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Wyszukujesz frazę "Nuclear Power" wg kryterium: Temat


Wyświetlanie 1-7 z 7
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
Artykuł
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
Artykuł
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
Artykuł
Tytuł:
Operating Experience with Hydrological External Hazards and Their Potential Safety Significance
Autorzy:
Röwekamp, M.
Gänssmantel, G.
Strack, C.
Powiązania:
https://bibliotekanauki.pl/articles/2068927.pdf
Data publikacji:
2017
Wydawca:
Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:
natural external hazards
hydrological impact
nuclear power plant
operating experience
Opis:
The nuclear accidents of Fukushima in March 2011 have indicated the significance of external hazards for nuclear installations safety. One lesson learned from post-Fukushima investigations worldwide is that the operating experience from external hazards, even if these did not pose any significant harm to the affected plant, do represent important precursors, which should be taken into account in deterministic as well as probabilistic safety assessment. This paper provides an overview on the significance of events or event combinations involving hydrological external hazards. Some more recent examples of events from hydrological external hazards and their potential safety significance for nuclear power plants are discussed.
Źródło:
Journal of Polish Safety and Reliability Association; 2017, 8, 1; 111--117
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
Tytuł:
Defence in depth conception in nuclear power plants and requirements for instrumentation and control systems
Autorzy:
Kosmowski, K. T.
Powiązania:
https://bibliotekanauki.pl/articles/2069514.pdf
Data publikacji:
2014
Wydawca:
Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:
nuclear power plants
defence in depth
instrumentation and control systems
functional safety
Opis:
The aim of this article is to identify and discuss some issues of the safety systems’ design for nuclear power plants equipped with the light water reactors using a defence in depth (D-in-D) conception. Because the functional safety solutions play nowadays an important role for the risk control, the basic requirements for the instrumentation and control systems are specified with regard to relevant international standards. For the design purposes the safety functions are categorized into three categories. The I&C systems implementing these functions are assigned to one of three classes that conform to defined design, manufacturing and qualification requirements. These systems are designed to implement functions of relevant categories. Additional design requirements are discussed, including hardware and software aspects, to achieve and maintain the required reliability commensurate with the importance of the safety functions to be performed to reduce risk.
Źródło:
Journal of Polish Safety and Reliability Association; 2014, 5, 2; 87--100
2084-5316
Pojawia się w:
Journal of Polish Safety and Reliability Association
Dostawca treści:
Biblioteka Nauki
Artykuł
    Wyświetlanie 1-7 z 7

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