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Journal articles on the topic 'Nuclear industry Risk assessment'

Author: Grafiati

Published: 4 June 2021

Last updated: 5 February 2022

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1

Thomson, J. R. "Quantified risk assessment - a nuclear industry viewpoint." Journal of Loss Prevention in the Process Industries 7, no. 5 (1994): 419–24. http://dx.doi.org/10.1016/0950-4230(94)80060-x.

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2

Davies, L. P. "Risk assessment in the UK nuclear power industry." Safety Science 40, no. 1-4 (2002): 203–30. http://dx.doi.org/10.1016/s0925-7535(01)00037-6.

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3

Guo, Lin, Ash Genaidy, Doran Christensen, and Kevin Huntington. "Macro-ergonomic risk assessment in nuclear remediation industry." Applied Ergonomics 27, no. 4 (1996): 241–54. http://dx.doi.org/10.1016/0003-6870(96)00010-5.

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4

Zamanali, J. "Probabilistic-risk-assessment applications in the nuclear-power industry." IEEE Transactions on Reliability 47, no. 3 (1998): SP361—SP364. http://dx.doi.org/10.1109/24.740552.

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5

Apostolakis, G. E., J. H. Bickel, and S. Kaplan. "Probabilistic risk assessment in the nuclear power utility industry." Reliability Engineering & System Safety 24, no. 2 (1989): 91–94. http://dx.doi.org/10.1016/0951-8320(89)90086-0.

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6

Isaeva, N. A., A. P. Bobrov, V. I. Sedin, and V. Yu Scheblanov. "Assessment criteria of individual occupational risks in nuclear industry employees." Medicо-Biological and Socio-Psychological Problems of Safety in Emergency Situations, no. 2 (June 22, 2019): 46–52. http://dx.doi.org/10.25016/2541-7487-2019-0-2-46-52.

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Relevance. In the concept of long-term development of social and economic policy of the Russian Federation, the problem of preservation and strengthening of employees’ health is given a top priority and requires improvement of the citizen health protection. Risk assessment and, in particular, occupational risk assessment is part of the process that includes probability analysis of dangerous events for employees’ health and decision-making about the necessity of risk reduction. The principles of prevention and constant improvement of the assessment system and occupational risk management in acc

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7

Hayns, M. R. "The Evolution of Probabilistic Risk Assessment in the Nuclear Industry." Process Safety and Environmental Protection 77, no. 3 (1999): 117–42. http://dx.doi.org/10.1205/095758299529947.

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8

Wu, J. S., and G. E. Apostolakis. "Experience with probabilistic risk assessment in the nuclear power industry." Journal of Hazardous Materials 29, no. 3 (1992): 313–45. http://dx.doi.org/10.1016/0304-3894(92)85040-8.

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9

Borysiewicz, Mieczysław Józef, Karol Kowal, Piotr Prusiński, and Marcin Dąbrowski. "AN INTEGRATED RISK INFORMED DECISION MAKING IN THE NUCLEAR INDUSTRY." Informatyka, Automatyka, Pomiary w Gospodarce i Ochronie Środowiska 3, no. 2 (2013): 22–34. http://dx.doi.org/10.35784/iapgos.1448.

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The regulatory body, established to ensure safety of nuclear facilities, is expected to make right decisions and provide appropriate regulations for the nuclear industry. The traditional manner of its activity has been based on a deterministic approach to safety analyses. However, increased maturity of Probabilistic Safety Assessment (PSA) makes it complementary to deterministic studies. The new IAEA concept, described in this article, is to apply an integrated approach by combining both deterministic and probabilistic insights with other requirements affecting the decision making process.

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10

Worrell, Clarence, and Christopher Rochon. "Fire Probabilistic Risk Assessment and its Applications in the Nuclear Power Industry." Fire Technology 52, no. 2 (2015): 443–67. http://dx.doi.org/10.1007/s10694-015-0493-y.

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11

Shalabi, Hossam, and George Hadjisophocleous. "CANDU FIRE PROBABILISTIC RISK ASSESSMENT (PRA) MODEL." CNL Nuclear Review 8, no. 2 (2019): 97–108. http://dx.doi.org/10.12943/cnr.2017.00020.

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Fire Probabilistic Risk Assessment (PRA) is being introduced to the fire protection engineering practice both locally and worldwide. The commercial nuclear power industry has also experiencing the impact of this new approach. This paper examines the work performed to assess the relative accuracy of fire models for CANDU nuclear power plant (NPP) applications. The Canadian NPP uses some portions of NUREG/CR-6850 in performing fire PRA. Canadian fire ignition frequencies have been provided by International Fire Data Exchange Project. The CANDU Fire PRA Model can quantitatively evaluate plant dam

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12

Bobrov, Aleksandr F., N. A. Isaeva, M. Yu Kalinina, V. Yu Sedin, V. Yu Shcheblanov, and E. S. Shchelkanova. "EVALUATION OF OCCUPATIONAL RISKS OF EMPLOYEES OF THE NUCLEAR INDUSTRY, ACCORDING TO A PERIODIC MEDICAL EXAMINATION AND MANDATORY PSYCHO-PHYSIOLOGICAL EXAMINATIONS." Hygiene and sanitation 96, no. 9 (2019): 892–96. http://dx.doi.org/10.18821/0016-9900-2017-96-9-892-896.

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The article is devoted to the assessment of occupational risks of employees of the nuclear industry. A literature review on currently used indices of occupational risks and working conditions on high-tech enterprises of the nuclear industry has shown that because of ther lack of occupational diseases related to exposure to ionizing radiation, and low level of industrial injuries, these indices are not appropriate for the inclusion in the evaluation of the individual professional risk. Classes of working conditions according to hazards and risk group health of the worker, work-related diseases

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13

Izhevskij, P. V. "Assessment of Radiation Risk in the Families of Reactor Industry Workers." Atomic Energy 114, no. 1 (2013): 65–68. http://dx.doi.org/10.1007/s10512-013-9672-4.

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14

REINHOLD, KARIN, PIIA TINT, and GUNNAR KIIVET. "RISK ASSESSMENT IN TEXTILE AND WOOD, PROCESSING INDUSTRY." International Journal of Reliability, Quality and Safety Engineering 13, no. 02 (2006): 115–25. http://dx.doi.org/10.1142/s021853930600215x.

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The working conditions in textile and wood processing industries have been investigated using a simple risk assessment method and questionnaires worked out for the purpose. A simple/flexible risk assessment method (beginning with a two-stage model that could be enlarged into a six-stage model) is worked out by the authors (Tint & Kiivet) and the implementation possibilities are presented. It is necessary to increase interest from the side of employers for using the method and analyzing the work environment with the aim of improvement implementations. The main complaints in textile industry

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15

Dewi, Dharu, Imam Bastori, Arief Tris Yuliyanto, Karina Stankevica, and Arnold Soetrisnanto. "Manufacturing Risk Identification in the Steel Industry." E3S Web of Conferences 190 (2020): 00006. http://dx.doi.org/10.1051/e3sconf/202019000006.

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The steel manufacturing industry is an inseparable part of the nuclear power plant construction project. This industry is a business full of dynamics, risks, and challenges. The implementation of risk management becomes an obligation that must be executed in managing this very complex project. In general, risk management in manufacturing includes steps to understand and identify potential problems that may occur, evaluate, monitor, and handle risks. The main risk management objectives are to prevent or minimize adverse effects due to unforeseen events through risk aversion or preparation of co

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16

Cameron, R. F., and A. Willers. "Use of risk assessment in the nuclear industry with specific reference to the Australian situation." Reliability Engineering & System Safety 74, no. 3 (2001): 275–82. http://dx.doi.org/10.1016/s0951-8320(01)00078-3.

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17

Shafiqul, Islam Md, and Tanvir Hassan Bhuiyan. "Assessment of costs of nuclear power in Bangladesh." Nuclear Energy and Technology 6, no. 3 (2020): 181–94. http://dx.doi.org/10.3897/nucet.6.54003.

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Financing and economic risks are two of the major challenges facing by the nuclear industry today for the construction of a new build Gen III+ or an advanced Gen IV nuclear power plant (NPP). Prediction of economics and financial aspects of an NPP always remains uncertain as these are heavily dependent on investment costs, construction time, licensing and regulation, operation and maintenance (O&amp;M) costs, fuel costs, financing costs, plant capacity factor (PCF), etc. Such uncertainty in accurately predicting the risk of financing and economics limits the growth of the nuclear industry.

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18

Tudoran, Cristian. "New trends in training nuclear power plant employees: probabilistic safety analysis." Proceedings of the International Conference on Business Excellence 12, no. 1 (2018): 983–91. http://dx.doi.org/10.2478/picbe-2018-0088.

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Abstract In the last four decades, as the nuclear industry grew and got mature, the importance of adequate risk evaluating tools became decisive. Therefore, the Probabilistic Risk Assessment (also known as Probabilistic Safety Analysis) became a cornerstone of the decisions in such high energy and high-risk industry. PSA has an internationally recognised standard, and it is supported by a group of highly trained experts, (no more than a few hundred worldwide).This work can be used as a guide for the improving the required individual and teamwork skills needed in a Probabilistic Safety Analysis

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19

Dubord, Renée M., Michael W. Golay, and Norman C. Rasmussen. "A Probabilistic Risk Assessment–Related Methodology to Support Performance-Based Regulation Within the Nuclear Power Industry." Nuclear Technology 114, no. 2 (1996): 169–78. http://dx.doi.org/10.13182/nt96-a35247.

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20

Mukhopadhyay, Sayanti, Jessica Halligan, and Makarand Hastak. "Assessment of major causes: nuclear power plant disasters since 1950." International Journal of Disaster Resilience in the Built Environment 7, no. 5 (2016): 521–43. http://dx.doi.org/10.1108/ijdrbe-11-2015-0056.

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Purpose This paper aims to investigate the major causes of the nuclear power plant (NPP) disasters since 1950, elucidates the commonalities between them and recommends strategies to minimize the risk of NPP disasters. Design/methodology/approach This paper analyzes facts from five case studies: Chernobyl disaster, USSR 1986; Fukushima Daiichi disaster, Japan 2011; Three Mile Island incident, USA 1979; Chalk River Accident, Canada 1952; and SL-1 Accident, USA 1961. A qualitative approach is adopted to compare and contrast the major reasons that led to the accidents, and consequent social and te

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21

Akarsu, E., D. J. Hamilton, and D. C. Tyler. "NORM IN THE OIL AND GAS INDUSTRY— EXPOSURE ASSESSMENT AND MANAGEMENT PLAN." APPEA Journal 41, no. 1 (2001): 737. http://dx.doi.org/10.1071/aj00043.

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Naturally Occurring Radioactive Material (NORM) is an inevitable by-product of petroleum exploration and production. It is produced with the reservoir fluids and is typically found in low concentrations, but potentially high volumes. However, Victorian regulations that cover NORM are based on acceptable public exposure to ionising radiation and appear to be formulated around high concentration, low volume sources such as those found in medical procedures.Esso Australia Pty Ltd conducted a comprehensive exposure assessment study to establish limits for NORM. The two-year study was carried out i

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22

Nadesan, Majia Holmer. "Nuclear governmentality: Governing nuclear security and radiation risk in post-Fukushima Japan." Security Dialogue 50, no. 6 (2019): 512–30. http://dx.doi.org/10.1177/0967010619868442.

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Nuclear governmentality is offered as a conceptual contribution to research on energy politics, security studies, and nuclearity. Nuclear governmentality is conceived as a logic of government in the Foucauldian sense, that describes contiguities in conduct and symbolic representations found across disparate dispositifs, especially (albeit not exclusively) those strategically aimed at eliciting and exploiting atomic forces in medicine, industry, and war. This project demonstrates the logic and technologies of power specific to nuclear governmentality in post-Fukushima Daiichi energy commitments

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23

Begun, V. V., and S. Yu Potetiuiev. "New method for fire risk assessment." Mathematical machines and systems 4 (2020): 125–35. http://dx.doi.org/10.34121/1028-9763-2020-4-125-135.

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Ukraine is at the last places at the international ratings concerning safety of life. It is related first of all to the fields of technogenic safety and fire safety. The values of annual losses due to fires, accidents and due to other emergency situations reach billions of hryvna, which is the essential part of the national budget and they have the increasing trends. Such situation is common for almost all branches of the industry of Ukraine except for the nuclear energy of Ukraine, which is under the additional guidance and under the additional control of the international organizations. The

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24

Petitot, Fabrice, Stéphanie Fages, Olivier Blanck, Sandrine Frelon, and François Paquet. "Percutaneous diffusion of uranium: What is the best experimental model for occupational risk assessment in the nuclear industry?" Toxicology Letters 172 (October 2007): S107. http://dx.doi.org/10.1016/j.toxlet.2007.05.288.

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25

Hammond, G. P., and R. Waldron. "Risk assessment of UK electricity supply in a rapidly evolving energy sector." Proceedings of the Institution of Mechanical Engineers, Part A: Journal of Power and Energy 222, no. 7 (2008): 623–42. http://dx.doi.org/10.1243/09576509jpe543.

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A range of major risks associated with a rapidly changing United Kingdom (UK) electricity sector have been identified and quantified with the aid of various stakeholder groups (academic researchers, civil servants, electricity companies, ‘green’ groups, power system engineers, and various others), who completed an online internet questionnaire. Each stakeholder ranked potential risks according to the perceived ‘severity of impact’ and ‘likelihood of occurrence’ using a three-point scale. The data were then used to perform a ranking of the risks by multiplying scores for impact and occurrence.

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26

Charvet, Cyril, Jean-Luc Chambon, François Corenwinder, and Jérôme Taveau. "Learning from the application of nuclear probabilistic safety assessment to the chemical industry." Journal of Loss Prevention in the Process Industries 24, no. 3 (2011): 242–48. http://dx.doi.org/10.1016/j.jlp.2010.09.007.

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27

Musauddin, Ashraf, and Juyoul Kim. "TRANSBOUNDARY RADIOLOGICAL EFFECTS OF A HYPOTHETICAL NUCLEAR ACCIDENT IN NORTHEAST ASIA." Radiation Protection Dosimetry 188, no. 4 (2020): 470–76. http://dx.doi.org/10.1093/rpd/ncz306.

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Abstract Offsite radiological consequence investigation using computerized software has been considered as an important quantitative risk communication in order to recognize and discuss public concerns about nuclear safety and health risk in case of hypothetical nuclear accidents around specific nuclear power plants (NPPs), with guideline of lessons learned from previous nuclear disasters. In this study, Northeast Asia nuclear accident simulator (NANAS) developed by Nuclear Safety and Security Commission (NSSC) in Korea was used to quantify the offsite radiological consequences from Haiyang un

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28

Kuzmanović, Predrag, Nataša Todorović, Jovana Nikolov, et al. "Assessment of radiation risk and radon exhalation rate for granite used in the construction industry." Journal of Radioanalytical and Nuclear Chemistry 321, no. 2 (2019): 565–77. http://dx.doi.org/10.1007/s10967-019-06592-9.

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29

Darolles, Carine, François Paquet, Philippe Voisin, and Fabrice Petitot. "Discrimination of radiotoxic and chemotoxic effects of uranium: Definition of biological markers for occupational risk assessment in the nuclear industry." Toxicology Letters 172 (October 2007): S166. http://dx.doi.org/10.1016/j.toxlet.2007.05.426.

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30

Шафранский, И., I. Shafransky, А. Туков, et al. "Estimation of the Excess Relative Risk of Malignant Neoplasms among Workers of the Nuclear Industry – Participants of the Accident Liquidation at the Chernobyl NPP." Medical Radiology and radiation safety 63, no. 6 (2018): 35–40. http://dx.doi.org/10.12737/article_5c0b8a6f16bcf5.47924988.

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Purpose: To assess the excess relative risk in terms of 1 Sv on the basis of materials on the incidence of malignant neoplasms of workers in the nuclear industry – liquidators of the Chernobyl accident, as well as part of workers who worked or continue to work with sources of ionizing radiation. Material and methods: The data base of the Industry Register of persons exposed to radiation as a result of the Chernobyl accident (ORF) was used in the work. Methods of cohort analysis of the accumulated disease incidence were used, based on Poisson regression and Cox regression. Estimates of the ERR

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31

DeGaspari, John. "Risky Business." Mechanical Engineering 124, no. 07 (2002): 42–44. http://dx.doi.org/10.1115/1.2002-jul-3.

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This article reviews risk analysis in process engineering. Process plants must be inspected and maintained more diligently as they age. Risk analysis methods, along with post-construction standards currently being developed, are evolving tools aimed at helping companies maintain plants better and save money. Risk analysis is routinely used in the nuclear power industry to identify areas of a plant that have the highest likelihood of failure and pose the most serious consequences. Post-construction standards, a current project of ASME, are focused on mechanical integrity, and will provide guide

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32

Ainsworth, R. A., M. B. Ruggles, and Y. Takahashi. "Flaw Assessment Procedure for High-Temperature Reactor Components." Journal of Pressure Vessel Technology 114, no. 2 (1992): 166–70. http://dx.doi.org/10.1115/1.2929024.

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An interim high-temperature flaw assessment procedure is described. This is a result of a collaborative effort between Electric Power Research Institute in the US, Central Research Institute of Electric Power Industry in Japan, and Nuclear Electric plc in the UK. The procedure addresses pre-existing defects subject to creep-fatigue loading conditions. Laws employed to calculate the crack growth per cycle are defined in terms of fracture mechanics parameters and constants related to the component material. The crack growth laws may be integrated to calculate the remaining life of a component or

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33

Gallucci, Raymond HV. "Risk-Deformed Regulation: What Went Wrong with NFPA 805." Civil Engineering Journal 4, no. 12 (2018): 2876. http://dx.doi.org/10.28991/cej-03091205.

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National Fire Protection Association (NFPA) Standard 805 was incorporated into Title 10 of the U.S. Code of Federal Regulations to allow commercial nuclear plants to transition their existing, deterministic fire protection licensing bases to ones that are “performance-based and risk-informed.” Both the US Nuclear Regulatory Commission (NRC) and the commercial reactor industry championed this major leap forward in “risk-informed regulation.” However, hidden behind all the “success” are compromises and manipulations that were necessary to make this “work,” as revealed in this article. It is writ

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34

Kalinkin, D., T. Takhauova, A. Karpov, et al. "Factors Influencing the Health Condition of the Adult Population Residing in the Activity Area of Atomic Industry Enterprise." Medical Radiology and radiation safety 65, no. 4 (2020): 5–11. http://dx.doi.org/10.12737/1024-6177-2020-65-4-5-11.

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Purpose: Development of the basic directions of a modern strategy for protecting the health of the adult population living in the activity zone of nuclear industry enterprises (using the example of the Seversk population). Material and methods: The object of the study was the population of the city of Seversk, formed around the Siberian Group of Chemical Enterprises. The subject of the study was demographic indicators; disability; incidence of malignant neoplasms, diseases of the circulatory system, injuries and accidents); socio-economic, behavioral and technological risk factors affect

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Shim, Do-Jun, Jae-Boong Choi, and Young-Jin Kim. "Failure Strength Assessment of Pipes With Local Wall Thinning Under Combined Loading Based on Finite Element Analyses." Journal of Pressure Vessel Technology 126, no. 2 (2004): 179–83. http://dx.doi.org/10.1115/1.1687382.

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Failure assessment of a pipe with local wall thinning draws increasing attention in the nuclear power plant industry. Although many guidelines have been developed and are used for assessing the integrity of a wall-thinned pipeline, most of these guidelines consider only pressure loading and thus neglect bending loading. As most pipelines in nuclear power plants are subjected to internal pressure and bending moment, an assessment procedure for locally wall-thinned pipeline subjected to combined loading is urgently needed. In this paper, three-dimensional finite element (FE) analyses are carried

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36

Sheppard, M. I., D. E. Elrick, and S. R. Peterson. "Review and performance of four models to assess the fate of radionuclides and heavy metals in surface soil." Canadian Journal of Soil Science 77, no. 3 (1997): 333–44. http://dx.doi.org/10.4141/s96-092.

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The nuclear industry uses computer models to calculate and assess the impact of its present and future releases to the environment, both from operating reactors and from existing licensed and planned waste management facilities. We review four soil models varying in complexity that could be useful for environmental impact assessment. The goal of this comparison is to direct the combined use of these models in order to preserve simplicity, yet increase the rigor of Canadian environmental assessment calculations involving soil transport pathways. The four models chosen are: the Soil Chemical Exc

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Malak, F., R. Baydoun, K. Zahraman, D. Dimitrov, and B. Nsouli. "Review and assessment of national efforts to manage radioactive sources and enhance nuclear security measures in Lebanon." Radioprotection 56, no. 2 (2021): 161–68. http://dx.doi.org/10.1051/radiopro/2020084.

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Radioactive and nuclear materials have been used for a long time in warfare. During the 20th and 21st centuries, a large number of atmospheric and underground nuclear weapons tests were carried out, even after the Non-Proliferation of Nuclear Weapons Treaty (NPT), leading to ecologically and socially destroyed sites. The most recent ones were in North Korea and Russia. With the widespread of peaceful use of radiological and nuclear material, the threats of nuclear terrorism or malicious use of these materials have become major concern across the world. Although the issuing of the Physical Prot

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38

Rossi, Esko, and Matti Ettala. "Recovery analysis in risk management of hazardous materials." Water Science and Technology 33, no. 2 (1996): 133–41. http://dx.doi.org/10.2166/wst.1996.0043.

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Recovery analysis as an adjoint activity in risk assessment is to account for situational and technical aspects of a plant's preparedness for incident response and accident management. Recovery analysis has been well established in nuclear industry in evaluation of the means to prevent accident propagation. The aim of this study was to apply recovery analysis principles in the management of accidental water pollution events due to uncontrolled releases of hazardous materials. A checklist comprising possible means to prevent accident propagation, was worked out. The checklist included correctio

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Gallucci, Raymond HV. "Risk-Reduction Credit for Very Early Warning Fire Detection at Nuclear Power Plants: From FAQ to Fiction." Civil Engineering Journal 5, no. 2 (2019): 309. http://dx.doi.org/10.28991/cej-2019-03091246.

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In 2004, the U.S. Nuclear Regulatory Commission (NRC), with support from the commercial nuclear power industry, adopted the 2001 Edition of National Fire Protection Association (NFPA) Standard 805, “Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants,” as the means by which commercial nuclear power licensees could comply with Title 10 of the Code of Federal Regulations, Part 50.48(c), to replace deterministic fire protection licensing bases with ones that are risk-informed and performance-based. To facilitate licensee “transitions” to the new licen

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40

Keller, William, and Mohammad Modarres. "A historical overview of probabilistic risk assessment development and its use in the nuclear power industry: a tribute to the late Professor Norman Carl Rasmussen." Reliability Engineering & System Safety 89, no. 3 (2005): 271–85. http://dx.doi.org/10.1016/j.ress.2004.08.022.

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Sukhova, Aleksandra, and Elena Elizareva. "Methods for analysis of and ways to minimize energy providers’ technology and technical risks." Bulletin of scientific research results, no. 1-2 (July 17, 2017): 39–48. http://dx.doi.org/10.20295/2223-9987-2017-1-2-39-48.

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Objective: Identifying an accurate quantitative risk assessment. FEC (Fuel and Energy Complex) plants are a high-risk area as they may cause manmade disasters, various accidents, pose a threat to human life and environment. In addition, the Russian energy industry is noted for its high complexity and social responsibility. Its specific feature is that it is not always possible to make an accurate quantitative risk assessment reasonably in advance and its degree determination methods are not well enough developed. In view of the above, there are some difficulties in minimizing the risks and est

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Vukanac, Ivana, Aleksandar Kandic, Mirjana Djurasevic, et al. "Radionuclide content in laundry detergents commercially available on the Serbian market and assessment of radiological environmental hazards." Nuclear Technology and Radiation Protection 32, no. 4 (2017): 366–70. http://dx.doi.org/10.2298/ntrp1704366v.

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Laundry detergents are chemicals widely used in everyday life, and in numerous industry branches. In order to perceive the radiological aspect of environmental pollution by wastewater, the analysis of laundry detergents available on the Serbian market was undertaken. Laundry detergent samples were measured by means of gamma spectrometry and the results are presented in this paper. Analysis of the obtained activity concentrations showed that laundry detergents in Serbia mostly fulfill the international recommendation and requirements regarding the phosphate content. Besides that, the content of

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43

Nosovskyi, A. V. "The Issue Of Linear No-Threshold Hypothesis." Nuclear and Radiation Safety, no. 4(80) (December 3, 2018): 54–57. http://dx.doi.org/10.32918/nrs.2018.4(80).09.

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Some issues concerning the effect of ionizing radiation on the human body and methodological approaches to the development of radiation safety standards are considered. It is shown that the use of the linear no-threshold hypothesis (LNT hypothesis) in up-to-date radiation safety standards is inconsistent with experimental and epidemiological dose-response data, introduces essential excessive conservatism in the safety assessment process and causes additional problems concerning nuclear power engineering development. Due to the absence of convincing proofs for the existence of the dose th

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Guo, Yundong, Youchao Sun, Xiufang Yang, and Zongpeng Wang. "Flight Safety Assessment Based on a Modified Human Reliability Quantification Method." International Journal of Aerospace Engineering 2019 (October 27, 2019): 1–12. http://dx.doi.org/10.1155/2019/2812173.

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Human error is one of the most important risk factors affecting aviation safety. The original Cognitive Reliability and Error Analysis Method (CREAM) developed for the nuclear industry is reliable for human reliability quantification, but it is not fully applicable to human reliability analysis in aviation because it neglects the characteristics of long-duration flights. Here, we propose a modified CREAM method to predict human error probability in flight and provide some improvement measures for critical operations. A set of performance influencing factors (PIFs), such as flight procedures an

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45

Shugailo, O., Yu Grebenyuk, O. Zelenyі, et al. "Experience Obtained and Lessons Learnt from the Transition of Ukrainian NPPs to Long-Term Operation." Nuclear and Radiation Safety, no. 1(85) (March 13, 2020): 15–29. http://dx.doi.org/10.32918/nrs.2020.1(85).02.

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Nuclear energy is a strategic Ukrainian industry that produces more than 50% of electricity at present. Over the last decade during the operation of Ukrainian NPPs, the set of technical matters have been found and corresponding tasks shall be decided with engaging of scientific potential of the country. One of such matter is a safety justification of NPP components and structures for the period that is bigger than an initial design one and that is defined as transition from design operation to the long-term operation (LTO). From the end of 2010 to the beginning of 2020, the State Nuclear

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Vukanac, Ivana, Marija Jankovic, Milica Rajacic, et al. "Assessment of natural radioactivity levels and radon exhalation rate potential from various building materials." Nuclear Technology and Radiation Protection 35, no. 1 (2020): 64–73. http://dx.doi.org/10.2298/ntrp2001064v.

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Various imported building materials commonly used in construction and industry in Serbia were analyzed using gamma spectrometry. Based on the activity concentrations of 226Ra, 232Th, and 40K in the investigated samples, radium equivalent activity, Raeq, absorbed dose rate, D, annual effective dose, DE, and the external hazard index, Hex, were calculated to assess the radiation hazard for people. The Raeq for most of the analyzed samples (416 in total) was lower than the maximum admissible value of 370 Bqkg-1 set in the UNSCEAR report. The absorbed gamma dose rate in air was found to vary from

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Sarkisov, Ashot A., Sergey V. Antipov, Dmitry O. Smolentsev, et al. "Low-power nuclear power plants in the context of electric power systems transformation." Nuclear Energy and Technology 7, no. 1 (2021): 55–59. http://dx.doi.org/10.3897/nucet.7.65315.

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Increasing economic importance of the Arctic, further intensification of northern sea routes, and exceptional sensitivity of the arctic natural environment to anthropogenic impacts are fundamental factors for a comprehensive study of environmental aspects in the application of innovative technologies for the development of infrastructure in the Arctic. Despite the growing interest in low-power nuclear power plants as a distributed generation facility, their possible application in technologically isolated power systems does not lose relevance. The development of both the Arctic and Far Eastern

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Sudjianto, Agus, Lokesh Juneja, Hari Agrawal, and Mahesh Vora. "Computer Aided Reliability and Robustness Assessment." International Journal of Reliability, Quality and Safety Engineering 05, no. 02 (1998): 181–93. http://dx.doi.org/10.1142/s0218539398000182.

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The competitive pressure to shorten product development time has necessitated the automotive industry to rely more on Computer Aided Engineering (CAE) for analyzing and proving product reliability and robustness. The challenge of this approach is the incorporation of product variability, due to manufacturing and customer usage variations in the analysis, requires a massive computation process which may be prohibitive even with today's advanced computers. In this paper, we demonstrate the use of an efficient computational procedure based on optimal Latin Hypercube Sampling (LHS) and a "cheap-to

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Fahmy, R. A., and R. I. Gomaa. "Dynamic fault tree analysis of auxiliary feedwater system in a pressurized water reactor." Kerntechnik 86, no. 2 (2021): 164–72. http://dx.doi.org/10.1515/kern-2020-0067.

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Abstract The safe and secure designs of any nuclear power plant together with its cost-effective operation without accidents are leading the future of nuclear energy. As a result, the Reliability, Availability, Maintainability, and Safety analysis of NPP systems is the main concern for the nuclear industry. But the ability to assure that the safety-related system, structure, and components could meet the safety functions in different events to prevent the reactor core damage requires new reliability analysis methods and techniques. The Fault Tree Analysis (FTA) is one of the most widely used l

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Osipov, Aleksey M., Aleksandr V. Ryabov, and Darya V. Finoshkina. "Assessment of the Dynamic Loads Applied to the RBMK-1000 Subreactor Room Walls and Slab during Vapor Explosion." Vestnik MEI 2, no. 2 (2021): 29–36. http://dx.doi.org/10.24160/1993-6982-2021-2-29-36.

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One of the conditions for the safe operation of a nuclear power plant (NPP) unit is a comprehensive design and experimental justification of its failure-free operation in all operating modes and limitation of accident radiation consequences, including those in the case of severe beyond design basis accidents. According to the nuclear power industry development plans in Russia, new NPPs equipped with RBMK-1000 reactors are not supposed to be constructed in the future. Although the assigned service life of RBMK-1000 based power units that remain in operation is close to expiration, these power u

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