Prioritization of components important for safety and sensitive to ageing. Application for TRIGA reactor

Nitoi, Mirela; Turcu, I.; Christiane, Bruynooghe; Pavelescu, M.

doi:10.1016/j.pnucene.2011.01.002

Cited by 10 publications

(6 citation statements)

References 3 publications

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“…Meanwhile, the unwanted event refers to the occurrence of the top event. It quantifies the contributions of a basic event by dividing the summation of the probabilities of all minimal cut sets containing the evaluated basic event by the probability of the top event [24]. The results of the FV importance can be used to identify potential components to be changed to improve the safety of the related system [20].…”

Section: Probability-based Importance Measure Approachesmentioning

confidence: 99%

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The Implementation of Importance Measure Approaches for Criticality Analysis in Fault Tree Analysis: A Review

Purba

Deswandri

2018

Jurnal Pengembangan Energi Nuklir

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THE IMPLEMENTATION OF IMPORTANCE MEASURE APPROACHES FOR CRITICALITY ANALYSIS IN FAULT TREE ANALYSIS: A REVIEW.Fault tree analysis (FTA) has been widely applied in nuclear power plant (NPP) probabilistic safety assessment to evaluate the reliability of a safety system. In FTA, criticality analysis is performed to identify the weakest paths in the system designs and components. For this purpose, an importance measure approach can be applied. Risk managers can apply information obtained from this analysis to improve safety by implementing risk reduction measure into the new design or build a more innovative design. Various importance measure approaches have been developed and proposed for criticality analysis in FTA. Each important measure approach offers specific purposes and advantages but has limitations. Therefore, it is necessary to understand characteristics of each approach in order to select the most appropriate approach to reach the purpose of the study. The objective of this study is to review the current implementations of importance measure approaches to rank individual basic events and/or minimal cut sets regarding their contributions to the unreliability or unavailability of NPP safety systems. This study classified importance measure approaches into two groups, i.e. probability–based importance measure approaches and fuzzy–based importance measure approaches. This study concluded that clear understanding of the purpose of the study, the type of reliability data at hands, and the uncertainty in the calculation need to be considered prior to the selection of the appropriate importance measure approach to the study of interest.

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Section: Probability-based Importance Measure Approachesmentioning

confidence: 99%

“…Risk achievement worth (RAW) is commonly used to determine whether the structure, system and component (SSC) degradation may be important to risk [24]. It measures risk relative increase due to the occurrence of a particular event, such as the unavailability of a system [26].…”

Section: Probability-based Importance Measure Approachesmentioning

confidence: 99%

The Implementation of Importance Measure Approaches for Criticality Analysis in Fault Tree Analysis: A Review

Purba

Deswandri

2018

Jurnal Pengembangan Energi Nuklir

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“…In addition, the prioritization of SCEs can substantially improve the reliability and productivity of equipment and processes. This study uses a modified FMEA tool, called Ageing Failure Mode and Effects Analysis (AFMEA) (Nitoi et al, 2011) for ranking and prioritising the SCEs. The Risk Priority Number (RPN) for potential ageing-related failure modes are evaluated using 10point rating scales for severity of impact (S), likelihood of occurrence (O) and likelihood of detection (D) which are tabulated in Tables (2)-(4).…”

Section: Screening and Prioritization Of Scesmentioning

confidence: 99%

Development of a techno-economic framework for life extension decision making of safety critical installations

Shafiee

Animah

Simms

2016

Journal of Loss Prevention in the Process Industries

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One of the major decisions in management of the industrial assets is to ensure the feasibility of life extension process for safety critical components when they reach end-of-life. Most of the existing life extension decision-making models are restricted solely to either "technical" or "economic" feasibility analyses that may lead to inaccurate results or incorrect conclusions. In this paper, a comprehensive life extension feasibility assessment framewok by taking into account both the technical and economic considerations is developed. The proposed technoeconomic model for life extension of safety critical elements consists of three phases: preparation, assessment, and implementation. The technical assessment part of the framework incorporates all aspects of data collection and review, screening and prioritization of safety critical elements, condition assessment, estimation of remaining useful life, and risk analysis, while the economic assessment part deals with cost-benefit analysis. The decision to qualify a safety critical element for continuous operation beyond its service life is made based on a "life extension measure (LEM)" which is calculated by combining two indexes of "equipment health condition" and "economic added-value" obtained respectively from the technical and economic assessments. The model is applied to support the life extension decision-making procedure for water deluge systems in offshore oil installations. The results of the study show that the model is highly capable of assisting asset owners to evaluate the technical and economic benefits of extending the service life of components.

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“…As the time passes, the functional capabilities of structures, systems and components (SSCs) deteriorate by ageing [10,11]. Ageing is a process in which the reliability of any equipment depreciates, and hence the likelihood of that equipment to fail increases [12].…”

Section: Introduction mentioning

confidence: 99%

“…Meanwhile, the physical ageing is caused by the physical, chemical and/or biological mechanisms such as thermal and/or radiation embrittlement [1]. Furthermore, Nitoi et al [10] confirmed four issues that need to be dealt with regarding the ageing management. Firstly, SSCs, which are sensitive to ageing, need to be identified.…”

Section: Introduction mentioning

confidence: 99%

Physical Ageing of The Research Reactor Core Structural Materials Due To Neutron Irradiation Exposure: A Review

Purba

2017

Jurnal Pengembangan Energi Nuklir

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PHYSICAL AGEING OF THE RESEARCH REACTOR CORE STRUCTURAL MATERIALS DUE TO NEUTRON IRRADIATION EXPOSURE: A REVIEW.A research reactor (RR) is a nuclear reactor that has function to generate and utilize neutron flux and radiation ionization for research purposes and industrial applications. More than 60% of current operating RRs have been operated for 30 years or more. As the time passes, the functional capabilities of structures, systems and components (SSCs) of those RRs deteriorate by physical ageing, which can be caused by neutron irradiation exposure such as irradiation induced dislocation and microstructural changes. To extend the lifetime and/or to avoid unplanned outages, ageing on the safety related SSCs of RRs need to be properly managed. An ageing management is a strategy to engineer, operate, maintenance, and control SSC degradation within acceptable limits. The purpose of this study is to review physical ageing of the core structural materials of the RRs caused by neutron irradiation exposure. In order to achieve this objective, a wide range of literatures are reviewed. Comprehensive discussions on irradiation behaviors are limited only on reactor vessel and core support structure materials made from zirconium and beryllium as well as their alloys, which are widely used in RRs. It is found that the stability of the mechanical properties of zirconium and beryllium as well as their alloys was mostly affected by the neutron fluences and temperatures. ABSTRAK PENUAAN MATERIAL STRUKTUR TERAS REAKTOR RISET SECARA FISIK YANG DISEBABKAN OLEH PAPARAN RADIASI NEUTRON: SEBUAH KAJIAN.Reaktor riset adalah reaktor nuklir yang difungsikan untuk pembangkitan dan pemanfaatan fluks neutron dan ionisasi radiasi untuk tujuan penelitian dan aplikasi industri. Lebih dari 60% reaktor riset yang ada saat ini telah beroperasi selama 30 tahun atau lebih. Seiring dengan berjalannya waktu, kemampuan struktur, sistem dan komponen (SSK) tentunya mengalami penurunan yang dikenal dengan penuaan fisik. Penuaan fisik ini dapat disebabkan oleh karena adanya paparan radiasi neutron seperti irradiasi yang menyebabkan terjadinya dislokasi dan perubahan mikrostruktur material. Untuk memperpanjang umur reaktor dan untuk mengurangi terjadinya pemadaman yang tidak diinginkan maka perlu dilakukan manajemen penuaan SSK, khususnya yang terkait dengan keselamatan operasi. Tujuan dari penelitian ini adalah untuk mengkaji penuaan fisik yang terjadi pada material struktur teras reaktor riset yang disebabkan oleh paparan iradiasi neutron. Untuk mencapai tujuan ini maka dilakukan kajian pada berbagai macam pustaka yang terkait. Pembahasan yang komprehensif tentang sifat-sifat iradiasi dibatasi hanya pada bejana reaktor dan material struktur pendukung teras yang terbuat dari zirconium dan beryllium dan senyawanya yang umum digunakan oleh reaktor riset. Dari kajian yang telah dilakukan, ditemukan bahwa stabilitas sifat-sifat mekanik zirconium dan beryllium serta senyawanya sangat dipengaruhi oleh fluent dan temperatur neutron. Kata kunci: Reaktor riset, p...

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Prioritization of components important for safety and sensitive to ageing. Application for TRIGA reactor

Cited by 10 publications

References 3 publications

The Implementation of Importance Measure Approaches for Criticality Analysis in Fault Tree Analysis: A Review

The Implementation of Importance Measure Approaches for Criticality Analysis in Fault Tree Analysis: A Review

Development of a techno-economic framework for life extension decision making of safety critical installations

Physical Ageing of The Research Reactor Core Structural Materials Due To Neutron Irradiation Exposure: A Review

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