Domesticating modernity: the Electrical Association for Women, 1924–86

1999 ◽  
Vol 32 (1) ◽  
pp. 47-67 ◽  
Author(s):  
CARROLL PURSELL
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Well Being ◽  
Point Of View ◽  
Early Years ◽  
Electrical Industry ◽  
Modern Vision ◽  
Religious Zeal ◽  
The One ◽  
British Home

For over half a century, from 1924 to 1986, the Electrical Association for Women (EAW) worked to modernize the British home by bringing the blessings of labour-saving appliances to the aid of British women. Adopting a strategy of facilitation, the EAW sought, on the one hand, to educate women about electricity and its advantages in the home, encourage them to demand greater access to that electricity and keep them abreast of new developments in appliances and the infrastructure (from a national grid to sufficient outlets) necessary for enjoying them. On the other hand, the organization sought to discover the real needs and desires of the women themselves, and to bring this forcibly to the attention of the electrical industry in Great Britain ; to make the ‘women's point of view’, as it was called, a factor in the production, distribution and application of electricity in the home.Although the very masculine electrical industry was a decisive part of both the EAW's context, and of its financial and advisory structure, the group proudly insisted that it was a women's organization in which women addressed other women about women's concerns and well-being. In its early years, the excitement of women coming together in a modern cause was palpable, but as the leadership aged and electricity turned from modern vision to commonplace reality, the almost religious zeal and pace of activities began to falter. A late-hour attempt to highlight nuclear power plants as evidence of a renewed and equally exciting modern moment fell short, and in 1986 the EAW quietly dissolved itself, the casualty of large social changes, some of which it had proudly helped to bring about.

scholarly journals Well-being and Sustainable Development of Mining Regions: the Universal Basic Income

2019 ◽  
Vol 105 ◽  
pp. 04035
Author(s):  
Oleg Mazavin ◽  
Mikhail Kaz ◽  
Irina Roshchina
Keyword(s):  
Social Insurance ◽  
Historical Context ◽  
Well Being ◽  
Point Of View ◽  
Economic Research ◽  
Basic Income ◽  
Long Time ◽  
Series Of Experiments ◽  
The One ◽  
Mining Regions

The article presents the results of the analysis of the practice of implementation the concept of universal basic income. It is shown that in estimating the results of a series of experiments in this field, conducted in a number of countries, it is recommended to abandon the approach based on the positivist point of view. For a long time, it dominated science in general and economic research in particular, but it continues to influence many researchers today. This conclusion should be taken into account in the formation of the structure and composition of regions’ welfare indices. The research materials are placed in a broad historical context. On the one hand, this made it possible to more vividly present the prerequisites, characteristics and consequences of repeated attempts to introduce universal basic income into the practice of social insurance, undertaken in different countries of the world (Finland, Canada, Kenya, Iran, India, USA). On the other hand, to reveal the possibilities and problems of using universal basic income as a tool to help overcome the dysfunctional development of certain territories, including mining regions.

Comparison of an Array of EMATs Technique and a Magnetostrictive Sensor Technique for a Guided Wave Inspection of a Pipe

2006 ◽  
Vol 321-323 ◽  
pp. 780-783 ◽  
Author(s):  
Yong Moo Cheong ◽  
Hyun Kyu Jung ◽  
Young Suk Kim
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Ultrasonic Method ◽  
Wave Structure ◽  
Guided Wave ◽  
Point Of View ◽  
Torsional Mode ◽  
Ultrasonic Methods ◽  
Sensor Technique ◽  
Magnetostrictive Sensor

The leakage of a pipe in nuclear power plants is a significant concern from the point of view of nuclear safety. Because of the geometrical complexity of a pipe and an inaccessibility due to a high radiation, it is difficult to inspect it by the conventional ultrasonic methods. The guided ultrasonic method can be useful for the inspection of a pipe in those harsh environments. Based on the analysis of the dispersion curves for a pipe, a torsional vibration mode, T(0,1) was selected for the detection of cracks. The T(0,1) mode has many advantages, such as a higher sensitivity for a crack from the viewpoint of its non-dispersion characteristics and its wave structure. The torsional mode can be generated by using either an array of electromagnetic acoustic transducers (EMATs) technique or a magnetostrictive sensor technique. The detectability of the cracks was estimated through a series of experiments with artificial notches on a pipe.

An Aging Simulation Model for the Emergency Diesel Generators of Angra 2 by Supplementary Variables

2008 ◽  
Author(s):  
Iona´ Maghali Santos de Oliveira ◽  
Paulo Fernando Ferreira Frutuoso e Melo ◽  
Marcos Oliveira de Pinho
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Point Of View ◽  
Failure Rates ◽  
Aging Effects ◽  
Supplementary Variables ◽  
Technical Specifications ◽  
Diesel Generators ◽  
Markovian Approach ◽  
Useful Lifetime

The extension of the useful lifetime of nuclear power plants is an issue of great importance and concern. From the reliability point of view, this problem requires the consideration of time-dependent failure rates and possible failure dependencies. This analysis has been typically performed through a Markovian approach. To illustrate this point, we have developed a computerized reliability analysis of the emergency diesel generators (EDGs) of a four “loop” PWR plant, considering the hypothesis of aging and perfect repair by using Supplementary Variables to cast the initially Nonmarkovian model into a Markovian one. In order to perform such analysis and to simulate aging effects, a nuclear plant has been taken for reference, which has been commercially operating for only six years. Failure rates were obtained from similar EDGs of another plant, already under aging, while repair data were taken from its technical specifications. Discontinuous repair rates were considered in order to improve maintenance strategies. Several ages were attributed to these equipments, allowing the calculus of the failure probability as well as their availability according to each regarded age. In this sense, the EDGs behavior as to aging can be obtained in detail and decisions concerning maintenance and useful lifetime extension can be made on a stronger basis. To get the desired results in terms of reliability figures and due to the discontinuous repair rates that had to be taken into account, a new numerical method that uses a part of the analytical solution, called Euler Iterative + Characteristic, has been developed in order to solve the differential equations systems, making the solving of the system faster and more efficient.

scholarly journals Neutron flux simulation of a one-dimensional reactor zone taking into account xenon generation

Energetika ◽  
2020 ◽  
Vol 65 (4) ◽  
Author(s):  
Zsófia Tóth ◽  
Dániel Péter Kis
Keyword(s):  
Numerical Methods ◽  
Neutron Flux ◽  
Nuclear Power ◽  
Power Plants ◽  
Research Work ◽  
Reactor Core ◽  
Time And Space ◽  
One Dimensional ◽  
Safety And Reliability ◽  
The One

The energy in nuclear power plants is produced by thermal fission. It is extremely important to be able to monitor the processes in the reactor to ensure the safety and reliability of the power plant. One of the main traits of the reactor core is neutron flux. It changes in time and space therefore it is crucial to be able to simulate its changes with computer codes. In the research work a program code was established in the Matlab software with which the neutron flux of a one-dimensional zone can be simulated with homogenous and heterogenic zone parameters as well. The code is written using the one-group one-dimensional time- and space-dependent diffusion equation. The equation of an average delayed neutron group and xenon and iodine distributions was also included in the system to give a more precise look on the problem. The main innovation in the code is that numerical methods were used to solve the problem: the finite difference approach was applied for the place-dependent and for the time-dependent solution. The advantage of this code compared to other ones is that one-dimensional zones can be simulated in a really short time and it still gives a precise solution because of the complex numerical methods used.

scholarly journals Human factor in emergency occurrence at NPP during the pandemic COVID-19: new potential risks and recommendations to minimize them

2021 ◽  
Vol 280 ◽  
pp. 09013
Author(s):  
Oleksandr Popov ◽  
Anna Iatsyshyn ◽  
Norbert Molitor ◽  
Andrii Iatsyshyn ◽  
Yevhen Romanenko ◽  
...  
Keyword(s):  
Mental Health ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Critical Infrastructure ◽  
Well Being ◽  
Psychological Support ◽  
Negative Consequences ◽  
Large Numbers ◽  
Potential Risks

COVID-19 pandemic is an emergency that spread across the planet. It threatens lives and health of the population, with many dead and injured. Also, during pandemic there was (and continues to be) a violation of normal living conditions, significant material damage to economies of different countries. Quarantine restrictions affected social, educational, cultural and spiritual spheres of society. There is an urgent threat to operation of critical infrastructure as the pandemic led to large numbers of hospitalized or self-isolated people and being treated at home. At present, the operation of critical infrastructure, and in particular nuclear power plants, is strategically important for the proper functioning of any country. Also, the research describes causes of emergencies at nuclear power plants and identifies another factor - the mass disease of NPP personnel or their relatives on COVID-19. It is determined that timely detection and appropriate work to restore mental health during the pandemic is no less important area of work along with providing medical care to population. Stress associated with uncertainty, threat to health, can have negative consequences for well-being and mental health of workers. Depression, emotional exhaustion, anxiety, irritability, suicidal thoughts, etc. can also be consequences. Socio-psychological support especially for critical infrastructure workers is important to promote mental health during COVID-19 pandemic. Recommendations for socio-psychological support of NPP personnel were developed. Specialized mobile applications are described as convenient and economical way for primary psychological care.

scholarly journals La comunicación de crisis en el sector atómico: protocolo, características, y recomendaciones en eventos nucleares = Crisis communication in the atomic sector: protocol, characteristics, and recommendations in nuclear events

2019 ◽  
pp. 19
Author(s):  
Enrique Cobos Urbina ◽  
María José Recoder Sellarés
Keyword(s):  
Crisis Communication ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Energy ◽  
Nuclear Power Plants ◽  
Strategic Communication ◽  
Public Confidence ◽  
Social Legitimacy ◽  
The One ◽  
Nuclear Crisis

Resumen: Las centrales nucleares necesitan una comunicación organizada para los dos tipos de situaciones es­peciales a las que se enfrentan: por un lado, para informar a los stakeholders de lo que está ocurriendo en una crisis operativa; y por otra parte para recuperar la confianza pública en aquellos acontecimientos imprevistos que afectan a la reputación de la central y a la legitimidad social de la energía nuclear. ¿Qué características definen la comunicación de crisis nuclear? ¿Qué protocolo comunicativo se sigue en España en caso de un accidente o incidente nuclear? ¿Se tienen en cuenta las teorías de comunicación estratégica en períodos de crisis?Palabras clave: centrales nucleares; energía nuclear; comunicación de crisis; comunicación nuclear; España.Abstract: Nuclear power plants need an organized communication for the two types of special situations they face: on the one hand to inform relevant stakeholders of what is happening in an operational crisis; and on the other hand to recover public confidence in those unforeseen events that affect the reputation of the nuclear power plant and the social legitimacy of nuclear energy. What characteristics define nuclear crisis communication? What communicative protocol is followed in Spain in case of a nuclear accident or incident? Are the theories of strategic communication taken into account during periods of crisis?Keywords: nuclear power plants; nuclear energy; crisis communication; nuclear communication; Spain.

French Nuclear Power Plants Life Management Ageing Management Process: Matrix of Degradation Evaluation for Strategic Decision Combined With Components

2005 ◽  
Author(s):  
Georges Bezdikian
Keyword(s):  
Asset Management ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Point Of View ◽  
Strategic Decision ◽  
Life Management ◽  
Life Evaluation ◽  
Maintenance Program ◽  
Periodic Maintenance

The life management of French Nuclear Power Plants is an important issue and a major stake considering the aging management assessment of the key components of the plant, both from an economic and a technical point of view. The actual life evaluation is: • The first 3-loop PWR plants have 25 years in operation, • The first 4-loop PWR plants have 19 years in operation. To optimize the best and strategic choice in order to achieve the best possible performance and to prepare the technical and economical choice and decision considering: • the mode of degradation for different components, • the industrial capacity and capability to replace or to repair components, • the life evaluation of components with time limit in operation, the French utility has organized the life management of Nuclear Plant in function of several program of knowledge on degradation mode from the large and long term experience feedback and the maintenance program for life management based on normal and periodic maintenance actions and exceptional maintenance carried out on strategic components. This paper shows the table of degradation mode and different actions engaged by utility on: • In-Service Inspection, periodic maintenance, • Alternative maintenance actions, • Exceptional program of maintenance based on several mitigation and strategic replacement of components. This paper provides the reader with an overview of how advanced information processing techniques to the improvement of in-service inspections, condition-based maintenance, and asset management.

Modelling of Pulse Height Spectra of Gamma Detectors for Simplified Models of a Radioactive Cloud

ANRI ◽  
2021 ◽  
Vol 0 (1) ◽  
pp. 45-52
Author(s):  
Sergey Gavrilov ◽  
Egor Il'ichev ◽  
Aleksey Kisilev ◽  
Artem Pimenov ◽  
Anton Shvedov
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Pulse Height ◽  
Point Of View ◽  
Nuclear Industry ◽  
Simplified Models ◽  
Radioactive Cloud ◽  
Radionuclide Composition ◽  
Gamma Sources ◽  
Conducting Research

The paper considers the issues of determining the pulse height spectra of gamma detector from a radioactive cloud. This task is of interest from the point of view of possible improvement of existing systems for monitoring the radiation situation around nuclear power plants and nuclear industry enterprises due to the wider use of gamma-spectrometric equipment. Modeling of pulse height spectra will allow conducting research on the capabilities of monitoring system posts for detecting radionuclides in the radioactive cloud. A general approach to modeling pulse height spectra using division of the radioactive cloud into elementary gamma sources is developed. The pulse height spectra of scintillator NaI ∅63×63 mm are calculated for simplified models of the radioactive cloud in the form of a linear gamma source and a semi-infinite space. The obtained data can be used for rapid estimates of pulse height spectra, while the formulated approach to spectra modeling also allows for more time-consuming calculations for an arbitraryshaped radioactive cloud with an arbitrary radionuclide composition.

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