Temat: probabilistic safety assessment - Katalog OPAC zbiorów

Skocz do pozycji: 1.

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: 2.

Tytuł:: Improving reactor safety systems using component redundancy allocation technique
Autorzy:: Habib, A.
Ashry, H.
Shokr, A.
Dakhly, A.
Powiązania:: https://bibliotekanauki.pl/articles/148878.pdf
Data publikacji:: 2005
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: redundancy allocation
risk management
safety systems
probabilistic safety assessment
ETRR-2
Opis:: This paper addresses the improvements to the reliability of the safety systems of nuclear reactors using redundancy allocation technique. The study has been carried out using the Probabilistic Safety Assessment (PSA). PSA involves, among others, the use of fault and event tree tools in the evaluation of the safety system failure probabilities and the quantification of annual occurrence probability of the accidental conditions postulated in the design of the nuclear reactors. The PSA has been presented and discussed. The Egypt Second Research Reactor, ETRR-2, has been used as a case study. The failure probability of the already existing safety systems has been reviewed. The effect of the allocation of more redundant components to the existing safety systems on the failure probability of the systems has been evaluated. The event trees for two selected initiating events, from those events postulated in the ETRR-2 design, have been studied considering the allocation of more redundant components to the safety systems. The result of the study showed that further improvement could be introduced to the reliability of the Confinement Ventilation System (CVS).
Źródło:: Nukleonika; 2005, 50, 3; 105-112
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 3.

Tytuł:: Development of a Library Based Tool for Screening External Hazards and Hazard Combinations
Autorzy:: Röwekamp, M.
Sperbeck, S.
Türschmann, M.
Powiązania:: https://bibliotekanauki.pl/articles/2068914.pdf
Data publikacji:: 2017
Wydawca:: Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:: probabilistic safety assessment
PSA
external hazards
hazard combinations
screening approach
Opis:: For a meaningful and efficient probabilistic risk analysis of external hazards and event combinations involving such hazards those hazards with significant risk potential need to be identified and considered for detailed anal-yses. Such a site and plant specific screening approach for external and internal hazards based on a hazards library covering all types of hazards is under development at GRS. The paper provides insights on the approach and first examples of application.
Źródło:: Journal of Polish Safety and Reliability Association; 2017, 8, 1; 105--110
2084-5316
Pojawia się w:: Journal of Polish Safety and Reliability Association
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 4.

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: 5.

Tytuł:: Risk analysis of external hydrological hazards with flooding potential for a German nuclear reference site
Autorzy:: Röwekamp, M.
Gänssmantel, G.
Peschke, J.
Strack, C.
Utschick, M.
Powiązania:: https://bibliotekanauki.pl/articles/2068763.pdf
Data publikacji:: 2018
Wydawca:: Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:: flooding
hydrological hazards
hazard combinations
Probabilistic Safety Assessment
PSA
risk analysis
Opis:: Probabilistic Safety Analyses (PSA) are a supplementary analytical tool used worldwide more and more in order to quantitatively assess the effect of hazards on the overall result regarding the safety of industrial installations, in particular nuclear power plants. In that way PSA provides a reliable basis for decisions on the necessity and the benefits of safety improvements. In the recent past, the existing methods and tools with respect to determining the site-specific risk of nuclear power plants have been comprehensively extended and further enhanced. The focus of extending the existing PSA methods was on external hydrological hazards with flooding potential. For systematically considering hydrological hazards within PSA a systematic approach has been developed. The paper demonstrates the extended approach in the example of a nuclear power plant site with different flooding risks.
Źródło:: Journal of Polish Safety and Reliability Association; 2018, 9, 3; 65--74
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:: 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: 7.

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

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Skocz do pozycji: 8.

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: 9.

Tytuł:: Monte Carlo simulation-based reliability model for the PSA of a radioactive waste repository
Autorzy:: Cadini, F.
Avram, D.
Zio, E.
Luce, A.
Taglioni, A.
Powiązania:: https://bibliotekanauki.pl/articles/2069572.pdf
Data publikacji:: 2010
Wydawca:: Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:: radioactive waste repository
probabilistic safety assessment
reliability-based model
Monte Carlo simulation
Opis:: Disposal facilities for radioactive wastes comprise a series of engineered barriers whose purpose is to contain the radionuclides until their radiation hazard has decreased to acceptable levels. In this regard, it is required that the long-term functionality of the system of barriers be evaluated by a quantitative risk analysis procedure, also called performance assessment. In this paper, a Monte Carlo simulation-based reliability model is propounded for the preliminary analysis of the safety performance of a radioactive waste repository, accounting also for barrier degradation processes. The model strengths are: simplicity, chich allows ease of computation, and flexibility, which allows modification to account for various physical aspects and inter-comparison of their effects. An application to a case study of literature is presented to validate the approach and demonstrate its flexibility.
Źródło:: Journal of Polish Safety and Reliability Association; 2010, 1, 1; 43--50
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:: Loss of offsite power caused by tornado in Surry NPP : a case study
Autorzy:: Borysiewicz, M.
Kaszko, A.
Kowal, K.
Potempski, S.
Powiązania:: https://bibliotekanauki.pl/articles/2069302.pdf
Data publikacji:: 2015
Wydawca:: Uniwersytet Morski w Gdyni. Polskie Towarzystwo Bezpieczeństwa i Niezawodności
Tematy:: Surry NPP
tornado
loss of offsite power
emergency power system
probabilistic safety assessment
Opis:: The aim of this work was to perform the real case study for the US Surry Nuclear Power Plant which was touched down by tornado in 2011 causing the electrical switch yard destruction and loss of offsite power. Probabilistic methods have been applied to assess the reliability of the reactor shutdown and effective heat removal after this accident. The reactor protection system and auxiliary feedwater system were thoroughly analysed in the context of their safety features designed to prevent the reactor core damage. The emergency power system reliability has been also considered due to the fact that some components of the safety systems are electrically operated. Moreover, time-dependent analysis has been performed in order to address the level of damages after an extreme external event like tornado. Depending on the severity of such events the time required to restore the electrical grid may be significantly different and longer than 24 hours. The reliability and requirements for safety systems are changing with time and these changes have been taken into account as well.
Źródło:: Journal of Polish Safety and Reliability Association; 2015, 6, 3; 25--30
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:: Probabilistic Safety Assessment of ESBWR gravity driven cooling system
Autorzy:: Kaszko, Aleksej
Niewiński, Grzegorz
Stępień, Michał
Powiązania:: https://bibliotekanauki.pl/articles/132047.pdf
Data publikacji:: 2020
Wydawca:: Centrum Rzeczoznawstwa Budowlanego Sp. z o.o.
Tematy:: nuclear power plant
Probabilistic Safety Assessment
PSA
Fault Tree Analysis
FTA
Gravity Driven Cooling System
GDCS
Opis:: According to Polish nuclear law, newly emerging nuclear facilities require probabilistic safety assessment (PSA). This article is intended to present the PSA method and to present the error tree method by which the probability of unavailability of the gravity reactor cooling system (GDCS) of the ESBWR power plant designed by GE Hitachi was determined. This work includes creatiion process of a damage tree and performing a quantitative analysis in SAPHIRE tool and estimating uncertainty using the Monte Carlo method. As a part of the work, it was shown that in the probability of failure of a single GDCS P LINE-A line, the most important element are the basic events related in particular to the operation of service valves.
Źródło:: Modern Engineering; 2020, 1; 18-25
2450-5501
Pojawia się w:: Modern Engineering
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 12.

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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Skocz do pozycji: 13.

Tytuł:: An integrated risk informed decision making in the nuclear industry
Zintegrowany proces decyzyjny uwzględniający ryzyko w przemyśle jądrowym
Autorzy:: Borysiewicz, M.
Kowal, K.
Prusiński, P. A.
Dąbrowski, M.
Powiązania:: https://bibliotekanauki.pl/articles/408818.pdf
Data publikacji:: 2013
Wydawca:: Politechnika Lubelska. Wydawnictwo Politechniki Lubelskiej
Tematy:: nuclear safety
Integrated Risk Informed Decision Making
probabilistic safety assessment
Deterministic Safety Assessment
bezpieczeństwo jądrowe
proces decyzyjny
ryzyko
probabilistyczne analizy bezpieczeństwa
deterministyczne analizy bezpieczeństwa
Opis:: The regulatory body, established to ensure safety of nuclear facilities, is expected to make right decisions and provide appropriate regulations for the nuclear industry. The traditional manner of its activity has been based on a deterministic approach to safety analyses. However, increased maturity of Probabilistic Safety Assessment (PSA) makes it complementary to deterministic studies. The new IAEA concept, described in this article, is to apply an integrated approach by combining both deterministic and probabilistic insights with other requirements affecting the decision making process.
Organ regulacyjny, powołany w celu zapewnienia bezpieczeństwa jądrowego, jest odpowiedzialny za podejmowanie decyzji i wprowadzanie rozporządzeń dla przemysłu jądrowego. Tradycyjny sposób jego funkcjonowania opiera się na deterministycznym podejściu do analiz bezpieczeństwa. Rozwój analiz probabilistycznych (PSA) sprawia jednak, iż są one traktowane jako podejście komplementarne. Nowa koncepcja IAEA, opisana w tym artykule, polega na zintegrowanym podejściu, uwzględniającym analizy deterministyczne, probabilistyczne i inne aspekty procesu decyzyjnego.
Źródło:: Informatyka, Automatyka, Pomiary w Gospodarce i Ochronie Środowiska; 2013, 2; 22-34
2083-0157
2391-6761
Pojawia się w:: Informatyka, Automatyka, Pomiary w Gospodarce i Ochronie Środowiska
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 14.

Tytuł:: The PSA analysis of PWR emergency coolant injection availability following SBLOCA
Autorzy:: Borysiewicz, M.
Bronowska, K.
Kopka, P.
Kowal, K.
Kwiatkowski, T.
Prusiński, A. M.
Prusiński, P. A.
Siess, G.
Powiązania:: https://bibliotekanauki.pl/articles/146189.pdf
Data publikacji:: 2013
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: probabilistic safety assessment (PSA)
small break LOCA (SBLOCA)
emergency coolant injection (ECI)
high pressure injection system (HPIS)
auxiliary feedwater system (AFWS)
Opis:: The aim of this article is to briefly introduce the probabilistic safety assessment (PSA) of nuclear power plants (NPPs), its scope, main concepts and application to a real case. The results of analysis presented here have been obtained by the Probabilistic Safety Analysis Group (GPSA) at the National Centre for Nuclear Research (NCBJ, Otwock) as a part of the work done for the Polish National Atomic Energy Agency (NAEA). As a reference, NPP Surry Unit 1 (USA), equipped with 800 MWe Westinghouse triple-loop PWR (pressurized water reactor), has been chosen. The emergency coolant injection (ECI) function availability following the small break loss of coolant accident (SBLOCA) was thoroughly analyzed. The approach and data, which were adopted for the selected part of the SBLOCA sequences, were those used in the U.S. NRC Reactor Safety Study (WASH-1400). As a result of this study, the SBLOCA event tree, including ECI systems, i.e. high pressure injection system (HPIS) and auxiliary feedwater system (AFWS) reliability models, was developed and quantified. The probability of each accident sequence was evaluated using Saphire v.8, the PSA software by U.S. NRC. The choice of the software was based on earlier PSA software study. The failure probability of at least one of the considered safety systems – P(FAIL) is equal to 5.76E-3 and the most pessimistic accident branch (unavailability of both HPIS and AFWS) is about 0.05% of P(FAIL). These results were obtained based on assumption that the SBLOCA has occured. The most significant failure components are those corresponding to charging pumps unavailability, loss of electric power and human errors.
Źródło:: Nukleonika; 2013, 58, 2; 307-316
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 15.

Tytuł:: Analiza niezawodności awaryjnego odbioru ciepła powyłączeniowego w reaktorze typu PWR
Reliability analysis of emergency decay heat removal in PWR reactor
Autorzy:: Kowal, K.
Borysiewicz, M.
Powiązania:: https://bibliotekanauki.pl/articles/407970.pdf
Data publikacji:: 2015
Wydawca:: Politechnika Lubelska. Wydawnictwo Politechniki Lubelskiej
Tematy:: pomocniczy system wody zasilającej
probabilistyczne analizy bezpieczeństwa
analiza drzewa uszkodzeń
SAPHIRE
symulacje Monte Carlo
Auxiliary Feedwater System (AFWS)
Probabilistic Safety Assessment (PSA)
Fault Tree Analysis (FTA)
Monte Carlo simulation
Opis:: Celem niniejszej pracy było określenie prawdopodobieństwa awarii pomocniczego systemu wody zasilającej reaktora typu PWR firmy Westinghouse. Obiektem referencyjnym, dla którego wykonano analizę była Elektrownia Jądrowa Surry (USA). Praca ta obejmuje utworzenie drzewa uszkodzeń i wykonanie analizy ilościowej w programie SAPHIRE oraz oszacowanie niepewności za pomocą metod Monte Carlo.
The aim of this work was to assess the failure probability of the Westinghouse PWR auxiliary feedwater system (AFWS). The reference facility for which the analysis has been made was Surry Nuclear Power Plant located in the United States. This work includes AFWS fault tree development and qualitative analysis using the SAPHIRE code, as well as the uncertainty assessment by applying the Monte Carlo techniques.
Źródło:: Informatyka, Automatyka, Pomiary w Gospodarce i Ochronie Środowiska; 2015, 3; 59-64
2083-0157
2391-6761
Pojawia się w:: Informatyka, Automatyka, Pomiary w Gospodarce i Ochronie Środowiska
Dostawca treści:: Biblioteka Nauki

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