Interdisziplinaere Risiko- und Innovationsforschung der Universitaet Stuttgart (ZIRIUS). The overall coordination has been carried out by the Deutsche Akademie der Technikwissenschaften (acatech). The social implications have been evaluated in module B based on the analysis of the scientific and technological aspects in module A. Recommendations for communication and actions to be taken for the future positioning of P and T have been developed. In the project part, coordinated by HZDR - status of R and D - an overview on the whole topic P and T is given. The topic is opened by a short description of reactor systems possible for transmutation. In the following the R and D status of separation technologies, safety technology, accelerator technology, liquid metal technology, spallation target development, transmutation fuel and structural material development, as well as waste conditioning is described. The topic is completed by the specifics of transmutation systems, the basic physics and core designs, the reactor physics, the simulation tools and the development of Safety Approaches. Additionally, the status of existing irradiation facilities with fast neutron spectrum is described. Based on the current R and D status, the research and technology gaps in the topics: separation and conditioning, accelerator and spallation target, and reactor

  2. Analysis of a prototype of a novel 1.5 MW, 170 GHz coaxial cavity gyrotron

    Rzesnicki, T.

    2007-06-01

    A 170 GHz, 2 MW coaxial cavity gyrotron is under development at the Institut fuer Hochleistungsimpuls- und Mikrowellentechnik (IHM) at Forschungszentrum Karlsruhe (FZK) which will be used as a high power microwave source for heating, current drive and stability control of plasmas in the International Thermonuclear Experimental Reactor (ITER). At frequencies above about 100 GHz the output power of conventional gyrotrons with cylindrical hollow waveguide cavities is limited to 1 MW in CW operation mainly due to the high Ohmic losses and the space charge voltage depression of the electron beam. The coaxial geometry enables a reduction of the mode competition in the gyrotron resonator and decreases also the influence of the beam voltage depression. As result a very high order operating mode (for example TE34,19 at 170 GHz) can be chosen which ultimately allows to increase the output power of the gyrotron in CW operation to a value as high as 2 MW. A first prototype of the 170 GHz, 2 MW coaxial cavity gyrotron has been designed, built and experimentally tested in short pulse operation at FZK. The main goal of this work was to investigate experimentally the design of the critical gyrotron components such as electron gun, resonator and a quasi-optical RF system. Those components are same as used in the first industrial coaxial prototype gyrotron for ITER. During the experiments a strong instability was observed inside the gyrotron tube due to the excitation of parasitic low frequency oscillations. The mechanism of the oscillations has been studied and possibilities for their suppression of these oscillations are proposed and experimentally verified. The RF output system is one of the most critical components. It is responsible for the coupling of the gyrotron power out of the gyrotron by converting the microwave power generated in the TE 34,19 -mode into a fundamental free space TEM 0,0 ''Gaussian'' mode. The performance of the RF output system has been tested in low

  3. Simulation of the fuel rod bundle test QUENCH-03 using the system codes ASTEC and ATHLET-CD

    Kruse, P.; Koch, M.K.

    2011-01-01

    The QUENCH-03 test was performed on the 21. of January 1999 at FZK (Forschungszentrum Karlsruhe) to investigate the behaviour on reflood of PWR (Pressurized Water Reactor) fuel rods with little oxidation. This paper presents the results of the simulation of QUENCH-03 performed with the version V1.3 of the integral code ASTEC (Accident Source Term Evaluation Code) which is being developed by IRSN (France) in cooperation with GRS (Germany) and with the program version 2.1A of the mechanistic code ATHLET-CD (Analysis of Thermal-hydraulics of Leaks and Transients - Core Degradation) which is under development by GRS. At first the QUENCH test facility and the QUENCH test program in general are described. The test conduct of the test QUENCH-03 follows as well as a description of the used codes ASTEC and ATHLET-CD with the associated modeling of the test section. The results of this calculation show that during the heat-up and transient phase both codes can calculate bundle and shroud temperatures as well as the hydrogen production in good approximation to the experimental data. During the quench phase and up to the end of the test only the oxidation model PRATER of ASTEC simulates the hydrogen production very well, the other oxidation models of ASTEC cannot calculate to some extent the measured amount of hydrogen. ATHLET-CD underestimates the integral amount at the end of the test. In the ASTEC calculations the temperatures during the quench phase show qualitatively good results, only time delays on some elevations of the bundle could be noticed. ATHLET-CD reproduces the thermal behaviour up to the first temperature escalation very well, after that the temperatures are partly over-estimated. The time delay recognized in the ASTEC calculations are seen as well. The results of the integral code ASTEC emphasize that the calculation of QUENCH-03 is possible and leading to good results concerning hydrogen release and corresponding temperatures. Because the QUENCH-03 test was

  4. Tritium release from EXOTIC-7 orthosilicate pebbles. Effect of burnup and contact with beryllium during irradiation

    Scaffidi-Argentina, F; Werle, H [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reaktortechnik

    1998-03-01

    EXOTIC-7 was the first in-pile test with {sup 6}Li-enriched (50%) lithium orthosilicate (Li{sub 4}SiO{sub 4}) pebbles and with DEMO representative Li-burnup. Post irradiation examinations of the Li{sub 4}SiO{sub 4} have been performed at the Forschungszentrum Karlsruhe (FZK), mainly to investigate the tritium release kinetics as well as the effect of Li-burnup and/or contact with beryllium during irradiation. The release rate of Li{sub 4}SiO{sub 4} from pure Li{sub 4}SiO{sub 4} bed of capsule 28.1-1 is characterized by a broad main peak at about 400degC and by a smaller peak at about 800degC, and that from the mixed beds of capsule 28.2 and 26.2-1 shows again these two peaks, but most of the tritium is now released from the 800degC peak. This shift of release from low to high temperature may be due to the higher Li-burnup and/or due to contact with Be during irradiation. Due to the very difficult interpretation of the in-situ tritium release data, residence times have been estimated on the basis of the out-of-pile tests. The residence time for Li{sub 4}SiO{sub 4} from caps. 28.1-1 irradiated at 10% Li-burnup agrees quite well with that of the same material irradiated at Li-burnup lower than 3% in the EXOTIC-6 experiment. In spite of the observed shift in the release peaks from low to high temperature, also the residence time for Li{sub 4}SiO{sub 4} from caps. 26.2-1 irradiated at 13% Li-burnup agrees quite well with the data from EXOTIC-6 experiment. On the other hand, the residence time for Li{sub 4}SiO{sub 4} from caps. 28.2 (Li-burnup 18%) is about a factor 1.7-3.8 higher than that for caps. 26.2-1. Based on these data on can conclude that up to 13% Li-burnup neither the contact with beryllium nor the Li-burnup have a detrimental effect on the tritium release of Li{sub 4}SiO{sub 4} pebbles, but at 18% Li-burnup the residence time is increased by about a factor three. (J.P.N.)

  5. Community-oriented support and research structures

    Attig, Norbert; Eickermann, Thomas; Gibbon, Paul; Lippert, Thomas

    2009-01-01

    Coordinated by the Partnership for Advanced Computing in Europe (PRACE) Europe is restructuring and strengthening its high-performance computing infrastructure with the aim to create a model HPC ecosystem. At the tip of the pyramid, up to six centres are envisaged that will operate systems of the highest performance class. The HPC Research Infrastructure (HPC-RI) will comprise European, national and regional centres. Science communities are integral partners, strong links will include Grid and Cloud users. The HPC-RI strives at providing scientists all over Europe, on the one hand, with unlimited and independent access to state-of-the-art computer resources in all performance classes and, on the other hand, with a world-class pan-European competence and support network. While the hardware-oriented buildup of the infrastructure is making progress, high-quality user support and software development in the upcoming era of unprecedented parallelism and exascale on the horizon have become the imminent challenges. This has been clearly recognized by the European Commission, who will issue calls for proposals to fund petascale software development in summer 2009. Although traditional support structures are well established in Europe's major supercomputing centres, it is questionable if these structures are able to meet the challenges of the future: in general, support structures are based on cross-disciplinary computer science and mathematics teams; disciplinary computational science support usually is given in an ad-hoc, project-oriented manner. In this paper, we describe our approach to establish a suitable support structure-Simulation Laboratories (SL). SLs are currently being established at the Juelich Supercomputing Centre of the Forschungszentrum Juelich (FZJ) and at the Steinbuch Centre for Computing (SCC) of the Karlsruhe Institute for Technology (KIT) in Germany. While SLs are community-oriented, i.e. each SL focusses on a specific community, they are structured

  6. Separate effects tests on hydrogen combustion during direct containment heating events

    Meyer, L.; Albrecht, G.; Kirstahler, M.; Schwall, M.; Wachter, E.

    2008-01-01

    In the frame of severe accident research for light water reactors Forschungszentrum Karlsruhe (FZK/IKET) operates the facilities DISCO-C and DISCO-H since 1998, conceived to investigate the direct containment heating (DCH) issue. Previous DCH experiments have investigated the corium dispersion and containment pressurization during DCH in different European reactor geometries using an iron-alumina melt and steam as model fluids. The analysis of these experiments showed that the containment was pressurized by the debris-to-gas heat transfer but also to a large part by hydrogen combustion. The need was identified to better characterize the hydrogen combustion during DCH. To address this issue separate effect tests in the DISCO-H facility were conducted. These tests reproduced phenomena occurring during DCH (injection of a hot steam-hydrogen mixture jet into the containment and ignition of the air-steam-hydrogen mixture) with the exception of corium dispersion. The effect of corium particles as igniters was simulated using sparkler systems. The data will be used to validate models in combustion codes and to extrapolate to prototypic scale. Tests have been conducted in the DISCO-H facility in two steps. First a small series of six tests was done in a simplified geometry to study fundamental parameters. Then, two tests were done with a containment geometry subdivided into a subcompartment and the containment dome. The test conditions were as follows: As initial condition in the containment an atmosphere was used either with air or with a homogeneous air-steam mixture containing hydrogen concentrations between 0 and 7 mol%, temperatures around 100 C and pressure at 2 bar (representative of the containment atmosphere conditions at vessel failure). Injection of a hot steam-hydrogen jet mixture into the reactor cavity pit at 20 bar, representative of the primary circuit blow down through the vessel and hydrogen produced during this phase. The most important variables

  7. X-ray tomography investigations on pebble bed structures

    Reimann, J.; Rolli, R.; Pieritz, R.A.; Ferrero, C.; Di Michiel, M.

    2007-01-01

    Granular materials (pebbles) are used in present ceramic breeder blankets both for the ceramic breeder material and beryllium. The thermal-mechanical behaviour of these pebble beds strongly depends on the arrangement of the pebbles in the bed, their contacts and contact surfaces with other pebbles and with walls. The influence of these quantities is most pronounced for beryllium pebble beds because of the large thermal conductivity ratio of beryllium to helium gas atmosphere. At present, the data base for the pebble bed thermal conductivity (k) and heat transfer coefficient (h) is quite limited for compressed beds and significant discrepancies exist in respect to h. The detailed knowledge of the pebble bed topology is, therefore, essential to better understand the heat transfer mechanisms. In the present work, results from detailed X-ray tomography investigations are reported on pebble topology in i) the pebble bed bulk (which is relevant for k), and ii) the region close to walls with thicknesses of several pebble diameters (relevant for h). At Forschungszentrum Karlsruhe, pebble beds consisting of aluminium spheres with diameters of 2.3 and 5 mm, respectively, (simulating the blanket relevant 1 mm beryllium pebbles), were uniaxially compressed at different pressure levels. High resolution three-dimensional microtomography (MT) experiments were subsequently performed at the European Synchrotron Radiation Facility, Grenoble. Radial and axial void fraction distributions were found to be oscillatory next to the walls and non-oscillatory in the bulk. For non-compressed pebble beds, the bulk void fraction is fairly constant; for compressed beds, a gradient exists along the compression axis. In the bulk, the angular distribution of pebble contacts was found to be fairly constant, indicating that no regular packing structure is induced. In the wall region, the pebble layer touching the wall is composed of zones with hexagonal structures as shown clearly by MT images. This

  8. GASFLOW: A Computational Fluid Dynamics Code for Gases, Aerosols, and Combustion, Volume 1: Theory and Computational Model

    Nichols, B.D.; Mueller, C.; Necker, G.A.; Travis, J.R.; Spore, J.W.; Lam, K.L.; Royl, P.; Redlinger, R.; Wilson, T.L.

    1998-01-01

    Los Alamos National Laboratory (LANL) and Forschungszentrum Karlsruhe (FzK) are developing GASFLOW, a three-dimensional (3D) fluid dynamics field code as a best-estimate tool to characterize local phenomena within a flow field. Examples of 3D phenomena include circulation patterns; flow stratification; hydrogen distribution mixing and stratification; combustion and flame propagation; effects of noncondensable gas distribution on local condensation and evaporation; and aerosol entrainment, transport, and deposition. An analysis with GASFLOW will result in a prediction of the gas composition and discrete particle distribution in space and time throughout the facility and the resulting pressure and temperature loadings on the walls and internal structures with or without combustion. A major application of GASFLOW is for predicting the transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containments and other facilities. It has been applied to situations involving transporting and distributing combustible gas mixtures. It has been used to study gas dynamic behavior (1) in low-speed, buoyancy-driven flows, as well as sonic flows or diffusion dominated flows; and (2) during chemically reacting flows, including deflagrations. The effects of controlling such mixtures by safety systems can be analyzed. The code version described in this manual is designated GASFLOW 2.1, which combines previous versions of the United States Nuclear Regulatory Commission code HMS (for Hydrogen Mixing Studies) and the Department of Energy and FzK versions of GASFLOW. The code was written in standard Fortran 90. This manual comprises three volumes. Volume I describes the governing physical equations and computational model. Volume II describes how to use the code to set up a model geometry, specify gas species and material properties, define initial and boundary conditions, and specify different outputs, especially graphical displays. Sample problems are included

  9. Anisotropy and buoyancy in nuclear turbulent heat transfer - critical assessment and needs for modelling

    Groetzbach, G.

    2007-12-01

    is shown that the turbulent Prandtl number concept and other available turbulence models have serious deficits in this convection type. Some of the respective model improvements are discussed which were recently developed at Forschungszentrum Karlsruhe. Finally, a sketch for a turbulent momentum and heat transfer model is given which summarizes the experience from literature and our own results. It is based on extended algebraic stress and heat flux models which use in total four or five transport equations for turbulence quantities. According to all experience one may expect that this model will give considerably improved results for the anisotropic transport in forced, mixed, and buoyant convection in fluids with different molecular Prandtl numbers. Therefore, it should be implemented in a CFD code and should be investigated in more detail. (orig.)

  10. Results of the QUENCH-12 experiment on reflood of a VVER-type bundle

    Stuckert, J.; Grosse, M.; Heck, M.; Schanz, G.; Sepold, L.; Stegmaier, U.; Steinbrueck, M.

    2008-09-01

    The QUENCH experiments are to investigate the hydrogen source term resulting from the water injection into an uncovered core of a Light-Water Reactor. The QUENCH test bundle with a total length of approximately 2.5 m usually consists of 21 fuel rod simulators of Western PWR (Pressurized Water Reactor) geometry. The QUENCH-12 test bundle, however, which was set up to investigate the effects of VVER materials and bundle geometry (hexagonal lattice) on core reflood consisted of 31 fuel rod simulators. 18 rods of which were electrically heated using tungsten heaters in the rod center. All claddings, corner rods and grid spacers were made of Zr1%Nb (E110) and the shroud of Zr2.5%Nb (E125). For comparison, the QUENCH-06 test (ISP-45) with Western PWR geometry (square lattice) was chosen as reference. QUENCH-12 conducted at the Forschungszentrum Karlsruhe (FZK, Karlsruhe Research Center) on 27 September, 2006 in the frame of the EC-supported ISTC program 1648.2 was proposed by FZK together with RIAR Dimitrovgrad and IBRAE Moscow (Russia), and supported by pretest calculations performed by PSI (Switzerland) and the Kurchatov Institute Moscow (Russia) together with IRSN Cadarache (France). It had been preceded by a low-temperature (maximum 1073 K) pretest on 25 August, 2006 to characterize the bundle thermal hydraulic performance and to provide data to assess the code models used for pretest calculational support. After a stabilization period at 873 K pre-oxidation took place at ∝1470 K for ∝3400 s to achieve a maximum oxide thickness of about 200 μm. A transient phase followed with a temperature rise to ∝2050 K. Then quenching of the bundle by a water flow of 48 g/s was initiated cooling the bundle to ambient temperature in ∝5 min. Following reflood initiation, a moderate temperature excursion of ∝50 K was observed, over a longer period than in QUENCH-06. The temperatures at elevations between 850 mm and 1050 mm exceeded the melting temperature of β-Zr, i

  11. 20 years of cosmic muons research performed in IFIN-HH

    Mitrica, Bogdan [Horia Hulubei National Institute of Physics and Nuclear Engineering - IFIN HH, Bucharest, P.O.B.MG-6 (Romania)

    2012-11-20

    During the last two decades a modern direction in particle physics research has been developed in IFIN-HH Bucharest, Romania. The history started with the WILLI detector built in IFIN-HH Bucharest in collaboration with KIT Karlsruhe (formerly Forschungszentrum Karlsruhe). The detector was designed for measurements of the low energy muon charge ratio (< 1GeV) based on a delayed coincidence method, measuring the decay time of the muons stopped in the detector: the positive muons decay freely, but the negative muons are captured in the atom thus creating muonic atoms and decay depending on the nature of the host atom. In a first configuration, the WILLI detector was placed in a fixed position for measuring vertical muons. Further WILLI has been transformed in a rotatable device which allows directional measurements of muon charge ratio and muon flux. The results exhibit a pronounced azimuthal asymmetry (East-West effect) due to the different in fluence of the geomagnetic field on the trajectories of positive and negative muons in air. In parallel, flux measurement, taking into account muon events with nergies > 0.4GeV, show a diurnal modulation of the muon flux. The analysis of the muon events for energies < 0.6GeV reveals an aperiodic variation of the muon flux. A new detection system performing coincidence measurements between the WILLI calorimeter and a small array of 12 scintillators plates has been installed in IFIN-HH starting from the autumn of 2010. The aim of the system is to investigate muon charge ratio from individual EAS by using the mini-array as trigger for the WILLI calorimeter. Such experimental studies could provide detailed information on hadronic interaction models and primary cosmic ray composition at energies around 10{sup 15}eV. Simulation studies and preliminary experimental tests, regarding the performances of the mini-array, have been performed using H and Fe primaries, with energies in a range 10{sup 13}eV - 10{sup 15}eV. The results show

  12. Results of the QUENCH-12 experiment on reflood of a VVER-type bundle

    Stuckert, J.; Grosse, M.; Heck, M.; Schanz, G.; Sepold, L.; Stegmaier, U.; Steinbrueck, M. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung, Programm Nukleare Sicherheitsforschung; Goryachev, A.; Ivanova, I. [RIAR (FSUE SSC-RIAR) Dimitrovgrad (Russian Federation)

    2008-09-15

    The QUENCH experiments are to investigate the hydrogen source term resulting from the water injection into an uncovered core of a Light-Water Reactor. The QUENCH test bundle with a total length of approximately 2.5 m usually consists of 21 fuel rod simulators of Western PWR (Pressurized Water Reactor) geometry. The QUENCH-12 test bundle, however, which was set up to investigate the effects of VVER materials and bundle geometry (hexagonal lattice) on core reflood consisted of 31 fuel rod simulators. 18 rods of which were electrically heated using tungsten heaters in the rod center. All claddings, corner rods and grid spacers were made of Zr1%Nb (E110) and the shroud of Zr2.5%Nb (E125). For comparison, the QUENCH-06 test (ISP-45) with Western PWR geometry (square lattice) was chosen as reference. QUENCH-12 conducted at the Forschungszentrum Karlsruhe (FZK, Karlsruhe Research Center) on 27 September, 2006 in the frame of the EC-supported ISTC program 1648.2 was proposed by FZK together with RIAR Dimitrovgrad and IBRAE Moscow (Russia), and supported by pretest calculations performed by PSI (Switzerland) and the Kurchatov Institute Moscow (Russia) together with IRSN Cadarache (France). It had been preceded by a low-temperature (maximum 1073 K) pretest on 25 August, 2006 to characterize the bundle thermal hydraulic performance and to provide data to assess the code models used for pretest calculational support. After a stabilization period at 873 K pre-oxidation took place at {proportional_to}1470 K for {proportional_to}3400 s to achieve a maximum oxide thickness of about 200 {mu}m. A transient phase followed with a temperature rise to {proportional_to}2050 K. Then quenching of the bundle by a water flow of 48 g/s was initiated cooling the bundle to ambient temperature in {proportional_to}5 min. Following reflood initiation, a moderate temperature excursion of {proportional_to}50 K was observed, over a longer period than in QUENCH-06. The temperatures at elevations

  13. Development of a 10 kW PEM fuel cell for stationary applications

    Barthels, H.; Mergel, J.; Oetjen, H.F. [Institute fuer Energieverfahrenstechnik (IEV), Juelich (Germany)] [and others

    1996-12-31

    A 10 kW Proton Exchange Membrane Fuel Cell (PEMFC) is being developed as part of a long-term energy storage path for electricity in the photovoltaic demonstration plant called PHOEBUS at the Forschungszentrum Julich.

  14. Tugi Eesti lastekodulastele / Aino Siebert

    Siebert, Aino

    2004-01-01

    7. mail Karlsruhe lähistel Eggensteini evangeelses kirikus toimunud rahvusvahelisest heategevuskontserdist, millega toetatakse eesti lastekodudes elavaid lapsi (kontserdi korraldajaks Heidelbergis asutatud Saksa-Eesti Foorum (SEF))

  15. The fast cyclic neutron activation technique at the Karlsruhe 3.75 MV Van de Graaff accelerator and the measurement of the 107,109Ag(n, γ)108,110Ag cross sections at kT = 25 keV

    Beer, H.; Rupp, G.; Walter, G.; Voss, F.; Kaeppeler, F.

    1994-01-01

    The neuton activation technique is studied for product nuclides with half-lives more than a year down to a few seconds. A new system for the measurement of Maxwellian averaged capture cross sections with this technique was developed especially for isotopes with induced activities with half-lives of only a few seconds. In order to collect sufficient capture events the two phases of an activation, irradiation and activity counting, are repeated periodically. This fast cyclic activation method is described and activation measurements on 107,109 Ag are reported. The Maxwellian averaged capture cross sections of 107 Ag, and 109 Ag at kT = 25 keV were found to be 786±60 mb and 887±75 mb, respectively. The abilities of the activation method to measure cross sections of only a few μbarns are discussed. (orig.)

  16. Cost/effectiveness aspects of road lighting : revised version of Contribution to CIE TC-4.6 Symposium on Measures of Road Lighting Effectiveness, Session II - Road lighting and accidents, Karlsruhe, 5-6 July 1977, SWOV R-77-46.

    Flury, F.C.

    1981-01-01

    The common method to determine the effect of road lighting on traffic safety, is to compare accident numbers during daylight and darkness, before and after the measure is taken. This approach ignores the possibility of increased risk of collisions with road side obstacles due to the erection of

  17. Computer codes KASCO and KARDIF for processing cross-sections data; Computerprogramme zur Bearbeitung der Wirkungsquerschnitts-Dateien KASCO und KARDIF

    Muenzel, H; Neumann, B; Klewe-Nebenius, H; Pfennig, G

    1981-12-01

    Document of internal interest, not to be sent out without permission of authors. Summary of the computer program developed at the Karlsruhe Charged Group (Kachapag) for producing from EXFOR the handbook series `Physik Daten/Physics Data Nr. 15` of the Fachinformationszentrum Karlsruhe. (author) 6 figs. The full text is available from IAEA Nuclear Data Section

  18. Computer codes KASCO and KARDIF for processing cross-sections data

    Muenzel, H.; Neumann, B.; Klewe-Nebenius, H.; Pfennig, G.

    1981-01-01

    Document of internal interest, not to be sent out without permission of authors. Summary of the computer program developed at the Karlsruhe Charged Group (Kachapag) for producing from EXFOR the handbook series 'Physik Daten/Physics Data Nr. 15' of the Fachinformationszentrum Karlsruhe. (author)

  19. Continuous operation of RODOS in case of long lasting releases

    Raskob, W.; Paesler-Sauer, J.; Rafat, M.

    2003-01-01

    users who want to explore the impact of long term countermeasures in more detail. The users has also the option to set the time (in days after the first release) at which they consider the release to be ended or all significant deposition to have occurred. This will be entered interactively via the user interface. This will enable the user to start the consideration of countermeasures after the majority of the release has occurred, as some releases might have a very long, low level tail, and it would be unrealistic to expect decision makers to wait until deposition had completely stopped in such circumstances. This approach also recognizes that deposition will not end everywhere on the same day. The demonstration will exemplify the continuous automatic operation of RODOS using a release scenarios lasting over several days. On-line meteorological data measured at Forschungszentrum Karlsruhe, assumed to be the release point, will be used as input for the diagnostic calculations performed automatically within a distance range of 160 km x 160 km every 10 minutes. Numerical weather forecast from the German Weather Service, updated every 12 hours, will be used for prognostic calculations repeated in the same calculation area every hour. In parallel, the European wide numerical weather forecasts calculated by the ALADIN model, run by the Austrian Weather service and updated every 12 hours, are used to calculate in interactive RODOS runs the longer distance contamination. All functions of RODOS and its broad spectrum of results will be presented by the demonstration team. In particular, the necessity of emergency actions and countermeasure and their consequences in terms of areas affected, radiation doses and resources needed can be tracked with the ongoing activity release. (author)

  20. Department of Cosmic Ray Physics; Overview

    Szabelski, J.

    2004-01-01

    Prof, M. Alania (Siedlce), and Prof. K. Kudela (Kosice, Slovakia). International collaborations are very important: the Department was a KASCADE member (EAS experiment dedicated to solving the problem of mass composition of Cosmic Rays at energies around 10 15 eV in Forschungszentrum Karlsruhe, Germany) and now is a member of KASCADE-Grande Collaboration - the large classical experiment for very high energy EAS. We collaborate in EAS data interpretation, detection technic and basic Cosmic Ray problems with College de France, Institute for Nuclear Research of the Russian Academy of Sciences, JINR Dubna and the Cosmophysical Institute in Yakutsk (Russia). In the area of high energy particle physics our Department is a member of CELSIUS/WASA Collaboration (Uppsala, Sweden), and participates in ZEUS experiment at DESY (Hamburg, Germany). Students of high schools in Lodz are visiting our Department and can perform small experiments with secondary Cosmic Ray particle detection. This activity is related to ''The Roland Maze Project'', the idea of large EAS arrays with detectors placed on the roofs of high schools in Lodz. (author)

  1. Scientific Equipment Division - Overview

    Halik, J.

    2001-01-01

    . The machine allows the following tool movements in particular axes: X - 1000 mm, Y- 500 mm, Z - 500 mm; it is controlled by HEIDENHAIN 407 Control System, and ensures the accuracy and reproducibility of machining of 0.01 mm in each of the axis. In 2000, the Department of Mechanical Construction designed, manufactured and assembled an equipment for the following foreign laboratories: - Deutches Elektronen Synchrotron, Hamburg, FRG; - Forschungszentrum Karlsruhe, FRG; - Institute of Physics, Polish Academy of Sciences, Warsaw, Poland; - Jagiellonian University, Cracow, Poland; - Massachusetts Institute of Technology, Cambridge, Massachusetts, USA; - Brookhaven National Laboratory, Upton, NY, USA. Besides the large designs and systems described below, some interesting works were made for the departments of our Institute and other institutions: 1. Design and manufacturing of the new photon calorimeter of Luminosity Monitor for ZEUS Experiment at DESY; 2. Final installation of Detector Enclosures and Dry Air System for PHOBOS Experiment at BNL; 3. Design and manufacturing of the shutter and manufacturing of supporting structures for AUGER Project in Argentina; 4. Manufacturing and installation of Deflectors I and II for cyclotron AIC-144 at our Institute; 5. Design and manufacturing of resonator joggle for cyclotron AIC-144 at our Institute; 6. Upgrade of outlet chamber of for cyclotron AIC-144 at our Institute. (author)

  2. IFMIF target and test cell - design and integration

    Heinzel, V.

    2007-01-01

    The International Fusion Material Irradiation Facility (IFMIF) aims at the qualification of appropriate materials for a Demonstration Fusion Power Plant (DEMO) to a fluence of up to 150 dpa (displacement per atom) at a DEMO typical neutron spectrum. It comprises two accelerators each providing a deuteron beam with 125 mA and 40 MeV. The deuterons strike a lithium target and create via stripping reactions neutrons. The neutrons are mainly forward directed into the High-Flux-Test-Module (HFTM). The Medium Flux-Test-Modules (MFTM) and the Low-Flux-Test-Modules (LFTM) are arranged in beam direction behind. In the HFTM a damage rate in steel of more than 20 dpa/fpy (displacement per atome per full power year) will be provide in a volume of 0.5 litre. The neutron spectrum is prone to produce helium and tritium in steel like in the first wall of a DEMO reactor. The Medium- Flux-Test-Modules are designed for creep fatigues in situ and tritium release test. The test modules are cooled with helium. The target is a lithium jet with a free surface towards the deuteron beams. The jet follows a concave curved so called back wall. Centrifugal forces increase the static pressure, which prevents lithium boiling at the beam tube pressure and the power release of 10 MW due to the deuteron beams. The target and Test Cell (TTC) houses the target and the test modules as well as the lithium supply tubes and a quench tank into which the lithium splashes after the target. The lithium containing components have a temperature of 250 to 350 C. Nuclear reactions mainly in beam direction contribute to heat releases in TTC components. The TTC is filled with a noble gas with almost atmospheric pressure. Natural convection transfers heat to the walls but also mitigates temperature peaks. The Forschungszentrum Karlsruhe (FZK) has developed or validated tools for: - The extended Monte Carlo Code McDeLicious for calculations of the neutron source term, dpa rates in the material specimens, activation

  3. Re/Os cosmochronometer: measurement of neutron cross sections

    Mosconi, M.

    2007-01-01

    the first excited level of 187 Os. This additional measurement was performed at the 3.7 MV Van de Graaff of Forschungszentrum Karlsruhe using monoenergetic neutron beams from the 7 Li(p, n) 7 Be reaction at threshold. The improved experimental results were used for the evaluation of the true stellar cross section and for the evaluation of the consequences for the Re/Os clock. It is found that the nuclear input is no longer determining the uncertainty of the derived age. First analyses using a simplified schematic model of the galactic chemical evolution yields a cosmic age of 15.6±1.4 Gyr, but needs to be complemented by a more realistic galactic evolution model. (orig.)

  4. Division of Scientific Equipment - Overview

    Halik, J.

    2002-01-01

    allows the following tool movements in particular axes: X - 1000 mm, Y - 500 mm, Z - 500 mm; it is controlled by HEIDENHAIN 407 Control System, and ensures the accuracy and reproducibility of machining of 0.01 mm in each of the axis. In 2001 the Department of Mechanical Construction designed, manufactured and assembled an equipment for the following foreign laboratories: * Deutches Elektronen Synchrotron, Hamburg, FRG, * European Organization for Nuclear Research CERN, Geneva, Switzerland, * Forschungszentrum Karlsruhe, FRG, * Institute of Physics, Polish Academy of Science, Warsaw, Poland, * Jagiellonian University, Cracow, Poland. Besides the large designs and systems described below, some interesting works were made for the departments of our Institute and other institutions: 1. Design and manufacturing of the new photon calorimeter of Luminosity Monitor for ZEUS Experiment at DESY, 2. Manufacturing of the shutter and supporting structures for AUGER Project in Argentina, 3. Manufacturing and assembly of 105 sets of mirror positioning devices for AUGER Project in Argentina, 4. Design of ion source for cyclotron AIC-144 at our Institute, 5. Design and manufacturing of a vacuum chamber and parts of vacuum lines for dual beam ion implantator at our Institute, 6. Design and manufacturing of experimental chamber for Proton Microprobe at our Institute. (author)

  5. ISP42 (PANDA Tests) - Blind Phase Comparison Report

    Luebbesmeyer, D.; Aksan, S.N.

    2003-05-01

    The International Standard Problem (ISP) No. 45 is part of the overall ISP program of the OECD/NEA and is dedicated to the behavior of heat-up and delayed reflood of fuel elements in nuclear reactors during a hypothetical accident. ISP-45 is related to the out-of-pile bundle quench experiment QUENCH-06, performed at Forschungszentrum Karlsruhe (FZK), Germany, on December 13, 2000. Special attention was paid to hydrogen production. To assess the ability of severe accident codes to simulate processes during core heat-up and reflood at temperatures above 2000 K, the behavior of the bundle during the whole experiment should be calculated on the basis of the necessary experimental initial and boundary conditions, but without knowing further experimental details. In this so-called blind phase 21 participants from 15 nations contributed with 8 different code systems (ATHLET-CD, ICARE/CATHARE, IMPACT/SAMPSON, GENFLO, MAAP, MELCOR, SCDAPSIM, SCDAP-3D). Additionally, posttest calculations using the in-house version SCDAP/RELAP5 mod3.2.irs are used for comparison. After the end of the blind phase all measured data were made available and the participants were invited to deliver a second calculation, where this knowledge could be used (so called open phase). In this report, results of the blind calculations are presented, analyzed, and compared to experimental data. During heat-up most results do not deviate significantly from one another, except as a consequence of some obvious user errors, so that a definition of a mainstream is justified. For the quench phase the lack of adequate hydraulic modeling becomes obvious: some participants could not match the observed cool-down rates, others had to use very fine meshes to compensate code deficiencies. To overcome this insufficiency some newly developed reflood models were used in MAAP and MELCOR. In QUENCH-06, oxide layers were thick enough to protect the cladding from melting and failure below 2200 K, so that no massive hydrogen

  6. Comparison and Interpretation Report of the OECD International Standard Problem No. 45 - Exercise (QUENCH-06)

    Hering, W.; Homann, Ch.; Lamy, J.S.; Miassoedov, A.; Schanz, G.; Sepold, L.; Steinbrueck, M.

    2002-10-01

    The International Standard Problem (ISP) No. 45 is part of the overall ISP program of the OECD/NEA and is dedicated to the behavior of heat-up and delayed reflood of fuel elements in nuclear reactors during a hypothetical accident. ISP-45 is related to the out-of-pile bundle quench experiment QUENCH-06, performed at Forschungszentrum Karlsruhe (FZK), Germany, on December 13, 2000. Special attention was paid to hydrogen production. To assess the ability of severe accident codes to simulate processes during core heat-up and reflood at temperatures above 2000 K, the behavior of the bundle during the whole experiment should be calculated on the basis of the necessary experimental initial and boundary conditions, but without knowing further experimental details. In this so-called blind phase 21 participants from 15 nations contributed with 8 different code systems (ATHLET-CD, ICARE/CATHARE, IMPACT/SAMPSON, GENFLO, MAAP, MELCOR, SCDAPSIM, SCDAP-3D). Additionally, posttest calculations using the in-house version SCDAP/RELAP5 mod3.2.irs are used for comparison. After the end of the blind phase all measured data were made available and the participants were invited to deliver a second calculation, where this knowledge could be used (so-called open phase). In this report, results of the blind calculations are presented, analyzed, and compared to experimental data. During heat-up most results do not deviate significantly from one another, except as a consequence of some obvious user errors, so that a definition of a mainstream is justified. For the quench phase the lack of adequate hydraulic modeling becomes obvious: some participants could not match the observed cool-down rates, others had to use very fine meshes to compensate code deficiencies. To overcome this insufficiency some newly developed reflood models were used in MAAP and MELCOR. In QUENCH-06, oxide layers were thick enough to protect the cladding from melting and failure below 2200 K, so that no massive hydrogen

  7. Cost estimation tools in Germany and the UK. Comparison of cost estimates and actual costs

    Pfeifer, W.; Gordelier, S.; Drake, V.

    2005-01-01

    Full text: Accurate cost estimation for future decommissioning projects is a matter of considerable importance, especially for ensuring that sufficient funds will be available at the time of project implementation. This paper looks at the experience of cost estimation and real implementation outcomes from two countries, Germany and the UK, and draws lessons for the future. In Germany, cost estimates for the decommissioning of power reactors are updated every two years. For this purpose, the STILLKO program of the NIS Company is used. So far, Forschungszentrum Karlsruhe has successfully decommissioned two prototype reactor facilities. Re-cultivation of the premises has already been completed. At the moment, the activated components of the multi-purpose research reactor (MZFR), the first pressurized water reactor in Germany that was moderated and cooled with heavy water, and of the prototype fast breeder reactor (KNK) are being dismantled remotely. Consequently, vast experience exists in particular for the updating of total costs on the basis of actually incurred expenses. The further the dismantling work proceeds, the more reliable is the total cost estimate. Here, the development of the estimated MZFR decommissioning costs shall be presented and compared with the estimates obtained for a German reference PWR-type power reactor of 1200 MW. In this way: - common features of the prototype reactor and power reactor shall be emphasized, - several parameters leading to an increase in the estimated costs shall be highlighted, - cost risks shall be outlined with the remote dismantling of the reactor pressure vessel serving as an example, - calculation parameters shall be presented, and - recommendations shall be made for a consistent estimation of costs. The United Kingdom Atomic Energy Authority (UKAEA) has a major programme for the environmental remediation of its former research and development sites at Dounreay, Windscale, Harwell and Winfrith together with the need to

  8. Experimental confirmation of the ITER cryopump high temperature regeneration scheme

    Day, C.; Haas, H.

    2007-01-01

    Forschungszentrum Karlsruhe (FZK) is developing the ITER high vacuum pumping systems for evacuation and maintenance of the required pressure levels in the torus (during burn and dwell, conditioning and leak detection), the neutral beam injectors and the cryostat vessel. All ITER high vacuum systems share the same concept of accumulative cryosorption pumping. The pumping surfaces, forced-cooled by 4.5 K supercritical helium, are coated with activated charcoal so as to be able to adsorb helium and hydrogens. All other gases are cryopumped by cryogenic phase transition from gaseous into the liquid/solid state. For the hydrogen processing pumps in the torus and the NBI, the maximum pumping time is given by the limitation of the maximum hydrogen inventory such that the resulting pressure in case of a loss of vacuum event and a corresponding oxy-hydrogen explosion is compatible to the design criteria of the vacuum vessel. To limit the gas accumulation, a staggered regeneration philosophy has been adopted, which involves three different temperature levels in order to achieve high regeneration efficiencies at best availability of the pumping system. The regular regeneration step is performed at a charcoal temperature of 90 K to release all hydrogen isotopomers (and helium), which are subsequently pumped out by the forevacuum pumping system. The second step at ambient temperature leads to the release of all air-like species. It has to be performed less frequently, probably over-night. Any water-like species with strong sorption bonding forces need still higher temperatures for effective desorption from the charcoal. These species comprise not only water itself but also high molecular tracers added to the water circuits in case of leak localisation and any pumped higher hydrocarbons from the plasma exhaust or. The latter in their tritiated forms may contribute significantly to the semi-permanent tritium inventory; a good knowledge of their regeneration characteristics is

  9. Re/Os cosmochronometer: measurement of neutron cross sections

    Mosconi, M.

    2007-12-21

    }) experiments and by an improved measurements of the inelastic scattering cross section for the first excited level of {sup 187}Os. This additional measurement was performed at the 3.7 MV Van de Graaff of Forschungszentrum Karlsruhe using monoenergetic neutron beams from the {sup 7}Li(p, n){sup 7}Be reaction at threshold. The improved experimental results were used for the evaluation of the true stellar cross section and for the evaluation of the consequences for the Re/Os clock. It is found that the nuclear input is no longer determining the uncertainty of the derived age. First analyses using a simplified schematic model of the galactic chemical evolution yields a cosmic age of 15.6{+-}1.4 Gyr, but needs to be complemented by a more realistic galactic evolution model. (orig.)

  10. STEPS: source term estimation based on plant status phase 0 - the technical specifications of the containment module

    Vamanu, D.V.

    1998-01-01

    In the framework of Project RODOS (Real-Time On-Line Decision Support System for Nuclear Emergencies in Europe), the European Atomic Energy Community (EAEC) of the Commission of the European Communities has commissioned the development of a unified concept, body of knowledge, models and software package meant to assist the evaluation of the source term of severe nuclear accidents in light water reactors of the types prevailing on the Continent. Code-named STEPS, for 'Source Term Estimation based on Plant Status', the project has evolved as Contract RODOS D (FI4P-CT96-0048), between EAEC and consortium of expert European centres including Commissariat a l'Energie Atomique, Institut de Protection et de Surete Nucleaire, (CEA-DPI-SEAC) as Coordinator and Forschungszentrum Karlsruhe GmbH (FZK-INR), the Finnish Centre for Radiation and Nuclear Safety, (STUK-NSD), the Technical Research Centre of Finland, Energy, Nuclear Energy (VTT-ET-NE), and Eidgenossische Technische Hochschule - ETH Zurich, Centre of Excellence (ETH-CERS) as Contractors. For the Phase 0 of the project, an IFIN-HH expert has been assigned by ETH-CERS to develop the Technical Specifications of the delivery component of the intended STEPS package, the CONTAINMENT Module. Sponsored by ETH-CERS headquarters in Zurich, the work was done on the premises and with the logistic support of CEA D PI-SEAC at Fontenay-aux-Roses, with the feedback processing and computer code development subsequently performed in Bucharest. The Technical Specifications of the STEPS CONTAINMENT Module were guided by specific terms of reference, including: (i) the capability of the software to function as a source term interface between targeted nuclear power plants and the RODOS System; (ii) the comparable capability of the system to be operated as a stand-alone assessment and decision support tool for a comprehensive variety of plants, nuclear emergency classes. On the technical side, the specifications had to focus on the possible

  11. BMFT. Subproject environmental research, ecological research. Annual report 1991

    1992-01-01

    This report summarizes the 1991 ecological research activities (ecosystems research, urban ecology, tropical ecology, forest decline, ecology of soils and waters, ecotoxicology, environmental pollution and health, protection of biotopes and protection of the species) which the project sponsors 'biology, energy, ecology' (Forschungszentrum Juelich) and 'environmental research and climatological research' (GSF-Forschungszentrum fuer Umwelt und Gesundheit) have been supervising on behalf of the Federal Ministry for Research and Technology to promote the subproject 'environmental research'. A general survey introduces the promoted projects, and standardized data sheets briefly introduce the individual activities. The appendix gives the project indices, the indices of joint projects, and a list of the supported companies and institutions. (BBR) [de

  12. Comparison between KARBUS and APOLLO 1

    Payer, L.; Broeders, C.

    1995-01-01

    A comparison is made between benchmark calculations by the French APOLLO 1 code and the Karlsruhe KARBUS procedure. Independently these two codes had been developed for transport computations in infinite reactor configurations and for burnup calculations. (orig.)

  13. Comparison between KARBUS and APOLLO 1; Vergleichsrechnungen mit KARBUS und APOLLO 1

    Payer, L.; Broeders, C.

    1995-08-01

    A comparison is made between benchmark calculations by the French APOLLO 1 code and the Karlsruhe KARBUS procedure. Independently these two codes had been developed for transport computations in infinite reactor configurations and for burnup calculations. (orig.)

  14. Work session on the SAR. Pt. 2

    Burkart, K.

    1980-01-01

    The present paper contains the tables of the contribution of K. Burkart 'Work Session on the SAR' to the IAEA Interregional Training Course held in Sept/Oct. 1980 at the Kernforschungszentrum Karlsruhe. (RW)

  15. Innovative ways of decontaminating nuclear facilities

    Bremmer, Jan; Gentes, Sascha; Ambos, Frank

    2009-01-01

    The great variety of surfaces to be decontaminated in a nuclear power plant increases demand for economic solutions and efficient processing systems. The Institute for Technology and Management in Building (TMB) of the University of Karlsruhe (TH) is working on this task in the new professorship of Sascha Gentes and, together with sat Kerntechnik GmbH, developing innovative techniques and tools for surface decontamination. In this effort, sat.Kerntechnik GmbH contributes 50% to the funding of the new professorship at the Karlsruhe Institute of Technology, the merger of the University of Karlsruhe and the Karlsruhe Research Center. The new professorship will extend its work also to various other innovative concepts to be employed not only in demolition but also in maintenance and operation of nuclear facilities. Above and beyond theoretical approaches, practical solutions are in the focus of work. For this reason, new developments are elaborated in close cooperation with the respective users. (orig.)

  16. A Desperate Struggle to Save a Condemned Army--A Critical Review of the Stalingrad Airlift

    Thyssen, Mike

    1997-01-01

    ... blunders of Adolf Hitler. Given that, this essay reflects a study of primary source material collected from key German commanders, as well as numerous documents collected in 1956 as part of the "Karlsruhe Collection...

  17. Usage of the cyclotron facility local area network

    Heinzmann, H.; Peters, J.; Thow, T.J.

    1988-01-01

    Local area network of controllers at the Karlsruhe cyclotyron is shown. Experience after two years of usage is described. The system is applied controlling, data acquisition, management, databases usage

  18. Wege der estnischen Musik von russischer Romantik zum Schamanentum. Lepo Sumera als prominenter Vertreter der Neuen Musik Estlands: seeine neue Sinfonie steht im Mittelpunkt von Konzerten der Staatskapelle

    1992-01-01

    Eesti muusika tee vene romantismist £amanismini: Lepo Sumera kui eesti uue muusika silmapaistev esindaja/ Tema uus sümfoonia on Staatskapelle kontsertide keskpunktiks. Eesti kultuuripäevadelt Karlsruhes; Lepo Sumera muusikast

  19. Solid electron sources for the energy scale monitoring in the KATRIN experiment

    Zbořil, Miroslav; Vénos, D

    The KArlsruhe TRItium Neutrino (KATRIN) experiment represents a next-generation tritium $\\beta$-decay experiment designed to perform a high precision direct measurement of the electron anti-neutrino mass m($\

  20. Experiments with the SUR 100 training reactor

    Milicic, B.

    1984-06-01

    This paper contains a compilation of various experiments using the SUR - 100 reactor for training purposes, which have been widly proved in practical work at the School for Nuclear Technology of the Karlsruhe Research Center. (orig.) [de