Autor: Berg, H, P. - Katalog OPAC zbiorów

Skocz do pozycji: 1.

Tytuł:: Optical infrared-sensor inside the cylinder to determine the EGR- and residual gas rate in diesel engine
Optyczny czujnik podczerwieni wewnątrz cylindra w celu określenia recyrkulacji spalin i reszty spalin w silniku wysokoprężnym
Autorzy:: Vanhaelst, R.
Thiele, O.
Berg, T.
Hahne, B.
Stellet, H.-P.
Wildhagen, F.
Hentschel, W.
Joerdens, Ch.
Czajka, J.
Wisłocki, K.
Pielecha, I.
Powiązania:: https://bibliotekanauki.pl/articles/133337.pdf
Data publikacji:: 2013
Wydawca:: Polskie Towarzystwo Naukowe Silników Spalinowych
Tematy:: exhaust gas recirculation (EGR)
IR sensors
engine research
recyrkulacja spalin
czujnik podczerwieni
badania silnikowe
Opis:: To meet the increased demands of new exhaust and CO₂ limits a research project of Volkswagen R&D, the Technical University of Poznan and the Ostfalia University of Applied Sciences has been initiated; its main target was the development and adaptation ICOS (Internal Combustion Optical Sensor) – an infrared sensor of LaVision for on-line measurements of EGR-rate in cylinder of an engine under operation. The objective of the project was to determine by different optical signals the CO₂ concentration, the EGR rate and residual gas which are cycle-resolved in the cylinder. In this paper the principle of measurement of optical indication has been described. The infrared sensor was validated by a one-cylinder diesel engine and compared to a synchronously running fast gas sampling system (CSV). Finally the practical application of various parameter variations is illustrated in the determination of the EGR and residual gas rate. Thus a new measurement technique for the development of future generations of engines introduced.
Aby umożliwić spełnienie wymagań nowych norm emisji spalin oraz spełnić limity emisji CO₂ podjęto projekt badawczy z udziałem: Volkswagen R&D, Politechniki Poznańskiej i Ostfalia University of Applied Sciences; jego głównym celem był rozwój i adaptacja ICOS (Internal Combustion Optical Sensor) – czujnika podczerwieni firmy LaVision dla bieżących pomiarów stopnia recyrkulacji spalin w cylindrze pracującego silnika. Celem projektu było określenie na podstawie różnych sygnałów optycznych wartość stężenia CO₂, stopnia recyrkulacji spalin (EGR – rate) oraz ilości spalin, które znajdują się w cylindrze przed rozpoczęciem procesu spalania. W artykule przedstawiono zasadę pomiaru zawartości spalin z wykorzystaniem czujnika optycznego. Możliwość zastosowania czujnika podczerwieni została potwierdzona przez badania na jednocylindrowym silniku wysokoprężnym, a otrzymane wyniki porównano z systemem do szybkiego pobierania próbek gazu (CSV). Przedstawiono również wyniki pozwalające na określenie recyrkulacji spalin oraz reszty spalin przy różnych parametrach pracy silnika. Nowa technika pomiarowa pozwala na dostosowanie nowoczesnych silników spalinowych do przyszłych norm ochrony środowiska i tworzy podstawę dla rozwoju przyszłych generacji silników spalinowych.
Źródło:: Combustion Engines; 2013, 52, 3; 3-11
2300-9896
2658-1442
Pojawia się w:: Combustion Engines
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 2.

Tytuł:: Methods to assess effects of cable failures caused by fire
Autorzy:: Piljugin, E.
Herb, J.
Röwekamp, M.
Berg, H, P.
Powiązania:: https://bibliotekanauki.pl/articles/2069632.pdf
Data publikacji:: 2011
Wydawca:: Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:: cable failure
fire
probabilistic risk assessment
FMEA
Opis:: It is state-of-the-art that a Level 1 PSA also includes a fire PSA for all plant operational states. In performing Fire PSA not only the malfunction of the components has to be assessed but also all supply systems and cables have to be traced for a given component. In the past it was assumed in the case of a fire in a compartment that all components and cables in that compartment are not functional anymore. However, this is in many cases a too conservative approach and could lead to overestimated fire induced core damage frequencies. Therefore, a method is necessary to assess in a more realistic manner the effects of cables failures caused by fire. Such a procedure requires a sound data base on equipment, list of cables and their properties as well as cable routing. Two methods are described which are currently developed. One of them is a cable failure mode and effect analysis which is easier to apply in practice.
Źródło:: Journal of Polish Safety and Reliability Association; 2011, 2, 1; 163--170
2084-5316
Pojawia się w:: Journal of Polish Safety and Reliability Association
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 3.

Tytuł:: Process of Judging Significant Modifications for Different Transportation Systems compared to the Approach for Nuclear Installations
Autorzy:: Petrek, N.
Berg, H. P.
Powiązania:: https://bibliotekanauki.pl/articles/116039.pdf
Data publikacji:: 2015
Wydawca:: Uniwersytet Morski w Gdyni. Wydział Nawigacyjny
Tematy:: Nuclear Installations
Green Culture in Shipping
Transportation Systems
Maritime Transportation
EU Regulations
Common Safety Method (CSM)
Safety Management System (SMS)
risk management
Opis:: The implementation of the CSM regulation by the European Commission in 2009 which harmonizes the risk assessment process and introduces a rather new concept of judging changes within the European railway industry. This circumstance has risen the question how other technology sectors handle the aspect of modifications and alterations. The paper discusses the approaches for judging the significance of modifications within the three transport sectors of European railways, aviation and maritime transportation and the procedure which is used in the area of nuclear safety. We will outline the similarities and differences between these four methods and discuss the underlying reasons. Finally, we will take into account the role of the European legislator and the fundamental idea of a harmonization of the different approaches.
Źródło:: TransNav : International Journal on Marine Navigation and Safety of Sea Transportation; 2015, 9, 4; 511-520
2083-6473
2083-6481
Pojawia się w:: TransNav : International Journal on Marine Navigation and Safety of Sea Transportation
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 4.

Tytuł:: Hazard assessment in case of external flooding
Autorzy:: Iancu, A.
Berg, H. P.
Krauß, M.
Powiązania:: https://bibliotekanauki.pl/articles/2069098.pdf
Data publikacji:: 2016
Wydawca:: Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:: external hazards
flooding
safety assessment
modelling
applications
nuclear power plants
Opis:: Risks relating to external hazards, either natural or man-made, have to be taken into consideration in the design of nuclear and other industrial facilities. These risks have to be studied to guarantee the availability and efficiency of safety functions which, e.g. in the case of power reactors, enable a safe shutdown, maintain the reactor in a safe shutdown state, ensure the residual heat removal and the containment of radioactive products. With a view to design protection against risks related to external hazards, these hazards have to be assessed in an appropriate manner. The methods used can be either deterministic or probabilistic. In both cases, the method strongly relies on observations (e.g. flood records) that are processed to define a maximum event for the respective facility design. Moreover, the validity of these records over a certain time frame like 100 years has to be checked. Coping with external hazards such as flooding in the future requires an in-depth assessment taking into account new data, further developed methodologies and criteria. Some of these ideas, developments and applications are provided.
Źródło:: Journal of Polish Safety and Reliability Association; 2016, 7, 1; 87--98
2084-5316
Pojawia się w:: Journal of Polish Safety and Reliability Association
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 5.

Tytuł:: Tsunamis and sea rise in the North and Baltic Sea and potential consequences for nuclear facilities
Autorzy:: Iancu, A.
Berg, H, P.
Powiązania:: https://bibliotekanauki.pl/articles/2068930.pdf
Data publikacji:: 2017
Wydawca:: Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:: weather-related hazards
hazard assessment
climate change
North and Baltic Sea
nuclear facilities
Opis:: Weather-related hazards are among the most frequent causes for disturbances of critical infrastructures. Flooding, tsunamis and sea level rise are examples of major threats to all types of nuclear facilities located at the seaside or at rivers. We report about exemplary investigations concerning weather-related hazards for the North Sea and the Baltic Sea. Climate change is expected to increase the already known threats but, in the long term, may also lead to new kinds of hazards. A possible future climate evolution, e.g. from warm (interglacial) to cold (glacial) periods, is not only a topic for seaside industrial facilities but also of concern in the long term safety assessment of deep geological nuclear waste repositories, in particular for high level waste, on the Baltic sea.
Źródło:: Journal of Polish Safety and Reliability Association; 2017, 8, 1; 55--66
2084-5316
Pojawia się w:: Journal of Polish Safety and Reliability Association
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 6.

Tytuł:: An importance measure for multi-component systems with Semi-Markov dynamics
Autorzy:: Hellmich, M.
Berg, H. P.
Powiązania:: https://bibliotekanauki.pl/articles/2069417.pdf
Data publikacji:: 2012
Wydawca:: Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:: multi-component system
importance measure
Semi-Markov process
state space model
Opis:: We consider semi-Markov reliability models of multi-component systems with a discrete state space, general enough to include systems with maintenance or repair. We assume that for all system states the functioning or failure of each component is specified. In this setup we propose a component importance measure which is close in spirit to the classical steady state Barlow–Proschan importance measure for repairable binary coherent systems. We discuss our importance measure to some extent, highlighting the relation to the classical Barlow–Proschan measure, and present formulas expressing it in terms of quantities easily obtained from the building blocks of the semi-Markov process. Finally an example of a two-component cold standby system with maintenance and repair is presented which illustrates how our importance measure can be used in practical applications.
Źródło:: Journal of Polish Safety and Reliability Association; 2012, 3, 1; 147--156
2084-5316
Pojawia się w:: Journal of Polish Safety and Reliability Association
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 7.

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

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Skocz do pozycji: 8.

Tytuł:: Corrosion mechanisms and their consequences for nuclear power Plants
Autorzy:: Berg, H.-P.
Powiązania:: https://bibliotekanauki.pl/articles/2069694.pdf
Data publikacji:: 2009
Wydawca:: Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:: corrosion
corrosion types
operating experience
nuclear power plants
Opis:: It is well known that operational conditions in light water reactors strongly influence the corrosion processes. This paper gives an overview which types of corrosion are identified in operating practice based on the evaluation of events which are reported to the authorities in line with the German reporting criteria. It has been found that the main contributor is the stress corrosion cracking. Several examples of different corrosion mechanisms and their consequences are provided for PWR although a high standard of quality of structures, systems and components has been achieved. Recommendations have been given to check the plant specifications concerning the use of auxiliary materials or fluids during maintenance as well as to examine visually the outer surfaces of austenitic piping with regard to residua of adhesive or adhesive tapes within the framework of in-service inspections. However, events in the last two years shows that such problems cannot be totally avoided.
Źródło:: Journal of Polish Safety and Reliability Association; 2009, 1; 23--32
2084-5316
Pojawia się w:: Journal of Polish Safety and Reliability Association
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 9.

Tytuł:: Power plant transformer explosion and fire
Autorzy:: Berg, H.-P.
Fritze, N.
Powiązania:: https://bibliotekanauki.pl/articles/2069665.pdf
Data publikacji:: 2010
Wydawca:: Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:: transformer
power plants
explosion
fire
simulation
failure
reliability
risk management
Opis:: The transformer is the key equipment for electric power transmission. It has been found that main transformer failures require an in-depth assessment because of the high failure frequency and the resultant reliability and safety implications. Transformers are considered as a critical equipment because of the large quantity of oil in contact with high voltage elements. In particular, experience has shown an increasing number of transformer explosions and fires in all types of power plants worldwide. Therefore, these phenomena have been investigated and are discussed in more detail in this paper with regard to causes for these events, potential influence of the age of the transformers and possible diagnostic measure in order to avoid such events. For that purpose different types of databases have been evaluated.
Źródło:: Journal of Polish Safety and Reliability Association; 2010, 1, 1; 35--42
2084-5316
Pojawia się w:: Journal of Polish Safety and Reliability Association
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 10.

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

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Skocz do pozycji: 11.

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

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Skocz do pozycji: 12.

Tytuł:: Analysis of the impact of external flooding to nuclear installations
Autorzy:: Berg, H. P.
Fröhmel, T.
Winter, C.
Powiązania:: https://bibliotekanauki.pl/articles/2069618.pdf
Data publikacji:: 2007
Wydawca:: Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:: nuclear power plant
probabilistic safety analysis
external flooding
protection
tsunami
Opis:: The German regulatory body has issued probabilistic safety assessment guidelines, elaborated for a comprehensive integrated safety review of all NPP in operation and containing a newly developed graded approach for the probabilistic assessment of external flooding. Main aspects are explained such as the underlying probabilistic considerations and the mathematical procedures for the calculation of exceedance frequencies. Exemplarily it has been investigated if extreme events such as tsunami waves could be a hazard for NPP at coastal sites in Germany.
Źródło:: Journal of Polish Safety and Reliability Association; 2007, 1; 9--16
2084-5316
Pojawia się w:: Journal of Polish Safety and Reliability Association
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 13.

Tytuł:: Approach to assess fire risk for nuclear power plants
Autorzy:: Berg, H. P.
Röwekamp, M.
Powiązania:: https://bibliotekanauki.pl/articles/2069409.pdf
Data publikacji:: 2012
Wydawca:: Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:: fire
risk assessment
screening
compartment configuration
databases
fire induced core damage states
Opis:: The results of the first fire risk assessments on an international level have shown that fires are one major contributor to the risk of a nuclear power plant depending on the plant specific fire protection concept. Therefore, fire risk assessment has today become an integral part of the probabilistic safety assessment of nuclear power plants in addition to deterministic analyses. Based on existing guidance documents a state-ofthe-art approach for performing probabilistic fire risk assessment has also been developed in Germany. This approach has been exemplarily and completely applied to a German nuclear power plant with boiling water reactor for the full power states PSA. The general approach outlines the steps necessary for performing fire risk assessment and the prerequisites for a sound and traceable database.
Źródło:: Journal of Polish Safety and Reliability Association; 2012, 3, 1; 135--146
2084-5316
Pojawia się w:: Journal of Polish Safety and Reliability Association
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 14.

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

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Skocz do pozycji: 15.

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

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