Relevant bibliographies by topics / Structures, systems and components (SSCs)

Academic literature on the topic 'Structures, systems and components (SSCs)'

Author: Grafiati
Published: 10 December 2022
Last updated: 28 January 2023

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Journal articles on the topic "Structures, systems and components (SSCs)"

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Kang, Mi-Yeon, Yeheun Jeong, and Youngsoo Jung. "Assessment Methodology of Practical Configuration Management (CM) for Sustainable Nuclear Power Plants (NPPs)." Sustainability 11, no. 8 (April 22, 2019): 2391. http://dx.doi.org/10.3390/su11082391.

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Since the Fukushima accident in 2011, nuclear safety has emerged as a very important political and social issue. Under this circumstance, the importance of configuration management (CM) is emphasized in order to ensure the reliability and safety of facility. However, configuration management (CM) is still in its conceptual stage in the nuclear industry due to the ambiguity of CM definitions, insufficiency of CM procedures, paucity of computerized systems and lack of CM professionals. In an attempt to address this issue, a previous study proposed a comprehensive CM framework for nuclear power plants (NPPs) by comparing CM concepts in seven different industries where the CM is actively utilized. In order to facilitate the practical implementation of the conceptual framework, this paper proposes an assessment methodology for prioritizing the importance of CM application areas based on the physical subjects of NPP structures, systems, components (SSCs). The proposed methodology is composed of an ‘extended CM framework’ with further details and ‘evaluation criteria’ based on CM functions. This study developed an SSCs list by analyzing Design Control Document (DCD) of Westinghouse AP1000 and also identified evaluation criteria through an extensive literature review. The concept of CM in this study encompasses the entire NPP project life-cycle in order to promote the practical CM application. The results of case-study performed in this paper would provide the SSCs priorities and guidelines for practical configuration management (CM) for sustainable NPP facilities.
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Purba, Julwan Hendry. "Physical Ageing of The Research Reactor Core Structural Materials Due To Neutron Irradiation Exposure: A Review." Jurnal Pengembangan Energi Nuklir 18, no. 2 (March 10, 2017): 93. http://dx.doi.org/10.17146/jpen.2016.18.2.3143.

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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 acceptablelimits. 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.
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Banks, P. J. "Ageing management within British Energy in support of safe, reliable operation and lifetime extension objectives." Kerntechnik 67, no. 4 (August 1, 2002): 200–212. http://dx.doi.org/10.1515/kern-2002-0082.

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Abstract British Energy has established a comprehensive suite of ageing/obsolescence asset management programmes. Through these programmes, the company has developed a thorough understanding of all the potentially significant degradation mechanisms which could affect the systems structures and components (SSCs) which are essential to the safe, reliable operation of their NPPs. The results from these ageing management programmes underwrite the existing design basis safety case, provide trending information for Safety System Reviews (SSRs) and Periodic Safety Reviews (PSRs) and provide data in support of extending the operating lifetimes of the NPPs. This paper describes te UK regulatory framework with respect to ageing management, British Energy’s overall approach to ageing management, The various ageing/obsolescence management programmes established by BEG, including examples of potentially significant ageing issues which have been successfully addressed by these programmes and the manner in which the results from the programmes are used in support of continued operation, SSRs, PSRs, lifetime extension and general performance enhancement.
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Chernukha, Nikita. "Inclusion of Aircraft Crash into NPP Design Bases and Probabilistic Justification of Loads on Civil Structures and Equipment." Earthquake Engineering. Construction Safety, no. 1 (February 25, 2020): 35–47. http://dx.doi.org/10.37153/2618-9283-2020-1-35-47.

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The article is about nuclear power plant (NPP) safety analysis in case of aircraft crash. Specifically, the article considers the following problems: inclusion of aircraft crash into NPP design bases regarding calculation of frequency of an aircraft crash into NPP; aspects of justification of loads on NPP structures, systems and components (SSCs) caused by mechanical action of a primary missile – aircraft fuselage impact. Probabilistic characteristics of such random parameters as frequency of aircraft crash and direction of aircraft trajectory are determined by the results of analysis of world statistics of aviation accidents. Method of calculation of aircraft crash frequency on structures, buildings and NPP as a whole is presented. It takes into account options of accidental and intentional aircraft crashes and various aircraft approach scenarios. Procedure of probabilistic justification of loads on civil structures under aircraft impact is described. The loads are specified so as not to exceed allowable value of failure probability of NPP as a whole. Calculation of failure frequency of civil structures of existing NPP is given as an example to show analysis in case of a crash of an aircraft heavier than considered in NPP design. Procedure of probabilistic justification of dynamic loads on NPP equipment in case of aircraft impact is described. Method of floor response spectra (FRS) calculation with the required non-exceedance probability is given. Probabilistically justified loads in case of intentional aircraft impact (act of terrorism) are also considered. Additionally it is presented how internal forces calculated with the use of FRS with the required non-exceedance probability can be summed to provide analysis of subsystems.
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Cancemi, Salvatore Angelo, and Rosa Lo Frano. "Preliminary Analysis of Long-Term Performance of a Piping: Aging and Creep Effects." Materials 14, no. 7 (March 30, 2021): 1703. http://dx.doi.org/10.3390/ma14071703.

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Combining global experience, comprehensive aging knowledge, and predictive methodologies provides ideal prerequisites for the long-term operation strategy (LTO) of a nuclear power plant (NPP). Applying management strategies with an understanding of the ways in which structures relevant for the plant safety perform and interact in their operating environments is of meaningful importance for operating the plant beyond its originally licensed service life. In performing aging studies on the nuclear systems, structure, and components (SSCs), the results are crucial for demonstrating the safety and reliability of the NPP beyond 30 years of nominal operation. In this study, the synergistic effect of a creep mechanism with the alteration suffered by piping material is analyzed by means of MSC©MARC finite element code. Nonlinear analyses were performed to calculate the effects of the long operational period on a primary pipe, assess its degradation, and determine its residual functionality. In these analyses, both homogeneous and inhomogeneous pipe wall thinning are considered, as well as the operating or expected thermal–mechanical loads. The obtained results indicate that thermo–mechanical loads are responsible for pipe deformation, which develops and increases as the transient progresses. Furthermore, an excessive (general or local) wall thinning may determine a dimensional change of the pipe, even causing bending or buckling.
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Baltis, Theodore, Douglas C. Hopkins, James M. Pitaressi, and Donald R. Hazelmyer. "High Thermal-Transient Packaging for a SiC-Based Solid State Circuit Breaker." International Symposium on Microelectronics 2011, no. 1 (January 1, 2011): 000608–18. http://dx.doi.org/10.4071/isom-2011-wa5-paper2.

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Solid-State Circuit Breakers (SSCBs), or Contactors, are critical components in next generation electric aircraft, and must be small in size, fast in response, and have high reliability. Silicon Carbide (SiC) semiconductor switches provide a series of improvements over traditional silicon-based breakers in both electrical and thermal performances. The reported SSCB uses SiC MOSFETs mounted on cast-aluminum traces, cast onto an aluminum nitride (AlN) ceramic co-captured in an aluminum composite baseplate. The system is similar to an AlSiC and Direct-Bonded-Aluminum (DBA) approach. This presentation details the transient thermal characterizations of an SSCB having the highest density in development. Previous work focused on a 30A SSCB that was constructed and tested to show a 300A, 500ns circuit breaking capability. The high density comes from allowing the SiC junctions to pulse to ∼350°C (in 5ms) from a 105°C ambient baseplate. The 30A/300A module was reported in IMAPS HiTEC’10 “Development of a SiC SSPC Module with Advanced High Temperature Packaging,” This paper builds on that paper adding the mechanical results and all new data on the larger, high energy density module with larger die. The objective of the presentation is to introduce (or update) the use of cast composite metal-ceramic structures for high thermal transient applications and document the mechanical stress/strain performance through simulations. The module is in development for military applications and has not been field-tested. This is also developed for Smart-Grid applications in local distribution systems.
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Khakim, Azizul. "ANALISIS KESELAMATAN TERMOHIDROLIK BULK SHIELDING REAKTOR KARTINI." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 17, no. 3 (October 1, 2015): 115. http://dx.doi.org/10.17146/tdm.2015.17.3.2321.

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ABSTRAK ANALISIS KESELAMATAN TERMOHIDROLIK BULK SHIELDING REAKTOR KARTINI. Bulk shielding merupakan fasilitas yang terintegrasi dengan reaktor Kartini yang berfungsi sebagai penyimpanan sementara bahan bakar bekas. Fasilitas ini merupakan fasilitas yang termasuk dalam struktur, sistem dan komponen (SSK) yang penting bagi keselamatan. Salah satu fungsi keselamatan dari sistem penanganan dan penyimpanan bahan bakar adalah mencegah kecelakaan kekritisan yang tak terkendali dan membatasi naiknya temperatur bahan bakar. Analisis keselamatan paling kurang harus mencakup analisis keselamatan dari sisi neutronik dan termo hidrolik Bulk shielding. Analisis termo hidrolik ditujukan untuk memastikan perpindahan panas dan proses pendinginan bahan bakar bekas berjalan baik dan tidak terjadi akumulasi panas yang mengancam integritas bahan bakar. Code tervalidasi PARET/ANL digunakan untuk analisis pendinginan dengan mode konveksi alam. Hasil perhitungan menunjukkan bahwa mode pendinginan konvekasi alam cukup memadai dalam mendinginkan panas sisa tanpa mengakibatkan kenaikan temperatur bahan bakar yang signifikan. Kata kunci: Bulk shielding, bahan bakar bekas, konveksi alam, PARET. ABSTRACT THERMAL HYDRAULIC SAFETY ANALYSIS OF BULK SHIELDING KARTINI REACTOR. Bulk shielding is an integrated facility to Kartini reactor which is used for temporary spent fuels storage. The facility is one of the structures, systems and components (SSCs) important to safety. Among the safety functions of fuel handling and storage are to prevent any uncontrolable criticality accidents and to limit the fuel temperature increase. Safety analyses should, at least, cover neutronic and thermal hydraulic calculations of the bulk shielding. Thermal hydraulic analyses were intended to ensure that heat removal and the process of the spent fuels cooling takes place adequately and no heat accumulation that challenges the fuel integrity. Validated code, PARET/ANL was used for analysing the spent fuels cooling with natural convection mode. The calculations results concluded that natural convection cooling mode can adequately cools down the decay heat without significant increase in fuel temperatur. Keywords: bulk shielding, spent fuels, natural convection, PARET.
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Saarenheimo, Arja, Michael Borgerhoff, Kim Calonius, Anthony Darraba, Alexandre Hamelin, Sara Ghadimi Khasraghy, Amin Karbassi, et al. "Numerical studies on vibration propagation and damping test V1." Rakenteiden Mekaniikka 51, no. 1 (August 16, 2018): 55–80. http://dx.doi.org/10.23998/rm.68954.

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Earthquakes and aircraft impacts induce vibrations that propagate throughout the entire building and they need to be considered in designing SSCs (Structures, Systems and Components). Mainly linear calculation methods have been in use in design practice and the codes and standards consider damping ratios only for linear structural analyses. Induced vibrations, especially in damaged concrete structures, have not been studied extensively enough for optimization of structural frameworks and/or qualified systems and components. Experimental data on damping properties of damaged reinforced concrete are needed also for benchmarking analysis programs and methods. Recently, within IMPACT project, a new type of test series considering vibration propagation has been carried out at VTT. The test target is a reinforced concrete structure with two parallel walls connected to a floor slab. The front wall is additionally supported by triangular shaped side walls which are connected to the floor slab too. The test structure is supported on elastomeric bearing pads, with back pipes effective mainly in compression and with bars effective in tension. In order to obtain information on vibration propagation in damaged concrete structure at different levels of damage grades the same structure was tested six times. At each time the mass of the deformable stainless steel missile was 50 kg. The hit point located in the middle of the front wall. The impact velocity was about 110 m/s in the first four tests (V1A-D) and about 60 m/s in the remaining two tests (V1E and F). In this paper, numerical results on tests V1A and V1F are compared with the corresponding experimental ones. The calculated results, such as accelerations, displacements, their response spectra and strains, are compared with experimental measurements. Five finite element (FE) programs are used in computations: Abaqus, Europlexus, LS-DYNA, SOFiSTiK and an in-house code (IHC). Most of the FE-codes in the present study use shell elements. In Abaqus and SOFiSTiK non-linear behaviour of shell section is modelled by dividing the cross section into layers. Reinforcements are also modelled as layers. In Europlexus and IHC, an alternative approach is adopted in which the non-linear behaviour of concrete and reinforcement is homogenized beforehand in the shell thickness direction obtaining relations between stress resultants and generalized strains valid for the shell section. In LS-DYNA, 3D solid elements for modelling concrete and beam elements for modelling reinforcements are used. Equations of motion are integrated with explicit central difference time integration method, except in SOFiSTiK implicit integration method is used. Modelling and computations with the mentioned FE-programs are made independently of each other. Computations with LS-DYNA are carried out as blind exercises. Consideration of the results from benchmarking point of view is still on-going. However it is evident that analysed results follow reasonable well test results in main design parameter level such as maximum displacements, accelerations and strains. Also frequency spectra are estimated reasonably well.
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Gvozdev, Vladislav, and Galina Kozinetc. "Nuclear qualification process for systems, structures and components." MATEC Web of Conferences 245 (2018): 11010. http://dx.doi.org/10.1051/matecconf/201824511010.

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The modern NPPs (Nuclear Power Plants) are the part of the very complex and demanding sector of industry. Its complexity is based on the innovate and the high-tech technologies, engineered safety features where the specific safety functions are to be performed to ensure the nuclear safety (as part of technosphere safety) and prevent radioactivity release, which consequently lead to the possible human losses and environmental disasters. Consequently, modern technologies incorporated in the design and construction of NPP (its systems, structure and components) shall be qualified to ensure its capability to perform designated safety functions in the demanded conditions, including harsh accident environment (qualified as intended) via the specific V&V activities. Thus, Qualification should not cover only the equipment, but the all: systems, structures and components (SSC), therefore a systematic approach to its organization and planning is needed, which is not fully presented in publications nowadays. The article objective is to define the SSC Qualification and its scope of application, identify the Functional and Environmental qualification and forming of the Qualification context. Then, the article determines the V&V actions that provide Qualification evidences.
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Pavlou, Eleni, and Michael C. Constantinou. "Response of Nonstructural Components in Structures with Damping Systems." Journal of Structural Engineering 132, no. 7 (July 2006): 1108–17. http://dx.doi.org/10.1061/(asce)0733-9445(2006)132:7(1108).

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Dissertations / Theses on the topic "Structures, systems and components (SSCs)"

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Murray, Kevin Paul. "The design of antenna systems on complex structures using characteristic modes." Thesis, University of Liverpool, 1993. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.385200.

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Lane, Dewey Hobson III. "Identification of natural frequency components of articulated flexible structures." Thesis, Georgia Institute of Technology, 1996. http://hdl.handle.net/1853/15972.

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Kasinos, Stavros. "Seismic response analysis of linear and nonlinear secondary structures." Thesis, Loughborough University, 2018. https://dspace.lboro.ac.uk/2134/33728.

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Understanding the complex dynamics that underpin the response of structures in the occurrence of earthquakes is of paramount importance in ensuring community resilience. The operational continuity of structures is influenced by the performance of nonstructural components, also known as secondary structures. Inherent vulnerability characteristics, nonlinearities and uncertainties in their properties or in the excitation pose challenges that render their response determination as a non-straightforward task. This dissertation settles in the context of mathematical modelling and response quantification of seismically driven secondary systems. The case of bilinear hysteretic, rigid-plastic and free-standing rocking oscillators is first considered, as a representative class of secondary systems of distinct behaviour excited at a single point in the primary structure. The equations governing their full dynamic interaction with linear primary oscillators are derived with the purpose of assessing the appropriateness of simplified analysis methods where the secondary-primary feedback action is not accounted for. Analyses carried out in presence of pulse-type excitation have shown that the cascade approximation can be considered satisfactory for bilinear systems provided the secondary-primary mass ratio is adequately low and the system does not approach resonance. For the case of sliding and rocking systems, much lighter secondary systems need to be considered if the cascade analysis is to be adopted, with the validity of the approximation dictated by the selection of the input parameters. Based on the premise that decoupling is permitted, new analytical solutions are derived for the pulse driven nonlinear oscillators considered, conveniently expressing the seismic response as a function of the input parameters and the relative effects are quantified. An efficient numerical scheme for a general-type of excitation is also presented and is used in conjunction with an existing nonstationary stochastic far-field ground motion model to determine the seismic response spectra for the secondary oscillators at given site and earthquake characteristics. Prompted by the presence of uncertainty in the primary structure, and in line with the classical modal analysis, a novel approach for directly characterising uncertainty in the modal shapes, frequencies and damping ratios of the primary structure is proposed. A procedure is then presented for the identification of the model parameters and demonstrated with an application to linear steel frames with uncertain semi-rigid connections. It is shown that the proposed approach reduces the number of the uncertain input parameters and the size of the dynamic problem, and is thus particularly appealing for the stochastic assessment of existing structural systems, where partial modal information is available e.g. through operational modal analysis testing. Through a numerical example, the relative effect of stochasticity in a bi-directional seismic input is found to have a more prominent role on the nonlinear response of secondary oscillators when compared to the uncertainty in the primary structure. Further extending the analyses to the case of multi-attached linear secondary systems driven by deterministic seismic excitation, a convenient variant of the component-mode synthesis method is presented, whereby the primary-secondary dynamic interaction is accounted for through the modes of vibration of the two components. The problem of selecting the vibrational modes to be retained in analysis is then addressed for the case of secondary structures, which may possess numerous low frequency modes with negligible mass, and a modal correction method is adopted in view of the application for seismic analysis. The influence of various approaches to build the viscous damping matrix of the primary-secondary assembly is also investigated, and a novel technique based on modal damping superposition is proposed. Numerical applications are demonstrated through a piping secondary system multi-connected on a primary frame exhibiting various irregularities in plan and elevation, as well as a multi-connected flexible secondary system. Overall, this PhD thesis delivers new insights into the determination and understanding of the response of seismically driven secondary structures. The research is deemed to be of academic and professional engineering interest spanning several areas including seismic engineering, extreme events, structural health monitoring, risk mitigation and reliability analysis.
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Enkler, Hans-Georg [Verfasser]. "Rechnergestützter Entwurf von Bauteilen mit stark streuenden Leitstützstrukturen am Beispiel hochbelastbarer urgeformter mikromechanischer Systeme = Computer aided design of components with channel and support structures subject to high scatter using high strength molded micromechanical systems as an example / Hans-Georg Enkler." Karlsruhe : IPEK, 2010. http://d-nb.info/1002577071/34.

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Sanchez, Dyana. "Etude structurale et fonctionnelle de la régulation de la compétence et du processus de transformation chez Streptococcus pneumoniae." Thesis, Université Paris-Saclay (ComUE), 2015. http://www.theses.fr/2015SACLS050.

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La transformation génétique naturelle contribue au maintien et à l'évolution des génomes bactériens, elle constitue pour les bactéries un mécanisme clé pour s'adapter à l'environnement. Elle permet l'intégration d'ADN exogène au sein du chromosome bactérien par recombinaison homologue lors d'un état physiologique particulier de la bactérie appelé compétence. Mon travail de thèse a porté sur la régulation de la compétence chez S. pneumoniae (ComD, ComE) et sur les interactions entre les protéines impliquées dans la prise en charge, le traitement et la recombinaison de l'ADN transformant (DprA, RecA). Chez cette bactérie, l'entrée en compétence est sous le contrôle du système à deux composantes ComD-ComE qui induit la transcription des gènes cibles. DprA est l'une des protéines surexprimée lors de la compétence, elle est très conservée dans le monde bactérien, et participe à la fermeture de la compétence via une interaction directe avec ComE. DprA est également une protéine centrale de la transformation impliquée dans la protection de l'ADN entrant contre les nucléases, et dans le recrutement de la recombinase RecA. L'analyse par SAXS du complexe ComD-ComE, la résolution de la structure cristallographique des domaines REC de ComE, et l'étude des interaction entre ComE et ses régions promotrices ont permis de mieux comprendre la chorégraphie de l'entrée en compétence de S. pneumoniae. En parallèle, nous avons étudié les interactions de SpDprA avec l'ADN et avec RecA. Ces données nous ont permis de proposer un modèle d'interaction entre DprA et RecA chez S. pneumoniae et de proposer un mécanisme de chargement de RecA sur l'ADNsb par DprA. Je me suis également intéressée à DprA de H. pylori en participant à la résolution de la structure 3D de son domaine C-terminal par RMN et en étudiant son interaction avec l'ADNdb
The natural genetic transformation contributes to the maintenance and the evolution of the genomes in bacteria; it is a key mechanism to adapt to their environment. It allows the integration of exogenous DNA into the bacterial chromosome by homologous recombination during a particular state called competence.My thesis focused on the regulation of the competence state in S. pneumoniae (ComD, ComE), and on the interactions between the proteins involved in the uptake, the processing and recombination of exogenous DNA (DprA, RecA). In this bacterium, the opening of the competence is under the control of the two-component system ComD-ComE, who induces the transcription of target genes. DprA is one of the protein induced during the competence state, it is very conserved into the bacterial kingdom, and is involved in the closure of competence via direct interaction with ComE. DprA is also a key transformation protein involved in processing the incoming DNA, protection against nucleases, and recruitment of the RecA recombinase. SAXS analysis of the ComD-ComE, resolution of the crystallographic structure of ComE REC domain study of the interactions between ComE and its promoter regions allowed us to understand the choreography of competence opening in S. pneumoniae. Meanwhile, we studied spDprA interactions with DNA and with RecA. These data allowed us to propose an interaction model between DprA and RecA in S. pneumoniae and to propose a mechanism for RecA's loading on the ssDNA by DprA. I focused too on H. pylori DprA participating on the resolution of the 3D structure of the C-terminal domain by NMR and studying its interaction with the dsDNA
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Scarfe, Bradley Edward. "Oceanographic Considerations for the Management and Protection of Surfing Breaks." The University of Waikato, 2008. http://hdl.handle.net/10289/2668.

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Although the physical characteristics of surfing breaks are well described in the literature, there is little specific research on surfing and coastal management. Such research is required because coastal engineering has had significant impacts to surfing breaks, both positive and negative. Strategic planning and environmental impact assessment methods, a central tenet of integrated coastal zone management (ICZM), are recommended by this thesis to maximise surfing amenities. The research reported here identifies key oceanographic considerations required for ICZM around surfing breaks including: surfing wave parameters; surfing break components; relationship between surfer skill, surfing manoeuvre type and wave parameters; wind effects on waves; currents; geomorphic surfing break categorisation; beach-state and morphology; and offshore wave transformations. Key coastal activities that can have impacts to surfing breaks are identified. Environmental data types to consider during coastal studies around surfing breaks are presented and geographic information systems (GIS) are used to manage and interpret such information. To monitor surfing breaks, a shallow water multibeam echo sounding system was utilised and a RTK GPS water level correction and hydrographic GIS methodology developed. Including surfing in coastal management requires coastal engineering solutions that incorporate surfing. As an example, the efficacy of the artificial surfing reef (ASR) at Mount Maunganui, New Zealand, was evaluated. GIS, multibeam echo soundings, oceanographic measurements, photography, and wave modelling were all applied to monitor sea floor morphology around the reef. Results showed that the beach-state has more cellular circulation since the reef was installed, and a groin effect on the offshore bar was caused by the structure within the monitoring period, trapping sediment updrift and eroding sediment downdrift. No identifiable shoreline salient was observed. Landward of the reef, a scour hole ~3 times the surface area of the reef has formed. The current literature on ASRs has primarily focused on reef shape and its role in creating surfing waves. However, this study suggests that impacts to the offshore bar, beach-state, scour hole and surf zone hydrodynamics should all be included in future surfing reef designs. More real world reef studies, including ongoing monitoring of existing surfing reefs are required to validate theoretical concepts in the published literature.
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Moreira, Ana Sofia Pereira. "Study of modifications induced by thermal and oxidative treatment in oligo and polysaccharides of coffee by mass spectrometry." Doctoral thesis, Universidade de Aveiro, 2016. http://hdl.handle.net/10773/17074.

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Doutoramento em Bioquímica
Os polissacarídeos são os componentes maioritários dos grãos de café verde e torrado e da bebida de café. Os mais abundantes são as galactomananas, seguindo-se as arabinogalactanas. Durante o processo de torra, as galactomananas e arabinogalactanas sofrem modificações estruturais, as quais estão longe de estar completamente elucidadas devido à sua diversidade e à complexidade estrutural dos compostos formados. Durante o processo de torra, as galactomananas e arabinogalactanas reagem com proteínas, ácidos clorogénicos e sacarose, originando compostos castanhos de alto peso molecular contendo nitrogénio, designados de melanoidinas. As melanoidinas do café apresentam diversas atividades biológicas e efeitos benéficos para a saúde. No entanto, a sua estrutura exata e os mecanismos envolvidos na sua formação permanecem desconhecidos, bem como a relação estrutura-atividade biológica. A utilização de sistemas modelo e a análise por espectrometria de massa permitem obter uma visão global e, simultaneamente, detalhada das modificações estruturais nos polissacarídeos do café promovidas pela torra, contribuindo para a elucidação das estruturas e mecanismos de formação das melanoidinas. Com base nesta tese, oligossacarídeos estruturalmente relacionados com a cadeia principal das galactomananas, (β1→4)-Dmanotriose (Man3), e as cadeias laterais das arabinogalactanas, (α1→5)-Larabinotriose (Ara3), isoladamente ou em misturas com ácido 5-Ocafeoilquínico (5-CQA), o ácido clorogénico mais abundante nos grãos de café verde, e péptidos compostos por tirosina e leucina, usados como modelos das proteínas, foram sujeitos a tratamento térmico a seco, mimetizando o processo de torra. A oxidação induzida por radicais hidroxilo (HO•) foi também estudada, uma vez que estes radicais parecem estar envolvidos na modificação dos polissacarídeos durante a torra. A identificação das modificações estruturais induzidas por tratamento térmico e oxidativo dos compostos modelo foi feita por estratégias analíticas baseadas principalmente em espectrometria de massa, mas também em cromatografia líquida. A cromatografia de gás foi usada na análise de açúcares neutros e ligações glicosídicas. Para validar as conclusões obtidas com os compostos modelo, foram também analisadas amostras de polissacarídeos do café obtidas a partir de resíduo de café e café instantâneo. Os resultados obtidos a partir dos oligossacarídeos modelo quando submetidos a tratamento térmico (seco), assim como à oxidação induzida por HO• (em solução), indicam a ocorrência de despolimerização, o que está de acordo com estudos anteriores que reportam a despolimerização das galactomananas e arabinogalactanas do café durante a torra. Foram ainda identificados outros compostos resultantes da quebra do anel de açúcares formados durante o tratamento térmico e oxidativo da Ara3. Por outro lado, o tratamento térmico a seco dos oligossacarídeos modelo (individualmente ou quando misturados) promoveu a formação de oligossacarídeos com um maior grau de polimerização, e também polissacarídeos com novos tipos de ligações glicosídicas, evidenciando a ocorrência de polimerização através reações de transglicosilação não enzimática induzidas por tratamento térmico a seco. As reações de transglicosilação induzidas por tratamento térmico a seco podem ocorrer entre resíduos de açúcares provenientes da mesma origem, mas também de origens diferentes com formação de estruturas híbridas, contendo arabinose e manose como observado nos casos dos compostos modelo usados. Os resultados obtidos a partir de amostras do resíduo de café e de café instantâneo sugerem a presença de polissacarídeos híbridos nestas amostras de café processado, corroborando a ocorrência de transglicosilação durante o processo de torra. Além disso, o estudo de misturas contendo diferentes proporções de cada oligossacarídeo modelo, mimetizando regiões do grão de café com composição distinta em polissacarídeos, sujeitos a diferentes períodos de tratamento térmico, permitiu inferir que diferentes estruturas híbridas e não híbridas podem ser formadas a partir das arabinogalactanas e galactomananas, dependendo da sua distribuição nas paredes celulares do grão e das condições de torra. Estes resultados podem explicar a heterogeneidade de estruturas de melanoidinas formadas durante a torra do café. Os resultados obtidos a partir de misturas modelo contendo um oligossacarídeo (Ara3 ou Man3) e 5-CQA sujeitas a tratamento térmico a seco, assim como de amostras provenientes do resíduo de café, mostraram a formação de compostos híbridos compostos por moléculas de CQA ligadas covalentemente a um número variável de resíduos de açúcar. Além disso, os resultados obtidos a partir da mistura contendo Man3 e 5-CQA mostraram que o CQA atua como catalisador das reações de transglicosilação. Por outro lado, nas misturas modelo contendo um péptido, mesmo contendo também 5-CQA e sujeitas ao mesmo tratamento, observou-se uma diminuição na extensão das reações transglicosilação. Este resultado pode explicar a baixa extensão das reações de transglicosilação não enzimáticas durante a torra nas regiões do grão de café mais ricas em proteínas, apesar dos polissacarídeos serem os componentes maioritários dos grãos de café. A diminuição das reações de transglicosilação na presença de péptidos/proteínas pode dever-se ao facto de os resíduos de açúcares redutores reagirem preferencialmente com os grupos amina de péptidos/proteínas por reação de Maillard, diminuindo o número de resíduos de açúcares redutores disponíveis para as reações de transglicosilação. Além dos compostos já descritos, uma diversidade de outros compostos foram formados a partir dos sistemas modelo, nomeadamente derivados de desidratação formados durante o tratamento térmico a seco. Em conclusão, a tipificação das modificações estruturais promovidas pela torra nos polissacarídeos do café abre o caminho para a compreensão dos mecanismos de formação das melanoidinas e da relação estrutura-atividade destes compostos.
Polysaccharides are the major components of green and roasted coffee beans, and coffee brew. The most abundant ones are galactomannans, followed by arabinogalactans. During the roasting process, galactomannans and arabinogalactans undergo structural modifications that are far to be completely elucidated due to their diversity and complexity of the compounds formed. During the roasting process, galactomannans and arabinogalactans react with proteins, chlorogenic acids, and sucrose, originating high molecular weight brown compounds containing nitrogen, known as melanoidins. Several biological activities and beneficial health effects have been attributed to coffee melanoidins. However, their exact structures and the mechanisms involved in their formation remain unknown, as well as the structure-biological activity relationship. The use of model systems and mass spectrometry analysis allow to obtain an overall view and, simultaneously, detailed, of the structural modifications in coffee polysaccharides promoted by roasting, contributing to the elucidation of the structures and formation mechanisms of melanoidins. Based on this thesis, oligosaccharides structurally related to the backbone of galactomannans, (β1→4)-D-mannotriose, and the side chains of arabinogalactans, (α1→5)-Larabinotriose, alone or in mixtures with 5-O-caffeoylquinic acid, the most abundant chlorogenic acid in green coffee beans, and dipeptides composed by tyrosine and leucine, used as models of proteins, were submitted to dry thermal treatments, mimicking the coffee roasting process. The oxidation induced by hydroxyl radicals (HO•) was also studied, since these radicals seem to be involved in the modification of the polysaccharides during roasting. The identification of the structural modifications induced by thermal and oxidative treatment of the model compounds was performed mostly by mass spectrometry-based analytical strategies, but also using liquid chromatography. Gas chromatography was used in the analysis of neutral sugars and glycosidic linkages. To validate the conclusions achieved with the model compounds, coffee polysaccharide samples obtained from spent coffee grounds and instant coffee were also analysed. The results obtained from the model oligosaccharides when submitted to thermal treatment (dry) or oxidation induced by HO• (in solution) indicate the occurrence of depolymerization, which is in line with previous studies reporting the depolymerization of coffee galactomannans and arabinogalactans during roasting. Compounds resulting from sugar ring cleavage were also formed during thermal treatment and oxidative treatment of Ara3. On the other hand, the dry thermal treatment of the model oligosaccharides (alone or when mixed) promoted the formation of oligosaccharides with a higher degree of polymerization, and also polysaccharides with new type of glycosidic linkages, evidencing the occurrence of polymerization via non-enzymatic transglycosylation reactions induced by dry thermal treatment. The transglycosylation reactions induced by dry thermal treatment can occur between sugar residues from the same origin, but also of different origins, with formation of hybrid structures, containing arabinose and mannose in the case of the model compounds used. The results obtained from spent coffee grounds and instant coffee samples suggest the presence of hybrid polysaccharides in these processed coffee samples, corroborating the occurrence of transglycosylation during the roasting process. Furthermore, the study of mixtures containing different proportions of each model oligosaccharide, mimicking coffee bean regions with distinct polysaccharide composition, subjected to different periods of thermal treatment, allowed to infer that different hybrid and non-hybrid structures may be formed from arabinogalactans and galactomannans, depending on their distribution in the bean cell walls and on roasting conditions. These results may explain the heterogeneity of melanoidins structures formed during coffee roasting. The results obtained from model mixtures containing an oligosaccharide (Ara3 or Man3) and 5-CQA and subjected to dry thermal treatment, as well as samples derived from spent coffee grounds, showed the formation of hybrid compounds composed by CQA molecules covalently linked to a variable number of sugar residues. Moreover, the results obtained from the mixture containing Man3 and 5-CQA showed that CQA acts as catalyst of transglycosylation reactions. On the other hand, in the model mixtures containing a peptide, even if containing 5-CQA and subjected to the same treatment, it was observed a decrease in the extent of transglycosylation reactions. This outcome can explain the low extent of non-enzymatic transglycosylation reactions during roasting in coffee bean regions enriched in proteins, although polysaccharides are the major components of the coffee beans. The decrease of transglycosylation reactions in the presence of peptides/proteins can be related with the preferential reactivity of reducing residues with the amino groups of peptides/proteins by Maillard reaction, decreasing the number of reducing residues available to be directly involved in the transglycosylation reactions. In addition to the compounds already described, a diversity of other compounds were formed from model systems, namely dehydrated derivatives formed during dry thermal treatment. In conclusion, the identification of the structural modifications in coffee polysaccharides promoted by roasting pave the way to the understanding of the mechanisms of formation of melanoidins and structure-activity relationship of these compounds.
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Books on the topic "Structures, systems and components (SSCs)"

1

Agency, International Atomic Energy, ed. Decommissioning of underground structures, systems and components. Vienna: International Atomic Energy Agency, 2006.

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American Institute of Aeronautics and Astronautics., ed. Standard space systems: Structures, structural components, and structural assemblies. Reston, VA: American Institute of Aeronautics and Astronautics, 2005.

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Ovidiu, Coman, ed. Design of hazardous mechanical structures, systems and components for extreme loads. New York: ASME Press, 2006.

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American Society of Civil Engineers. American Society of Civil Engineers seismic design criteria for structures, systems, and components in nuclear facilities. Reston, Va: American Society of Civil Engineers, 2005.

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American Society of Civil Engineers. American Society of Civil Engineers seismic design criteria for structures, systems, and components in nuclear facilities. Reston, VA: American Society of Civil Engineers, 2006.

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Wu, Shih-Chin. Large angle transient dynamics (LATDYN): Demonstration problem manual. [Washington, D.C.]: National Aeronautics and Space Administration, Office of Management, Scientific and Technical Information Program, 1991.

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Verma, Ajit Kumar, Hari Prasad Muruva, and G. R. Reddy. Textbook of Seismic Design: Structures, Piping Systems, and Components. Springer, 2019.

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Jiang, Liqiang, Liping Wang, and Lingyu Zhou. Design of Steel Structures: Materials, Connections, Components and Structural Systems. Elsevier, 2022.

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American Institute of Aeronautics and Astronautics. Space Systems: Structures, Structural Components, And Structural Assemblies (Aiaa Standards). AIAA (American Institute of Aeronautics & Ast, 2005.

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Space Systems-Metallic Pressure Vessels, Pressurized Structures, and Pressure Components. Amer Inst of Aeronautics &, 1999.

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Book chapters on the topic "Structures, systems and components (SSCs)"

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Arbach, Youssef, David Karcher, Kirstin Peters, and Uwe Nestmann. "Dynamic Causality in Event Structures." In Formal Techniques for Distributed Objects, Components, and Systems, 83–97. Cham: Springer International Publishing, 2015. http://dx.doi.org/10.1007/978-3-319-19195-9_6.

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Crowther, M. F., M. G. Phillips, and R. C. Wyatt. "Design Stress Considerations for GRP Components of Power Station Cooling-water Systems." In Composite Structures 3, 540–61. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-009-4952-2_38.

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Reddy, G. R., and R. K. Verma. "Seismic Qualification of Structures, Systems, and Components by Test." In Textbook of Seismic Design, 419–55. Singapore: Springer Singapore, 2019. http://dx.doi.org/10.1007/978-981-13-3176-3_12.

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Postell, Matthew, Daniel Kiracofe, Onome Scott-Emuakpor, and Tommy George. "Experimental Observations of Nonlinear Damping of Additively Manufactured Components with Internal Particle Dampers." In Nonlinear Structures & Systems, Volume 1, 87–96. Cham: Springer International Publishing, 2012. http://dx.doi.org/10.1007/978-3-031-04086-3_14.

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Hassan, Maguid H. M. "A Reliability Assessment Model for MR Damper Components within a Smart Structural Control Scheme." In Emboding Intelligence in Structures and Integrated Systems, 218–24. Stafa: Trans Tech Publications Ltd., 2008. http://dx.doi.org/10.4028/3-908158-13-3.218.

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Khoo, Khoongming, Thomas Peyrin, Axel Y. Poschmann, and Huihui Yap. "FOAM: Searching for Hardware-Optimal SPN Structures and Components with a Fair Comparison." In Advanced Information Systems Engineering, 433–50. Berlin, Heidelberg: Springer Berlin Heidelberg, 2014. http://dx.doi.org/10.1007/978-3-662-44709-3_24.

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Raj, Baldev, and P. Chellapandi. "Multifunctional Components in Sodium Cooled Fast Reactor: Design and Development." In IUTAM Symposium on Multi-Functional Material Structures and Systems, 163–73. Dordrecht: Springer Netherlands, 2009. http://dx.doi.org/10.1007/978-90-481-3771-8_17.

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Obando, Sergio E., and Peter Avitabile. "Prediction of Forced Response on Ancillary Subsystem Components Attached to Reduced Linear Systems." In Dynamics of Coupled Structures, Volume 1, 51–72. Cham: Springer International Publishing, 2014. http://dx.doi.org/10.1007/978-3-319-04501-6_5.

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Feizi, Ten. "Carbohydrate Structures as ONCO-Developmental Antigens and Components of Receptor Systems." In The Molecular Immunology of Complex Carbohydrates, 317–29. Boston, MA: Springer US, 1988. http://dx.doi.org/10.1007/978-1-4613-1663-3_11.

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Maradudin, A. A., V. Kuzmiak, and A. R. McGurn. "Photonic Band Structures of Systems with Components Characterized by Frequency-Dependent Dielectric Functions." In Photonic Band Gap Materials, 271–318. Dordrecht: Springer Netherlands, 1996. http://dx.doi.org/10.1007/978-94-009-1665-4_16.

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Conference papers on the topic "Structures, systems and components (SSCs)"

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Imbro, Eugene, and Thomas G. Scarbrough. "Incorporation of Risk Insights in the Regulatory Treatment of Nuclear Power Plant Structures, Systems, and Components." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22658.

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The U.S. Nuclear Regulatory Commission (NRC) has established an initiative to risk-inform the requirements in Title 10 of the Code of Federal Regulations (10 CFR) for the regulatory treatment of structures, systems, and components (SSCs) used in commercial nuclear power plants. As discussed in several Commission papers (e.g., SECY-99-256 and SECY-00-0194), Option 2 of this initiative involves categorizing plant SSCs based on their safety significance, and specifying treatment that would provide an appropriate level of confidence in the capability of those SSCs to perform their design functions in accordance with their risk categorization. The NRC has initiated a rulemaking effort to allow licensees of nuclear power plants in the United States to implement the Option 2 approach in lieu of the “special treatment requirements” of the NRC regulations. In a proof-of-concept effort, the NRC recently granted exemptions from the special treatment requirements for safety-related SSCs categorized as having low risk significance by the licensee of the South Texas Project (STP) Units 1 and 2 nuclear power plant, based on a review of the licensee’s high-level objectives of the planned treatment for safety-related and high-risk nonsafety-related SSCs. This paper discusses the NRC staff’s views regarding the treatment of SSCs at STP described by the licensee in its updated Final Safety Analysis Report (FSAR) in support of the exemption request, and provides the status of rulemaking that would incorporate risk insights into the treatment of SSCs at nuclear power plants.
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Wang, Congjian, Diego Mandelli, Shawn St Germain, Curtis Smith, David Morton, Ivilina Popova, and Stephen Hess. "Stochastic Optimization for Long Term Capital Structures, Systems, and Components Refurbishment and Replacement." In ASME 2020 Power Conference collocated with the 2020 International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/power2020-16195.

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Abstract As commercial nuclear power plants (NPPs) pursue extended plant operations in the form of Second License Renewals (SLRs), opportunities exist for these plants to provide capital investments to ensure long-term, safe, and economic performance. Several utilities have already announced their intention to pursue extended operations for one or more of their NPPs via SLR2. The goal of this research is to develop a risk-informed approach to evaluate and prioritize plant capital investments made in preparation for, and during the period of, extended plant operations to support decisions in NPP operations. In order to prioritize project selection via a risk-informed approach we developed a single decision-making tool that integrates safety/reliability, cost, and stochastic optimization models to provide users with data analysis capabilities to more cost effectively manage plant assets. Both stochastic analysis methods — such as Monte Carlo-based sampling strategies — and multi-stage stochastic optimization strategies are employed to provide priority lists to decision-makers in support of risk-informed decisions. We applied the proposed method to a trial application of projected replacement/refurbishment expenditures for plant capital assets (i.e., structures, systems, and components [SSCs]). The objective is to optimize the SSC replacement/refurbishment schedule in terms of economic constraints, data uncertainties, and SSC reliability data, as well to generate a priority list for maximizing returns on investment.
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Meyer, Theodore A., G. Gary Elder, and Ricardo Llovet. "Life Cycle Management: Managing the Aging of Critical Nuclear Plant Components." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22536.

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Life Cycle Management is a structured process to manage equipment aging and long-term equipment reliability for nuclear plant Systems, Structures and Components (SSCs). The process enables the identification of effective repair, replace, inspect, test and maintenance activities and the optimal timing of the activities to maximize the economic value to the nuclear plant. This paper will provide an overview of the process and some of the tools that can be used to implement the process for the SSCs deemed critical to plant safety and performance objectives. As nuclear plants strive to reduce costs, extend life and maximize revenue, the LCM process and the supporting tools summarized in this paper can enable development of a long term, cost efficient plan to manage the aging of the plant SSCs.
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Florescu, Gheorghe, and Mihail Cojan. "Identification of CSSC Caused by Ageing and Degradation." In 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89286.

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PSA studies, that were developed for some NPPs, permit the using of the created models to perform many research tests, in order to optimize the structures, systems and components (SSCs) operation or to identify the NPP or systems weaknesses, due to specific or special factors. SSCs that influence decisively the NPP reliability are considered as critical. Also, for the accident conditions, the SSC, which have a major influence to the system availability or operability, are considered as critical. Many worldwide NPPs reached the life time or are very close to do that. Several SSCs have shorter life times than NPP’s life time. Ageing is one of the factors that decrease the SSC life time. Due to ageing, if are not replaced, some SSCs, or groups of redundant SSCs, become critical looking to safety. Some questions for what to do in the situation when a SSC must be replaced and the SSC specific manufacturer doesn’t exist, could also be put. The paper tried to solve the problem of SSC modeling by introducing of an ageing factor in SSC model. Fault tree (F/T) modeling approach is assumed. There are two possibilities for modeling: failure rates that are changed or specific MCS (minimal cut set) term modified by ageing. Risk analysis and PSA techniques are used as a basis for analysis. The paper includes: the steps to establish the systems or components that suffer ageing; methods to identify CSSC taking into account ageing; the events associated to ageing/degradation and presentation of method to determine the ageing related events, selection of the SSCs that are important for analyses; selection of the most significant ageing events; ranking of ageing events; association of events to these components in order to decide for the CSSC detailed analyses; ranking / ordering of the ageing related events; optimization of NPP systems design and operation considering ageing; impact of ageing to NPP operation/safety/safety margins and to manufacturer technical specifications. The paper presents a brief description of the most important aspects of the methods, used to analyze the ageing effects on appearing of CSSCs, taking into account the previous developed NPP PSA models and PSA modeling tools.
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Balls, Vondell J., David S. Duncan, and Stephanie L. Austad. "The Component Test Facility: A National User Facility for Testing of High Temperature Gas-Cooled Reactor (HTGR) Components and Systems." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58250.

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The Next Generation Nuclear Plant (NGNP) and other High-Temperature Gas-cooled Reactor (HTGR) Projects require research, development, design, construction, and operation of a nuclear plant intended for both high-efficiency electricity production and high-temperature industrial applications, including hydrogen production. During the life cycle stages of an HTGR, plant systems, structures and components (SSCs) will be developed to support this reactor technology. To mitigate technical, schedule, and project risk associated with development of these SSCs, a large-scale test facility is required to support design verification and qualification prior to operational implementation. As a full-scale helium test facility, the Component Test facility (CTF) will provide prototype testing and qualification of heat transfer system components (e.g., Intermediate Heat Exchanger, valves, hot gas ducts), reactor internals, and hydrogen generation processing. It will perform confirmation tests for large-scale effects, validate component performance requirements, perform transient effects tests, and provide production demonstration of hydrogen and other high-temperature applications. Sponsored wholly or in part by the U.S. Department of Energy, the CTF will support NGNP and will also act as a National User Facility to support worldwide development of High-Temperature Gas-cooled Reactor technologies.
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Zeng, Wei, and Hongxing Yu. "On the Use of Binary Importance Decision for Risk-Informed Categorization of SSCs." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75071.

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The categorization of Structures, Systems and Components (SSCs) is one of the foundations in the design of the nuclear reactor. The regulation requirements based on the current deterministic categorization are over-conservative in some aspects; on the other hand, some requirements for the nonsafety-related components are too loose. In order to make the requirements reasonable, the risk-informed significance categorization of SSCs has been presented. Risk-informed significance categorization (RISC) is to categorize structures, systems, or components (SSCs) of a nuclear power plant (NPP) into two or more groups, according to their significance using both probabilistic and deterministic insights. The SSCs are quantitatively categorized by their importance measures; Fussell–Vesely (FV) and Risk Achievement Worth (RAW) are widely used. But in conventional methods for the RISC, first, a component will be categorized as significance once the value of FV or RAW is over the thresholds. So the significant components are treated equally regardless of the difference between FV and RAW, that is not suitable. Second, the component RAW derived from the sum or maximum of the basic events is not realistic. Third, the categorization threshold for FV is not uniform, different reactors have the different thresholds. The three key problems will be researched in this paper, the quartered way will be presented base on the discussion about combination of the two importance measures (binary importance decision). And then through transferring the additivity from FV to RAW, the realistic component RAW derived from FV will be got. Finally, according to the relationship between FV and RAW, the threshold for FV will be gained similar to RAW. In the study, the author will use the new method to make a practice on the Daya Bay Nuclear Power Plant, 43% components of the low pressure safety injection system which are safety-related are categorized as low significant; 2.6% components which are nonsafety-related of the auxiliary feed water system are categorized as significant.
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Heymer, Adrian P. "Risk-Informing: The SSC Scope of U.S. NRC Special Treatment Requirements – Treatment of Low Safety-Significant SSCs." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22788.

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This paper provides a general description and rationale for licensee-established industrial controls for structures, systems and components (SSCs) that have been categorized as low safety-significant through a process consistent with 10 CFR 50.69 requirements.
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Jing, Zhou, Ran Wen Wang, Gong Quan, and Lv Wei Feng. "Assessment and Control Value Formulation on Radiological Consequence of On-Site Worker due to Radioactive Component Failure for Pressurized Water Reactor Plant." In 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-91624.

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Abstract All Structures, Systems, and Components (SSCs) in a nuclear power plant need to be classified according to their importance to safety to protect people and the environment. The Specific Safety Guide, No. SSG-30, issued by IAEA, guides how to meet the requirements for identifying safety functions and classification of SSCs and ensuring their appropriate quality and reliability. However, the relevant guidance has not specified the perspectives of low radiological consequences on on-site workers. To refine the SSCs classification and complement the IAEA guidance, a proposed limiting value and corresponding assessment method for low radiological consequence caused by SSCs failure from the on-site workers’ perspective based on international good practices are developed, which include the main process of on-site radiological consequence evaluation, the calculation method for different exposure pathways and the assessment assumptions. Also, typical examples of SSCs failure are also assessed to validate the proposed method’s feasibility. The assessment results show that the activity concentration of failure SSCs, the workers’ locations, the exposure duration of workers, and the local dose rate of each location are the main factors for on-site radiological consequence evaluation, and the proposed method in this paper can assist in the safety classification of SSCs in the third generation of pressurized water reactor nuclear power plants.
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Lyons, Sara, and Shilp Vasavada. "Seismic Probabilistic Risk Assessment of Nuclear Power Plants: 10 CFR 50.69 Assumptions and Sources of Uncertainty." In ASME 2018 International Mechanical Engineering Congress and Exposition. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/imece2018-87677.

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The U.S. Nuclear Regulatory Commission (NRC) promulgated Part 50.69 to Title 10 of the Code of Federal Regulations (CFR), “Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors,” in November 2004 (hereafter referred to as 10 CFR 50.69). The rule provides a voluntary alternative to compliance with many regulations which require “special treatment,” or regulatory requirements which go beyond industrial controls, including: specific inspection, testing, qualification, and reporting requirements. The voluntary alternative includes a process for categorization of structures, systems, and components (SSCs) as having either low safety significance (LSS) or high safety significance (HSS). The categorization process can result in increased requirements for HSS SSCs which were previously treated as non-safety-related, and reduced requirements for LSS SSCs which were previously treated as safety-related. The categorization process includes plant-specific risk analyses which are used in combination with an integrated decision-making panel (IDP) to determine whether the SSC has a low or high safety significance. Seismic probabilistic risk assessment (SPRA) is one of the risk analyses options to account for the seismic risk contribution. Because the 10 CFR 50.69 rule has currently not been implemented widely, the significance of various SPRA assumptions and sources of uncertainty to the categorization process has had limited evaluation for a broad spectrum of U.S. nuclear power plants. This paper will assess the importance of certain aspects of the seismic risk contribution to the categorization process. NRC Standardized Plant Analysis Risk (SPAR) models will be used to perform sensitivity studies to quantify the impact of various assumptions and sources of uncertainty on the outcome of the categorization process.
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Rothenho¨fer, Horst, Friedrich Scho¨ckle, and Gu¨nter Ko¨nig. "How a Knowledge Data Base Assists the Process of Aging Management." In ASME 2011 Pressure Vessels and Piping Conference. ASMEDC, 2011. http://dx.doi.org/10.1115/pvp2011-57895.

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Abstract:
The process of aging management in a nuclear power plant requires collaborative work of different departments. In this process information has to be gathered and evaluated systematically. At the beginning of the process it is important to classify all systems, structures and components (SSCs) into 3 categories of descending importance concerning safety where only the first two categories have to be considered for aging management. Basic information on the material and dimensions, operational parameters, quality status, analysis reports and relevant degradation mechanisms is stored in the data base for all SSCs of category 1 and 2. While a nuclear power plant is in service numerous events may occur which are related to aging and may have an influence on the quality of SSCs. Relevant events may be malfunction messages, maintenance results, operational experience, results of surveillance or events in external installations. It is important to evaluate these events concerning the aspect of aging and to decide which measures are required to prevent unexpected events of the same kind in the future. In some cases the new experience has to be assigned to comparable SSCs. These evaluations, the definition of measures and the tracking of their effectiveness have to be done by an aging management team that meets regularly every 3 months. The knowledge data base supports the application of the PDCA cycle and provides an overview and fast access to all quality documents related to each SSC including surveillance measures and results. It simplifies the generation of annual status reports which are valuable quality documents that reveal the effectiveness of aging management. Finally the procedure can be extended to SSCs which are important for the availability of the plant and thus take a step forward from aging management to plant life management.
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Reports on the topic "Structures, systems and components (SSCs)"

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I. Cuesta. Design-Load Basis for LANL Structures, Systems, and Components. Office of Scientific and Technical Information (OSTI), September 2004. http://dx.doi.org/10.2172/835892.

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Pete Jordan. Next Generation Nuclear Plant Structures, Systems, and Components Safety Classification White Paper. Office of Scientific and Technical Information (OSTI), September 2010. http://dx.doi.org/10.2172/991911.

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Hicks, D. F. Tank waste remediation system safety structures, systems, and components: requirements and characteristics. Office of Scientific and Technical Information (OSTI), September 1996. http://dx.doi.org/10.2172/293383.

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Hossain, Q. A., T. A. Nelson, and R. C. Murray. Topical issues on performance categorization of structures, systems and components for natural phenomena hazards mitigation. Office of Scientific and Technical Information (OSTI), December 1992. http://dx.doi.org/10.2172/188934.

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CREA, B. A. Application of Seismic Design Requirements to Cold Vacuum Drying (CVD) Facility Structures and Systems and Components. Office of Scientific and Technical Information (OSTI), November 1999. http://dx.doi.org/10.2172/798691.

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Forsberg, C. W., D. L. Moses, E. B. Lewis, R. Gibson, R. Pearson, W. J. Reich, G. A. Murphy, R. H. Staunton, and W. E. Kohn. Proposed and existing passive and inherent safety-related structures, systems, and components (building blocks) for advanced light-water reactors. Office of Scientific and Technical Information (OSTI), October 1989. http://dx.doi.org/10.2172/7023863.

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Hartman, D. J., D. D. Miller, and L. J. Klamerus. Identification of structures, systems, and components important to safety at the potential repository at Yucca Mountain; Yucca Mountain Site Characterization Project. Office of Scientific and Technical Information (OSTI), October 1991. http://dx.doi.org/10.2172/138258.

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Moe, Wayne L., and Amir Afzali. Modernization of Technical Requirements for Licensing of Advanced Non-Light Water Reactors: Safety Classification and Performance Criteria for Structures, Systems, and Components. Office of Scientific and Technical Information (OSTI), August 2019. http://dx.doi.org/10.2172/1560535.

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Moe, Wayne, and Amir Afzali. Modernization of Technical Requirements for Licensing of Advanced Non-Light Water Reactors: Safety Classification and Performance Criteria for Structures, Systems, and Components. Office of Scientific and Technical Information (OSTI), March 2020. http://dx.doi.org/10.2172/1700535.

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Braverman, Joseph, Richard Morante, Thomas Houston, B. Ellingwood, and Carl Costantino. Evaluation of ASCE 4-16 and AISC 43-18 (Draft) for use in the Risk-Informed Performance-Based Seismic Design of Nuclear Power Plant Structures, Systems, and Components. Office of Scientific and Technical Information (OSTI), December 2020. http://dx.doi.org/10.2172/1749907.

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