scholarly journals Analysis of the Relationship between Risk Perception and Willingness to Pay for Nuclear Power Plant Risk Reduction

2016 ◽  
Vol 2016 ◽  
pp. 1-9 ◽  
Author(s):  
Mirae Yun ◽  
Sang Hun Lee ◽  
Hyun Gook Kang
Keyword(s):  
Risk Perception ◽  
Willingness To Pay ◽  
Nuclear Power ◽  
Power Plants ◽  
New Technologies ◽  
Background Level ◽  
Modern Society ◽  
Scientific Background ◽  
Contingent Valuation Methods ◽  
The Relationship

With the adoption of new technologies, more risk is introduced into modern society. Important decisions about new technologies tend to be made by specialists, which can lead to a mismatch of risk perception between citizens and specialists, resulting in high social cost. Using contingent valuation methods, this paper analyzes the relationship between willingness to pay (WTP) and the factors expressed through people’s image of nuclear power plants (NPP), their perception of NPP safety, and how these can be affected by their scientific background level. Results indicate that groups with a high scientific background level tend to have low risk perception level, represented through their image and safety levels. Further, the results show that mean WTP is dependent on scientific background and image levels. It is believed that these results could help decision makers address the mismatch of trust between the public and specialists in terms of new policy.

Operating Reliability Assessment of FPGA-Based NPP I&C Systems: Approach, Technique and Implementation

2017 ◽  
Author(s):  
Eugene Babeshko ◽  
Ievgenii Bakhmach ◽  
Vyacheslav Kharchenko ◽  
Eugene Ruchkov ◽  
Oleksandr Siora
Keyword(s):  
Integrated Circuits ◽  
Nuclear Power ◽  
Power Plants ◽  
Failure Modes ◽  
New Technologies ◽  
Systems Approach ◽  
Reliability Assessment ◽  
Design Stage ◽  
Fpga Design ◽  
Operating Reliability

Operating reliability assessment of instrumentation and control systems (I&Cs) is always one of the most important activities, especially for critical domains like nuclear power plants (NPPs). Intensive use of relatively new technologies like field programmable gate arrays (FPGAs) in I&C which appear in upgrades and in newly built NPPs makes task to develop and validate advanced operating reliability assessment methods that consider specific technology features very topical. Increased integration densities make the reliability of integrated circuits the most crucial point in modern NPP I&Cs. Moreover, FPGAs differ in some significant ways from other integrated circuits: they are shipped as blanks and are very dependent on design configured into them. Furthermore, FPGA design could be changed during planned NPP outage for different reasons. Considering all possible failure modes of FPGA-based NPP I&C at design stage is a quite challenging task. Therefore, operating reliability assessment is one of the most preferable ways to perform comprehensive analysis of FPGA-based NPP I&Cs. This paper summarizes our experience on operating reliability analysis of FPGA based NPP I&Cs.

scholarly journals CS Measures for Nuclear Power Plant Protection: A Systematic Literature Review

Signals ◽  
2021 ◽  
Vol 2 (4) ◽  
pp. 803-819
Author(s):  
Nabin Chowdhury
Keyword(s):  
Literature Review ◽  
Systematic Literature Review ◽  
Cyber Security ◽  
Nuclear Power ◽  
Power Plants ◽  
New Technologies ◽  
Plant Protection ◽  
Security Requirements ◽  
Protection Measures ◽  
Defense In Depth

As digital instrumentation in Nuclear Power Plants (NPPs) is becoming increasingly complex, both attack vectors and defensive strategies are evolving based on new technologies and vulnerabilities. Continued efforts have been made to develop a variety of measures for the cyber defense of these infrastructures, which often consist in adapting security measures previously developed for other critical infrastructure sectors according to the requirements of NPPs. That being said, due to the very recent development of these solutions, there is a lack of agreement or standardization when it comes to their adoption at an industrial level. To better understand the state of the art in NPP Cyber-Security (CS) measures, in this work, we conduct a Systematic Literature Review (SLR) to identify scientific papers discussing CS frameworks, standards, guidelines, best practices, and any additional CS protection measures for NPPs. From our literature analysis, it was evidenced that protecting the digital space in NPPs involves three main steps: (i) identification of critical digital assets; (ii) risk assessment and threat analysis; (iii) establishment of measures for NPP protection based on the defense-in-depth model. To ensure the CS protection of these infrastructures, a holistic defense-in-depth approach is suggested in order to avoid excessive granularity and lack of compatibility between different layers of protection. Additional research is needed to ensure that such a model is developed effectively and that it is based on the interdependencies of all security requirements of NPPs.

scholarly journals THE NEED FOR INFORMATION AND THE ATTITUDE TOWARDS DIGITAL TECHNOLOGIES AS FACTORS OF CRITICAL AND UNCRITICAL DISSEMINATION OF PANDEMIC NEWS

2021 ◽  
pp. 170-195
Author(s):  
Elena I. Rasskazova ◽  
Galina V. Soldatova ◽  
Yulia Y. Neyaskina ◽  
Olga S. Shiriaeva
Keyword(s):  
Subjective Experience ◽  
New Technologies ◽  
Modern Society ◽  
Sociodemographic Factors ◽  
Subjective Experiences ◽  
Individual Level ◽  
Related Information ◽  
Digital World ◽  
The Individual ◽  
The Relationship

Relevance. The modern society creates the image of a successful person as actively interacting with different information flows, including an impressive stream of news content. This paper assumes that there is a personal need for tracking and spreading news that develops in the interaction between person and digital world. The individual level of this need could explain the interaction with information (its critical and uncritical dissemination) and the subjective experience of its redundancy and inaccuracy, including those experiences and actions in a pandemic situation. The aim of the study was to reveal the relationship of the subjective need for news with personal values, beliefs about technologies (“technophilia”) and the dissemination of news about the pandemic. Method. 270 people (aged 18 to 61) filled out The short (Schwartz) Portrait Values Questionnaire (PVQ), Beliefs about New Technologies Questionnaire, Monitoring of Information about Coronavirus Scale as well as items on the subjective need for receiving and disseminating news, readiness for critical and non-critical dissemination of news about pandemics, subjective experiences of redundancy and distrust of pandemic-related information. Results. According to the results, the Need for News Scale allows assessing the subjective importance of receiving news and discussing them with other people and is characterized by sufficient consistency and factor validity. The need for regular news is more pronounced among men, older people, people with higher education, married people, people who have children, while the need to discuss news is not related to sociodemographic factors. For people, who are more prone to technophilia, it is more important to regularly receive and discuss news information with others, which, in turn, mediates the relationship between technophilia and monitoring news about coronavirus. The need for news dissemination mediates the relationship between technophilia and readiness for critical and non-critical dissemination of information about the pandemic.

Toward a Big Data-Based Approach: A Review on Degradation Models for Prognosis of Critical Infrastructure

2020 ◽  
Vol 4 (2) ◽  
Author(s):  
Guru Prakash ◽  
Xian-Xun Yuan ◽  
Budhaditya Hazra ◽  
Daijiro Mizutani
Keyword(s):  
Big Data ◽  
Nuclear Power ◽  
Power Plants ◽  
Critical Infrastructure ◽  
Degradation Mechanism ◽  
Modern Society ◽  
Small Data ◽  
Practical Applications ◽  
Degradation Modeling ◽  
Degradation Models

Abstract Safety and reliability of large critical infrastructure such as long-span bridges, high-rise buildings, nuclear power plants, high-voltage transmission towers, rotating machinery, and so on, are important for a modern society. Research on reliability and safety analysis started with a “small data” problem dealing with relative scarce lifetime or failure data. Later, degradation modeling that uses performance deterioration, or, condition data collected from in-service inspections or online health monitoring became an important tool for reliability prediction and maintenance planning of highly reliable engineering systems. Over the past decades, a large number of degradation models have been developed to characterize and quantify the underlying degradation mechanism using direct and indirect measurements. Recent advancements in artificial intelligence, remote sensing, big data analytics, and Internet of things are making far-reaching impacts on almost every aspect of our lives. The effect of these changes on the degradation modeling, prognosis, and safety management is interesting questions to explore. This paper presents a comprehensive, forward-looking review of the various degradation models and their practical applications to damage prognosis and management of critical infrastructure. The degradation models are classified into four categories: physics-based, knowledge-based, data-driven, and hybrid approaches.

2025 Nuclear Code: The Vision for the Future of ASME Nuclear Codes and Standards

2018 ◽  
Author(s):  
Dale E. Matthews ◽  
Ralph S. Hill ◽  
Charles W. Bruny
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
New Technologies ◽  
Fusion Energy ◽  
Life Cycle Management ◽  
Economic Benefits ◽  
Plant Design ◽  
Element Analysis ◽  
Energy Devices ◽  
The Future

ASME Nuclear Codes and Standards are used worldwide in the construction, inspection, and repair of commercial nuclear power plants. As the industry looks to the future of nuclear power and some of the new plant designs under development, there will be some significant departures from the current light water reactor (LWR) technology. Some examples are gas-cooled and liquid metal-cooled high temperature reactors (HTRs), small modular reactors (SMRs), and fusion energy devices that are currently under development. Many of these designs will have different safety challenges from the current LWR fleet. Variations of the current LWR technology are also expected to remain in use for the foreseeable future. Worldwide, many LWRs are planned or are already under construction. However, technology for construction of these plants has advanced considerably since most of the current construction codes were written. As a result, many modern design and fabrication methods available today, which provide both safety and economic benefits, cannot be fully utilized since they are not addressed by Code rules. For ASME Nuclear Codes and Standards to maintain and enhance their position as the worldwide leader in the nuclear power industry, they will need to be modernized to address these items. Accordingly, the ASME Nuclear Codes and Standards organizations have initiated the “2025 Nuclear Code” initiative. The purpose of this initiative is to modernize all aspects of ASME’s Nuclear Codes and Standards to adopt new technologies in plant design, construction, and life cycle management. Examples include modernized finite element analysis and fatigue rules, and incorporation of probabilistic and risk-informed methodology. This paper will present the vision for the 2025 ASME Nuclear Codes and Standards and will discuss some of the key elements that are being considered.

scholarly journals Analysis of Factors Affecting Thermodynamic Efficiency in Generation III+ PWR Nuclear Power Plants.

2017 ◽  
Vol 4 ◽  
pp. 141-154
Author(s):  
Marcus Vitlin ◽  
Miroshan Naicker ◽  
Augustine Frederick Gardner
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Rankine Cycle ◽  
Steam Temperature ◽  
Factors Affecting ◽  
Electrical Efficiency ◽  
Balance Of Plant ◽  
The Impact ◽  
The Relationship

Generation III+ reactors are the latest generation of Nuclear Power Plants to enter the market. The key evolution in these reactors is the introduction of stringent safety standards. This is done through thorough incident scenario analysis and preparation, resulting in the addition of novel active and passive auxiliary safety systems, affecting the power consumption in the balance of plant. This paper analyses the parameters of PWR power plants of similar design, to determine the parameters for optimal efficiency, regarding gross and net electrical output, determining the impact the balance of plant has on this efficiency. While two of the three main factors affecting the Rankine cycle – boiler pressure and steam temperature – behaved as theoretically expected, there was a notable point of departure with the third parameter – condenser pressure. The relationship between steam temperature and gross electrical efficiency was linear across all reactors but the relation between the steam temperature and the net electrical efficiency ceased to be linear for secondary loop steam temperatures above 290°C. The relationship between boiler pressure and both gross and net electrical efficiency was linear, proving the Rankine cycle. A relationship was not observed between the condenser pressure and either the gross or net electrical efficiency

scholarly journals Chinese Public Willingness to Pay to Avoid Having Nuclear Power Plants in the Neighborhood

2014 ◽  
Vol 6 (10) ◽  
pp. 7197-7223 ◽  
Author(s):  
Chuanwang Sun ◽  
Nan Lyu ◽  
Xiaoling Ouyang
Keyword(s):  
Willingness To Pay ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Chinese Public

Instrumentation and Controls Design and Maintenance Strategy for Small Modular Reactors

2014 ◽  
Author(s):  
Alex H. Hashemian ◽  
Hash M. Hashemian ◽  
Tommy C. Thomasson ◽  
Jeffrey R. Kapernick
Keyword(s):  
Response Time ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
New Technologies ◽  
Early Stage ◽  
Department Of Energy ◽  
Forced Flow ◽  
Small Modular Reactors ◽  
And Control

Small Modular Reactors (SMRs) under design and development today are working to crystallize the measurements that must be made to control the reactor and monitor its safety. Traditionally, temperature, pressure, level, flow, and neutron flux are measured in conventional nuclear reactors for operation and control and to protect against equipment and process deviations that can affect safety. In most current SMR designs, essentially the same process variables may have to be measured; especially primary coolant flow depending on whether the core cooling and heat transfer results from natural circulation or forced flow. The flow can be measured directly or inferred from other measurements or estimated through empirical or physical modeling. The conventional sensors that are qualified for nuclear services and are currently used in nuclear power plants may or may not be suitable for SMRs. It all depends on the size and qualification requirements, installation details, static and dynamic performance specifications, wiring details, and sensor life expectancy. This paper will explore the possibilities that exist for SMRs to use today’s sensors and any need for new sensor designs. In addition, the paper will identify new means for automated monitoring of instrumentation and control (I&C) sensor performance in SMRs. In particular, the existing array of online calibration monitoring techniques and in-situ response time measurement methods will be evaluated for implementation in SMRs. This is important at this early stage as SMRs can easily build provisions in their mechanical, electrical, and I&C designs to accommodate online and automated I&C maintenance. For example, it is envisioned that SMRs will not be performing periodic sensor calibrations using classical hands-on procedures. Rather, SMRs are expected to be equipped with new technologies to verify the I&C performance automatically and flag the sensors and systems to be calibrated, response time tested, repaired, or replaced. The paper will explore these possibilities and will report on a current R&D project that is underway at AMS with funding from the U.S. Department of Energy (DOE) with the goal to adapt the existing online monitoring (OLM) technologies for implementation in SMRs. The existing OLM technologies have been used by AMS in commercial nuclear power plants and research reactors for monitoring of I&C equipment performance including calibration, response time, detection of sensing line blockages, and to distinguish whether a signal anomaly is due to cables/connectors, electromagnetic interference, an end device being a sensor or a pump, other rotating equipment, etc.

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