Seraphina Poem Analysis - 1265 Words

In the land of Novyd lived a bard named Spero, who always wore his heart on his sleeve. He traveled from court to court, charming the nobles with his songs and poems about love. In each court, Spero longed to meet the love of his life: he pursued any woman who caught his eye, offering them a piece of his heart in exchange for their affection. One evening in the castle courtyard, he came across a noblewoman surrounded by her handmaidens. They trembled in her presence, scampering away like frightened rats once she waved them away. She was Seraphina, the fairest lady of the court. No man could win her over. Nonetheless, Spero was determined to woo her. He spent the next few days picking the most vibrant flowers in the garden: blue†¦show more content†¦When he returned, the whole court marveled at sight of his kaleidoscopic bouquet, - including the woman, who introduced herself as Lyra. Spero sang his song for her, not a note out of place, then handed her a piece of his heart. S he accepted with delight. The next few days passed without incident. They were a happy couple, smiling and holding hands at every opportunity. The bard found himself performing better each night - on stage and in bed - for his new love ignited all his senses. But one night, Lyra came to him in tears. â€Å"I’ve lost the piece of your heart,† she cried, â€Å"if you will give me another, I promise I shan’t lose it.† And so Spero did, for he knew that lovers ought to forgive each other. He felt himself grow weaker as he gave her a new piece, but he wanted nothing more than to see Lyra happy. A couple of days passed and she lost another piece, and another, and another, until Spero finally drew the line. His voice was hoarse as of late, and he could no longer sing as well as he used to. â€Å"I cannot give you any more pieces of my heart,† he said. â€Å"You do not value it enough to take care of it. † Lyra was hurt by his words, but knew that h er chances of being forgiven were spent. She gathered her belongings from his bedchamber and bade him a tearful farewell. After giving a weak performance for the court, - and enduring his audience’s painful silence - Spero decided to stay and

Persepolis Marjane Satrapi s Persepolis - 1525 Words

Persepolis Research – Marjane Satrapi Notations: 1. Satrapi was born in Tehran, Iran (the nation’s capital) in the year 1969. The time in which Satrapi was born is critical to the events in her life due to the political turmoil that was occurring in her country. In 1979, at the age of 10, Satrapi witness firsthand the persecution and horrific consequences of the Islamic Revolution. The Islamic Revolution occurred due to the growing opposition lead by Ayatollah Khomeini against Mohammad Reza Shah and his secret police known as the Savak. The radical regime of shah gained support during this time, and hundreds of people were executed as a result. Soon after, Khomeini was able to declare an Islamic republic that reflected his ideals after an incredibly biased national referendum. He also became Iran’s supreme spiritual leader, soon instituting new rules and regulations in the country like the women’s clothing described in Persepolis. 2. Satrapi was the only child of a westernized, secular, and Marxist family that was against the regime of shah. Satrapi was lucky in that she belonged to a privileged upper class in Iran that exposed her to Western culture and allowed for her to receive a good education. Her parents encouraged her to think for herself and create her own opinions as a child. However, due to the views and lifestyle held by Satrapi’s family, the Islamic revolution changed her life dramatically. It is also important to note her family’s religious and politicalShow MoreRelatedPersepolis : Marjane Satrapi s Persepolis1756 Words   |  8 PagesPersepolis is a graphic novel by Marjane Satrapi, this graphic novel was based on the eyes of a Ten year old that experiences all types of emotions before and after the Islamic revolution, the oppression from the leaders. This novel gives us a brief on the history of Iran and their leaders, to the Embassy being taken over, via how they weren’t allowed to party. They also experience prohibition just like the United States in the 1920-1933 and like many coun tries they didn’t have any freedom. In theRead MoreMarjane Satrapi s Persepolis 1646 Words   |  7 Pages Marjane Satrapi’s graphic novel Persepolis is an expressive memoir of her growing up in Iran during the Islamic Revolution, the fall of the Shah’s regime and the Iran-Iraq War. Unlike conventional memoirs, she uses the black-and-white comic book form to find her identity through politics and her personal experiences in Iran and it has become effective and relevant in today’s society because she is a normal person that has had to live through extreme circumstances. Marjane has contributed to a wholeRead MoreMarjane Satrapi s Persepolis 1314 Words   |  6 PagesPersepolis is an autobiography of Marjane Satrapi’s childhood in her native Iran. She writes about being a child in Iran through the Iranian revolution and the Iran-Iraq war. As Satrapi recounts stories of her youth, one can observe that the Iran-Iraq war and the Iranian revolution are the central events driving the entire story. When the revolution and war happens, the dynamics of the book change completely. War creates a sense of unity and nationalism. Marjane shows a large contrast between herRead MorePersepolis : Marjane Satrapi s Persepolis Essay1448 Words   |  6 Pagesup. In the autobiography, Persepolis by Marjane Satrapi, the author recounts her life story by applying different literary tools into highlighting and revealing not just the events of her life, but the emotions and thoughts accompanying the events as well. Seeing events occur affects humans much more personally than reading. To put it another way, seeing a stranger getting run over by a car will be more emotionally dramatic than reading it in the news. Therefore, Satrapi chooses to accompany herRead MoreMarjane Satrapi s Persepolis 1501 Words   |  7 Pages The Iranian author of Persepolis, Marjane Satrapi, narrates a Bildungsroman showing her growth and development in Iran, as well as a memoir, showing the historical events in Iran. She discusses historical events like the Islamic revolution in 1979, which made it compulsory for the Iranian females to wear veils. Satrapi’s life story is mainly set in Iran, where she shows readers the strict, controlling and oppressive government the Iranians live under as well as the importance of clothing and bodyRead MoreMarjane Satrapi s Persepolis 1728 Words   |  7 PagesMarjane Satrapi deliberately uses an interesting layout usually used in successful comic books that convey deep m essages. The layout of the graphics in Persepolis include elements such as panels, gutters, and graphic weight. The panels, or distinct segments of a comic containing a combination of images and texts, provide transitions that are instantaneous and direct. For example, on page seven, Satrapi uses a panel to show an innocent conversation with her grandmother about the rules she will assignRead MoreMarjane Satrapi s Story Of The Complete Persepolis Essay1022 Words   |  5 Pagesunfriendly world. This is not a fictitious story. This is an actual event that happened to the author of The Complete Persepolis. Marjane Satrapi, the author of The Complete Persepolis, grew up during the 1979 Revolution. This event changed many people’s lives, either it was for the better or worse is hard to say. Nevertheless, it influenced Satrapi s whole life. In the book, Satrapi expresses her childhood memories through her eyes as a child. Her experiences and ancestry can be clearly shown througho utRead MoreHistorical Context Of Persepolis By Marjane Satrapi s Persepolis 761 Words   |  4 PagesShayauna Harris Ms. Cwiak IB World Literature I 3 November 2014 Part I: Historical Context Persepolis was written by Marjane Satrapi and was published in 2004. Marjane wrote this book to tell the life that she was living and the difficulties she faced. Persepolis takes place at the same time as the Islamic Revolution. The Islamic Revolution is seen to be one of the most important events to take place in Iranian history. This is significant to know while reading the book because it shows how theRead MoreAnalysis Of Marjane Satrapi s Persepolis 1425 Words   |  6 Pagesto childhood. Political socialization, the process by which an individual attains their political attitudes and values, argues that a number of agents, primarily family influences ideological development (Burnham). In Marjane Satrapi’s graphic autobiographical novel Persepolis, Satrapi affirms the notions of political socialization, specifically the importance of family as the primary agent of socialization, through her depiction of growing up during the Islamic Revolution and the infancy of the Isl amicRead MoreAnalysis Of Marjane Satrapi s Persepolis1264 Words   |  6 Pagessociety, ideas of violent loss and laying down your life for your country seem distant, an army’s world. During the Iranian revolution, loss and suffering were weaved into the fabric of their lives. To know Iran was to know war. In Marjane Satrapi’s graphic novel Persepolis, she argues that Marji’s developing views on death and martyrdom serve to personalize our perspective on war. From the beginning of her story, Marji is suspended in limbo between two clashing ideological worlds. She is educated

The Regulation and Management of Nuclear Safety Free Essays

The study looks at the safe management of radioactive materials. As demand for products and services using radioactive material is growing, there is an increasing demand for appropriate guidelines to manage nuclear installations safety. In particular, there are two competing strategies for managing nuclear plants and radioactive materials: Defence in Depth and Probabilistic Safety Analysis (PSA), which are deterministic and probabilistic in nature respectively. We will write a custom essay sample on The Regulation and Management of Nuclear Safety or any similar topic only for you Order Now There has been considerable debate concerning which is the best approach, leading to a need to address the negatives and positives of each in an academic study. This need informs this study, which considers the nature of each in risk assessment, prevention of nuclear incidents, and response to events. The study therefore presents a review of relevant recent literature on the topic. The study considers each approach in detail, looking first at the deterministic approach, which aims to address damage limitation at each of the potential stages involved in nuclear incidents. As an approach it uses expected deviations from normal operations. It has been improved over the years and currently allows realistic modelling of nuclear processes and events, and is currently an important way to assess potential problems and address them if they occur.Similarly, PSA is widely used around the world today, but offers a wider assessment of risk and also allows for operational events to be interpreted more accurately, leading to better perception of risk, and more ability to rank risks according to the likelihood they will occur. However, the study also shows that current regulations regarding nuclear safety, particularly the PSA are inadequate. Both approaches rely upon the assumption of normal conditions, which introduces uncertainty in quantification and hence in calculations.A possible approach to minimise the inherent problems of each approach is offered. Project Details: Order Number: 4180 Title: The Regulation and Management of Nuclear Safety Project Type: Essay. Academic Level: Masters. Work done so far: 2,000 Words Purchase Details: The abstract you just read is for a pre-written project. These projects are plagiarism free and of a 2.1. (B) quality. Click here for more information on our pre-written essays and dissertations for sale. These projects were written to match a client’s specific requirements, and may need to be tweaked to match yours. If you’re interested in one of these titles, kindly contact us, so we may send you a sample. Kindly include the name of the essay and order number in your email. Once you have paid, it would be taken off this page and never re-sold. You would also be sent a plagiarism report. Click here to Buy this Essay How to cite The Regulation and Management of Nuclear Safety, Essay examples The regulation and management of nuclear safety Free Essays Abstract Deterministic and Probabilistic safety assessments are both important aspects of the ‘Defense in depth’ strategy that is globally adopted today. Advancements in computational capacities, along with development of superior algorithms and code development for probabilistic safety assessments have significantly improved our risk assessment, preparedness, and event response. Innovative approaches such as 2 Phase Monte Carlo simulations and the use of second order probabilities and nested iterations produce better mixed aleatory and epistemic uncertainty quantifications. We will write a custom essay sample on The regulation and management of nuclear safety or any similar topic only for you Order Now Introduction Radioactive materials are in wide use. The applications for radioactive material are growing, especially in scientific domains such as medical diagnosis and treatment, industrial research, and power generation. However, safety continues to be a major concern due to the scale of damage that could be caused by radioactive contamination or an uncontrolled nuclear reaction. The Nuclear Energy Agency (NEA) continuously strives to update guidelines pertaining to the safety regulations of nuclear installations and their operations. Though ‘Defense in depth’ has been the main strategy adopted by all nuclear countries over the last couple of decades, there has been considerable trend in the inclusion of ‘Probabilistic Safety Analysis’ (PSA) as part of the regulatory requirements in nuclear plants (NEA 2007). Today, in most countries, deterministic designs and probabilistic assessments have become key components in achieving compliance with international nuclear safety regulations. With the phenomenal growth in modern computational capabilities, the PSA has also evolved significantly and is providing nuclear scientists better evolutional tools and capabilities for risk metrics. With PSA being a part of the periodic safety reviews it is useful in identifying design and operational improvements that could translate to lowered risks. Decoupling of uncertainty and containment of damage are important safety goals in nuclear installations. This paper will focus on deterministic and probabilistic safety analysis and will discuss the role played by these techniques in better risk assessment disaster prevention and better preparedness, event response, and damage control in the event of an incident that is beyond the design basis safety. In particular events such as ‘Station blackout (SBO), ‘Hydraulic study, Flood modeling and Correlation hazards would be discussed using examples. The Deterministic Approach Deterministic safety analysis includes the ‘defense in depth’ and ‘Leak tight barriers’ approach that ensure successive stages of preventive measures to limit the damage due to possible equipment failures and human errors. Deterministic safety analysis provides for expected operational deviations, ‘Design Basis Accidents’ (DBAs), and those that are ‘Beyond Design Basis Accidents’ (BDBAs) (IAEA 2009). Over the years, the improvements in computational capacities have improved deterministic safety analysis from purely conservative estimates of anticipated operational deviations towards more realistic modeling of complicated nuclear processes and thermal hydraulic events. For instance, ‘Two phase flow’ models that are currently gaining popularity are beginning to provide a more accurate modeling of thermal hydraulic events in the water piping systems connected to the nuclear reactors. This allows nuclear scientists to achi eve a more realistic uncertainty evaluation. With the best estimate approach, it is currently possible to obtain more accurate simulations of operational occurrences – for instance such an approach would be highly effective in the evaluation of ‘Loss of coolant accidents’ (IAEA 2009). Performing a best estimate analysis involves the use of best estimate codes with realistic data along with an evaluation of uncertainties pertaining to both the models used and the data input. This approach contributes in identifying the safety parameters that are most relevant to the plant functioning. Deterministic safety analysis, also known as ‘accident analysis’ is one of the important tools in assessing and fixing problems. Periodic analysis is essential to ensure the safety of the nuclear systems. It is possible that design based safety may sometimes be overridden during the operational stages of the reactor. One of the well known examples of how design based safety was made invalid was the Fermi-1 reactor incident of 1966. In this case, an unexpected and inexplicable sub-assembly fuel blockage scenario resulted in fuel melting and triggering of radiation alarms, which was contained within the reactor. Luckily the control systems that were in place worked perfectly to limit any further damage. Incident analysis later revealed that Design Basis Safety was over ridden by a late stage addition of 6 Zircaloy plates that were used to direct NA coolant flow. It turned out that one of these Zircaloy plates got detached from the section liners and obstructed the fuel ass emblies. Since these plates were not in the original design basis, they escaped quality control pertaining to the design. However, from the point of deterministic safety analysis, this incident provided valued input to design specifications, with future fuel assemblies incorporating multiple fuel inlets to avoid possible complete blockage and fuel starvation as was the case in Fermi-1 (Ragheb 2010). Probabilistic Safety Analysis The Probabilistic Safety Assessments (PSA) also referred to as the ‘Probabilistic Risk Assessment’ (PRA), is currently part of the regulatory safety assessment of nuclear plants in most countries. The PSA provides plant mangers with a more comprehensive risk assessment and better interpretation of operational events. The PSA enables plant operators achieve broader risk perception and better prioritization of these risks based on their probabilistic values. It provides for better sensitivity testing and provision of a broader range of counter measures to these probabilistic events. In a nut shell, the PSA enables plant managers to operate with better knowledge and anticipation by providing a ‘risk informed- integrated decision making process’ (NEA, 2007). PSA results could be used as a complement to deterministic analysis to improve the overall safety of the nuclear plant. One of the earliest applications of probabilistic models that was used in the UK was in the design of ‘Advanced Gas-Cooled reactors.’ The Hartlepool and Heysham 1 reactors were among the first to incorporate probabilistic analysis alongside deterministic safety evaluation in the UK. Today, the PSA is mandatory in the UK for all nuclear plants and a PSA review is conducted periodically for all plants to make sure that plant designs are in conformance with the safety standards that ensure the risk to staff and public are ‘as low as reasonably practicable’ (ALARP) (NEA 2007). The inadequacy of the current regulations with regards to safety review and in particular the PSAs was bought to the fore by the Fukushima disaster. The Fukushima nuclear plant in Japan is a well known case in point of the failure of a proper PSA assessment of external correlated hazards. This type of PSA assessment is done by applying statistical correlation to the related data pertaining to the site’s external conditions. The extensive incident report of the Fukushima disaster concluded that the current regulatory requirements in many aspects, including flooding studies and flood modeling simulations and station blackout requirements, need to be reviewed and improved. In the Fukushima case, the prolonged station blackout, instrumentation failure, and the consequent core meltdown provided many useful conclusions. In particular, the boiling water reactors at the site suffered from design failures. Moreover, during a power outage, the operators could not vent out the hydrogen g as accumulation which eventually caused the explosions. Therefore, the probability of hydrogen accumulation and explosion during a station blackout event assumes greater significance for future PSA studies. Furthermore, the Fukushima incident also highlight that the interactions between multiple units were left out of the PSA purview. Future PSA assessments should also consider several correlated hazards such as ‘mechanical overload’, ‘submergence’, ‘powerful winds’, ‘seismic hazard’ and the potential combined effect of these (Lyubarskiy et.al 2012). Level 1 PSA (Monte Carlo simulations) Both deterministic and probabilistic analyses are based on our current knowledge of the behavior of processes and their parameters under normal conditions. However, this introduces epistemic uncertainty. The following figures illustrate these uncertainties. Fig: Curves showing Continuous epistemic distribution (Rao et.al, 2008) The standard practice for the calculation of epistemic uncertainties is the use of Monte Carlo Simulations. Also, to identify aleatory uncertainties, several models such as ‘Reliability Block Diagram’(RBD), ‘Fault Tree Analysis’ (FTA), and ‘Event tree analysis’ are used. The problem with using FTA to simulate reliability and availability of engineering systems is that it ignores variables pertaining to ‘time to repair/failure’ resulting in aleatory uncertainties. To overcome these defects and to reduce the uncertainty component in the risk assessment, some improvements are suggested. One of them is the use of 2 point Monte Carlo Simulations that sample both epistemic and aleatory variables (Rao et.al, 2008). A better approximation of uncertainties is possible by separating the aleatory uncertainties from the epistemic uncertainties. The following figure illustrates a 2 phase Monte Carlo simulation with the epistemic and the aleato ry variables (Rao et.al, 2008). A model that provides better uncertainty quantification for events that involve both aleatory and epistemic uncertainties is to perform second order probability analysis. This involves individual treatment of both aleatory and epistemic variables followed by nested iterations (Eldred 2009). Level 2 PSA (ASTEC) One of the important aspects of defense- in depth strategy is to consider the possibility of ‘Severe Accidents’ (SA). These accidents are outside the design basis accidents and usually have a powerful impact on the environment. Analyzing these SAs necessitates comprehensive knowledge of critical processes, such as the ‘containment system,’ ‘core melting,’ ‘core concrete interaction,’ ‘fuel flow mechanics,’ etc. Very often the results of the analysis would be affected by many factors such as, computer code related uncertainties, data uncertainties and plant-based uncertainties, and last but not the least is the user expertise. One of the well known simulation codes that is also approved by the ARPNET is the ASTEC. Primarily used for level 2 PSA, the ASTEC provides a comprehensive simulation of the complete phenomenology of nuclear accidents. This provides researchers with detailed stage specific simulations in any part of the reactor. Several models including the Core degradation model and fuel and aerosol hydraulics model that are part of the ASTEC PSA code provide for a through investigation of the incident (IRSN 2012). The following figure illustrates this (IRSN, 2012). The simulations can also illustrate core meltdown and corium formation, hydraulics of aerosols, etc (IRSN, 2012). While the ASTEC code is widely recognized and approved as an industry standard for PSA simulations, there are still problems that are reactor specific. For instance, the SOPHAEROS simulation (an ASTEC module) that is used to understand the transfer of fission products inside the reactor produces deviations in CANDU type reactors. This is ascribed to the differences in model geometry as used in SOPHAEROS compared with CANDU reactors. The following graph illustrates the differences in deposits of Cs, Sr and I with respect to the feeder radius (APOSTOL et.al, 2011). The following table illustrates the differences in results obtained using Taylor expansion (M1) and the direct SOPHAEROS code based calculation (APOSTOL et.al 2011). This difference is due to the use of average feeder dimensions in the SOPHAEROS code. This aberration could be corrected by creating a structure with Md diameters and Ml lengths (Apostol 2011). Fault Tree Analysis Fault tree analysis is the simple logical method to identify the relationship between the various component parts and how it affects the overall functioning of a system. Fault tree analysis is important tool for the probabilistic models used in the study of nuclear plant safety. The following illustration shows a fault tree Fig: Fault Tree: Injection Failure (Manely, 2003) Though fault trees are very effective in probabilistic risk assessment, they may become difficult for human analysis purpose, particularly, if the fault trees are large and there are so many logical levels between the ‘Top event’ and the lower initiating events (Woody 2011). Conclusion Nuclear power is one of the primary energy sources for many countries. The fast depleting carbon-based energy sources and their costly global warming foot prints have increased the shift towards Nuclear energy. However, issues about safety of design and operations of nuclear plants causes significant concerns among the public. Particularly, the history of nuclear accidents such as the ‘Three Mile Island’, ‘Chernobyl disaster’ and the more recent Fukushima incident have prompted for more stringent regulatory requirements and safety testing procedures. The Fermie-1 incident clearly indicates how ‘design based safety’ scrutiny could be inadvertently circumvented resulting in serious problems. Deterministic and Probabilistic safety assessments are both important aspects of the ‘Defense in depth’ strategy that is globally adopted today. Advancements in computational capacities, along with development of superior algorithms and code development for probabilistic safety assessments have significantly improved our risk assessment, preparedness and event response. Fault trees and event tree analysis and the use of state of the art software simulations (ASTEC) provide better security review and valid input for future plant designs or alterations to current plant designs. Innovative approaches, such as 2 Phase Monte Carlo simulations, and newer methods, such as applying second order probabilities and nested iterations, produce better mixed aleatory and epistemic uncertainty quantifications. The increasing complexit y of current model in itself contributes to model uncertainty, as was discussed in the case of the SOPHAEROS module. However, by applying innovative solutions (Taylor expansion, in this case) these inadequacies between models could be resolved. Bibliography Dan Manely, (2003), Nuclear Safety and Reliability, viewed Nov 13th 2012, IAEA, (2009), Deterministic Safety Analysis for Nuclear Power Plants, Safety Guide. K. Durga Rao, H.S. Kushwahaa, A.K. Vermab A. Srividya (2008), Quantification of epistemic and aleatory uncertainties in level-1 probabilistic safety assessment studies, Indian Institute of Technology, Mumbai. Lyubarskiy, A, Kuzmina I, El-Shanawany M, (2012). Potential Areas for Enhancement of the PSA Methodology based on Lessons Learned from the Fukushima Accident, IAEA. M Ragheb PhD, (2010), The Fermi-1 Fuel meltdown incident, viewed Nov 12th 2012, https://netfiles.uiuc.edu/mragheb/www/NPRE%20457%20CSE%20462%20Safety%20Analysis%20of%20Nuclear%20Reactor%20Systems/ Michael S. Eldred, Laura P. Swiler, (2009), Efficient Algorithms for Mixed Aleatory-Epistemic Uncertainty Quantification with Application to Radiation-Hardened Electronics Part I: Algorithms and Benchmark Results, Sandia Report. NEA, 2007, Use and development of probabilistic safety assessment, Published by OECD, viewed Nov 13th 2012, www.oecd-nea.org/nsd/docs/2007/csni-r2007-12.pdf IRSN, (2012), Enhancing Nuclear Safety: The AZTEC software package, viewed Nov13th 2012, Minodora APOSTOL, Aureliu LECA, Marin CONSTANTIN Ilie PRISECARU (2011), Dealing with uncertainties in Nuclear Safety Analysis (Part 11), U.P.B. Sci. Bull., Series C, Vol. 73, Iss. 4. Woody Epstein, (2011), What’s wrong with Fault tree linking approach for complex PRA modelsviewed Nov 13th 2012, woody.com/papers/whats-wrong-with-the-fault-tree/ How to cite The regulation and management of nuclear safety, Essay examples