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Wyszukujesz frazę "Berg, H. P." wg kryterium: Autor


Wyświetlanie 1-6 z 6
Tytuł:
Assessing the risk of the transport of radioactive material
Autorzy:
Berg, H. P.
Powiązania:
https://bibliotekanauki.pl/articles/2069441.pdf
Data publikacji:
2012
Wydawca:
Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:
transport
transport modes
probabilistic safety assessment
risk-informed decision making
transport computer code
spent fuel
radioactive waste
Opis:
Transport of dangerous goods are always under critical observation of the public, in particular in case of transport of spent fuel or radioactive waste. In both cases transports are often crossing borders of countries, e.g., waste resulting from reprocessing of spent fuel. The transports could take place by ships, trucks, rails and airplanes and these options and the resulting risks are compared. Transport risk includes health and safety risks that arise from the exposures to workers and members of the public to radiation from shipments Moreover, it is shown that the more modern approach of risk-informed decision making elaborated for application to nuclear installations can also be applied to assess the risk of the transport of radioactive material.
Źródło:
Journal of Polish Safety and Reliability Association; 2012, 3, 1; 89--100
2084-5316
Pojawia się w:
Journal of Polish Safety and Reliability Association
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Aircraft crash onto a nuclear power plant : screening procedure and approach for a probabilistic analysis
Autorzy:
Berg, H.-P.
Powiązania:
https://bibliotekanauki.pl/articles/2069647.pdf
Data publikacji:
2010
Wydawca:
Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:
aircraft crash
crash frequency
probabilistic safety assessment
screening
Opis:
International experience has shown that external hazards (e.g. aircraft crash, flooding) can be safety significant contributors to the risk in case of nuclear power plants` operation. This is due to the fact that such hazards have the potential to reduce simultaneously the level of redundancy by damaging redundant systems or their supporting systems. In this paper, the procedure for the external hazard aircraft crash is described In more detail, starting with the screening procedure in order to determine scope and content of the assessment and the approach for those cases where a full scope analysis has to be performed. The consideration regarding this hazard does as not cover an intended aircraft crash.
Źródło:
Journal of Polish Safety and Reliability Association; 2010, 1, 1; 27--34
2084-5316
Pojawia się w:
Journal of Polish Safety and Reliability Association
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Assessing external explosions and their probabilities
Autorzy:
Berg, H. P.
Hauschild, J.
Powiązania:
https://bibliotekanauki.pl/articles/2069498.pdf
Data publikacji:
2011
Wydawca:
Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:
external explosion
explosion pressure waves
Monte Carlo simulation
probabilistic safety assessment
Opis:
External hazards such as explosions can be safety significant contributors to the risk in case of operation of industrial plants. The procedure to assess external hazard explosion pressure waves within probabilistic safety assessment starts with a screening procedure in order to determine scope and content of the assessment. The second step is to choose an appropriate approach in case that a full scope analysis has to be performed. Several methods can be applied to evaluate the probability of occurrence of an external explosion event. The presented results indicate that the probability of occurrence of external explosion pressure waves can be successfully assessed by means of the Monte Carlo simulation, in particular in difficult site-specific conditions.
Źródło:
Journal of Polish Safety and Reliability Association; 2011, 2, 1; 23--32
2084-5316
Pojawia się w:
Journal of Polish Safety and Reliability Association
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Ageing PSA as a support for effective ageing management
Autorzy:
Berg, H. P.
Volkanovski, A.
Powiązania:
https://bibliotekanauki.pl/articles/2069520.pdf
Data publikacji:
2014
Wydawca:
Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:
ageing
ageing management
probabilistic safety assessment
prioritization
management of activities
Opis:
Because of the growing operational age of nuclear power plants, the ageing management of structures, systems and components used in these plants is gaining an important role. Technical systems are subject to timedependent and operationally caused ageing phenomena with modifications of originally given characteristics and, thus, of relevance in terms of safety. Especially physical ageing is of importance. Therefore, a comprehensive ageing management is required. In the context of an integrated safety management it has to be shown how to integrate the safety related issues of ageing into probabilistic safety assessment (PSA). In particular the question is to be answered whether the effort for the execution of an ageing PSA is justified, in particular if the safety significant effects of ageing can be identified and quantitatively estimated. Method for prioritization of the components in the nuclear power plant considering implication of their ageing on safety of the nuclear power plant is presented. On the basis of an actual report on ageing management in German nuclear power plants and a literature survey, this paper tries to estimate the necessity and value for the introduction of an ageing PSA in Germany.
Źródło:
Journal of Polish Safety and Reliability Association; 2014, 5, 2; 1--10
2084-5316
Pojawia się w:
Journal of Polish Safety and Reliability Association
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Methods for the treatment of common cause failures in redundant systems
Autorzy:
Berg, H. P.
Görtz, R.
Kesten, J.
Powiązania:
https://bibliotekanauki.pl/articles/2069575.pdf
Data publikacji:
2007
Wydawca:
Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:
nuclear power plant
probabilistic safety assessment
simulation
common cause failure
modelling
Opis:
Dependent failures are extremely important in reliability analysis and must be given adequate treatment so as to minimize gross underestimation of reliability. German regulatory guidance documents for PSA stipulate that model parameters used for calculating frequencies should be derived from operating experience in a transparent manner. Progress has been made with the process oriented simulation (POS) model for common cause failure (CCF) quantification. A number of applications are presented for which results obtained from established CCF models are available, focusing on cases with high degree of redundancy and small numbers of observed events.
Źródło:
Journal of Polish Safety and Reliability Association; 2007, 1; 1--8
2084-5316
Pojawia się w:
Journal of Polish Safety and Reliability Association
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Proposal for estimating leak and break frequencies of piping systems in probabilistic safety assessment
Autorzy:
Berg, H.-P.
Gersinska, R.
Sievers, J.
Powiązania:
https://bibliotekanauki.pl/articles/2069698.pdf
Data publikacji:
2009
Wydawca:
Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:
leak frequencies
break frequencies
probabilistic safety assessment
piping system
nuclear power plant
Opis:
The estimation of leak and break frequencies in piping systems is part of the probabilistic safety assessment of technical plants. In this paper, the statistical method based on the evaluation of the German operational experience for piping systems with different diameters is described because an earlier estimation has been updated and extended introducing new methodical aspects and data. Major point is the inclusion of structure reliability models based on fracture mechanics calculation procedures. As an example of application the statistical estimation method for leak and break frequencies of piping systems with a nominal diameter of 50 mm (the volume control system of a German pressurized water reactor) was updated. Moreover, the evaluation of the operational experience was extended to 341 years with respect to cracks, leaks and breaks in the volume control system of German pressurized water reactors (PWR). Using the actual data base, new calculations of leak and break frequencies have been performed and the results have been compared with the previous values.
Źródło:
Journal of Polish Safety and Reliability Association; 2009, 1; 33--42
2084-5316
Pojawia się w:
Journal of Polish Safety and Reliability Association
Dostawca treści:
Biblioteka Nauki
Artykuł
    Wyświetlanie 1-6 z 6

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