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).

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

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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

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.

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

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

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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

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

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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.)

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

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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.

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.

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

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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.

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

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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.

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

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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

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.

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.)

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)

Energy Technology Data Exchange (ETDEWEB)

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.

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

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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

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.)

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.

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.

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

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

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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.)

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

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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.