WorldWideScience

Sample records for kerntechnischen ausschusses inhaltsangabe

  1. Leitlinie für Fakultäts-interne Leistungsnachweise während des Medizinstudiums: Ein Positionspapier des GMA-Ausschusses Prüfungen und des Kompetenzzentrums Prüfungen Baden-Württemberg [

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    ,

    2008-02-01

    Full Text Available [english] With the implementation of a new licensing regulation for doctors in 2002 the responsibility for assessment was assigned from the German national examination board to the individual faculties, especially so for clinical subjects.39 graded reports have to be issued between the first national board examination (after 2 years of preclinical studies and the start of the internship (6th year. This new task provides special demands for assessment organization at faculty level. A number of prerequisites have to be met to guarantee adequate quality in assessment. To support faculties in meeting these requirements, guidelines were issued in cooperation with GMA assessment committee and the Baden-Württemberg competence centre for assessment in medical education. Developed on broad consensus these guidelines define quality requirements based on international standards. Their effect on quality improvement in German medical faculty’s examinations in clinical subjects is to be researched concomitantly.[german] Die neue ärztliche Approbationsordnung (ÄAppO aus dem Jahre 2002 verlagert die Prüfungsverantwortung insbesondere für den klinischen Studienabschnitt auf die Fakultäten:39 benotete Leistungsnachweise sind zwischen der ersten Staatsprüfung und praktischem Jahr zu erstellen. Diese neue Aufgabe stellt besondere Anforderungen an das fakultäre Prüfungswesen. Um eine angemessene Qualität der fakultären Prüfungen sicher zu stellen, sind eine Reihe von Voraussetzungen zu erfüllen. Die vorliegenden Leitlinien des GMA-Ausschusses Prüfungen und des Kompetenzzentrums Prüfungen des Landes Baden-Württemberg wurden erstellt, um die Fakultäten in dieser Aufgabe zu unterstützen. Die vorliegenden Leitlinien definieren die Qualitätsanforderungen unter Berücksichtigung internationaler Standards und wurden in breitem Konsens entwickelt. Ihre Wirkung im Hinblick auf die Qualitätsverbesserung der fakultären Prüfungen im klinischen

  2. Konsensusstatement "Praktische Fertigkeiten im Medizinstudium" – ein Positionspapier des GMA-Ausschusses für praktische Fertigkeiten [A Consensus Statement on Practical Skills in Medical School – a position paper by the GMA Committee on Practical Skills

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    Schnabel, Kai P.

    2011-11-01

    standardisieren. Auf Initiative der deutschsprachigen Skills Labs wurde der GMA-Ausschuss für praktische Fertigkeiten gegründet, der einen kompetenzbasierten Lernzielkatalog entwickelte, dessen Entstehung und Struktur hier beschrieben wird.Ziel des Kataloges ist es, die praktischen Fertigkeiten im Medizinstudium zu definieren und damit den Fakultäten eine rationale Planungsgrundlage für die zur Vermittlung praktischer Fertigkeiten notwendigen Ressourcen zu geben.Methodik: Aufbauend auf schon vorhandenen deutschsprachigen Lernzielkatalogen wurde mittels einem mehrfach iterativem Kondensationsprozesses, der der Erarbeitung von S1-Leitlinien entspricht, vorgegangen, um eine breite fachliche und politische Abstützung zu erhalten. Ergebnisse: Es wurden 289 verschiedene praktische Lernziele identifiziert, die zwölf verschiedenen Organsystemen, drei Grenzbereichen zu anderen Kompetenzbereichen und einem Bereich mit organsystemübergreifenden Fertigkeiten zugeordnet. Sie wurden drei verschiedenen zeitlichen und drei verschiedenen Tiefendimensionen zugeordnet und mit dem Schweizer und dem Österreichischem Pendant abgeglichen. Diskussion: Das vorliegende Konsensusstatement kann den deutschen Fakultäten eine Grundlage zur Planung der Vermittlung praktischer Fertigkeiten bieten und bildet einen wichtigen Schritt zu einem nationalen Standard medizinischer Lernziele.Blick in die Zukunft: Das Konsensusstatement soll einen formativen Effekt auf die medizinischen Fakultäten haben, ihre praktischen Unterrichtsinhalte entsprechend zu vermitteln und die Ressourcen danach zu planen.

  3. Die Zukunft der ärztlichen Weiterbildung in Deutschland – Positionspapier des Ausschusses Weiterbildung der Gesellschaft für Medizinische Ausbildung (GMA [The future of graduate medical education in Germany – Position paper of the committee on graduate medical education of the Society for Medical Education (GMA

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    Weih, Markus

    2013-05-01

    Full Text Available [english] The German graduate medical education system is going through an important phase of changes. Besides the ongoing reform of the national guidelines for graduate medical education (Musterweiterbildungsordnung, other factors like societal and demographic changes, health and research policy reforms also play a central role for the future and competitiveness of graduate medical education.With this position paper, the committee on graduate medical education of the Society for Medical Education (GMA would like to point out some central questions for this process and support the current discourse.As an interprofessional and interdisciplinary scientific society, the GMA has the resources to contribute in a meaningful way to an evidence-based and future-oriented graduate medical education strategy.In this position paper, we use four key questions with regards to educational goals, quality assurance, teaching competence and policy requirements to address the core issues for the future of graduate medical education in Germany. The GMA sees its task in contributing to the necessary reform processes as the only German speaking scientific society in the field of medical education.[german] Die ärztliche Weiterbildung in Deutschland befindet sich im Umbruch. Neben der aktuellen Reform der Musterweiterbildungsordnung spielen gesellschaftliche, demographische, gesundheits- und forschungspolitische Faktoren eine wichtige Rolle für die Zukunft und Konkurrenzfähigkeit der ärztlichen Weiterbildung.Der Ausschuss für Weiterbildung der Gesellschaft für Medizinische Ausbildung (GMA möchte mit diesem Positionspapier auf zentrale Fragen in diesem Prozess aufmerksam machen und Impulse für den aktuellen Diskurs geben.Dabei kann die GMA als interdisziplinäre und interprofessionelle Fachgesellschaft wichtige Beiträge zu einer evidenzbasierten und zukunftsorientierten Weiterbildungsstrategie liefern.Im vorliegenden Papier werden anhand von vier Leitfragen zu

  4. Public notice concerning safety guides of the Kerntechnischer Ausschuss (Rule KTA 3201. 2)

    Energy Technology Data Exchange (ETDEWEB)

    1985-01-30

    This standard is to be applied to components made of metallic materials, operated at design temperatures of up to 673 K (400/sup 0/C). The primary circuit as the pressure containment of the reactor coolant comprises: reactor pressure vessel (without internals), steam generator (primary loop), pressurizer, reactor coolant pump housing, interconnecting pipings between the components mentioned above and appropriate various valve and instrument casings, pipings branding from the above components and interconnecting pipings, including the appropriate instrument casings, up to and including the first isolating valve, pressure shielding of control rod drives.

  5. Public notice concerning safety guides of the Kerntechnischer Ausschuss (Rule KTA 3201.2)

    International Nuclear Information System (INIS)

    1985-01-01

    This standard is to be applied to components made of metallic materials, operated at design temperatures of up to 673 K (400 0 C). The primary circuit as the pressure containment of the reactor coolant comprises: Reactor pressure vessel (without internals), steam generator (primary loop), pressurizer, reactor coolant pump housing, interconnecting pipings between the components mentioned above and appropriate various valve and instrument casings, pipings branding from the above components and interconnecting pipings, including the appropriate instrument casings, up to and including the first isolating valve, pressure shielding of control rod drives. (orig.) [de

  6. Cutting and decontamination technologies for nuclear facility dismantling; Technologien zur Zerlegung und zur Dekontamination von kerntechnischen Anlagen

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    Huebner, Felix; Grone, Georg von; Schultmann, Frank

    2017-03-15

    The German Government's decision to phase-out nuclear power will lead to a substantial increase of the number of nuclear decommissioning and dismantling projects. The decommissioning of nuclear facilities must meet the requirements of the radiation protection ordinance. This study deals with the decontamination and dismantling technologies available to meet radiation protection requirements. The aim of this study is to determine the state of the art in the field of decommissioning and dismantling technologies. Furthermore, future trends in the development and application of such technologies should be identified. A detailed study of current literature provides an overview of established decommissioning technologies. Moreover, experts were consulted in order to facilitate a practical assessment. The experts' statements indicate that (apart from the chemical decontamination of the primary circuit) the use of mechanical methods is generally preferred. Abrasive methods are rated as particularly efficient. According to the experts, the development of new decontamination technologies may allow a more efficient decontamination. However, the success of a new technology will be subject to its application costs. Mechanical technologies are preferred for the dismantling of nuclear facilities. The band saw has been identified as a standard tool in nuclear dismantling. The survey has concluded that there is no need for new dismantling technologies. The potential lies in the optimization of existing processes and techniques. With regard to remotely operated systems, experts' opinions vary on whether the use of these systems will increase in future. Most areas inside a nuclear facility have low radiation levels that allow the use of human labour for the dismantling. However, there is a need for an improvement in the allocation and management of decommissioning projects.

  7. The draft on the act in the reorganisation of responsibility in nuclear waste management; Der Gesetzentwurf zur Neuordnung der Verantwortung in der kerntechnischen Entsorgung

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    Raetzke, Christian [CONLAR Consulting on Nuclear Law and Regulation, Leipzig (Germany)

    2016-12-15

    The German Federal Cabinet passed the draft ''Act for the Reorganisation of Responsibility in Nuclear Waste Management''. The individual elements of the act shape an overall concept. The public sector, also assumes the interim storage of the waste in addition to the previous responsibility for final disposal of radioactive waste. Both tasks will be financed by a new public fund into which the operators pay their provisions. By paying an additional risk premium the operators can also exclude future margin requirements. This new concept is to be welcomed because it would lead to a structurally viable and sustainable solution for the final disposal of nuclear wastes, not withstanding many difficulties and partly uncertainties in detail.

  8. The German act on the reorganisation of responsibility in nuclear waste management; Des Gesetz zur Neuordnung der Verantwortung in der kerntechnischen Entsorgung

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    Raetzke, Christian [CONLAR Consulting on Nuclear Law and Regulation, Leipzig (Germany)

    2017-04-15

    The author discussed the Draft on the Act in the Reorganisation of Responsibility in Nuclear Waste Management in atw 12 (2016). Now, amendments are discussed, which resulted from the legislative procedure until today's draft. Significant additions affect the authorisation for the conclusion of a public-law contract between the Federal Government and the nuclear power plant operators, the deadline for the payment of the basic amount, and the option for the operation of the interim storage facilities for a transitional period by the operators on behalf of the federal company. Since the adoption of the draft act, it has become clear that the nuclear power plant operators will pay the risk premium. This will fulfil the full logic of the new system. It has also become known, that the public law contract is now ready for signing. According to the author, the act will bring a final arrangement for financing nuclear waste disposal. However, adjustment can not be avoided in practice. The concrete implementation will be a exciting topic in many ways.

  9. Radiation protection. Measures in the event of a serious accident at a nuclear plant. Strahlenschutz. Massnahmen im Falle eines groesseren Unfalls in einer kerntechnischen Anlage

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    Riedel, W. (Klinikum Steglitz, Berlin (Germany))

    1990-04-01

    The report presents a fictitious scenarium conceived for the event of a release of radioactive substances in connection with a reactor accident, taking into account the geographic situation of Berlin. Depending on the dose to be expected, specific countermeasures of an organizational, administrative, and measurement-technical nature must be instituted. These include, inter alia, the formation of a group of experts, and measurements of the whole body, the skin and/or thyroid gland as a basis for the planned countermeasures. (DG).

  10. Climate change. Important findings from the 4. fact finding report of the intergovernmental commission on climate change of the United Nations (IPCC); Klimaaenderung. Wichtige Erkentnisse aus dem 4. Sachstandsbericht des Zwischenstaatlichen Ausschusses fuer Klimaaenderungen der Vereinten Nationen (IPCC)

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    Maeder, Claudia

    2009-12-19

    The Report covers the following topics: 1. anthropogenic climate change - since when do we know about it? 2. IPCC - the intergovernmental commission for climate change. 3. Assignable causes for climate change: changes of incoming solar radiation, changes of the reflected solar radiation, change of the heat radiation lost into space, aerosols, internal variability of the climate system. 4. Historical climate changes in long periods. 5. Development of the greenhouse gases in the atmosphere. 6. Observed climate changes. 7. Projections of future climate changes. 8. Consequences of climate change: consequences of the actual temperature increase, possible future consequences, freshwater resources and their management, ecosystems, agricultural production, coastal regions and low lying areas.

  11. Publication of the KTA 3702.1 safety rule of the Kerntechnischer Ausschuss from July 3, 1980. Stand-by units with diesel aggregates in nuclear power plants. Pt. 1

    International Nuclear Information System (INIS)

    1980-01-01

    The rule applies to stationary nuclear power plants. Depending on their application, one of the following diesel aggregates should be chosen: Stand-by aggregates, fast emergency aggregates, or no-delay emergency aggregates. (HP) [de

  12. Geographically application RFUE-WebGIS Rhineland-Palatinate/Saarland; RFUe-WebGIS Rheinland-Pfalz/Saarland. Geographisches Informationssystem (GIS) fuer den kerntechnischen Notfallschutz. Modulares Monitoring in statu nascendi

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    Lindenbeck, Christian; Kaiser, J. [in medias res, Freiburg/Breisgau (Germany); Amthauer, R.; Ren, Y.; Wilbois, Thomas [T-Systems GEI GmbH, Ulm (Germany); Mueller, B.; Seewald, C. [EES GmbH, Berlin (Germany); Fenn, H.; Hentzschel, R.; Maurer, M. [Ministerium fuer Wirtschaft, Klimaschutz, Energie und Landesplanung, Mainz (Germany)

    2014-01-20

    The geographically application RFUE-WebGIS integrates various FOSS (Free and Open Source Software) technologies to bring together the relevant data sources of the reactor remote monitoring (RFUE) in Rhineland-Palatinate and Saarland for the interests of the nuclear emergency response across national borders.

  13. Sites with nuclear facilities in the state of dismantling and their future from the public perspective; Standorte mit kerntechnischen Anlagen im Rueckbau und deren Zukunft aus der Perspektive der Bevoelkerung

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    Kretz, Simon Philipp

    2015-07-17

    The thesis on the public perspective at sites of nuclear facility dismantling covers the following issues: the change of German energy landscapes under social and political points of view, theoretical frame of the work, combination of empirical studies and the theoretical approaches in a space concept, action model and hypotheses on the situation and development in communities with nuclear facilities in the state of dismantling, description of the interviewees, and the empirical results of the interviews.

  14. A study of internal dosimetry of Am-241 and Sr-90 by dismantling of a nuclear installation; Eine Fallstudie zur internen Dosimetrie von Am-241 und Sr-90 bei Rueckbau einer kerntechnischen Anlage

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    Froning, M.; Hill, P. [Forschungszentrum Juelich GmbH (Germany). Geschaeftsbereich Sicherheit und Strahlenschutz

    2016-07-01

    During dismantling operation in former nuclear facility routine incorporation monitoring had been part of the safety measures. For an occupational radiation worker positive measurements results for {sup 241}Am, {sup 90}Sr and {sup 137}Cs were obtained after the end of the working period. Follow up monitoring had been performed assessing urine and faeces samples for {sup 241}Am and {sup 90}Sr as well as in-vivo measurements for {sup 137}Cs. Ingestion could be proven as incorporation path. The internal dose assessment according to GMBl 2007{sup [1]} finally yielded internal dose at 13 μSv.

  15. Application of the results of pipe stress analyses into fracture mechanics defect analyses for welds of nuclear piping components; Uebernahme der Ergebnisse von Rohrsystemanalysen (Spannungsanalysen) fuer bruchmechanische Fehlerbewertungen fuer Schweissnaehte an Rohrleitungsbauteilen in kerntechnischen Anlagen

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    Dittmar, S.; Neubrech, G.E.; Wernicke, R. [TUeV Nord SysTec GmbH und Co.KG (Germany); Rieck, D. [IGN Ingenieurgesellschaft Nord mbH und Co.KG (Germany)

    2008-07-01

    For the fracture mechanical assessment of postulated or detected crack-like defects in welds of piping systems it is necessary to know the stresses in the un-cracked component normal to the crack plane. Results of piping stress analyses may be used if these are evaluated for the locations of the welds in the piping system. Using stress enhancing factors (stress indices, stress factors) the needed stress components are calculated from the component specific sectional loads (forces and moments). For this procedure the tabulated stress enhancing factors, given in the standards (ASME Code, German KTA regulations) for determination and limitation of the effective stresses, are not always and immediately adequate for the calculation of the stress component normal to the crack plane. The contribution shows fundamental possibilities and validity limits for adoption of the results of piping system analyses for the fracture mechanical evaluation of axial and circumferential defects in welded joints, with special emphasis on typical piping system components (straight pipe, elbow, pipe fitting, T-joint). The lecture is supposed to contribute to the standardization of a code compliant and task-related use of the piping system analysis results for fracture mechanical failure assessment. [German] Fuer die bruchmechanische Bewertung von postulierten oder bei der wiederkehrenden zerstoerungsfreien Pruefung detektierten rissartigen Fehlern in Schweissnaehten von Rohrsystemen werden die Spannungen in der ungerissenen Bauteilwand senkrecht zur Rissebene benoetigt. Hierfuer koennen die Ergebnisse von Rohrsystemanalysen (Spannungsanalysen) genutzt werden, wenn sie fuer die Orte der Schweissnaehte im Rohrsystem ausgewertet werden. Mit Hilfe von Spannungserhoehungsfaktoren (Spannungsindizes, Spannungsbeiwerten) werden aus den komponentenweise berechneten Schnittlasten (Kraefte und Momente) die benoetigten Spannungskomponenten berechnet. Dabei sind jedoch die in den Regelwerken (ASME-Code, KTA-Regelwerk) zur Ermittlung und Begrenzung der Vergleichsspannungen tabellierten Spannungserhoehungsfaktoren nicht immer und unmittelbar zur Berechnung der Spannungskomponenten senkrecht zur Rissebene geeignet. Im Vortrag werden die grundsaetzlichen Moeglichkeiten und Gueltigkeitsgrenzen der Uebernahme der Ergebnisse von Rohrsystemanalysen zur bruchmechanischen Bewertung von Axial- und Umfangsfehlern in Schweissnaehten eroertert sowie fuer typische Rohrleitungsbauteile (Geradrohr, Rohrbogen, Formstueck, T-Stueck) spezifiziert. Der Vortrag soll insgesamt einen Beitrag leisten zur Vereinheitlichung der sicheren regelwerkskonformen und aufgabenbezogenen Nutzung der Ergebnisse vorliegender Rohrsystemanalysen bei der bruchmechanischen Fehlerbewertung. (orig.)

  16. Evaluation of scheduling problems for the project planning of large-scale projects using the example of nuclear facility dismantling; Evaluation von Schedulingproblemen fuer die Projektplanung von Grossprojekten am Beispiel des kerntechnischen Rueckbaus

    Energy Technology Data Exchange (ETDEWEB)

    Huebner, Felix; Schellenbaum, Uli; Stuerck, Christian; Gerhards, Patrick; Schultmann, Frank

    2017-05-15

    The magnitude of widespread nuclear decommissioning and dismantling, regarding deconstruction costs and project duration, exceeds even most of the prominent large-scale projects. The deconstruction costs of one reactor are estimated at several hundred million Euros and the dismantling period for more than a decade. The nuclear power plants built in the 1970s are coming closer to the end of their planned operating lifespan. Therefore, the decommissioning and dismantling of nuclear facilities, which is posing a multitude of challenges to planning and implementation, is becoming more and more relevant. This study describes planning methods for large-scale projects. The goal of this paper is to formulate a project planning problem that appropriately copes with the specific challenges of nuclear deconstruction projects. For this purpose, the requirements for appropriate scheduling methods are presented. Furthermore, a variety of possible scheduling problems are introduced and compared by their specifications and their behaviour. A set of particular scheduling problems including possible extensions and generalisations is assessed in detail. Based on the introduced problems and extensions, a Multi-mode Resource Investment Problem with Tardiness Penalty is chosen to fit the requirements of nuclear facility dismantling. This scheduling problem is then customised and adjusted according to the specific challenges of nuclear deconstruction projects. It can be called a Multi-mode Resource Investment Problem under the consideration of generalized precedence constraints and post-operational costs.

  17. Consequences of Fukushima 11032011 - Radiological consequences from the nuclear accidents in Fukushima on 11 March 2011; Fukushima Auswirkung 11032011 -- Radiologische Auswirkungen aus den kerntechnischen Unfaellen in Fukushima vom 11.03.2011

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-12-15

    On 11 March 2011 at 14.46 the strongest earthquake ever recorded in Japan struck the Pacific coast in front of Fukushima. The earthquake and the following tsunami damaged the nuclear power plants in Fukushima Dai-ichi to such an extent that the Japanese government declared the state of catastrophic accident with degree 7 according to the International Nuclear and Radiological Event Scale (INES). At Fukushima Dai-ichi there were 6 boiling water reactors (BWR), a storage pool for spent fuel assemblies and a dry cask storage. 12 km apart at Fukushima Dai-ni there were 4 more BWR. At the moment of the earthquake the reactors 1 to 3 of Fukushima Dai-ichi, as well as the 4 reactors at Fukushima Dai-ni, were at full power, while the reactors 4 to 6 of Fukushima Dai-ichi were shut down for revision. From 12 March 2011 on, fairly large quantities of radioactive materials were released from Fukushima Dai-ichi reactors with meaningful consequences on the population in the near neighbourhood. The irradiation from the radioactivity bearing clouds, the ingestion and inhalation, and the deposit of radioactive materials on the ground threatened the population. The inhabitants of large areas had to be evacuated. Furthermore, radioactive materials contaminated the drinking water, the sea water and finally the plants and animals, i.e. the food chain of the people living there. The Swiss Federal Nuclear Safety Inspectorate (ENSI) continuously proceeded with the evaluation of the situation in Japan and a specialists' team made a detailed analysis of the accident, with emphasis on the human and organisational factors and on the lessons learned from this. The present report describes the present knowledge about the radiological consequences of the accident in Fukushima Dai-ichi on the population in the neighbourhood and on the staff at the power plant, until October 2011. First, the unrolling of the accident and its consequences on the plant site are analysed according to international criteria. Then the transport of radioactive materials out of the reactors 1 to 3 is described and evaluated. The continuous mean discharge rate of radioactive materials is estimated and the treatment of the contaminated water accumulated in the power plant is explained. Through pressure release from the reactor containment and hydrogen explosions in the reactor buildings the released fission products gave rise to high dose rates on the plant site. The staff engaged on the plant was submitted to radiation exposure, what strongly worsened the working conditions. Because of the high radioactive background, the dosimetric surveillance was difficult. What regards the radiation exposure of the population in the neighbourhood of the plant through the released radioactive materials, in the first phase of the accident most of the dose was delivered through the crossing radioactive clouds and the inhaled radioactive dust. In the next phase the radioactive materials deposited on the ground contributed to a long-dated dose through external irradiation. Radioactive materials, which either directly or indirectly arrived on fodder plants and on greens, represent another important source of dose through ingestion. Besides, radioactive materials came into the food chain from lakes, rivers and sea through fish and sea fruits. Delivery of radioactive materials to surface waters contaminated drink water reservoirs and so contributed to higher radiation exposure. The Japanese government took measures to reduce the radiation exposure. The report also describes the effects of the Fukushima accident for the Swiss population and gives information on the most important measures and consequences for Switzerland. Finally the Fukushima accident is compared to the one in Chernobyl concerning the effects on the population and the environment. The release of radioactive materials at Chernobyl was 5 to 10 times higher than it was at Fukushima, and they were conveyed to much larger areas.

  18. Lessons Fukushima 11032011 -- Lessons learned and points to be checked from the nuclear accidents in Fukushima; Lessons Fukushima 11032011 -- Lessons learned und Pruefpunkte aus den kerntechnischen Unfaellen in Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-10-15

    Since a long time, severe accidents are one of the main areas in the surveillance activities of the Swiss Federal Nuclear Safety Inspectorate (ENSI). The analysis of events all over the world and the evaluation of their relevance for the Swiss nuclear power plants belong to the permanent obligations of the regulatory authority. In Switzerland, for more than two decades, core melting accidents are studied using probabilistic safety assessment methods. Comprehensive risk analyses were set up for external events like earthquakes, sabotages or airplane crashes. Strategies for the mitigation of the consequences of severe accidents, so-called Severe Accident Management Guidance (SAMG), were written down by the regulatory authority and made available to the Swiss plant operators. In international comparison the Swiss nuclear power plants have reached a very high standard in the field of severe accidents. Moreover, the safety of the Swiss plants is continuously reviewed by means of permanent supervision and especially through the 10-year periodic safety review. However, the Fukushima accident justifies a renewed evaluation on whether the preparation against severe reactor accidents could be improved and additional measures be taken for the protection of the population. In the present report, ENSI indicates points to be checked, which were considered as important in the course of the analysis of the Fukushima accident, for the future improvement of the nuclear safety and radiation protection in Switzerland. These points were identified from the analysis of the behaviour of the plant staff, techniques and organisation during the accident. The resulting measures concern the plant design, the emergency management, the feed-back from the encountered events, the surveillance, the radiation protection and the safety culture, with a special emphasis on the emergency management in Switzerland. The implementation of the necessary short-term measures was launched by ENSI decrees and is already partly fulfilled. The mean- and long-term measures will be introduced in action plans during the on-going surveillance of the plants. No significant deficiencies were identified in the Swiss power plants. The required improvement of the reliability of the cooling water supply in the nuclear power plant at Muehleberg was already implemented during the 2011 revision of the plant.

  19. Sensory testing of emissions from construction products. Integration into the Blue Angel award criteria and assessment scheme of the Committee for Health Evaluation of Building Products; Sensorische Bewertung der Emissionen aus Bauprodukten.- Integration in die Vergabegrundlagen fuer den Blauen Engel und das Bewertungsschema des Ausschusses zur gesundheitlichen Bewertung von Bauprodukten

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, Birgit; Danielak, Maciej [Technische Univ. Berlin (Germany); Panaskova, Jana [Technische Univ. Berlin (Germany); RWTH Aachen (Germany). Inst. for Energy Efficient Buildings and Indoor Climate; Horn, Wolfgang; Jann, Oliver [Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin (Germany); Mueller, Dirk [RWTH Aachen (Germany). Inst. for Energy Efficient Buildings and Indoor Climate

    2011-06-15

    Emissions from construction products impact the quality of indoor air considerably. The AgBB scheme is employed to evaluate the emissions of volatile organic compounds (VOC) from construction products. The hygienic evaluation according to the AgBB scheme requires product-specific measuring procedures. These exist for a range of products. They have been validated in co-operation with several research and testing institutes and have been included in the criteria for awarding the eco-label Blue Angel. The evaluation is, however, stricter and generally has lower limits. VOC emissions and odours can cause health problems so sensory testing is an important element in the evaluation of construction products and has - for reasons of precaution - been set down in the AgBB scheme. The main goal of the project is to derive a method of sensory evaluation and limits for awarding the Blue Angel and for the AgBB scheme. Based on the research conducted (see Chapter 5 Results and Discussion), perceived intensity and hedonics are suggested for the evaluation method. The derivation of limits for the sensory evaluation on the 28th day was effected in the present study through the additional questioning of the test subjects on the reasonability of a sample. For the Blue Angel, there could be different limits of perceived intensity and hedonic for each group of products. A preliminary suggestion for possible limits - here for all product groups - is a perceived intensity of 7 pi (5 pi + 2 pi as confidence coefficient, Chapter 5.1.5. ''Minimum Requirements for the Size of Test Groups'') and -1 (0{+-}0.8, rounded to -1) for the hedonic value (see Figure 6-1). (orig.)

  20. Durchführung der universitären Prüfungen im klinischen Abschnitt des Medizinstudiums nach den Leitlinien des GMA-Ausschusses Prüfungen: Eine Bestandsaufnahme der medizinischen Fakultäten in Baden-Württemberg [Implementation of assessments according to the guidelines of the GMA: A survey of the medical faculties in Baden-Württemberg

    Directory of Open Access Journals (Sweden)

    Jünger, Jana

    2010-08-01

    Full Text Available [english] With the introduction of the new medical licensing regulation [1] in 2002, a reform process was initiated nationwide that aimed to redesign medical degree programs at universities to make them more practice-oriented and to establish quality assurance in teaching. Five centers of excellence were set up at the medical schools in Baden-Württemberg that merged to form the Network for Excellence in Medical Education.The Network for Excellence in Medical Education carried out a survey among the five medical schools in Baden-Württemberg on the implementation of the requirements set down in the GMA guidelines for university-specific, high-quality assessments during the clinical phase of medical studies. The network’s next steps for improving the quality of assessments at medical schools were prioritized in order to determine the urgency of support to be given to Baden-Württemberg’s faculties of medicine in implementing the GMA requirements.It became apparent that essential parts of the requirements formulated in the guidelines had already been fulfilled or at least could be fulfilled in the near future. It was observed that establishing structured review processes during assessment preparation and in particular the follow-up presented considerable difficulties. A focus group analysis identified the following objectives for the network: supporting medical schools in their review processes; compiling a comprehensive assessment program and assessment reports with statistical analysis. Training the people responsible for assessment is another priority.The results largely correspond to those from a similar survey carried out among medical schools in Bavaria and show that organizational structures, such as those that have been established in the centers of excellence in education and assessment in Baden-Württemberg and Bavaria, can offer essential support in the quality assurance of assessment.[german] Mit der Einführung der novellierten Ärztlichen Approbationsordnung im Jahr 2002 wurde bundesweit ein Reformprozess in Gang gesetzt, mit dem Ziel, das Medizinstudium an den Universitäten praxisorientierter zu gestalten und eine Qualitätssicherung im Bereich der Lehre zu etablieren. Um hierbei die medizinischen Fakultäten Baden-Württembergs zu unterstützen, wurden fünf Kompetenzzentren an den medizinischen Fakultäten des Landes gegründet, die sich zum Kompetenznetz Lehre Baden-Württemberg zusammengeschlossen haben.Das Kompetenznetz Lehre hat an den fünf medizinischen Fakultäten Baden-Württembergs eine Befragung zum Umsetzungsstatus der in der GMA-Leitlinie für fakultätsinterne Leistungsnachweise dargelegten Anforderungen an qualitativ hochwertige Prüfungen im klinischen Abschnitt des Medizinstudiums durchgeführt. Um den vordringlichen Bedarf für die Unterstützung der medizinischen Fakultäten des Landes Baden-Württemberg bei der Umsetzung der Leitlinien durch das Kompetenznetz Lehre zu ermitteln, wurde eine Priorisierung der nächsten Aufgaben bei der Verbesserung der Qualität der universitären medizinischen Prüfungen vorgenommen.Es zeigte sich, dass wesentliche Teile des in den Leitlinien formulierten Anforderungskatalogs bereits erfüllt wurden oder wenigstens mittelfristig an den Fakultäten umsetzbar sind. Festgestellt wurde aber, dass die Etablierung strukturierter Reviewprozesse bei der Prüfungsvorbereitung und insbesondere der Nachbereitung noch auf deutliche Schwierigkeiten stößt. Im Rahmen einer Fokusgruppenanalyse wurden als vorrangige Arbeitsziele für das Kompetenznetz Lehre die Unterstützung der medizinischen Fakultäten für den Begutachtungsprozess der Prüfungsaufgaben („Review“, die Erstellung eines Gesamtprüfungsprogramms und von Prüfungsberichten mit statistischer Auswertung definiert. Einen weiteren Schwerpunkt bildet die Qualifizierung von Prüfungsverantwortlichen zum Thema Prüfungen.Die Ergebnisse decken sich im Wesentlichen mit einer ähnlichen Befragung der medizinischen Fakultäten in Bayern und zeigen, dass organisatorische Strukturen, wie sie mit den Kompetenzzentren für Lehre und Prüfungen in Baden-Württemberg und Bayern geschaffen wurden, eine wesentliche Hilfestellung bei der Qualitätssicherung von Prüfungen bieten können.

  1. Autonomy of industry - possibilities and limits in a pluralistic society

    International Nuclear Information System (INIS)

    Schoch, W.

    1976-01-01

    Examples of free enterprise acting on its own responsibility are given which relate to the state-independent area in which the state has no need to intervene, or to an area in which the state cooperates with the autonomous forces of society in solving tasks as one of the responsible partners. The examples are a) the Arbeitsgemeinschaft Druckbehaelter (AD), b) the Deutsches Institut fuer Normung (DIN), c) the Deutscher Dampfkessel-Ausschuss (DDA) and the Kerntechnischer Ausschuss (KTA) as the initiators of standards, and d) the Technische Ueberwachungs-Vereine (TUeV) as service organizations. (orig./HP) [de

  2. Measurement of Kr-85 and Xe-133 as undisturbed tracers for the representing of atmospheric transport after disposal of radioactivity from nuclear facilities; Messungen von Kr-85 und Xe-133 als ungestoerte Tracer zur Darstellung atmosphaerischer Transportvorgaenge nach Freisetzung von Radioaktivitaet aus kerntechnischen Anlagen

    Energy Technology Data Exchange (ETDEWEB)

    Frank, G.; Steinkopff, T. [Deutscher Wetterdienst (Germany); Salvamoser, J. [Institut fuer Angewandte Isotopen-, Gas- und Umweltuntersuchungen (IGU), Woerthsee (Germany)

    2016-07-01

    The Deutscher Wetterdienst (DWD, German Meteorological Service) operates since 1996 a sampling and measurement device for the radioactive rare gases Kr-85 and Xe-133 in Offenbach. These measurements are embedded in the German Measurement and Information System for Monitoring Environmental Radioactivity (Integriertes Mess- und Informationssystem zur Ueberwachung der Radioaktivitaet in der Umwelt, IMIS) [1]. In addition to these measurements the DWD is sampling rare gases in Potsdam and since 2014 in Trier in cooperation with the Bundesamt fuer Strahlenschutz (Federal Office for Radiation Protection, BfS). In the frame of the Global Atmosphere Watch (GAW)-program of the WMO the DWD operated a sampling station at the Zugspitze (Schneefernerhaus) from 1999 to 2005. This location at the Zugspitze is well suited for the observation of long distance transport of Kr-85 in the higher atmosphere. The DWD in Offenbach operates a complex analytical system for the measurement of Kr-85 and Xe-133 since 1998. This system consists of sampling with first enrichment, second enrichment, gas chromatographic separation and preparation of Krypton and Xenon and measurement of Kr-85 and Xe-133. Using the example Fukushima, it is shown, that the radioactive rare gases Kr-85 and Xe-133 are well undisturbed tracers for atmospheric transport in case of a nuclear accident or routine nuclear reprocessing plants. Measurements of Xe-133, I-131, Cs-137 and Kr-85 are correlated with source and atmospheric transport to the sampling sites at Offenbach and Potsdam.

  3. Public information regarding radioactive emissions from nuclear power plants in North-Rhine Westphalia. Radiation protection report for April, May and June 1986. Unterrichtung der Oeffentlichkeit ueber radioaktive Emissionen aus kerntechnischen Anlagen in Nordrhein-Westfalen. Strahlenschutzbericht fuer die Monate April, Mai und Juni 1986

    Energy Technology Data Exchange (ETDEWEB)

    1986-01-01

    A short survey of the consequences of the reactor accident at Chernobyl with regard to the Land North-Rhine Westphalia is followed by information about radioactive emissions from nuclear power plants in North-Rhine Westphalia.

  4. The KWS training power plant Zwentendorf. Optimal conditions for practical training in the sectors of maintenance and dismantling of nuclear power plants; Das KWS-Schulungskraftwerk Zwentendorf. Die ideale Voraussetzung fuer praktische Schulungen in den Bereichen Instandhaltung und Rueckbau von kerntechnischen Anlagen

    Energy Technology Data Exchange (ETDEWEB)

    Maassen, Herbert [KRAFTWERKSSCHULE E.V., Essen (Germany). Weiterbildung Instandhaltung fuer konventionelle-/kerntechnische Anlagen und erneuerbare Energien

    2014-06-15

    In consequence of several years of interbranch staff reduction, started middle of the 1990th, at producers of power plant installation engineering, at plant service companies as well as at the operators of power plants and nuclear power plants themselves, an area-wide decline in know-how took place, which put the safe performance of maintenance activities in nuclear power plants more and more into question. The search for adequate training possibilities to cover these deficits lead to the reorganization of the nuclear power plant Zwentendorf at the year 2002, which was changed into a training facility for maintenance trainings, particularly for the sectors of reactor service, decommissioning and dismantling of nuclear power plants and other types of power plant specific training measures. For this purpose Zwentendorf was upgraded and transformed within a long-time process, and its combination may be considered as unique throughout the world. The Kraftwerksschule e.V. (KWS) owns the exclusive rights for the performance of training measures at Zwentendorf. During the last 10 years the KWS has made almost all sectors of this nuclear power plant accessible for trainings and inspections and offers a large training program. It is the aim of the training measures to ensure the operational reliability of the mechanical and installation engineering of nuclear power plants as well as fossil fired power plants in the long term through optimized maintenance planning and performance and therefore to operate the plants safely. Because of the direct practical reference to the original mechanical and installation engineering in the real atmosphere of a power plant, the nuclear power plant of Zwentendorf is highly suitable as a training centre for staff training in theory and practice. (orig.)

  5. Quality management in nuclear power plant technology

    International Nuclear Information System (INIS)

    Brosche, D.; Ehrnsperger, K.

    2001-01-01

    Quality assurance and therefore quality management are essential preconditions for the safety and availability of nuclear power plants. On the basis of the rules of the Kerntechnischer Ausschuss KTA 1401 the quality management in the former Bayernwerk AG and the Bayernwerk Kernenergie GmbH as well as in the Arbeitsgemeinschaft Auftragnehmerbeurteilung within the VGB Technical Association of Large Power Plant Operators is described. (orig.) [de

  6. Supervision of fuelling stations and pipelines; Ueberwachung von Tankanlagen und Rohrleitungen

    Energy Technology Data Exchange (ETDEWEB)

    Leimbach, W. [Rietschle Thomas Puchheim GmbH (Germany). ASF Leckanzeiger Systeme

    2005-08-01

    Construction of fuelling stations and fuel stores requires deep knowledge in order to ensure uninterrupted operation according to specifications (TRbF 20 Laeger and TRbF 40 Tankstellen). Even after the coming into force of the Operational Safety Ordinance (Betriebssicherheitsverordnung), the current technical rules will remain in force until new technical rules will have been developed by the Experts Committee for Operational Safety (Ausschuss fuer Betriebssicherheit) and published by the Federal Minister of Economy and Labour. (orig.)

  7. Deregulation in the field of decommissioning and dismantling of nuclear facilities. Legal frame conditions and regulations in the field of nuclear engineering; Deregulierung bei der Stillegung und Beseitigung nuklearer Anlagen; Rechtliche Rahmenbedingungen und kerntechnisches Regelwerk

    Energy Technology Data Exchange (ETDEWEB)

    Kurz, A [Kernforschungszentrum Karlsruhe GmbH (Germany). Vorstandsbereich 2 - Neue Technologien und Grundlagenforschung; Baumgaertel, G [Kernforschungszentrum Karlsruhe GmbH (Germany). Koordinationsstelle Genehmigungsverfahren (KGV)

    1994-05-01

    The report comprises two articles covering current topics of the decommissioning and dismantling of nuclear facilities. In the first article written by Kurz, the legal standards are listed together with conclusions and proposals regarding their implementation for the further development of this field of law. The article by Baumgaertel is aimed at evaluating the regulations governing nuclear technology as regards their applicability to the decommissioning and dismantling of nuclear facilities. These articles shall contribute to the discussions taking place in this field at the moment. As a result, an appropriate and project-specific application of the legal provisions and not legally binding (technical) regulations in the field of nuclear technology (deregulation) in the licensing procedures required for the decommissioning and dismantling of nuclear facilities is requested by the authors. (orig.) [Deutsch] Der Bericht enthaelt zwei Ausarbeitungen zu aktuellen Themenstellungen der Stillegung und Beseitigung nuklearer Anlagen. Der Bericht von Kurz beinhaltet eine thesenartige Auflistung der normativen Voraussetzungen mit Schlussfolgerungen und Umsetzungsvorschlaegen zur Weiterentwicklung dieses Rechtsgebietes; die Ausarbeitung von Baumgaertel beinhaltet eine wertende Durchsicht des kerntechnischen Regelwerkes im Hinblick auf die Anwendbarkeit bei der Stillegung und Beseitigung nuklearer Anlagen. Die Ausarbeitungen dienen als Beitrag zur aktuellen Diskussion in diesem Themenfeld. Im Ergebnis fordern die Autoren die angemessene, vorhabensspezifische Anwendung der rechtlichen Voraussetzungen des kerntechnischen Regelwerkes (Deregulierung) in den zur Stillegung und Beseitigung nuklearer Anlagen erforderlichen Genehmigungsverfahren. (orig.)

  8. 25 Jahre Empowerment der Frau 25 Years of Female Empowerment

    Directory of Open Access Journals (Sweden)

    Sarah Wittkopp

    2008-07-01

    Full Text Available Anlässlich des 25-jährigen Jubiläums des Ausschusses des Übereinkommens zur Beseitigung jeder Form von Diskriminierung der Frau (United Nations Convention on the Elimination of All Forms of Discrimination against Women, CEDAW wird in dem Buch The Circle of Empowerment eine Bilanz der Arbeit des Vertragsorgans gezogen. Herausgegeben von Hanna Beate Schöpp-Schilling, dem deutschen Mitglied im CEDAW-Ausschuss seit 1989, und Cees Flinterman, dem niederländischen Mitglied seit 2003, enthält der Band Essays und persönliche Reflexionen von ehemaligen oder gegenwärtigen Mitgliedern des CEDAW-Ausschusses und UN-Mitarbeitern. Das Buch eignet sich als Einstieg in und Überblick über die Frauenrechtskonvention für Frauenrechtler/-innen, Wissenschaftler/-innen und Studierende, da es ein differenziertes Bild der Konvention, ihrer Mechanismen und ihrer Umsetzungsprobleme zeichnet. Gleichzeitig werden Hintergründe der tatsächlichen Arbeit eines Vertragsorgans beleuchtet, die sonst verschlossen bleiben.In celebration of the 25-year anniversary of the United Nations Convention on the Elimination of All Forms of Discrimination against Women (CEDAW, the book The Circle of Empowerment analyses the results of the work of this treaty institution. The volume, edited by Hanna Beate Schöpp-Schilling, German member in the CEDAW-commission since 1989, and Cees Flinterman, Dutch member since 2003, contains essays and personal reflections from former and current members of the CEDAW-commission and UN staff. The book is an appropriate introduction into and overview of the convention on women’s rights for activists, scholars, and students because it sketches a differentiated image of the convention, its mechanisms, and problems of implementation. At the same time, the book illuminates the background issues of the treaty institution’s actual work, something that normally remains secret.

  9. Quality assurance of civil works during the construction of a nuclear power plant in Germany, F.R

    International Nuclear Information System (INIS)

    Hillemeier, B.

    1980-01-01

    During the construction of Nuclear Power Plants in Germany extended system-oriented steps will have to be mentioned, which the 'Kerntechnischer Ausschuss' has gathered up in his KTA-rules. The lecture outlines the organization and the performance of QA-requirements which are the common and lawful basis for the construction in Germany. The organizational structure and the functional responsability assignments at HOCHTIEF, one of the leading European contractors, will be represented. At last the QA-procedures will be described for a Nuclear Power Plant under erection. (orig.)

  10. Quality assurance systems - a means for an integrating organization of nuclear power plants

    International Nuclear Information System (INIS)

    Adams, H.W.

    1984-01-01

    The operators of nuclear power plants are in the process of introducing quality assurance systems of the type required in Rule 1401 by the German Kerntechnischer Ausschuss (Nuclear Technology Committee). These systems as a cross sectional function cover most of the organizational areas of a nuclear power plant. Their introduction offers an opportunity to harmonize and supplement existing systems where necessary. Integrated quality assurance systems built up on a data base allow existing DP data and other logical data to be organized in such a way that certain sequences of events can be managed by enforced control. This relieves the personnel responsible for the safety of a nuclear power plant of routine jobs and routine decisions. Greater flexibility is created for personal decisions. Organized sequences of events can be monitored by having lists printed out in which the necessary data are combined into data sets. (orig.) [de

  11. Annual report 1974

    International Nuclear Information System (INIS)

    1975-01-01

    The 1974 annual report deals with the work of the 'Kerntechnischer Ausschuss' (KTA) in its second year of existence. While in 1973 a great deal of time was necessarily spent on questions of organization and procedure, the regulatory work is prominent in 1974. This is illustrated by the following facts: Of 26 regulatory guides under review two have been wound up privisionally as the KTA approved the publication of these regulatory guides drafts. Another 16 regulatory guides have gone through the preliminary reporting phase, and a motion was passed to start the work on the regulatory guide drafts. The description of the activities concerning regulatory work is arranged according to subjects in order to make the report easy to survey. (orig./LN) [de

  12. Automation of ultrasonic testing, instrumentation and rules for application and evaluation. Proceedings; Automatisierung der Ultraschallpruefung, Geraetetechnik und Regeln zur Anwendung und Auswertung. Vortraege des Seminars

    Energy Technology Data Exchange (ETDEWEB)

    Wuestenberg, H. [comp.

    1997-12-31

    The proceedings volume contains 18 lectures of the seminar addressing the following (selected) aspects: Requirements to be met by PC cards for US testing applications, defined by producers and appliers; digital technology and its impact on multichannel US testing instruments; the ALOK and array systems combined into one very efficient testing system (SAPHIR); a testing system combining US radiation source arrays and the pulsed eddy current method by means of highly integrated microelectronics (ASICs); regulatory standards and specifications for automated US testing; requirements for automated US testing in compliance with nuclear engineering codes; state of the art in standardisation for definition of required properties of US testing systems; critical review of the proposed standard relating to the TOFD method; automated evaluation shown with the example of US testing of pipelines. (orig./CB) [Deutsch] Dieser Band enthaelt 18 Vortraege mit folgenden Themen (Auswahl): Anforderungen an Ultraschall-PC-Karten aus der Sicht von Hersteller und Betreiber; Einfluss der Digitaltechnik auf Mehrkanal-Ultraschall-Pruefanlagen; Vereinigung der ALOK- und der Gruppenstrahler-Technik in einem leistungsfaehigen Pruefsystem (SAPHIR); Ein kombiniertes Pruefsystem fuer die Ultraschall-Gruppenstrahler- und Impuls-Wirbelstrom-Technik auf der Basis von hochintegrierter Mikroelektronik (ASICs); Regelwerke und Spezifikationen fuer die automatisierte Ultraschallpruefung; Anforderungen der kerntechnischen Regelwerke an die automatisierte Ultraschallpruefung; Stand der Normung bei der Charakterisierung der Eigenschaften von Ultraschall-Pruefsystemen; Kritische Bewertung des Normungsvorschlages zur Beugungslaufzeittechnik (TOFD); und Automatisierte Auswertung am Beispiel der Ultraschallpruefung von Fernrohrleitungen. (orig.)

  13. Organizing nuclear power plant operation

    International Nuclear Information System (INIS)

    Adams, H.W.; Rekittke, K.

    1987-01-01

    With the preliminary culmination in the convoy plants of the high standard of engineered safeguards in German nuclear power plants developed over the past twenty years, the interest of operators has now increasingly turned to problems which had not been in the focus of attention before. One of these problems is the organization of nuclear power plant operation. In order to enlarge the basis of knowledge, which is documented also in the rules published by the Kerntechnischer Ausschuss (Nuclear Technology Committee), the German Federal Minister of the Interior has commissioned a study of the organizational structures of nuclear power plants. The findings of that study are covered in the article. Two representative nuclear power plants in the Federal Republic of Germany were selected for the study, one of them a single-unit plant run by an independent operating company in the form of a private company under German law (GmbH), the other a dual-unit plant operated as a dependent unit of a utility. The two enterprises have different structures of organization. (orig.) [de

  14. On-line monitoring and inservice inspection in codes; Betriebsueberwachung und wiederkehrende Pruefungen in den Regelwerken

    Energy Technology Data Exchange (ETDEWEB)

    Bartonicek, J.; Zaiss, W. [Gemeinschaftskernkraftwerk Neckar GmbH, Neckarwestheim (Germany); Bath, H.R. [Bundesamt fuer Strahlenschutz, Salzgitter (Germany). Geschaeftsstelle des Kerntechnischen Ausschusses (KTA)

    1999-08-01

    Betriebsueberwachung und wiederkehrende Pruefungen in angemessenem Umfang. In auslaendischen kerntechnischen Regelwerken erfolgt die Absicherung im Betrieb hauptsaechlich durch zerstoerungsfreie wiederkehrende Pruefungen, wobei der Umfang und die Pruefintervalle vorwiegend vom ASME-Code, Section XI abgeleitet wurden. (orig.)

  15. Decommissioning and dismantling: Qualification of the gamma scanning method as a certified method for radiological decontrolling measurement. Final report; Stillegung und Rueckbau: Qualifizierung des Gamma-Scanning zur Freimessung. Genehmigungspraxis. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Kirchhoff, J.; Stasch, W.P.

    1998-10-01

    Prior to release from the radiological supervision and control regime of the AtG (German Atomic Energy Act), nuclear facilities have to be scanned using licensed radioactivity measuring methods for providing evidence that the remaining radioactive contamination is below the legally defined limits and excludes hazards to the population, material goods, or the environment. The manually performed {alpha}/{beta} measuring methods applied so far for radiological decontrolling measurement are surface scanning methods measuring the contamination of very thin surface layers of the structures, while radioactivity in deeper layers is not necessarily detected. The gamma scanning method presented in this document is capable of scanning the structures and materials of nuclear facilities from the surface down to much deeper layers in just one measuring run. The automated scanning process at the same time offers the advantage of preventing the uncertainties possibly contributed through human factors. (orig./CB) [Deutsch] Vor der Entlassung von kerntechnischen Anlagen aus dem Geltungsbereich des AtG ist sicherzustellen, dass von der Anlage nach Freigabe aus der atomrechtlichen Ueberwachung keine Gefahren fuer Personen, Sachgueter und die Umwelt ausgehen koennen. Hierzu sind die Anlagen freizumessen, d.h. es ist durch qualifizierte Messverfahren sicherzustellen, dass festgelegte radiologische Grenzwerte unterschritten werden. Die bisherigen auf {alpha}/{beta}-Messung beruhenden Freimessverfahren (Kontaminationsmonitore) erfassen nur die Radioaktivitaet in duennsten Oberflaechenschichten. Radioaktivitaet in darunter liegenden Schichten wird nicht zwangslaeufig erfasst. Zudem erfolgen diese Messungen ausschliesslich manuell. Das Gamma-Scanning-Freimessverfahren erfasst neben der Oberflaechenschicht gleichzeitig auch tiefere Schichten. Der Nachweis der Grenzwertunterschreitung kann somit in nur einem Arbeitsgang erbracht werden. Durch automatisiertes Scannen koennte darueber hinaus

  16. Status of the inservice inspection in codes; Stand der wiederkehrenden Pruefung im Regelwerk

    Energy Technology Data Exchange (ETDEWEB)

    Hienstorfer, W G [TUEV Energie- und Systemtechnik GmbH Baden-Wuerttemberg, Filderstadt (Germany); Hansch, M [Preussische Elektrizitaets-AG (Preussenelektra), Hannover (Germany); Koenig, G [Gemeinschaftskernkraftwerk Neckar GmbH, Neckarwestheim (Germany); Bath, H R [Kerntechnischer Ausschuss (KTA), Salzgitter (Germany)

    1998-11-01

    The body of regulatory nuclear engineering and inspection codes and subordinate codes defines on the one hand the general framework conditions for determination of the scope of inservice inspections, and on the other hand, for some defined components, contains detailed provisions relating to the scope of inservice tests to be made. These provisions are based on operating experience and engineering analyses. In order to establish a basis for optimization, the codes have been reviewed for possible optimization potentials, including a comparative analysis of foreign regulatory codes and approaches and the German codes. The conclusion drawn was that there is room for optimization, which should be done taking into account the following aspects: 1. Instrumentation for inservice monitoring of the state variables of relevance to the integrity of the primary loops has to be adapted, requiring acquisition of data showing local loading conditions and specific risks. 2. Inservice examinations of components and pipework should be optimized on the basis of updated, real-status information, i.e. upon availability of latest data showing verified operational loads and stresses and degradation mechanisms and risks, inspection methods, scopes and intervals can be optimized taking into account manufacturing quality. (orig./CB) [Deutsch] In dem aus gesetzlichen und untergesetzlichen Regelungen bestehenden kerntechnischen Regelwerk werden einerseits allgemeine Randbedingungen fuer die Bestimmung des Umfangs wiederkehrender Pruefungen vorgegeben und andererseits fuer einige Komponenten konkrete Festlegungen zum Pruefumfang getroffen. Diesen Festlegungen zum Pruefumfang lagen Betriebserfahrungen und ingenieurmaessige Analysen zugrunde. Als Grundlage fuer eine Optimierung der bisherigen Pruefumfaenge wurden die diesbezueglichen Moeglichkeiten des deutschen Regelwerks untersucht und ein Vergleich mit der Herangehensweise in den wichtigsten auslaendischen Regelwerken durchgefuehrt. Es zeigt

  17. Nuclear power and the logic of globalization; Politisierung der Wirtschaft, Rueckfall in den alten Nationalstaat

    Energy Technology Data Exchange (ETDEWEB)

    Weizsaecker, C.C. von [Koeln Univ. (Germany). Energiewirtschaftliches Inst.

    2000-02-01

    Denkprozess ist in Deutschland noch nicht verinnerlicht, da Kernenergie als kapitalintensive Technik fuer suedliche Laender als nicht geeignet angesehen wird. Es ist aber voellig illusorisch zu glauben, dass wir in Deutschland mit dem Ausstieg aus der Kernenergie ein Vorbild abgeben, dem andere Laender nacheifern werden. Vielmehr entsteht fuer uns die moralische Frage, wodurch wir helfen koennen, die Unfallrisiken von kerntechnischen Anlagen weltweit zu minimieren. Das koennen wir nur, indem wir bei der Kernenergie bleiben und unser Sicherheitsniveau exportieren, denn die Risiken werden nicht kleiner, indem wir aussteigen. (orig.)

  18. Empfehlungen zur Begutachtung eines Manuskriptes für die GMS Zeitschrift für Medizinische Ausbildung [Recommendations for reviewing a manuscript for the GMS Zeitschrift für Medizinische Ausbildung

    Directory of Open Access Journals (Sweden)

    Schüttpelz-Brauns, Katrin

    2010-11-01

    Full Text Available [english] The aim of this paper, written by the committee of educational research methodology of the “Society for Medical Education” of the German-speaking countries, will give recommendations for the review process of scientific papers in medical education. The recommendations are based on the results of a workshop in 2007 and on a survey among reviewers of the journal GMS Z Med Ausbild. It reflects on international standards and research in medical education in Germany. The paper describes reviewer’s function concerning the journal of GMS Z Med Ausbild and specifies criteria for the review process with regard to the editors and reviewers; it also gives proposals for a feedback to the author. The catalogue of criteria for the reviewers is pictured in a checklist. The present recommendations shall help to increase the quality of the review process and to improve the national and international acceptance of the journal GMS Z Med Ausbild. Additionally, transparency of the review processes will support authors to submit a scientific article of high quality. [german] Ziel des vorliegenden Artikels des „Ausschusses für Methodik der Ausbildungsforschung“ der Gesellschaft für Medizinische Ausbildung ist, Empfehlungen für die Begutachtung von Manuskripten in der medizinischen Ausbildungsforschung vorzustellen. Die Empfehlungen basieren auf den Ergebnissen eines Workshops 2007 und einer Befragung von Gutachtern. Sie berücksichtigen darüber hinaus sowohl internationale Standards als auch die Situation der medizinischen Ausbildungsforschung in Deutschland. Es werden die Aufgaben eines Gutachters der GMS Z Med Ausbild dargelegt und Kriterien für den Begutachtungsprozess sowohl für die Herausgeber als auch für die Gutachter beschrieben. Sie enthalten außerdem Vorschläge für ein Autoren-Feedback. Der Kriterienkatalog für die Gutachter wird darüberhinaus in einer Checkliste abgebildet. Die vorliegenden Empfehlungen sollen dazu beitragen

  19. Instrucción provisional para el empleo de puntos de soldadura eléctrica por resistencia en las construcciones de acero

    Directory of Open Access Journals (Sweden)

    Batanero, J.

    1963-06-01

    Full Text Available As an initial measure to generalise spot welding in the field of metallic structures, the Deutsche Ausschuss fur Stahlbau has issued a provisional specification, of which a full translation is given in this paper. The Specification includes a number of rules, as well as comments and recommendations on the method of establishing the aptitude of a given firm, or a workshop, to practise this spot welding technique. The various chapters of these Specifications give an account of the fundamental calculation principles and the best practise that should be followed in this type of welding. Advise is also offered on the initial care to be taken in applying these principles and specifications in actual practice. The comments that follow serve to clarify and explain the reasons which underlie the various conditions specified in this text. Finally, the recommendations on the method of establishing the aptitude of given workshops to undertake spot welding work are based on the following principle: the construction of structures with spot welded joints can only be entrusted to people who have attained a certain standard of skill, precisely because these structures are meant to be load bearing, and their real strength cannot be checked in practise, a posteriori, except by means of destruction tests. The full text of these Provisional Specifications will be given in three consecutive numbers of the magazine.La soldadura por resistencia es un medio de unión que, en ocasiones, puede resultar muy cómodo y económico. En las estructuras metálicas puras se ha venido empleando poco hasta ahora, aunque su utilización estaba bastante difundida en el empalme a tope de redondos, formación de parrillas de losas y tuberías, etc., con destino a las estructuras de hormigón. Sin embargo, las experiencias realizadas en los últimos años han demostrado que los puntos de soldadura por resistencia pueden constituir medios de unión que, bajo ciertas condiciones

  20. Full speed ahead into a blind alley?; Mit Vollgas in die Sackgasse?

    Energy Technology Data Exchange (ETDEWEB)

    Berke, C.

    1999-01-01

    For many decades, Dr. Claus Berke worked at the interface of technology and politics. This is particularly true of nuclear technology. Between 1985 and 1989, he was Chairman of the Kerntechnische Gesellschaft; between 1989 and 1995, President of the Deutsches Atomforum. In Brussels, he was President of Foratom for a period of two years. Dr. Berke has been distinguished by a number of awards for his services. The Kerntechnische Gesellschaft has now appointed him its Honorary Member in recognition of his commitment to nuclear technology. The article is an excerpt from a speech made by Dr. Berke to the KTG at the awarding ceremony. Dr. Berke deals with the question why the acceptance of nuclear power in this country has become so negative, in contrast to the situation with our main competitors on the world market, especially France. He traces the growth of ideologies in the German political party scene, which resulted in destroying national unity in this important issue for the future. He feels that one of the major reasons for this development lies in the considerable loss of reputation and influence in the German public of science and engineering over the past thirty years. The situation with our French neighbors is quite different. Already French schools attach particular importance to mathematics, biology, physics, and chemistry. As a consequence, technical and scientific curricula are very attractive in France, while Germany is heading toward the paradoxical situation that industry will soon be short of more than ten thousand young engineers annually, while German universities produce a surplus of humanists for whom there will often be no proper jobs. (orig.) [Deutsch] Dr. Claus Berke war viele Jahrzehnte lang dort erfolgreich taetig, wo sich Technik und Politik beruehren. Das gilt insbesondere fuer die Kerntechnik. Von 1985 bis 1989 war er Vorsitzender der Kerntechnischen Gesellschaft und von 1989 bis 1995 Praesident des Deutschen Atomforums. In Bruessel hat er

  1. Enlarged level-1 PSA in regard to assessment of cross-cutting effects of hazards and consideration of their uncertainties for a KONVOI type PWR reference plant; Erweiterte PSA der Stufe 1 im Hinblick auf die Behandlung uebergreifender Einwirkungen und die Beruecksichtigung ihrer Unsicherheiten am Beispiel einer Anlage vom Typ Konvoi

    Energy Technology Data Exchange (ETDEWEB)

    Haider, C.; Hofer, E.; Kloos, M.; Kuntze, W.; Liemersdorf, H.; Roewekamp, M.; Schwinges, B.; Tuerschmann, M.; Brenig, H.W.; Sommerfeld, H.

    2001-06-01

    examination for aircraft crashes, explosion shock waves from accidents in the close vicinity of the plant, seismic hazards, external flooding, and extreme weather conditions has been performed within this report. A probabilistic estimation was performed for all of these events except the seismic. None of them gave a significant contribution to the total damage frequency. A procedure for the estimation of uncertainties of external hazards was developed exemplary for the aircraft crash based on an experts questionnaire. (orig.) [German] Im Rahmen der fachlichen Unterstuetzung des BMU bei uebergeordneten Fragen zu probabilistischen Sicherheitsanalysen von Kernkraftwerken und bei der kerntechnischen Regelerarbeitung sollten die massgebende Beitraege fuer Schadenszustaende aus uebergreifenden internen und externen Einwirkungen fuer eine Referenzanlage von Typ DWR-Konvoi ermittelt und dabei Methoden zur probabilistischen Bewertung solcher Einwirkungen auf ihre Eignung hin geprueft werden. Von den grundsaetzlich zu betrachtenden uebergreifenden Einwirkungen wurde im Rahmen des vorliegenden Berichts nur das anlageninterne Ereignis Brand eingehend probabilistisch untersucht. Dazu wurden zunaechst Screening-Analysen durchgefuehrt, um relevante Raumbereiche zu identifizieren und um deren Effizienz fuer ein sachgerechtes Auswahlverfahren zu bewerten. Fuer einen ausgewaehlten und als relevant identifizierten Raumbereich (Kabelverteilung innerhalb des Reaktorgebaeudeinnenraums) wurde eine vertiefte probabilistische Analyse durchgefuehrt, welche die gesamte Bewertungskette, ausgehend von der Ermittlung der Brandeintrittshaeufigkeit, der Brandwirkungen und der Brandausbreitung bis zur Ermittlung der brandbedingten Ausfallwahrscheinlichkeit von sicherheitsrelevanten Einrichtungen und deren systemtechnische Folgen umfasste. Die Untersuchungen beinhalteten des weiteren auch spezielle Unsicherheits- und Sensitivitaetsanalyse fuer die Ermittlung der Brandwirkungen und deren systemtechnische