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1

Risk orientated analysis of the SNR 300  

International Nuclear Information System (INIS)

To make a quantitative comparison of risks between the SNR 300 and a modern PWR (Biblis B), the consequences of an accident or the extent of damage of a release of radionuclides to the environment due to an accident are estimated by computer programs for accident consequence models. The accident analysis includes an analysis of events for Bethe-Tait accidents with failure of the outer containment. The FGSB release rates are compared with those of the Society for Reactor Safety (GRS). (HP).

2

Steam turbine-service. Upgrading the low-pressure steam turbines in the Emsland nuclear power plant; Dampfturbinen-Service. Wirkungsgrad verbessernde Massnahmen im Kernkraftwerk Emsland  

Energy Technology Data Exchange (ETDEWEB)

A century of technical development put steam turbines on a high level regarding efficiency and reliability. This procedure is still ongoing. The technological-commercial point of view - influenced intensively by liberalisation of the energy-market - makes great demands on field services. Well suited concepts in service and modernization are the solutions, as shown in NPP Emsland upgrade. [German] Ein Jahrhundert technischer Entwick lung brachte Dampfturbinen auf ein hohes Niveau bezueglich Effizienz und Zuverlaessigkeit. Dieser Vorgang ist auch in der heutigen Zeit nicht ab geschlossen. Die technologisch-wirtschaftliche Betrachtungs weise '' von der Liberalisierung des Strommarktes intensiv beeinflusst '' stellt dementsprechend hohe Anforderungen auch an den Kraftwerksservice. Massgeschneiderte Modernisierungs- und Servicekonzepte sind die Antwort, wie das Beispiel Kernkraftwerk Emsland zeigt. (orig.)

2001-07-01

3

Risk-oriented analysis for the SNR-300  

International Nuclear Information System (INIS)

The aim of the risk assessment consists of a comparative security evaluation for the SNR-300 and the PWR Biblis B. The failure analysis focusses on the reactor core; in addition, possible fission product release from the spent fuel pits is examined. By reliability analyses, the frequency of events leading to incidents is determined together with the probability of core destruction. In the accident analysis, the kind and frequency of failure of the activity barriers, i.e., primary system (reactorvessel) and inner and outer containment are investigated for the various incident sequences. The radionuclide release into the environment is classified into five different release categories. Besides internal failures, external causes (especially earthquakes and plane crashes) are considered under the aspect of their risk contribution. (RF).

4

Risk orientated analysis of the SNR-300. Release of radionuclides in high energy Bethe-Tait conditions. Consequences of accidents. Comparison of the consequences of an SNR-300 accident and accidents in a PWR. Risikoorientierte Analyse zum SNR 300. Radionuklidfreisetzung unter hochenergetischen Bethe-Tait-Bedingungen. Unfallfolgen. Vergleich der Unfallfolgen des SNR-300 und eines DWR  

Energy Technology Data Exchange (ETDEWEB)

To make a quantitative comparison of risks between the SNR-300 and a modern PWR (Biblis B), the consequences of an accident or the extent of damage of a release of radionuclides to the environment due to an accident are estimated by computer programs for accident consequence models. The accident analysis includes an analysis of events for Bethe-Tait accidents with failure of the outer containment. The FGSB release rates are compared with those of the Society for Reactor Safety (GRS).

1982-01-01

5

Decommissioning, safe enclosure, and dismantling licensing for nuclear power plants according to section 7 subsection 3 of the Atomic Energy Act. Die Stillegungs-, Einschluss- und Abbaugenehmigung fuer Kernkraftwerke nach Paragraph 7 Abs. 3 des Atomgesetzes  

Energy Technology Data Exchange (ETDEWEB)

The contribution is concerned from a legal point of view with the systematic recording, classification and assessment of specific problems concerning the post-operational phase of a nuclear power plant. As an introduction, present experience with decommissioning in the Federal Republic of Germany is dealt with. The first part treats the factual side of section 7 III AtG, explains the terms mentioned, the concrete extent of licensing and priority relations. In part 2 the preconditions for licensing pursuant to section 7 III AtG are dealt with, the stipulations of which are made difficult in particular on account of the reference in section 7 III sentence 2 AtG. The third part is concerned with the legal consequence of section III AtG, i.e. the extent of official discretionary powers, whereby aspects of radioactive waste management carry great weight. In part four administrative and procedural particularities in the legal sense relating to licensing according to section III AtG are ...

1990-01-01

6

Risk oriented analysis of the SNR-300  

International Nuclear Information System (INIS)

The Fact Finding Committee on 'Future Nuclear Power Policy' established by the 8th German Federal Parliament in its report of June 1980 among other items published the recommendation to commission a 'risk oriented analysis' of the SNR-300 in order to enable a pragmatic comparison to be made of the safety of the German prototype fast breeder reactor and a modern light water reactor (a Biblis B PWR). The Federal Minister for Research and Technology in August 1981 officially commissioned the Gesellschaft fuer Reaktorsicherheit (GRS) to conduct the study. Following a recommendation by the Fact Finding Committee, additional studies were performed also by a group of opponents of the breeder reactor. On the instigation of the group of opponents the delivery date of the study was altered several times and finally set at April 30, 1982. GRS submitted its report by this deadline. However, a joint report by the two groups could not be compiled, as had been requested by the ...

7

Modernizing steam turbines for nuclear power plants; Modernisierung von Dampfturbinen fuer Kernkraftwerke  

Energy Technology Data Exchange (ETDEWEB)

Economic and safe operation of nuclear power plants requires reliable steam turbines with high efficiencies. The progress in flow mechanics achieved over the past few years has allowed the use of powerful methods of flow calculation in developments of new blading with greatly enhanced efficiencies. Thanks to the latest manufacturing techniques, the newly developed blading systems can be produced at low cost. Next to progress in flow mechanics, also the broadbased use of advanced finite-element calculations resulted in a more thorough grasp of the many problems associated with structural mechanics assessment of steam turbine components. The theoretical methods have been supplemented by comprehensive efforts in fracture mechanics and experimental materials studies, thus helping to create a reliable knowledge base which will help to avoid the dreaded stress corrosion cracking phenomenon, in components of steam turbines. The measures introduced to improve operational reliability already in ...

1996-01-01