Initiating nuclear power programmes: Responsibilities and capabilities of owners and operators

International Nuclear Information System (INIS)

2009-01-01

There is an increasing interest in developing nuclear power due to growing energy needs, limitations on natural resources and concern for the environment. However, the introduction and development of nuclear power is a major undertaking. This requires building the necessary national infrastructure to construct and operate nuclear power plants in a safe, secure and technically sound manner. Many IAEA Member States that do not yet have nuclear power programmes have expressed their interest to the IAEA about the possibility of introducing nuclear power plants to help meet their energy needs. To assist these Member States, the IAEA is preparing a series of guides and reports. An overall description of the issues was presented by the IAEA in a brochure entitled Considerations to Launch a Nuclear Power Programme (GOV/INF/2007/2), which was targeted mainly at policy makers. A subsequent IAEA Nuclear Energy Series publication, Milestones in the Development of a National Infrastructure for Nuclear Power (NG-G-3.1), describes 19 infrastructure issues that should be addressed through the three phases of development outlined in the brochure, Considerations to Launch a Nuclear Power Programme. The IAEA is preparing a number of guides addressing these issues. Once a firm decision has been made by a government to proceed with the development of a nuclear programme, a number of organizations must be developed. A key organization for the successful construction and operation of the first nuclear power plant is the owner/operator, who provides ownership and management of the project. The owner/operator must clearly understand what must be done and how it has to act, who are partners and supporters and the corresponding interactions that have to be established. The owner or operator may be state owned or a private company. It may be an existing utility, or a specially established project organization. Its responsibilities include bidding, construction, licensing, commissioning

Japanese programme on the development of high duty fuel and related power ramping tests

International Nuclear Information System (INIS)

Mishima, Y.

1983-01-01

Power ramping tests hitherto planned or carried out in Japan can be classified into two categories: 1) the tests programme by private organizations on fuel behaviour under various conditions of power ramping, in participating international programmes; and 2) a partially government sponsored programme, which was officially inaugurated in 1981 under the title of High-Duty Fuel Development Programme. The latter has been carried out by the Nuclear Power Engineering Test Centre, based on the schedule decided by the MITI Committee (chaired by the author), for a period of 10 years. These programmes will be described with emphasis on the latter (National Programme). (author)

Japanese programme on the development of high duty fuel and related power ramping tests

Energy Technology Data Exchange (ETDEWEB)

Mishima, Y

1983-06-01

Power ramping tests hitherto planned or carried out in Japan can be classified into two categories: 1) the tests programme by private organizations on fuel behaviour under various conditions of power ramping, in participating international programmes; and 2) a partially government sponsored programme, which was officially inaugurated in 1981 under the title of High-Duty Fuel Development Programme. The latter has been carried out by the Nuclear Power Engineering Test Centre, based on the schedule decided by the MITI Committee (chaired by the author), for a period of 10 years. These programmes will be described with emphasis on the latter (National Programme). (author)

Nuclear power training programmes in Spain

International Nuclear Information System (INIS)

Tanarro, A.; Izquierdo, L.

1977-01-01

The introduction of nuclear power in Spain is developing very rapidly. At present 1.1GW(e) are installed in Spain and this is expected to increase to 8GW(e) in 1980 and to 28GW(e) in 1990. Spanish industry and technology are also rapidly increasing their participation in building nuclear stations, in manufacturing the necessary components and in the activities related to the nuclear fuel cycle. All of this requires properly trained personnel, which is estimated to become approximately 1200 high-level technicians, 1100 medium-level technicians and 1500 technical assistants by 1980. This personnel is trained: (a) in engineering schools; (b) in the Nuclear Studies Institute; (c) in the electric companies with nuclear programmes. The majority of the high-level engineering schools in the country include physics and basic nuclear technology courses in their programmes. Some of them have an experimental low-power nuclear reactor. The Nuclear Studies Institute is an official organism dependent on the Nuclear Energy Commission and responsible, among other subjects, for training personnel for the peaceful use and development of nuclear energy in the country. The electric companies also participate in training personnel for future nuclear stations and they plan to have advanced simulators of PWR and BWR type stations for operator training. The report deals with the personnel requirement forecasts and describes the training programmes. (author)

Nuclear Engineering Education in Support of Thailand’s Nuclear Power Programme

International Nuclear Information System (INIS)

Chanyotha, S.; Pengvanich, P.; Nilsuwankosit, S.

2015-01-01

This paper aims to introduce the nuclear engineering education at the Department of Nuclear Engineering, Chulalongkon University, Bangkok Thailand. The department has been offering curriculum in nuclear engineering to support the national nuclear power programme since 1970s. It is the oldest established nuclear engineering educational programme in the South East Asia region. Nevertheless, since the nuclear power programme has been postponed several times due to various reasons, the educational programme at the department has been continuously adapted to meet the nation’s needs. Several areas of study have been introduced, including nuclear power engineering, industrial applications of radioisotope, nuclear instrumentation, radioisotope production, radiation processing, environment and safety, nuclear materials, as well as the newly created nuclear security and non-proliferation. With the renewed interest in using nuclear power in Thailand in 2007, the department has been actively assisting both the government and the electric utility in preparing human resources to support the nuclear power programme through various educational and training modules. Realizing the importance of establishing and balancing all 3 aspects of the nuclear 3S (safety, security and safeguard) in Thailand and in the Southeast Asian region. The new curriculum of nuclear security and safeguard programme has been offered since 2013. Since the establishment, the department has produced hundreds of graduates (Diploma, Master’s, and Ph.D. levels) to feed the continuously expanding Thai nuclear industry. The full paper will provide detailed information of the curriculum, the challenges and obstacles that the department has encountered, as well as the national and international linkages which have been established over the years. (author)

Power consumption of programmable controllers; Energieverbrauch von Prozesssteuerungen (SPS)

Energy Technology Data Exchange (ETDEWEB)

Schalcher, M.; Battaglia, U.; Busch, E.

2003-07-01

This final report for the Swiss Federal Office for Energy addresses the field of programmable logic controllers and thus investigates a topic that has been neglected up to now - the energy consumption of such controllers. The results of measurements made on programmable logic controllers in use both in operational industrial plants and in the Automation Laboratory at the University of Applied Science in Chur, Switzerland are presented, where a detailed analysis was made on a demonstration plant. Also, technical documentation (catalogues) were evaluated and discussed with experts who had practical experience at their disposal. The results of the study are discussed: these show that the power consumption of any particular programmable logic controller is low in comparison to the energy consumption of the processes that are being controlled. Additionally, it was found that the optimisation of newer devices has to a great extent already been realised and that standard solutions for energy optimisation are not easy to put into practice. It is suggested that savings can possibly be made in the controllers by improving the efficiency of their power supply units and by choosing power ratings to better suit the actual power needed.

Nuclear power programmes in developing countries: Promotion and financing

International Nuclear Information System (INIS)

Bennett, L.L.

1987-01-01

In 1986 the Agency's Director General established a Senior Expert Group on Mechanisms to Assist Developing Countries in the Promotion and Planning of Nuclear Power Programmes. This group, which was comprised of 20 experts with extensive experience in the topics to be studied, coming from 15 Member States plus the World Bank, was asked to: identify and analyse the problems of and constraints on nuclear power introduction/expansion in developing countries, with particular attention being paid to the problems of financing nuclear power projects; study mechanisms for dealing with the identified problems and constraints in order to assist developing countries with the promotion and financing of their nuclear power programmes and to determine the role of the IAEA in this context. This paper summarizes the Senior Expert Group's study

Indian experience in the training of manpower for nuclear power programme

International Nuclear Information System (INIS)

Iyengar, P.K.; Damodaran, K.K.; Sarma, M.S.R.; Wagadarikar, V.K.

1977-01-01

In India manpower training for the nuclear power programme started several years before the introduction of nuclear power plants. Early efforts were concentrated on developing manpower in basic sciences related to nuclear power; for example, nuclear physics, chemistry, metallurgy of nuclear materials, aspects of chemical engineering etc. The setting up of the research centre viz. Atomic Energy Establishment Trombay, now named the Bhabha Atomic Research Centre, was an important step in this direction. A programme of design and construction of research reactors and its utilization formed the backbone of manpower development. This enabled the first batch of engineers and scientists to be trained on the design and operation in the programmes connected with research reactors and use of isotopes in industry, agriculture and medicine. The next step was to establish a Training School in the Bhabha Atomic Research Centre in which fresh graduates from the Universities could be given courses both in their own disciplines and in other inter-connected disciplines of nuclear sciences. About 200 such graduates are being trained every year since 1957. An inter-disciplinary approach with teaching by working scientists and engineers and the attachment for short periods to the research laboratories is the framework of this training programme. At present about 3000 graduates from this Training School are involved in various capacities in India's nuclear power programme. With the commissioning of the first power reactors, it became necessary to conceive of training engineers, scientists and technicians, particularly for operation and maintenance of such systems on a larger scale. For this purpose, a separate training institute at Rajasthan Atomic Power Project near Rana Pratapsagar was set up. Models, simulators and courses, particularly emphasizing the heavy water system of reactors was introduced. In addition, a number of craftsmen for servicing equipment have also been trained as

Indian experience in the training of manpower for a nuclear power programme

International Nuclear Information System (INIS)

Iyengar, P.K.; Damodaran, K.K.; Sarma, M.S.R.; Wagadarikar, V.K.

1977-01-01

In India manpower training for the nuclear power programme started several years before the introduction of nuclear power plants. Early efforts were concentrated on developing manpower in basic sciences related to nuclear power. The setting up of the Bhabha Atomic Research Centre was an important step in this direction. This enabled the first batch of engineers and scientists to be trained on design and operation in the programmes connected with research reactors and use of isotopes in industry, agriculture and medicine. The next step was to establish a Training School in the Centre where young university graduates could be given courses in their own and interconnected disciplines of nuclear sciences. An interdisciplinary approach with teaching by working scientists and engineers and attachment for short periods to the research laboratories is the framework of this training programme. At present about 3000 graduates from this Training School are involved in various capacities in India's nuclear power programme. With the commissioning of the first power reactors, it became necessary to train engineers, scientists and technicians for the operation and maintenance of such systems on a larger scale. For this purpose, a separate training centre at Rajasthan Atomic Power Project was set up. Models, simulators and courses with emphasis on heavy water reactors were introduced. In addition, a number of craftsmen for servicing equipment have also been trained in power station equipment maintenance. The paper describes the development of this programme in its present form. (author)

Microwave assisted air drying of osmotically treated pineapple with variable power programmes

CSIR Research Space (South Africa)

Botha, GE

2012-01-01

Full Text Available Variable power programmes for microwave assisted air drying of pineapple were studied. The pineapple pieces were pre-treated by osmotic dehydration in a 55º Brix sucrose solution at 40ºC for 90 minutes. Variable power output programmes were designed...

The Communities' research and development programme on decommissioning of nuclear power plants

International Nuclear Information System (INIS)

1981-01-01

This is the first progress report of the European Community's programme (1979-1983) of research on the decommissioning of nuclear power plants. It shows the status of the programme on 31 December 1980. The programme seeks to promote a number of research and development projects as well as the identification of guiding principles. The projects concern the following subjects: long-term integrity of buildings and systems; decontamination for decommissioning purposes; dismantling techniques; treatment of specific waste materials: steel, concrete and graphite; large transport containers for radioactive was produced in the dismantling of nuclear power plants; estimation of the quantities of radioactive wastes arising from decommissioning of nuclear power plants in the Community; influence of nuclear power plant design features on decommissioning

Material development for India's nuclear power programme

Indian Academy of Sciences (India)

rials with emphasis on development of fabrication routes of zirconium alloys for .... nuclear power programme, which envisages design and construction of thermal breeder ... Production of Hf-free nuclear grade zirconium ..... Later on for pressure tubes specified limit for hydrogen content in the as manufactured condition.

Quality assurance programme of Temelin nuclear power plant

International Nuclear Information System (INIS)

Eybl, J.; Nowak, O.

1988-01-01

The fundamental principle of the system of quality assurance in Czechoslovak nuclear power is quality assurance at all stages of the construction and operation of nuclear power plants and the grading fo measures taken, this in dependence on the impact on nuclear safety of the respective nuclear installation or its part. The system has been made fully operational during the construction of nuclear power plants in Temelin and Mochovce. State surveillance is executed by the Czechoslovak Atomic Energy Commission, and the Czech and Slovak Offices for Work Safety. Briefly discussed are the tasks of the building subcontractor of the Temelin nuclear power plant with regard to the programme of quality assurance as well as the results of the solution of the respective research tasks. The programme of quality assurance classifies the selected sections of the structure of a nuclear power plant into three safety categories. No part of the structure is classified into the first category, the second category includes, e.g., the reactor building, cooling tanks and diesel generator units, the third includes the reactor building and the building of auxiliary workshops. Attention is also paid to the problems of the qualification of personnel and to inspection activity. (Z.M.). 12 refs

Establishing the quality assurance programme for a nuclear power plant project

International Nuclear Information System (INIS)

1984-01-01

This Safety Guide provides requirements, recommendations and illustrative examples for establishing the overall quality assurance programme, and its constituent programmes, for a nuclear power plant project. It also provides guidance on the planning and documenting of programme plans and actions that are intended to ensure the achievement of the appropriate quality throughout the design, procurement, manufacture, construction, commissioning, operation and decommissioning of the nuclear power plant. The provisions of this Safety Guide are applicable to all organizations performing activities affecting the quality of items important to safety, such as designing, purchasing, fabricating, manufacturing, handling, shipping, storing, cleaning, erecting, installing, testing, commissioning, operating, inspecting, maintaining, repairing, refuelling, modifying and decommissioning

Finnish research programmes on nuclear power plant safety

International Nuclear Information System (INIS)

Puska, E. K.

2010-01-01

The current Finnish national research programme on nuclear power plant safety SAFIR2010 for the years 2007-2010 as well as the coming SAFIR2014 programme for the years 2011-2014 are based on the chapter 7a, 'Ensuring expertise', of the Finnish Nuclear Energy Act. The objective of this chapter is realised in the research work and education of experts in the projects of these research programmes. SAFIR2010 research programme is divided in eight research areas that are Organisation and human, Automation and control room, Fuel and reactor physics, Thermal hydraulics, Severe accidents, Structural safety of reactor circuit, Construction safety, and Probabilistic Safety Analysis (PSA). All the research areas include both projects in their own area and interdisciplinary co-operational projects. Research projects of the programme are chosen on the basis of annual call for proposals. In 2010 research is carried out in 33 projects in SAFIR2010. VTT is the responsible research organisation in 26 of these projects and VTT is also the coordination unit of SAFIR2010 and SAFIR2014. In 2007-2009 SAFIR2010 produced 497 Specified research results (Deliverables), 618 Publications, and 33 Academic degrees. SAFIR2010 programme covers approximately half of the reactor safety research volume in Finland currently. In 2010 the programme volume is EUR 7.1 million and 47 person years. The major funding partners are VYR with EUR 2.96 million, VTT with EUR 2.66 million, Fortum with EUR 0.28 million, TVO with EUR 0.19 million, NKS with EUR 0.15 million, EU with only EUR 0.03 million and other partners with EUR 0.85 million. The new decisions-in-principle on Olkiluoto unit 4 for Teollisuuden Voima and new nuclear power plant for Fennovoima ratified by the Finnish Parliament on 1 July 2010 increase the annual funding collected according to the Finnish Nuclear Energy Act from Fennovoima, Fortum and Teollisuuden Voima for the SAFIR2014 programme to EUR 5.2 million from the current level of EUR 3

Power ramp tests of BWR-MOX fuels

International Nuclear Information System (INIS)

Asahi, K.; Oguma, M.; Higuchi, S.; Kamimua, K.; Shirai, Y.; Bodart, S.; Mertens, L.

1996-01-01

Power ramp test of BWR-MOX and UO 2 fuel rods base irradiated up to about 60 GWd/t in Dodewaard reactor have been conducted in BR2 reactor in the framework of the international DOMO programme. The MOX pellets were provided by BN (MIMAS process) and PNC (MH method). The MOX fuel rods with Zr-liner and non-liner cladding and the UO 2 fuel rods with Zr-liner cladding remained intact during the stepwise power ramp tests to about 600 W/cm, even at about 60 GWd/t

Nuclear power plant operation experience - a feedback programme

International Nuclear Information System (INIS)

Banica, I.; Sociu, F.; Margaritescu, C.

1994-01-01

An effective high quality maintenance programme is required for the safe reliable operation of a nuclear power plant. To achieve the objectives of such a programme, both plant management and staff must be highly dedicated and motivated to perform high quality work at all levels. Operating and maintenance experience data collections and analysis are necessary in order to enhance the safety of the plant and reliability of the structures systems and components throughout their operating life. Significant events, but also minor incident, may reveal important deficiencies or negative trends adverse to safety. Therefore, a computer processing system for collecting, classifying and evaluating abnormal events or findings concerning operating-maintenance and for feeding back the results of the lessons learned from experience into the design and the operation of our nuclear power plant is considered to be of paramount importance. (Author)

FPGA Implementation of the stepwise shutdown system

International Nuclear Information System (INIS)

Lotjonen, L.

2012-01-01

This report elaborates the design process of applications for field-programmable gate array (FPGA) devices. Brief introductions to EPGA technology and the design process are first given and then the design phases are walked through with the aid of a case study. FPGA is a programmable logic device that is programmed by the customer rather than the manufacturer. They are also usually re-programmable which enables updating their programming and otherwise modifying the design. There are also one-time programmable FPGAs that can be used when security issues require it. FPGA is said to be 'hardware designed like software', which means that the design process resembles software development but the end-product is considered a hardware application because the execution of the functions is entirely different from a microprocessor. This duality can give both the flexibility of software and the reliability of hardware. The FPGA design and verification and validation (V and V) methods for NPP safety systems have not yet matured because the technology is rather new in the field. Software development methods and standards can be used to some extent but the hardware aspects bring new challenges that cannot be tackled using purely software methods. International efforts are being made to development formal and consistent design and V and V methodology regulations for FPGA devices. A preventive safety function called Stepwise Shutdown System (SWS) was implemented on an Actel M1 IGLOO field-programmable gate array (FPGA) device. SWS is used to drive a process into a normal state if the process measurements deviate from the desired operating values. This can happen in case of process disturbances. The SWS implementation process from the requirements to the functional device is elaborated. The design is tested via simulation and hardware testing. The case study is to be further expanded as a part of a master's thesis. (orig.)

FPGA Implementation of the stepwise shutdown system

Energy Technology Data Exchange (ETDEWEB)

Lotjonen, L.

2012-07-01

This report elaborates the design process of applications for field-programmable gate array (FPGA) devices. Brief introductions to EPGA technology and the design process are first given and then the design phases are walked through with the aid of a case study. FPGA is a programmable logic device that is programmed by the customer rather than the manufacturer. They are also usually re-programmable which enables updating their programming and otherwise modifying the design. There are also one-time programmable FPGAs that can be used when security issues require it. FPGA is said to be 'hardware designed like software', which means that the design process resembles software development but the end-product is considered a hardware application because the execution of the functions is entirely different from a microprocessor. This duality can give both the flexibility of software and the reliability of hardware. The FPGA design and verification and validation (V and V) methods for NPP safety systems have not yet matured because the technology is rather new in the field. Software development methods and stanfards can be used to some extent but the hardware aspects bring new challenges that cannot be tacled using purely software methods. International efforts are being made to development formal and consistent design and V and V methodology regulations for FPGA devices. A preventive safety function called Stepwise Shutdown System (SWS) was implemented on an Actel M1 IGLOO field-programmable gate array (FPGA) device. SWS is used to drive a process into a normal state if the process measurements deviate from the desired operating values. This can happen in case of process disturbances. The SWS implementation processfrom the reguirements to the functional device is elaborated. The design is tested via simulation and hardware testing. The case study is to be further expanded as a part of a master's thesis. (orig.)

Nuclear power plant ageing management programmes in foreign countries

International Nuclear Information System (INIS)

Simola, K.; Laakso, K.; Pekkonen, A.

1992-09-01

The report describes ageing studies of nuclear power plants and research programmes on plant life extension in foreign countries. Ageing studies are aimed to ascertain that the availability and safety of components and structures can be maintained throughout the plant lifetime. In life extension programmes the purpose is to evaluate the technical and economical possibilities to extend the plant lifetime beyond the originally planned operation period, without reducing the plant safety. The main emphasis of the report is put on the ageing and life extension programmes in the United States. Besides the U.S. studies, research on plant life extension possibilities conducted in France and Japan are also described. Examples of studies performed in other nuclear energy producing countries are given. These examples are mainly related to the development of maintenance programmes and techniques

Development of human resources for Indian nuclear power programme

International Nuclear Information System (INIS)

Grover, R.B.; Puri, R.R.

2013-01-01

The continuing research and development on nuclear technology by research establishments in the country and maturing of Indian industry have brought the nuclear energy programme in India to a stage where it is poised to take a quantum leap forward. The vision of expansion of nuclear power also requires a well-structured specialized human resource development programme. This paper discusses the requirements of the human resource development programme for nuclear energy, the challenges in the way of its realization, its national and international status and traces the history of nuclear education in the country. It brings out the linkage of human resource development programme with the nuclear energy programme in the country. It also describes the initiatives by the university system in the area of nuclear education and support provided by the Department of Atomic Energy to the university system by way of extra-mural funding and by providing access to research facilities. (author)

Power programmes review: Power reactors in the Federal Republic of Germany

Energy Technology Data Exchange (ETDEWEB)

NONE

1960-04-15

Compared with work in some other industrialized countries, the atomic energy programme in the Federal Republic of Germany got off to a somewhat late start. Nevertheless, after about four years of research and training of scientists, the country is today on the threshold of a major phase in atomic energy development. While research and training are being continued, the first concrete steps are also being initiated for the commercial utilization of nuclear energy as a source of power. Several experimental nuclear power stations are being set up, designed or planned

The French nuclear power programme and energy policy in France

International Nuclear Information System (INIS)

Carle, R.

1988-01-01

After briefly describing the Chernobyl reactor accident and its consequences in Western Europe, especially its psychological effects, the French nuclear energy programme is presented in detail. The role of standardization and education as well as of construction time and cost is pointed out. Moreover, the results of the programme are given including extension of the capable French nuclear power industry, economical and ecological benefits. Future measures such as increase of the flexibility of nuclear power plants, improved fuel management, reduction of personnel radiation doses and employment of advanced reactors (the reactor system N4) will facilitate French efforts to free the country from mineral oil and coal imports. (author)

France's nuclear power programme; Le programme nucleaire francais

Energy Technology Data Exchange (ETDEWEB)

Cabanius, J [Electricite de France (EDF), 75 - Paris (France); Horowitz, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1964-07-01

The prospects of development of France's consumption of electricity will widen the deficit of her national energy resources. Nuclear power stations should enable this deficit to be reduced, provided a certain number of uncertainties prevailing today are resolved. The first programme, put forward by Messrs. AILLERET and TARANGER at the 1955 Geneva Conference aimed at commissioning 850 MWe by 1965; the programme was devoted to developing the natural uranium graphite-gas sequence and reaches its completion with the construction of EDF 3, the world's first unit capable of 500 MWe. Before changing over from the prototype stage to their duplication, Electricite De France decided, in agreement with the Commissariat A L'energie Atomique to build EDF 4, which, while reproducing EDF 3's reactor, together with the referring equipment, the entire control equipment and various other systems, pioneers an important innovation by incorporating the heat exchangers and fans inside the prestressed concrete pressure vessel housing the core. At the same time, studies are being carried on on the same type of reactor enabling possible use of a new annular-shaped fuel element, whose use would considerably improve the performance of EDF 5, to be envisaged. On the heavy water side, the construction of EL 4 at Brennilis jointly by the Commissariat A L'energie Atomique and Electricite De France is continuing. Design work on a 500 MWe reactor of this type has already started. As regards pressurized water reactors, the Chooz power station is built jointly by Electricite De France and Belgian Utilities. Finally, the Commissariat A L'energie Atomique is continuing the construction of the 'Rapsodie' rapid neutron reactor at Cadarache, together with studies on a larger power reactor. It may thus be seen that the technical and economic knowledge gained on these various types of reactor mean that an equipment program may be contemplated which will endow nuclear power stations with a place of ever

Operational safety review programmes for nuclear power plants. Guidelines for assessment

International Nuclear Information System (INIS)

2002-01-01

The IAEA has been offering the Operational Safety Review Team (OSART) programme to provide advice and assistance to Member States in enhancing the operational safety of nuclear power plants (NPPs). Simultaneously, the IAEA has encouraged self-assessment and review by Member States of their own nuclear power plants to continuously improve nuclear safety. Currently, some utilities have been implementing safety review programmes to independently review their own plants. Corporate or national operational safety review programmes may be compliance or performance based. Successful utilities have found that both techniques are necessary to provide assurance that (i) as a minimum the NPP meets specific corporate and legal requirements and (ii) management at the NPP is encouraged to pursue continuous improvement principles. These programmes can bring nuclear safety benefits to the plants and utilities. The IAEA has conducted two pilot missions to assess the effectiveness of the operational review programme. Based on these missions and on the experience gained during OSART missions, this document has been developed to provide guidance on and broaden national/corporate safety review programmes in Member States, and to assist in maximizing their benefits. These guidelines are intended primarily for the IAEA team to conduct assessment of a national/corporate safety review programme. However, this report may also be used by a country or utility to establish its own national/corporate safety review programme. The guidelines may likewise be used for self-assessment or for establishing a baseline when benchmarking other safety review programmes. This report consists of four parts. Section 2 addresses the planning and preparation of an IAEA assessment mission and Sections 3 and 4 deal with specific guidelines for conducting the assessment mission itself

Symmetric and Programmable Multi-Chip Module for Low-Power Prototyping System

OpenAIRE

Yen, Mao-Hsu; Chen, Sao-Jie; Lan, Sanko H.

2001-01-01

The advantages of a Multi-Chip Module (MCM) product are its low-power and small-size. But the design of an MCM system usually requires weeks of engineering effort, thus we need a generic MCM substrate with programmable interconnections to accelerate system prototyping. In this paper, we propose a Symmetric and Programmable MCM (SPMCM) substrate for this purpose. This SPMCM substrate consists of a symmetrical array of slots for bare-chip attachment and Field Programmable Interco...

Step-wise stimulated martensitic transformations

International Nuclear Information System (INIS)

Airoldi, G.; Riva, G.

1991-01-01

NiTi alloys, widely known both for their shape memory properties and for unusual pseudoelastic behaviour, are now on the forefront attention for step-wise induced memory processes, thermal or stress stimulated. Literature results related to step-wise stimulated martensite (direct transformation) are examined and contrasted with step-wise thermal stimulated parent phase (reverse transformation). Hypothesis are given to explain the key characters of both transformations, a thermodynamic model from first principles being till now lacking

Manpower development for the nuclear power programme in Bangladesh

International Nuclear Information System (INIS)

Hossain, A.; Rahman, M.A.; Quaiyum, M.A.

1978-01-01

Surveys undertaken in the early sixties established that nuclear power had a great potential for meeting energy demands in Bangladesh. Therefore, since then the development of the requisite manpower for producing nuclear power in the country has been supported by the authorities. Through the co-operation of the IAEA and national and international agencies, Bangladesh has been able to create a corps of scientists and engineers trained at M.Sc. and Ph.D. levels in various nuclear science and technology disciplines. Some are professional nuclear engineers who have participated in the planning, safety evaluation, construction, commissioning and the subsequent operation of nuclear power plants. This paper reviews the present activities and the future plans for developing qualified manpower for Bangladesh's nuclear power programme. The difficulties in developing skilled manpower are also discussed. Overall manpower requirements have been evaluated. It has been found that in certain areas, such as quality control and quality assurance, BAEC has no trained personnel, and existing trained manpower falls short in requirements. Hence, recruitment is being done and training in selected areas is being arranged under different IAEA and bilateral assistance programmes, and a national nuclear training institution with adequate facilities is being established. (author)

Stepwise Nanopore Evolution in One-Dimensional Nanostructures

KAUST Repository

Choi, Jang Wook

2010-04-14

We report that established simple lithium (Li) ion battery cycles can be used to produce nanopores inside various useful one-dimensional (1D) nanostructures such as zinc oxide, silicon, and silver nanowires. Moreover, porosities of these 1D nanomaterials can be controlled in a stepwise manner by the number of Li-battery cycles. Subsequent pore characterization at the end of each cycle allows us to obtain detailed snapshots of the distinct pore evolution properties in each material due to their different atomic diffusion rates and types of chemical bonds. Also, this stepwise characterization led us to the first observation of pore size increases during cycling, which can be interpreted as a similar phenomenon to Ostwald ripening in analogous nanoparticle cases. Finally, we take advantage of the unique combination of nanoporosity and 1D materials and demonstrate nanoporous silicon nanowires (poSiNWs) as excellent supercapacitor (SC) electrodes in high power operations compared to existing devices with activated carbon. © 2010 American Chemical Society.

Managing Environmental Impact Assessment for Construction and Operation in New Nuclear Power Programmes

International Nuclear Information System (INIS)

2014-01-01

This publication describes the environmental impact assessment (EIA) process, its utilization and the necessary infrastructure for such a process in order to provide a holistic approach for EIA in new nuclear power programmes. It also emphasizes the environmental aspects unique to a nuclear power programme, assuming that a State embarking on such a programme already has an environmental regulatory framework for the industrial projects in place. This publication also describes the phased implementation of the EIA programme in accordance with the phases described in IAEA Nuclear Energy Series No. NG-G-3.1. This publication is addressed to senior managers, project managers or coordinators and technical specialists of government authorities and agencies, including regulatory bodies, operating organizations and supporting industries, and other organizations involved in environmental issues

Occupational exposures at nuclear power plants. Fourteenth annual report of the ISOE programme, 2004

International Nuclear Information System (INIS)

2006-01-01

The ISOE Programme was created by the OECD Nuclear Energy Agency in 1992 to promote and co-ordinate international co-operative undertakings in the area of worker protection at nuclear power plants. The programme provides experts in occupational radiation protection with a forum for communication and exchange of experience. The ISOE databases enable the analysis of occupational exposure data from 478 operating and shutdown commercial nuclear power plants participating in the programme (representing some 90% of the world's total operating commercial reactors). The Fourteenth Annual Report of the ISOE Programme summarises achievements made during 2004 and compares annual occupational exposure data. Principal developments in ISOE participating countries are also described. (author)

Occupational exposures at nuclear power plants. Eleventh annual report of the Isoe programme, 2001

International Nuclear Information System (INIS)

2002-01-01

The ISOE Programme was created by the OECD Nuclear Energy Agency in 1992 to promote and co-ordinate international co-operative undertakings in the area of worker protection at nuclear power plants. The programme provides experts in occupational radiation protection with a forum for communication and exchange of experience. The ISOE databases enable the analysis of occupational exposure data from the 452 commercial nuclear power plants participating in the programme (representing some 90 per cent of the world's total operating commercial reactors). The Eleventh Annual Report of the ISOE Programme summarises achievements made during 2001 and compares annual occupational exposure data. Principal developments in ISOE participating countries are also described. (author)

Collective dose commitments from nuclear power programmes

International Nuclear Information System (INIS)

Beninson, D.

1977-01-01

The concepts of collective dose and collective dose commitment are discussed, particularly regarding their use to compare the relative importance of the exposure from several radiation sources and to predict future annual doses from a continuing practice. The collective dose commitment contributions from occupational exposure and population exposure due to the different components of the nuclear power fuel cycle are evaluated. A special discussion is devoted to exposures delivered over a very long time by released radionuclides of long half-lives and to the use of the incomplete collective dose commitment. The maximum future annual ''per caput'' doses from present and projected nuclear power programmes are estimated

Numerical study of radial stepwise fuel load reshuffling traveling wave reactor

International Nuclear Information System (INIS)

Zhang Dalin; Zheng Meiyin; Tian Wenxi; Qiu Suizheng; Su Guanghui

2015-01-01

Traveling wave reactor is a new conceptual fast breeder reactor, which can adopt natural uranium, depleted uranium and thorium directly to realize the self sustainable breeding and burning to achieve very high fuel utilization fraction. Based on the mechanism of traveling wave reactor, a concept of radial stepwise fuel load reshuffling traveling wave reactor was proposed for realistic application. It was combined with the typical design of sodium-cooled fast reactors, with which the asymptotic characteristics of the inwards stepwise fuel load reshuffling were studied numerically in two-dimension. The calculated results show that the asymptotic k_e_f_f parabolically varies with the reshuffling cycle length, while the burnup increases linearly. The highest burnup satisfying the reactor critical condition is 38%. The power peak shifts from the fuel discharging zone (core centre) to the fuel uploading zone (core periphery) and correspondingly the power peaking factor decreases along with the reshuffling cycle length. In addition, at the high burnup case the axial power distribution close to the core centre displays the M-shaped deformation. (authors)

Realizing vision of Dr. Homi Bhabha - first stage of nuclear power programme

International Nuclear Information System (INIS)

Bhardwaj, S.A.

2009-01-01

Full text: Dr. Homi Bhabha had a vision to harness nuclear energy for peaceful uses of mankind. Considering typical nuclear resources in the country, Dr Bhabha conceptualized the three stage nuclear power programme and gave a road map for its implementation. The robustness of the vision is such that the programme has not undergone a change in last five decades. The first stage of the three-stage programme, based on natural uranium fuelled Pressurised Heavy Water Reactors (PHWRs) has been precursor to the nuclear power programme in India. This paper describes the developments in the last five decades. The establishment of research laboratories and reactors, training school for the manpower needs, industrial infrastructure and establishment of regulatory framework are briefly described. Setting up of first nuclear power reactor in the country as turnkey project and experience on operation of these reactors in India are discussed. The learning phase consisting of setting up of first PHWR in technical collaboration with Canada and design of 220 MWe PHWRs for MAPS is described. The safety features consistent with development of nuclear power globally were incorporated in Narora design and this became a standardized 220 MWe reactor of which many PHWRs of 220 MWe were set up. The experiences with operation of these small size reactors leading to internationally best operational experience in the year 2002 are discussed. The efforts of plant life extension, in-core maintenance jobs and other renovation and modernization jobs are discussed. The increase in unit size of 540 MWe, of which two reactors have been already set up, is explained in detail. The economies of scale demanded increase in the unit size and design of 700 MWe PHWR has been established and the salient features of this design are also discussed in detail. Eight reactors of 700 MWe each would complete the first stage of about 10,000 MWe PHWR programme and plans for setting up of these reactors are discussed

Human Resource Development for Introducing and Expanding Nuclear Power Programmes. Summary of an International Conference

International Nuclear Information System (INIS)

2012-01-01

Currently, the world is witnessing a resurgence of interest in nuclear power. More than fifty Member States, with support from the IAEA, are considering the introduction of nuclear power, and human resource development is one of the crucial areas in terms of requests for support. The need for human resources in the nuclear sector is not only experienced by countries embarking on new nuclear power programmes, but also by countries with existing programmes that are considering expansion, as many current professionals are approaching retirement age and the number of newly trained staff is generally not sufficient to meet the potential demand. The IAEA conference on Human Resource Development for Introducing and Expanding Nuclear Power Programmes was held from 14 to 18 March 2010 in Abu Dhabi, hosted by the Government of the United Arab Emirates. This conference was organized to address work force issues faced by countries which are embarking on new nuclear power programmes, expanding current programmes or planning to supply nuclear technology to other countries. The situation is different for each country; some need to develop their own local expertise, while others need to scale up existing educational and training programmes to increase the number of professionals. The purpose of this conference was to bring together Member States to help formulate country specific policies on human resource development, education, training and knowledge management to help support each country's nuclear power programme. In addition, the IAEA can facilitate better use of other educational opportunities, including research reactors and development of training facilities. These proceedings highlight the key findings and recommendations of the meeting and the conclusions of the chairperson. All papers presented and discussed during the meeting are included on the attached CD-ROM. To access the papers, click on 'Index' on the CD-ROM.

Human Resource Development for Introducing and Expanding Nuclear Power Programmes. Summary of an International Conference

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-10-15

Currently, the world is witnessing a resurgence of interest in nuclear power. More than fifty Member States, with support from the IAEA, are considering the introduction of nuclear power, and human resource development is one of the crucial areas in terms of requests for support. The need for human resources in the nuclear sector is not only experienced by countries embarking on new nuclear power programmes, but also by countries with existing programmes that are considering expansion, as many current professionals are approaching retirement age and the number of newly trained staff is generally not sufficient to meet the potential demand. The IAEA conference on Human Resource Development for Introducing and Expanding Nuclear Power Programmes was held from 14 to 18 March 2010 in Abu Dhabi, hosted by the Government of the United Arab Emirates. This conference was organized to address work force issues faced by countries which are embarking on new nuclear power programmes, expanding current programmes or planning to supply nuclear technology to other countries. The situation is different for each country; some need to develop their own local expertise, while others need to scale up existing educational and training programmes to increase the number of professionals. The purpose of this conference was to bring together Member States to help formulate country specific policies on human resource development, education, training and knowledge management to help support each country's nuclear power programme. In addition, the IAEA can facilitate better use of other educational opportunities, including research reactors and development of training facilities. These proceedings highlight the key findings and recommendations of the meeting and the conclusions of the chairperson. All papers presented and discussed during the meeting are included on the attached CD-ROM. To access the papers, click on 'Index' on the CD-ROM.

Pressurised water reactor. A critique of the Government's nuclear power programme

Energy Technology Data Exchange (ETDEWEB)

Flood, M; Chudleigh, R; Conroy, C

1981-01-01

The subject is covered in sections, entitled: energy forecasts - their decline and fall (Department of Energy; electricity supply industry; the writing on the wall); nuclear economics - how the dream dissolved (Britain's programme - off to a bad start; the government's programme -a catastrophe about to be repeated; the cost of a British PWR; a new choice - nuclear power versus insulation); PWR safety - the unresolvable problem (one in a million (query); fundamental weaknesses; consequences of an accident; unresolved safety problems; the select committee's findings); a new energy strategy - catering for our needs (energy efficiency; district heating/combined heat and power; solar heating; liquid fuels; the international context); conclusions.

The role of nuclear research centers for the introduction of a nuclear power programme

International Nuclear Information System (INIS)

Perovic, B.; Frlec, B.; Kundic, V.

1977-01-01

Full development of nuclear energy has imposed a new role on nuclear energy centers. Nuclear technology for different reactor concepts is also now in a phase of high development. Several reactor concepts have been developed for industrial use and electric power production. Development of fast reactors is still under way and needs further research efforts. Having in mind these two main guidelines, research programmes in nuclear energy centers should be geared to the development of the activities vital to the implementation of national nuclear energy programmes. In this respect, national nuclear centers should devote their attention to three major tasks. First, to establish a background for the introduction of nuclear energy into the national energy system and to support a national safety system. Second, to support the national programme by skilled manpower, to provide the basic training in nuclear technology for future staff of nuclear power stations and to assist the universities in establishing the necessary educational programme in nuclear energy. Third, to follow the development of nuclear energy technology for the fast breeder reactor concepts. This paper describes some experience in introducing a new programme to the national nuclear energy centers in Yugoslavia. Recently, Yugoslavia has started building its first nuclear power station. Further introduction of nuclear power stations in the national electric energy system is also planned. This implies the need to reconsider the current nuclear energy programme in the nuclear energy centers. It has been decided to evaluate past experience and further needs for research activities regarding the nuclear power programme. Yugoslavia has three main nuclear energy centers whose activities are devoted to the development of national manpower in the field of nuclear sciences. Besides these three organizations, there are several others whose activities are concentrated on specific tasks in nuclear technology. In the

Green power certification: environmental and consumer protection benefits of the Green-e programme

Energy Technology Data Exchange (ETDEWEB)

Wingate, M.; Hamrin, J. [Center for Resource Solutions (United States); Rabago, K. [Rocky Mountain Inst. (United States); Wiser, R. [Lawrence Berkeley National Lab. (United States)

2000-06-01

This article gives details of the Green-e environmental certification programme which certifies electricity generated from renewable energy sources in the US. This first non-profit certification programme originally was set up for California, and has now spread to other regions. The objectives of the Green-e programme, the need for the electricity product to meet minimum criteria to qualify, marketer requirements, verification of product claims, administration of the programme, and the second year programme results are discussed. The way in which the Green-e programme fits in with other programmes such as those set up by the state and federal customer protection agencies to help consumers select environmentally superior power is described.

Developing industrial infrastructures to support a programme of nuclear power

International Nuclear Information System (INIS)

1988-01-01

This Guidebook is intended to offer assistance in the many considerations and decisions involved in preparing the national industry for participation in a nuclear power programme. The heavy financial investment, the setting up of certain infrastructures many years ahead of plant construction, plus the high level of technology involved require early and systematic planning. A further purpose of this Guidebook is to serve particularly those decision makers and planners in the various governmental authorities, the technological institutions and in the industries likely to be involved in a nuclear project. These industries include the services of the national engineering resources, the domestic design and manufacturing groups as well as the civil construction companies. These will be responsible for plant erection, testing and commissioning and most of all for the establishment of a framework for quality assurance. All of these are the components of an essential infrastructure necessary to raise the standards of the national industry and to displace increasingly foreign suppliers to the extent possible. In addition, this Guidebook should help to show some of the implications, consequences and options involved in a nuclear power programme. It does not consider the basic decisions for going nuclear, nor does it review the choice of the technology or nuclear process selected for the programme. Instead, it limits itself to a consideration of the nuclear power plant and its essential cycle activities. Figs and tabs

A Review of Fast Reactor Programme in India, April 1930

International Nuclear Information System (INIS)

Paranjpe, S.R.

1980-01-01

Nuclear energy has to play a significant role in the energy resources of India in the next century. To-day's apparently vast reserves of fossil fuels would be under severe strain due to rapidly increasing demand for energy. Long-term perspective planning requires Nuclear Energy to play a significant role from early part of the next century and share a major load. But, India is not endowed with vast reserves of uranium and must therefore aim to utilise more abundant thorium reserves which are estimated to be about 350,000 tonnes. Department of Atomic Energy which is responsible for the development of nuclear energy in India has therefore planned a step-wise approach consisting of: (i) First phase of the programme of natural uranium based thermal reactors to produce power and plutonium which is the basis of the next phase. (ii) Second phase of the programme to produce power and breed more and more plutonium through fast breeder deployment so as to build sufficient inventories of fissile material which can then become the basis of the third stage. (iii) To utilise thorium with the help of fissile material produced by 2nd phase of Breeder Reactors

A Review of Fast Reactor Programme in India, April 1930

Energy Technology Data Exchange (ETDEWEB)

Paranjpe, S. R. [Reactor Research Centre Kalpakkam, Tamil Nadu (India)

1980-10-15

Nuclear energy has to play a significant role in the energy resources of India in the next century. To-day's apparently vast reserves of fossil fuels would be under severe strain due to rapidly increasing demand for energy. Long-term perspective planning requires Nuclear Energy to play a significant role from early part of the next century and share a major load. But, India is not endowed with vast reserves of uranium and must therefore aim to utilise more abundant thorium reserves which are estimated to be about 350,000 tonnes. Department of Atomic Energy which is responsible for the development of nuclear energy in India has therefore planned a step-wise approach consisting of: (i) First phase of the programme of natural uranium based thermal reactors to produce power and plutonium which is the basis of the next phase. (ii) Second phase of the programme to produce power and breed more and more plutonium through fast breeder deployment so as to build sufficient inventories of fissile material which can then become the basis of the third stage. (iii) To utilise thorium with the help of fissile material produced by 2nd phase of Breeder Reactors.

Radiation protection programme at Krsko nuclear power plant

International Nuclear Information System (INIS)

Breznik, B.

1996-01-01

Krsko NPP, a Westinghouse two-loop PWR of 632 M We power, is in commercial operation since 1982. Reduction of radioactive releases to the environment and the reduction of doses to workers is the basic goal in the plant radiological protection. The radiation protection programme is established to ensure that the radiation exposures to workers and members of the public are minimized according to the As Low As Reasonably Achievable approach and controlled in accordance with international safety standards and Slovenian regulations. The basis for the operational and technical measures has been provided according to the industrial good practice. The effluent control is based on the Standard Radioactive Effluent Technical Specifications, and environmental surveillance is established according to the programme defined by the regulations. The dose constraints and performance indicators are used to assure the effectiveness of the radiation protection programme and provide a convenient follow-up tool. The monitoring programme results of each year show that there is no measurable dose to the public due to radioactive releases. The commitment to the dose burden of any member of a critical group is assessed to be below the dose constraint. Individual and collective doses of the workers are within a range typical for the PWRs of a similar type. (author)

Nuclear power programmes in developing countries: Costs and financing

International Nuclear Information System (INIS)

Charpentier, J.P.; Bennett, L.L.

1985-01-01

This article refers to a seminar (organized by the IAEA) on Costs and Financing of Nuclear Power Programmes in Developing Countries held in Vienna from 9-12 September 1985. Its main objective was to promote a dialogue among the various parties involved in the domain of nuclear power financing, i.e. buyers, suppliers and financing organizations. At the meeting the Agency presented information showing that nuclear power plants are an economic means of generating electricity. In relation hereto the article deals with such topics as performance records, economic records, projected nuclear plant additions, financing constraints, current debt problems and new working relationships

Using a Voltage Domain Programmable Technique for Low-Power Management Cell-Based Design

Directory of Open Access Journals (Sweden)

Ching-Hwa Cheng

2011-09-01

Full Text Available The Multi-voltage technique is an effective way to reduce power consumption. In the proposed cell-based voltage domain programmable (VDP technique, the high and low voltages applied to logic gates are programmable. The flexible voltage domain reassignment allows the chip performance and power consumption to be dynamically adjusted. In the proposed technique, the power switches possess the feature of flexible programming after chip manufacturing. This VDP method does not use an external voltage regulator to regulate the supply voltage level from outside of the chip but can be easily integrated within the design. This novel technique is proven by use of a video decoder test chip, which shows 55% and 61% power reductions compared to conventional single-Vdd and low-voltage designs, respectively. This power-aware performance adjusting mechanism shows great power reduction with a good power-performance management mechanism.

A Matlab program for stepwise regression

Directory of Open Access Journals (Sweden)

Yanhong Qi

2016-03-01

Full Text Available The stepwise linear regression is a multi-variable regression for identifying statistically significant variables in the linear regression equation. In present study, we presented the Matlab program of stepwise regression.

Some aspects of programmable digital systems usage in nuclear power plants

International Nuclear Information System (INIS)

Mandic, D.; Smolej, M.; Sucic, B.

2004-01-01

During the operation of the NPP Krsko - NEK and other nuclear power plants, it has been recognized that certain issues related to the usage of digital equipment and associated software in NPP technological process protection, control and monitoring, are usually not adequately addressed in the existing programs and procedures. Moreover, often the problems related to the programmable digital systems usage are not understood correctly, which means that they can not be treated properly. Owing to the specifics of the programmable digital systems usage they have to be treated in a different way than other plant equipment and related documentation. The term as well as the process of Process Computers Configuration Control was introduced to control, among other issues, three 10CFR50 Appendix B quality requirements related to the Process Computers application in NPP: Design Control, Document Control, Identification and Control of Materials, Parts and Components. Based on the experience from NEK and published experience from other NPP and other organizations, this paper sheds light on specifics of the programmable digital systems usage in nuclear power plants. The wording Programmable Digital Systems was used rather than Process Computers, to emphasize wide area of applicability of this term: from simple digital components with burned-in programs to the PLC (Programmable Logic Controllers) and large process computer systems. In order to satisfy requirements of the Process Computer Configuration Control, specific characteristics and specific problems related to the usage of programmable digital systems require specific treatment of these issues. This paper describes those specific characteristics and traditional misunderstandings, false beliefs, false expectations and common errors that are most frequently committed in the life cycle of the programmable digital systems, as well as consequences and problems that could develop. The paper also refers to the regulations, industry

Final report of the programme on the safety of WWER and RBMK nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

International Nuclear Information System (INIS)

1999-05-01

The review of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants focuses on the wide scope of the activities aimed at identifying safety deficiencies, ranking their importance on the results of safety improvement programmes and on areas where future work is necessary. The information in the report reflects to a large extent, the situation as it stood when individual IAEA tasks actually took place. It deals with the IAEA activities and it discusses selected safety issues and safety review results as they apply to each reactor type. The results, recommendations and conclusions resulting from the IAEA Programme are intended to assist national decision makers who have the sole responsibilities for the regulation and safety operation of their nuclear power plants

Occupational exposures at nuclear power plants. Twelfth annual report of the Isoe programme, 2002

International Nuclear Information System (INIS)

2004-01-01

The Information System on Occupational Exposure (ISOE) was created by the OECD Nuclear Energy Agency in 1992 to promote and co-ordinate international co-operative undertakings in the area of worker protection at nuclear power plants. The ISOE Programme provides experts in occupational radiation protection with a forum for communication and exchange of experience. The ISOE databases enable the analysis of occupational exposure data from the 465 commercial nuclear power plants participating in the Programme (representing some 90 per cent of the world's total operating commercial reactors). The Twelfth Annual Report of the ISOE Programme summarises achievements made during 2002 and compares annual occupational exposure data. Principal developments in ISOE participating countries are also described. (author)

The Indian nuclear power programme: Challenges in PHWR technology

International Nuclear Information System (INIS)

Prasad, Y.S.R.

1997-01-01

The long-term strategy for development of nuclear power generation in India is based on a three-stage programme, formulated by Dr. H.J. Bhabha. This strategy takes into account and is optimally suited for achieving self reliance in nuclear technology; India's technological infrastructure; limited resources of Natural Uranium and abundant availability of Thorium within the country

The Swedish approach to spent fuel disposal - stepwise implementation

International Nuclear Information System (INIS)

Gustaffson, B.

1997-01-01

This presentation describes the stepwise implementation of direct disposal of spent fuel in Sweden. The present status regarding the technical development of the Swedish concept will be discussed as well the local site work made in co-operation with the affected and concerned municipalities. In this respect it should be noted that the siting work in some cases has caused heavy opposition and negative opinions. A brief review will also be given regarding the Aspo Hard Rock Laboratory. The objectives of this laboratory as well as the ongoing demo-project will be discussed. In order to give the symposium organizer a more broad view of the Swedish programme a number of recent papers has been compiled. Theses papers will be summarized in the presentation. (author). 4 tabs., 22 figs

Enhanced eumelanin emission by stepwise three-photon excitation

Science.gov (United States)

Kerimo, Josef; Rajadhyaksha, Milind; DiMarzio, Charles A.

2011-03-01

Eumelanin fluorescence from Sepia officinalis and black human hair was activated with near-infrared radiation and multiphoton excitation. A third order multiphoton absorption by a step-wise process appears to be the underlying mechanism. The activation was caused by a photochemical process since it could not be reproduced by simple heating. Both fluorescence and brightfield imaging indicate the near-infrared irradiation caused photodamage to the eumelanin and the activated emission originated from the photodamaged region. At least two different components with about thousand-fold enhanced fluorescence were activated and could be distinguished by their excitation properties. One component was excited with wavelengths in the visible region and exhibited linear absorption dependence. The second component could be excited with near-infrared wavelengths and had a third order dependence on the laser power. The third order dependence is explained by a step-wise excited state absorption (ESA) process since it could be observed equally with the CW and femtosecond lasers. The new method for photoactivating the eumelanin fluorescence was used to map the melanin content in human hair.

Programmable Power Supply for AC Switching Magnet of Proton Accelerator

CERN Document Server

Jeong, Seong-Hun; Kang Heung Sik; Lee, Chi-Hwan; Lee, Hong-Gi; Park, Ki-Hyeon; Ryu, Chun-Kil; Sik Han, Hong; Suck Suh, Hyung

2005-01-01

The 100-MeV PEFP proton linac has two proton beam extraction lines for user' experiment. Each extraction line has 5 beamlines and has 5 Hz operating frequency. An AC switching magnet is used to distribute the proton beam to the 5 beamlines, An AC switching magnet is powered by PWM-controlled bipolar switching-mode converters. This converter is designed to operate at ±350A, 5 Hz programmable step output. The power supply is employed IGBT module and has controlled by a DSP (Digital Signal Process). This paper describes the design and test results of the power supply.

Development of the national nuclear programme and preparations for the introduction of nuclear power in Hungary

International Nuclear Information System (INIS)

Szili, G.; Erdosi, N.; Varga, I.; Ocsai, M.; Szabo, B.

1977-01-01

Hungary's energy situation, energy policy and its interest in the use of nuclear energy are reviewed and the main nuclear power programme targets for the medium term (by 1990) and long term (by 2000) are given. Preparatory steps for the introduction of nuclear energy are outlined, emphasizing the important areas of the preparatory programme. A short technical description is given of Hungary's first nuclear power plant, the Paks Nuclear Power Station, including the preparations for construction and erection, the present construction plan, fuel supply, basic technical aspects of safety, and the social consequences of the plant's erection. The problems involved in the introduction of nuclear energy that must be solved by the state administration are summarized. A review is given of earlier legislation on projects and works representing a radiation hazard; duties are discharged by different state administrations. Additional problems arise from the large-scale use of nuclear energy. These require regulation by the authorities. Preliminary steps have been taken to frame appropriate laws. The activities of the authorities in regard to the practical realization of the first nuclear power station are outlined: there will be a scheduled procedure of authorization. The present potentials and trends in the development and design capacities for energy in general and particularly for nuclear power research are discussed. Hungarian R and D and design resources participate in the joint nuclear power development programme of the CMEA countries. Work is divided amongst various institutes. Preparations being made in the manufacturing, building and construction industries will lead to an expected increase in the domestic share in the construction of future nuclear power plants, compared to the first plant, for which the proportions of foreign and domestic participation are given. Hungary's industry is preparing for the manufacture of nuclear power equipment within the framework of the

Considerations and proposals for a LAWI-RED-programme

International Nuclear Information System (INIS)

Krug, W.

1994-01-01

The capability of LAWI offers the possibility of use Lawi as a tool for an extensive test programme before starting the radioactive operation. This programme includes the incineration of specific kinds of waste with local- and country-specific compositions. Based on results and experiences gained from this programme a stategy for waste removal is to be elaborated for the application of incinerator plants of proper capacities at suitable sites. The content of this ample and long term 'Incineration Programme', as discussed right now, is summarized. It consists of two parallel branches, the 'Plant Development' as the main line and the 'Energy Utilization'. They will be performed stepwise, as can be seen from the figures and as described below. (orig./HP)

Step-wise refolding of recombinant proteins.

Science.gov (United States)

Tsumoto, Kouhei; Arakawa, Tsutomu; Chen, Linda

2010-04-01

Protein refolding is still on trial-and-error basis. Here we describe step-wise dialysis refolding, in which denaturant concentration is altered in step-wise fashion. This technology controls the folding pathway by adjusting the concentrations of the denaturant and other solvent additives to induce sequential folding or disulfide formation.

Planning and development of the Spanish nuclear power programme

International Nuclear Information System (INIS)

Lopez-Rodriguez, M.

1983-01-01

The paper analyses the Spanish nuclear power programme from its inception to the present time, doing so within the context of the country, characterized by the fairly rapid change from a basically agricultural economy to an economy in which industry and services play an important part and the transformation of which took place mainly during the decade prior to the energy crisis 1973. Reference is made to the early establishment of the Junta de Energia Nuclear (Nuclear Energy Board) (JEN), which was set up as a research body even before nuclear energy became competitive with other sources for the production of electric power and which, by adapting its structure and programmes to the different phases in the development and utilization of nuclear energy in the country, contributed the necessary scientific, technical and legal infrastructure. There is also an analysis of the most striking features of the Spanish energy system and an account of the planning and construction of the first three Spanish nuclear power stations. A further subject of discussion is the energy planning and development projects devised by the Government which gave rise to the second generation of nuclear power plants, some of which are already in operation and the remainder in an advanced state of construction. Emphasis is placed on the action taken by the Spanish Government to increase the participation of Spanish industry in the construction of nuclear power plants and in the supply of equipment and services required for their operation. Reference is made to the experimental changes which have been made in the institutional infrastructure in order to adapt it to the phase of development which has been reached and to the objectives subsequently laid down in the planning: establishment of ENUSA (the national uranium enterprise), the Equipos Nucleares corporation and the Nuclear Safety Council, and also the changes made in the JEN

SAFIR2014. The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014. Interim Report

Energy Technology Data Exchange (ETDEWEB)

Simola, K. [ed.

2013-02-15

The Finnish Nuclear Power Plant Safety Research Programme 2011-2014, SAFIR2014, is a 4-year publicly funded national technical and scientific research programme on the safety of nuclear power plants. The programme is funded by the State Nuclear Waste Management Fund (VYR), as well as other key organisations operating in the area of nuclear energy. The programme provides the necessary conditions for retaining knowledge needed for ensuring the continuance of safe use of nuclear power, for developing new know-how and for participation in international co-operation. The SAFIR2014 Steering Group, responsible of the strategic alignements of the programme, consists of representatives of the Finnish Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oy (Fortum), Fennovoima Oy, Lappeenranta University of Technology (LUT), Aalto University (Aalto), Finnish Funding Agency for Technology and Innovation (Tekes), Finnish Institute of Occupational Health (TTL) and the Swedish Radiation Safety Authority (SSM). The research programme is divided into nine areas: Man, organisation and society, Automation and control room, Fuel research and reactor analysis, Thermal hydraulics, Severe accidents, Structural safety of reactor circuits, Construction safety, Probabilistic risk analysis (PRA), and Development of research infrastructure. A reference group is assigned to each of these areas to respond for the strategic planning and to supervise the projects in its respective field. Research projects are selected annually based on a public call for proposals. Most of the projects are planned for the entire duration of the programme, but there can also be shorter one- or two-year projects. The annual volume of the SAFIR2014 programme in 2011-2012 has been 9,5-9,9 M euro. Main funding organisations were the State Nuclear Waste Management Fund (VYR) with over 5 M euro and

SAFIR2014. The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014. Interim Report

International Nuclear Information System (INIS)

Simola, K.

2013-02-01

The Finnish Nuclear Power Plant Safety Research Programme 2011-2014, SAFIR2014, is a 4-year publicly funded national technical and scientific research programme on the safety of nuclear power plants. The programme is funded by the State Nuclear Waste Management Fund (VYR), as well as other key organisations operating in the area of nuclear energy. The programme provides the necessary conditions for retaining knowledge needed for ensuring the continuance of safe use of nuclear power, for developing new know-how and for participation in international co-operation. The SAFIR2014 Steering Group, responsible of the strategic alignements of the programme, consists of representatives of the Finnish Nuclear Safety Authority (STUK), Ministry of Employment and the Economy (MEE), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oyj (TVO), Fortum Power and Heat Oy (Fortum), Fennovoima Oy, Lappeenranta University of Technology (LUT), Aalto University (Aalto), Finnish Funding Agency for Technology and Innovation (Tekes), Finnish Institute of Occupational Health (TTL) and the Swedish Radiation Safety Authority (SSM). The research programme is divided into nine areas: Man, organisation and society, Automation and control room, Fuel research and reactor analysis, Thermal hydraulics, Severe accidents, Structural safety of reactor circuits, Construction safety, Probabilistic risk analysis (PRA), and Development of research infrastructure. A reference group is assigned to each of these areas to respond for the strategic planning and to supervise the projects in its respective field. Research projects are selected annually based on a public call for proposals. Most of the projects are planned for the entire duration of the programme, but there can also be shorter one- or two-year projects. The annual volume of the SAFIR2014 programme in 2011-2012 has been 9,5-9,9 M euro. Main funding organisations were the State Nuclear Waste Management Fund (VYR) with over 5 M euro and

The role of wind energy in the programme of power supply of northern Russia territories

Energy Technology Data Exchange (ETDEWEB)

Bezroukikh, P [Ministry for Fuel and Energy, Moscow (Russian Federation)

1996-12-31

In this article examined technical, management and economic problems has been arising during working out of above mentioned Power Supply Programm based on the renewable energy sources usage and proved the leading role of wind energy in this Programm. (author)

The role of wind energy in the programme of power supply of northern Russia territories

Energy Technology Data Exchange (ETDEWEB)

Bezroukikh, P. [Ministry for Fuel and Energy, Moscow (Russian Federation)

1995-12-31

In this article examined technical, management and economic problems has been arising during working out of above mentioned Power Supply Programm based on the renewable energy sources usage and proved the leading role of wind energy in this Programm. (author)

The role of wind energy in the programme of power supply of northern Russia territories

International Nuclear Information System (INIS)

Bezroukikh, P.

1995-01-01

In this article examined technical, management and economic problems has been arising during working out of above mentioned Power Supply Programm based on the renewable energy sources usage and proved the leading role of wind energy in this Programm. (author)

Programme of Preparatory Activities on Launching First Nuclear Power Plant in Croatia

International Nuclear Information System (INIS)

Jakic, I.; Lebegner, J.; Perovic, N.

2010-01-01

New Croatian energy policy recognizes nuclear energy as solution for rising needs for energy and, thus, opens the possibility to construct first nuclear power plant in Croatia. Within this frame, the Croatian government is developing an implementation programme according to this policy and preparing basis for making decision about construction of nuclear power plant. Croatian parliament is responsible for this decision which is expected by the end of 2012. During this period, stake holders in this project (government, regulatory body and future operator of the plant) have to complete activities of preparatory phase of Croatian Nuclear Energy Programme (CRONEP) project according to methodology recommended by IAEA (International Atomic Energy Agency). This paper defines these activities and estimate the costs of first, preparatory phase based on previous experience of other countries which finished the phase successfully. Also, it describes the potential role of Croatian utility as stake holder due to its experience as co-owner of Nuclear power plant Krsko.(author).

International Conference on Human Resource Development for Nuclear Power Programmes: Building and Sustaining Capacity. Presentations

International Nuclear Information System (INIS)

2014-01-01

The objectives of the conference are to: • Review developments in the global status of HRD since the 2010 international conference; • Emphasize the role of human resources and capacity building programmes at the national and organizational level for achieving safe, secure and sustainable nuclear power programmes; • Discuss the importance of building competence in nuclear safety and security; • Provide a forum for information exchange on national, as well as international, policies and practices; • Share key elements and best practices related to the experience of Member States that are introducing, operating or expanding nuclear power programmes; • Highlight the practices and issues regarding HRD at the organizational and national level; • Highlight education and training programmes and practices; • Emphasize the role of nuclear knowledge management for knowledge transfer and HRD; and • Elaborate on the role and scope of various knowledge networks

Regulatory issues on using programmable logic device in nuclear power plants

International Nuclear Information System (INIS)

Park, G. Y.; Yu, Y. J.; Kim, H. T.; Kwon, Y. I.; Park, H. S.; Jeong, C. H.

2012-01-01

For replacing obsolete analog equipment in nuclear power plant, the Programmable Logic Devices (PLDs) using Hardware Description Language (HDL) have been widely adopted in digitalized Instrumentation and Control (I and C) systems because of its flexibility. For safety reviews on Nuclear Power Plants (NPPs,) qualifying digitalized safety I and C system using PLDs is an important issue. As an effort to provide regulatory position on using PLDs in safety I and C system, there is a research project to provide the regulatory positions against emerging issues involved with digitalisation of I and C system including using PLDs. Therefore, this paper addresses the important considerations for using PLDs in safety I and C systems such as diversity, independence and qualification, etc. In this point, this study focuses on technical reports for Field Programmable Gate Array (FPGA) from EPRI,. U.S. NRC, and relevant technical standards

Regulatory issues on using programmable logic device in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Park, G. Y.; Yu, Y. J.; Kim, H. T.; Kwon, Y. I.; Park, H. S.; Jeong, C. H. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2012-10-15

For replacing obsolete analog equipment in nuclear power plant, the Programmable Logic Devices (PLDs) using Hardware Description Language (HDL) have been widely adopted in digitalized Instrumentation and Control (I and C) systems because of its flexibility. For safety reviews on Nuclear Power Plants (NPPs,) qualifying digitalized safety I and C system using PLDs is an important issue. As an effort to provide regulatory position on using PLDs in safety I and C system, there is a research project to provide the regulatory positions against emerging issues involved with digitalisation of I and C system including using PLDs. Therefore, this paper addresses the important considerations for using PLDs in safety I and C systems such as diversity, independence and qualification, etc. In this point, this study focuses on technical reports for Field Programmable Gate Array (FPGA) from EPRI,. U.S. NRC, and relevant technical standards.

ANYOLS, Least Square Fit by Stepwise Regression

International Nuclear Information System (INIS)

Atwoods, C.L.; Mathews, S.

1986-01-01

Description of program or function: ANYOLS is a stepwise program which fits data using ordinary or weighted least squares. Variables are selected for the model in a stepwise way based on a user- specified input criterion or a user-written subroutine. The order in which variables are entered can be influenced by user-defined forcing priorities. Instead of stepwise selection, ANYOLS can try all possible combinations of any desired subset of the variables. Automatic output for the final model in a stepwise search includes plots of the residuals, 'studentized' residuals, and leverages; if the model is not too large, the output also includes partial regression and partial leverage plots. A data set may be re-used so that several selection criteria can be tried. Flexibility is increased by allowing the substitution of user-written subroutines for several default subroutines

Manpower requirements for nuclear power programmes in nations of intermediate capacity

International Nuclear Information System (INIS)

Cantarell, I.; Cerrolaza, J.A.; Llado, J.M.

1980-01-01

A study is made of the manpower required for initiating and carrying out a nuclear power programme in countries which have not developed their own nuclear technology but where the technical and economic level is such to permit a substantial input from local industry. The discussion is based on Spanish experience. The three basic elements in a nuclear programme are taken to be the operating company, the regulating authority and the engineering firm involved. The role of each of these is briefly considered and the manpower requirements during the design, construction and operational phases of a power station are evaluated. A short account is also given of the manpower requirements of other enterprises such as those involved in the civil engineering, the assembly and construction control. The variations in the labour force are described with the aim of deriving estimates of the number of people involved in the development of a nuclear power programme as a function of time: actual numbers are given for the case of the Spanish national energy plan. A brief description is given of the various courses on nuclear science and engineering provided in Spain and the requirements laid down by the regulations. A short account is given of Spanish nuclear development, with emphasis on the work carried out by the Nuclear Energy Board, not only as a research organization but also in its promotional and training capacities and as a source of personnel for industry. Finally, some comments are made on the possibilities opened up by international co-operation. (author)

The role of nuclear research centres in the introduction of a nuclear power programme

International Nuclear Information System (INIS)

Afgan, N.; Anastasijevic, P.; Kolar, D.; Strohal, P.

1977-01-01

Full development of nuclear energy has imposed a new role on nuclear energy centres. Nuclear technology for different reactor concepts is also now in a phase of high development. Several reactor concepts have been developed for industrial use and electric power production. Development of fast reactors is still under way and needs further research efforts. Having in mind these two main guidelines, research programmes in nuclear energy centres should be geared to the development of the activities vital to the implementation of national nuclear energy programmes. In this respect, national nuclear centres should devote their attention to three major tasks. First, to establish a background for the introduction of nuclear energy into the national energy system and to support a national safety system. Secondly, to support the national programme by skilled manpower, to provide the basic training in nuclear technology for future staff of nuclear power stations and to assist the universities in establishing the necessary educational programme in nuclear energy. Thirdly, to follow the development of nuclear energy technology for fast breeder reactor concepts. (author)

Power programmes review: Nuclear power for India

International Nuclear Information System (INIS)

1959-01-01

India will require a substantial increase in the generation of electrical power to meet the demands of her developing economy. A survey of available resources has been made in the context of development envisaged under the country's five-year plans and it is felt that atomic energy will have to be used in increasing quantities to supplement conventional fuel resources in order to attain the anticipated power targets in the next two decades. It has, therefore, been decided that a small beginning will be made with the erection and commissioning of anatomic power station of 250 MW (electric) capacity by the end of 1964. The installation of a further 750 MW of nuclear power by the end of the third five-year plan period, i.e. by March 1966, is under consideration. Present Pattern and future demand of energy is discussed, as well as available resources and immediate needs. Concerning nuclear fuel cycle and cost estimates it is stated that India's uranium reserves are not large enough to sustain a very long-term programme of power generation, but the reserves for thorium are. Therefore India's nuclear power production will have to be based primarily on thorium with a rather complicated fuel cycles and first, second and third generation atomic power stations. The Atomic Energy Establishment Trombay is India's national centre for research in the peaceful uses of atomic energy. India's first reactor, Apsara, which is of the swimming pool type, has been in operation for more than three years now and two other research reactors are under construction. These are the Canada-India Reactor, which is being built under the Colombo Plan in collaboration with Canada, and Zerlina, which is being designed and built by Indian scientists and engineers. The Canada-India Reactor will be a versatile high flux research reactor and will have facilities in which various power reactor concepts can be tried out in the so-called loop experiments. In addition, it will produce considerable

Power programmes review: Nuclear power for India

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-10-15

India will require a substantial increase in the generation of electrical power to meet the demands of her developing economy. A survey of available resources has been made in the context of development envisaged under the country's five-year plans and it is felt that atomic energy will have to be used in increasing quantities to supplement conventional fuel resources in order to attain the anticipated power targets in the next two decades. It has, therefore, been decided that a small beginning will be made with the erection and commissioning of anatomic power station of 250 MW (electric) capacity by the end of 1964. The installation of a further 750 MW of nuclear power by the end of the third five-year plan period, i.e. by March 1966, is under consideration. Present Pattern and future demand of energy is discussed, as well as available resources and immediate needs. Concerning nuclear fuel cycle and cost estimates it is stated that India's uranium reserves are not large enough to sustain a very long-term programme of power generation, but the reserves for thorium are. Therefore India's nuclear power production will have to be based primarily on thorium with a rather complicated fuel cycles and first, second and third generation atomic power stations. The Atomic Energy Establishment Trombay is India's national centre for research in the peaceful uses of atomic energy. India's first reactor, Apsara, which is of the swimming pool type, has been in operation for more than three years now and two other research reactors are under construction. These are the Canada-India Reactor, which is being built under the Colombo Plan in collaboration with Canada, and Zerlina, which is being designed and built by Indian scientists and engineers. The Canada-India Reactor will be a versatile high flux research reactor and will have facilities in which various power reactor concepts can be tried out in the so-called loop experiments. In addition, it will produce considerable

Periodic safety review of operational nuclear power plants. A publication within the NUSS programme

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide which supplements the IAEA Safety Fundamentals: The Safety of Nuclear Installations and the Code on the Safety of Nuclear Power Plants: Operation, forms part of the Agency's programme, referred to as the NUSS programme, for establishing Codes and Guides relating to nuclear power plants. A list of NUSS publications is given at the end of this book. This Guide was drafted on the basis of a systematic review approach that was endorsed by the IAEA Conference on the Safety of Nuclear Power: Strategy for the Future. The purpose of this Safety Guide is to provide guidance on the conduct of Periodic Safety Reviews (PSRs) for an operational nuclear power plant. The Guide is directed at both owners/operators and regulators. This Safety Guide deals with the PSR of an operational nuclear power plant. A PSR is a comprehensive safety review addressing all important aspects of safety, carried out at regular intervals. 22 refs, 4 figs

Field Programmable Gate Array Control of Power Systems in Graduate Student Laboratories

National Research Council Canada - National Science Library

O'Connor, Joseph E

2008-01-01

...) continuously develops new design and education resources for students. One area of focus for students in the Power Electronics curriculum track is the development of a design center that explores Field Programmable Gate Array (FPGA...

UK experience of planning the nuclear contribution to the UK power programme

International Nuclear Information System (INIS)

Catchpole, S.; Jenkin, F.P.

1977-01-01

The paper outlines U.K. experience in planning nuclear programmes. It examines the factors which have determined the size of such programmes together with those factors which have influenced their implementation. The paper also discusses the role which the utility has played in the deployment of nuclear power in the U.K. At present, nuclear energy can only be utilised on a large scale via the electricity route and the forecasting of electricity demand is therefore a key element in determining the size of the nuclear programme. Other important issues which affect the nuclear contribution are: national fuel policies, discontinuities in price and availability of imported fossil fuels, plant capital costs, fuel price relativities, plant siting, rate of introduction of new nuclear systems, manufacturer's capability, public attitudes towards nuclear power and financing. These issues are dealt with in some detail including their relative importance in the U.K. The paper also discusses the contribution of the various nuclear bodies in the U.K. in securing the implementation of the nuclear programmes. From the inception of nuclear power in the U.K., it has been recognised that a major utility has a central role to play not only in commercial operation but also in the procurement of plant and materials. As explained in the paper this ''informed buyer'' approach, which is being increasingly adopted by other major utilities, calls for an organisation and technical infrastructure far more complex than is the case for fossil plants. The requirements of safety, which is unambiguously the responsibility of the utility, and of high availability of plant operation demand a rigorous approach to design, quality assurance, project management, construction and operation. To this must be added sound research and development and staff training facilities. The paper explains how experience in these vital areas has been built up

Electricite de France Strategy for its nuclear power plants' decommissioning programme

International Nuclear Information System (INIS)

Knockaert, J.M.; Gatineau, J.P.

1992-01-01

Although final shutdown of the first large PWR Power Stations should not occur before 2015, Electricity of France is nevertheless directly concerned by the decommissioning of its nuclear plants. The shutdown programme of the gas-graphite units is in progress and the medium-power PWR plant (300 MWe) installed at Chooz in the Ardennes will be finally shutdown at the end of 1991. This solution requires EDF to have a policy available which enables it to simultaneously run the double operation 'Plant shutdown-decommissioning' and 'New constructions-increasing available power' from both the technical and financial viewpoints. (author)

RATU Nuclear power plant structural safety research programme 1990-1994. Final report

International Nuclear Information System (INIS)

Rintamaa, R.; Sarkimo, M.

1995-12-01

The major part of nuclear energy research in Finland has been organized as five-year nationally coordinated research programmes. The research programme on the Nuclear Power Plant Structural Safety was carried out during the period from 1990 to 1994. The total volume was about 76 person-years and the expenditure about 49 million FIM. Studies on the structural materials in nuclear power plants created the experimental data and background information necessary for the structural integrity assessments of mechanical components. The research was carried out by developing experimental fracture mechanics methods including statistical analysis methods of material property data, and by studying material ageing and, in particular, mechanisms of material deterioration due to neutron irradiation, corrosion and water chemistry. Besides material studies, new testing methods and sensors for the measurement of loading and water chemistry parameters have been developed

The role of national consultant services industries to support the first nuclear power plant programme in Indonesia

International Nuclear Information System (INIS)

Dharu Dewi; Sahala Lumbanraja; Sriyana

2007-01-01

Study has been done which concerning the role of Indonesian National Consultant Services Industries to support the First Nuclear Power Plant (NPP) Programme in Indonesia. NPP programme activities will be success if the studies should be started with good planning. To obtain the optimal results, the opportunity and the role of national consultants should be considered to the localization of NPP Programme to be bigger. Utilizing of national consultants services can be expected to become second opinion which is to play important role in socialization of NPP Programme. The Government and NPP Project Owner's candidate should analysis, plan and implement the Nuclear Power Plant Programme activities, started from identification of the available national consultants, considering the national consults procurement process, definition of scope of works of national consultants activities, carry out the selection of national consultants, evaluation, monitoring and supervision so that the utilizing of national consultants will give benefit more effective, efficient, economic appropriate objectives and good quality. This study to assess the structure and type of national consultants, works package which can be done by national consultants, selection methods of national consultants, constraints of national consultants and enhancing of the role of national consultants to involve and support in the nuclear power plant programme in Indonesia. The research methods are literature study, consultation with resource person and exploring of website/internet. (author)

Current status of LTO licensing programme for Bohunice nuclear power plant

International Nuclear Information System (INIS)

Borak, J.; Kupca, L.

2012-01-01

The objective of long term operation (LTO) licensing programme for Bohunice nuclear power plant is to demonstrate that the relevant structures and components shall perform their functions throughout the entire LTO period during which they shall meet all the relevant safety requirements. All the activities-which should result in utility's request to obtain the licence for LTO-must be performed in line with the relevant legal basis. As of May 2012, the anticipated duration of currently running programme is thirteen months. All relevant documentation, required by the established legal basis, shall be submitted to the licensing authority one year before the Unit 3 design life expiry. (author)

The de-construction programme for EDF'S first generation power plants

International Nuclear Information System (INIS)

Zask, G.; Corcuff, A.

2003-01-01

Before 2001 EDF had adopted a 'long wait' scenario for the de-construction of nuclear power plants, consisting of waiting for a period of 5 to 10 years for IAEA level 2 (partial release of the site), then postponing the total de-construction of the facility for 25 to 50 years, in order to benefit from the natural decay of the radioactivity and thereby reduce the dosimetry of the personnel and the costs. Today, as regards the 8 power plants of the first generation and Creys-Malville, EDF has decided to undertake the total de-construction over a period of 25 years of all its reactors that have ceased commercial operation. The forecast cost of this programme amounts to Euro 3 billion. It thus intends to demonstrate its capacity to control, within the scale of the human lifespan, the entire life cycle of its nuclear power plants, while minimising the impact on man and the environment. This choice of immediate dismantling for the power plants of the first generation does not prejudge what will be done, when the time comes, for the PWR plants currently in operation. The paper has the following contents: 1. General; 2.The facilities concerned; 3. Chronological sequence adopted for de-construction; 4. Milestones and critical paths; 4.1. Simplification of the administrative procedures; 4.2. The waste channels; 4.3. Industrial organisation; 4.3.1. Creation of Centre d'Ingenierie De-construction et Environnement (CIDEN); 4.3.2. Responsibilities, interfaces and co-ordination of the various departments concerned (Role of owner: Responsibility as nuclear operator; Overall co-ordination; Operational steering of projects); 4.3.3. Internal authorization process; 4.3.4. Obtaining and maintaining skills (Training; Environment; De-construction; Radiological protection, radiology, radioecology; Processing of waste and approval of the cycle); 4.3.5. Monitoring of works and surveillance of service providers; 4.3.6. Radiological protection, environment; 4.3.7. Control of conventional

Radioactivity monitoring programme of Krsko nuclear power plant

International Nuclear Information System (INIS)

Miklavzic, U.; Martincic, R.; Kanduc, M.; Lulic, S.; Kovac, J.; Breznik, B.

1996-01-01

As a successor to the preoperational surveillance programme, the regular offsite radioactivity monitoring programme (RMP) of the Krsko Nuclear Power Plant (NPP) was implemented in 1982, when the power plant formally commenced operating. Observations collected during the first years of its operation were later also the basis for setting up the official 'Regulatory guide on monitoring of nuclear installations', issued not earlier than in 1986. The basic criterion which governed the selection of measuring methods, sampling techniques and locations, was the extent to which the data obtained could serve for the realistic assessment of the committed dose to a member of the population, and later on to members of a representative (critical) group. To be able to differentiate the radioactivity released through the liquid and gaseous effluents of the NPP from other radiation sources (natural radioactivity, global contamination), and especially because of the varying radiotoxicity of different radionuclides, in principle monitoring in the environment, as at the source, had to provide activity data for each individual radionuclide appearing in the effluents. Therefore, as early as 1982 the programme attributed the main weight to high resolution gamma spectrometry, combined with specific radiochemical analytical methods (e.g. 90 Sr/ 89 Sr, 3 H, 14 C, alpha spectrometry of Pu isotopes) which together made feasible determination of individual specific activities of the most significant man-made and natural radionuclides. By weighting the specific activities of the radionuclides identified and measured in the media surveyed by dose factors for intake, the quantity 'B' - the so-called 'radiological burden', was calculated and introduced in the yearly-summary tables. Expressed in relative units, from which the committed dose could be readily calculated, the burden B very lucidly disclosed the relative importance of different artificial pollutants and natural radioactivity present in

French wind power generation programme EOLE 2005 - first results

Energy Technology Data Exchange (ETDEWEB)

Laali, A.R. [Electricite de France (EDF), Chatou (France); Benard, M. [Electricite de France (EDF), Paris (France)

1997-12-31

EOLE 2005 has been launched in July 1996 by the French Ministry of Industry, Electricite de France and ADEME (Agency for Environment and Energy Management). The Ministries of Research and Environment are participating also in this programme. The purpose is to create an initial market in France for wind power generation in order to evaluate the cost-effectiveness and the competitiveness of the wind energy compared to other energy sources by 2005. The installed capacity will reach at least 250 MW and possibly 500 MW.

The Performance of Step-Wise Group Screening Designs

Directory of Open Access Journals (Sweden)

M.M. Manene

2005-06-01

Full Text Available In this paper we evaluate the performance of step-wise group screening designs in which group-factors contain an equal number of factors in the initial step.  A usual assumption in group screening designs is that the directions of possible effects are known a-priori. In practice, however, this assumption is unreasonable. We shall examine step-wise group screening designs without errors in observations when this assumption is relaxed. We shall consider cancellations of effects within group-factors. The performance of step-wise group-screening designs shall then be compared with the performance of multistage group screening designs.

Programme of studies. Vol. 3: Energy. Pt. 2

International Nuclear Information System (INIS)

1995-01-01

This volume contains the reports on studies carried out by different institutions. Their titles are: 1. Overall economic impact of strategies for cutting down emissions, 2. Analysis of obstacles to, and steps towards, the realization of CO 2 emission reduction targets, 3. Future regulatory framework, especially for line-transmitted energy, in support of climate protection targets, 4. Conceptual study for a further-education and market introduction programme ''Efficient and economical use of electricity'', 5. Perspectives and consequences of the completion of the internal European market, especially the stepwise establishment of a European power market, and of international conventions (in particular with a view to climate protection) for a policy aiming to reduce greenhouse gas emissions, 6. Concept for, and valuation of, economic relations with developing countries, the Commonwealth of independent states (CIS), and eastern Europe with the aim of cutting down greenhouse gases, as well as population projections for united Germany to the year 2100 - with special regard to migrations. (orig.) [de

ICRP publication 26. Its applicability in a nuclear power programme

International Nuclear Information System (INIS)

Wilson, R.; Donnelly, K.

1980-01-01

Ontario Hydro is a major Canadian provincial utility with more than 5 GW(e) installed nuclear electricity generating capacity and with a planned commitment to an additional 8.5 GW(e), all units being of the CANDU pressurized heavy-water type. The radiation protection programme, in addition to complying with Canadian Federal regulations, has been consistent with the philosophy and intent of ICRP recommendations and is frequently reviewed to ensure compliance with these recommendations, the most recent of which is ICRP-26. The application of the ALARA principle in this power reactor programme is described. A set of general guidelines has been established, the main features of which are: (a) achieving a dose consumption per unit of electricity generated which is low compared with reactors of a similar type; (b) ensuring that stations are operable with the dose equivalent of their labour-dictated manpower; (c) ensuring that the risk to atomic radiation workers is compatible with a corporate fatality rate standard of 8 man-hours worked. Achievement of these guidelines has necessitated implementing a continued dose-management programme. This programme is described generally. The cost applied to justify a dose reduction of 1 man.Sv is given, and a comparison is made with the equivalent life costs this implies and the costs used by safety agencies for other risk-reduction activities. Finally, some practical problems associated with some of the recommendations of ICRP-26 are discussed. (author)

The Community's research and development programme on decommissioning of nuclear power plants

International Nuclear Information System (INIS)

1982-01-01

The programme, adopted by the Council of the European Communities, seeks to promote a number of research and development projects as well as the identification of guiding principles. The projects concern the following subjects: long-term integrity of buildings and systems; decontaminations for decommissioning purposes; dismantling techniques; treatment of specific waste materials (steel, concrete and graphite); large transport containers for radioactive waste arising from decommissioning of nuclear power plants in the Community; and influence of nuclear power plant design features on decommissioning

Meeting the physics design challenges of modern LWRs being inducted into the Indian nuclear power programme

International Nuclear Information System (INIS)

Jagannathan, V.; Pal, Usha; Karthikeyan, R.; Raj, Devesh; Srivastava, Argala; Khan, Suhail Ahmad

2007-01-01

Indian nuclear power programme started with the two Boiling Water Reactors (BWR) of 210 MWe capacity at Tarapur. Two VVER-1000 MWe reactors which are Pressurized Water Reactors (PWR) of Russian design are being constructed at Kudankulam, Tamilnadu and are expected to be commissioned by end 2008. There may be also a possibility of inducting some western PWRs in future. These reactors belong to the category of light water reactors (LWR). The LWRs are compact and have complex physical characteristics distinctly different from those of the Pressurized Heavy Water Reactors (PHWR) which, currently form the mainstay of our indigenous nuclear power programme. The physics design and analysis capability for the modern LWRs (BWR, PWR and VVER) has been developed at Light Water Reactors Physics Section, BARC. This paper presents the current state of art in this key technology area to meet the physics design and operation challenges when LWRs would be inducted in a major way into the Indian nuclear power programme and commence operating in the coming decades. (author)

RATU2. The Finnish research programme on the structural integrity of nuclear power plants. Interim report 1995 - April 1997

International Nuclear Information System (INIS)

Solin, J.; Sarkimo, M.; Asikainen, M.

1997-06-01

The projects within the Finnish public funded research programme on the structural integrity of nuclear power plants (RATU2) are briefly introduced and the scientific and technical results obtained during the first two years, 1995-April 1997, are summarised in this report. The RATU2 programme was started in 1995 and will be continued until 1998. In 1996 this programme represented 6 % of the nuclear energy R and D in Finland. The research programme is mainly publicly funded and supplies impartial expertise for the regulation of nuclear energy. It also plays an important role in the education of new experts, technology transfer and international exchange of scientific results. The programme is organised into five research projects on the following topics: Material degradation in the reactor environment, Reliability of nondestructive inspections of nuclear power plants, Structural analyses for nuclear power plant components, Maintenance strategies and dependability, and Fire safety. The ageing of the structures and components in the Finnish nuclear power plants is one of the main issues to be considered when safety and economic operation of the plants is evaluated. At the same time, ways are being sought to extend the lifetime of components. The first half of the RATU2 research programme has already brought significant scientific findings and useful applications for ensuring the reliability of NPP components. New technology has been transferred to domestic use through active participation to international co-operation. On the other hand, international acceptance of the results has provided valuable feedback and benchmarking. (orig.)

RATU2. The Finnish research programme on the structural integrity of nuclear power plants. Interim report 1995 - April 1997

Energy Technology Data Exchange (ETDEWEB)

Solin, J; Sarkimo, M; Asikainen, M [VTT Manufacturing Technology, Espoo (Finland). Materials and Structural Integrity; eds.

1997-06-01

The projects within the Finnish public funded research programme on the structural integrity of nuclear power plants (RATU2) are briefly introduced and the scientific and technical results obtained during the first two years, 1995-April 1997, are summarised in this report. The RATU2 programme was started in 1995 and will be continued until 1998. In 1996 this programme represented 6 % of the nuclear energy R and D in Finland. The research programme is mainly publicly funded and supplies impartial expertise for the regulation of nuclear energy. It also plays an important role in the education of new experts, technology transfer and international exchange of scientific results. The programme is organised into five research projects on the following topics: Material degradation in the reactor environment, Reliability of nondestructive inspections of nuclear power plants, Structural analyses for nuclear power plant components, Maintenance strategies and dependability, and Fire safety. The ageing of the structures and components in the Finnish nuclear power plants is one of the main issues to be considered when safety and economic operation of the plants is evaluated. At the same time, ways are being sought to extend the lifetime of components. The first half of the RATU2 research programme has already brought significant scientific findings and useful applications for ensuring the reliability of NPP components. New technology has been transferred to domestic use through active participation to international co-operation. On the other hand, international acceptance of the results has provided valuable feedback and benchmarking. (orig.). 112 refs.

SAFIR. The Finnish research programme on nuclear power plant safety 2003-2006. Executive summary

International Nuclear Information System (INIS)

Puska, E.

2006-12-01

Major part of Finnish public research on nuclear power plant safety during the years 2003-2006 has been carried out in the SAFIR programme. The programme has been administrated by the steering group that was nominated by the Ministry of Trade and Industry (KTM). The steering group of SAFIR has consisted of representatives from Radiation and Nuclear Safety Authority (STUK), Ministry of Trade and Industry (KTM), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oy (TVO), Fortum Power and Heat Oy, Fortum Nuclear Services Oy (Fortum), Finnish Funding Agency for Technology and Innovation (Tekes), Helsinki University of Technology (TKK) and Lappeenranta University of Technology (LTY). The key research areas of SAFIR have been (1) reactor fuel and core, (2) reactor circuit and structural safety, (3) containment and process safety functions, that was divided in 2005 into (3a) thermal hydraulics and (3b) severe accidents, (4) automation, control room and IT, (5) organisations and safety management and (6) risk-informed safety management. The research programme has included annually from 20 up to 24 research projects, whose volume has varied from a few person months to several person years. The total volume of the programme during the four year period 2003-2006 has been 19.7 million euros and 148 person years. The research in the programme has been carried out primarily by Technical Research Centre of Finland (VTT). Other research units responsible for the projects include Lappeenranta University of Technology, Fortum Nuclear Services Oy, Helsinki University of Technology and RAMSE Consulting Oy. In addition, there have been a few minor subcontractors in some projects. The programme management structure has consisted of the steering group, a reference group in each of the seven research areas and a number of ad hoc groups in the various research areas. This report gives a short summary of the results of the SAFIR programme for the period January 2003 - November

Significance of stepwise excretion pattern in renogram

International Nuclear Information System (INIS)

Tamaki, Nagara; Ishihara, Takashi; Mori, Toru; Bito, Sanae; Ito, Hidetomi

1981-01-01

In 204 routine renogram examinations using 131 I-iodohippurate, stepwise excretion curves were observed in 22 cases (14 with chronic thyroiditis, 4 with idiopathic edema, 3 with lower urinary tract disorders, and 1 with Bartter's syndrome). Such a phenomenon was observed in 74% of euthyroid edematous patients with chronic thyroiditis and 57% of patients with idiopathic edema. The stepwise pattern was considered to have certain correlations with spasm or increased peristalsis of the urinary tract through the studies of excretory urogram, butylscopolamine treated renogram, and regional renogram. In one of these edematous patients with chronic thyroiditis, this renogram pattern could not be reproduced after bed rest corresponding with the clinical evidence that physical rest reduce the edema. Thus, the stepwise excretory pattern in renogram seemed to be a useful indicator of the fluctuating edema in patients with chronic thyroiditis and idiopathic edema. (author)

Human resource issues related to an expanding nuclear power programme

International Nuclear Information System (INIS)

2006-05-01

The IAEA Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that the IAEA develop guidelines on human resource management (including staffing) and training/education programmes for new nuclear power plant (NPP) designs. This recommendation was made in recognition that these future NPPs may have significantly different needs in this area compared to operating plants, and if so, NPP operating organizations should integrate these needs into their planning for future NPP projects. This report is primarily intended for use by NPP operating organizations that already have units in operation and that are considering adding to their fleet. Therefore, the addition of both new and current designs are addressed in this report. However, it should also be of value to those organizations that are considering the initial implementation of nuclear power, as well as decision makers in government, and in other nuclear industry organizations

National Nuclear Power Plant Safety Research 2003-2006. Proposal for the Content and Organisation of a New Research Programme

International Nuclear Information System (INIS)

2002-11-01

A country utilising nuclear energy is presumed to possess a sufficient infrastructure to cover the education and research in this field, besides the operating and supervisory organisations of the plants. The starting point of public nuclear safety research programmes is that they provide the necessary conditions for retaining the knowledge needed for ensuring the continuance of safe and economic use of nuclear power, for development of new know-how and for participation in international cooperation. In fact, the Finnish organisations engaged in research in this sector have been an important resource which the various ministries, the Radiation and Nuclear Safety Authority (STUK) and the power companies have had at their disposal. The Steering Group to the Finnish Research Programme on Nuclear Power Plant Safety (FINNUS), which was launched upon the assignment of the Advisory Committee on Nuclear Energy, appointed in spring 2002 a group to plan the contents of the new programme. This report contains a proposal for the general outline of the programme, preliminarily entitled as SAFIR (SAfety of Nuclear Power Plants - Finnish National Research Programme). The plan has been made for the period 2003-2006, but it is based on safety challenges identified for a longer time span as well. The favourable decision-in-principle on a new nuclear power plant unit adopted by Parliament has also been taken into account in the plan. The safety challenges set by the existing plants and the new plant unit, as well as the ensuing research needs do, however, converge to a great extent. The construction of the new power plant unit will increase the need for experts in the field in Finland. At the same time, the retirement of the existing experts is continuing. These factors together will call for more education and training, in which active research activities play a key role. This situation also makes long-term safety research face a great challenge. The general plan aims to define the

Cushing's syndrome: Stepwise approach to diagnosis

Science.gov (United States)

Lila, Anurag R.; Sarathi, Vijaya; Jagtap, Varsha S.; Bandgar, Tushar; Menon, Padmavathy; Shah, Nalini S.

2011-01-01

The projected prevalence of Cushing's syndrome (CS) inclusive of subclinical cases in the adult population ranges from 0.2–2% and it may no longer be considered as an orphan disease (2–3 cases/million/year). The recognition of CS by physicians is important for early diagnosis and treatment. Late-night salivary cortisol, dexamethasone suppressiontesti, or 24-h urine free cortisol are good screening tests. Positively screened cases need stepwise evaluation by an endocrinologist. This paper discusses the importance of screening for CS and suggests a stepwise diagnostic approach to a case of suspected hypercortisolism. PMID:22145134

Characterization of vegetative and grain filling periods of winter wheat by stepwise regression procedure. II. Grain filling period

Directory of Open Access Journals (Sweden)

Pržulj Novo

2011-01-01

Full Text Available In wheat, rate and duration of dry matter accumulation and remobilization depend on genotype and growing conditions. The objective of this study was to determine the most appropriate polynomial regression of stepwise regression procedure for describing grain filling period in three winter wheat cultivars. The stepwise regression procedure showed that grain filling is a complex biological process and that it is difficult to offer a simple and appropriate polynomial equation that fits the pattern of changes in dry matter accumulation during the grain filling period, i.e., from anthesis to maximum grain weight, in winter wheat. If grain filling is to be represented with a high power polynomial, quartic and quintic equations showed to be most appropriate. In spite of certain disadvantages, a cubic equation of stepwise regression could be used for describing the pattern of winter wheat grain filling.

Cost Effective Ways of Implementing Nuclear Power Programme in African Countries

International Nuclear Information System (INIS)

Aderojua, Abraham; Choi, Kwang Sik

2011-01-01

still growing fast and hence are characterized by a foreseeable increase in electricity demand to drive the factors of production. 1.3 Objective of this Paper The purpose of this paper is to explore the efficient means of building nuclear power plants and associated infra structure in African countries. The concept adopted in this paper to achieve efficient allocation of resources is sharing of infrastructural items. The paper lists examples of sharing arrangement on the African continent for other purposes other than nuclear power programme. This is an attempt to justify the workability of the concept for nuclear power programme. Mention has also been made of similar sharing arrangement in other countries for the purpose of nuclear power programme. The factors that will enhance the success of sharing concept in African countries have also been highlighted

Experience in the Swiss programme in preparing for DGRs of all waste types. The implementer's view

International Nuclear Information System (INIS)

Zuidema, Piet; Schneider, Juerg; Fries, Thomas

2014-01-01

In Switzerland, a stepwise approach has been chosen to implement the repositories needed to safely manage the wastes arising in Switzerland. Although the Swiss programme is still in an early phase of implementation with the current focus on site selection, all issues relevant to construct, to operate and to close the repositories are considered at least at a conceptual level. The stepwise approach, which foresees that both findings from previous steps and from foreign programmes are taken into account at each step, ensures that optimised projects are developed. After some background information on the Swiss waste disposal programme and its current status, this paper presents the basic approach to developing the repositories and gives a broad overview of key requirements and issues related to radiological safety (post-closure safety as a dominant factor for site selection, safety during the operational phase) and key issues related to the construction and operation of the repositories

Nuclear waste management programme 2003 for the Loviisa and Olkiluoto nuclear power plants

International Nuclear Information System (INIS)

2002-09-01

A joint company Posiva Oy founded by nuclear energy producing Teollisuuden Voima Oy (TVO) and Fortum Power and Heat Oy coordinates the research work of the companies on nuclear waste management in Finland. In Posiva's Nuclear Waste Management Programme 2003, an account of the nuclear waste management measures of TVO and Fortum is given as required by the sections 74 and 75 of the Finnish Nuclear Energy Degree. At first, nuclear waste management situation and the programme of activities are reported. The nuclear waste management research for the year 2003 and more generally for the years 2003-2007 is presented

Robust media processing on programmable power-constrained systems

Science.gov (United States)

McVeigh, Jeff

2005-03-01

To achieve consumer-level quality, media systems must process continuous streams of audio and video data while maintaining exacting tolerances on sampling rate, jitter, synchronization, and latency. While it is relatively straightforward to design fixed-function hardware implementations to satisfy worst-case conditions, there is a growing trend to utilize programmable multi-tasking solutions for media applications. The flexibility of these systems enables support for multiple current and future media formats, which can reduce design costs and time-to-market. This paper provides practical engineering solutions to achieve robust media processing on such systems, with specific attention given to power-constrained platforms. The techniques covered in this article utilize the fundamental concepts of algorithm and software optimization, software/hardware partitioning, stream buffering, hierarchical prioritization, and system resource and power management. A novel enhancement to dynamically adjust processor voltage and frequency based on buffer fullness to reduce system power consumption is examined in detail. The application of these techniques is provided in a case study of a portable video player implementation based on a general-purpose processor running a non real-time operating system that achieves robust playback of synchronized H.264 video and MP3 audio from local storage and streaming over 802.11.

The regulatory evaluation of radiation protection training programmes at Canadian nuclear power plants

International Nuclear Information System (INIS)

Legare, M.; Tennant, D.

1996-01-01

The responsibility for providing the necessary assurance that the use of nuclear energy in Canada does not pose undue risk to health, safety, security and the environment is vested with the Atomic Energy Control Board (AECB). This responsibility has led the Operator Certification Division of the AECB to develop methods to obtain assurance that nuclear power plant operations personnel are well trained and adequately competent to perform their duties. The features of the AECB approach to evaluation of training programmes based on a systematic approach to training is described. An overview of the Canadian nuclear power plants' radiation protection qualification levels is given. The developing evaluation process is contributing to the improvement of licensee radiation protection training programmes. This is making possible the transfer of part of the responsibility for licensed personnel radiation protection qualification assessment to the licensees, thus enabling a reduction in the operator certification division formal qualification activities. (author)

Specification for a total quality assurance programme for nuclear power plants

International Nuclear Information System (INIS)

1980-01-01

This British Standard specifies principles for the establishment and implementation of quality assurance programmes during all phases of design, procurement, fabrication, construction, commissioning, operation, maintenance and decommissioning of structures, systems and components of nuclear power plants. These principles apply to activities affecting the quality of items, such as designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, testing, commissioning, operating, inspecting, maintaining, repairing, refuelling, modifying and, eventually decommissioning. (author)

Considerations in Emergency Preparedness and Response for a State Embarking on a Nuclear Power Programme, Training Materials

International Nuclear Information System (INIS)

2013-01-01

The aim of these training materials is to provide a practical tool for emergency planning for a State embarking on a nuclear power programme, and to fulfil, in part, functions assigned to the IAEA under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (the Assistance Convention). Under Article 5.a(ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and available results of research relating to such emergencies. One of the concerns associated with nuclear power is the possibility that a State embarking on a nuclear power programme might not have sufficient capabilities and therefore would not be adequately prepared to respond to a radiation emergency caused by severe accident conditions. Protecting the public, the environment and property in the event of a failure of any level of defence in depth is the most important safety objective. A robust framework for emergency preparedness and response to a radiation emergency forms the last level of defence in depth and, as such, must be developed and implemented by any State embarking on a nuclear power programme, using best international practices. The establishment of capabilities and arrangements for emergency preparedness and response to severe accident conditions is one of the principal tasks in the development of a national infrastructure for nuclear power. State of the art emergency preparedness and response is a key element in achieving overall plant safety. This training course complements the IAEA publication 'Considerations in Emergency Preparedness and Response for a State Embarking on a Nuclear Power Programme' (EPR-Embarking 2012). These materials are designed to help States apply the guidance in EPR-Embarking 2012, in order to develop the capability to adequately prepare for and respond to a radiation emergency after the commissioning and start of

Stepwise management of asthma.

Science.gov (United States)

Khalid, Ayesha N

2015-09-01

Stepwise management of asthma remains an area of evolving research. Asthma is one of the most expensive chronic diseases in the United States; stepwise management is an important area of focus, with several recent guidelines recommending management. This is a review of published English language literature, focusing on management guidelines for asthma in adult and pediatric patients. Asthma is a chronic disease whose assessment of severity allows for therapeutic goals to match the impairment noted. Good evidence exists to aid risk reduction, leading to decreased emergency room visits, preventing loss of lung function in adults and lung growth in children, and optimizing pharmacotherapy with reduced side effects profile. Recent asthma management guidelines incorporate 4 components of asthma care including: monitoring of severity, patient education, controlling external triggers, and medications, including recent attention to medication adherence. Asthma is an expensive chronic disease with preventive measures leading to reduced healthcare costs. Future targeted cytokine therapy to decrease serum and blood eosinophils may become an integral part of asthma management. © 2015 ARS-AAOA, LLC.

Promotion and financing of nuclear power programmes in developing countries

International Nuclear Information System (INIS)

Bennett, L.L.; Skjoeldebrand, R.

1988-01-01

Nuclear power has been introduced only to a small extent in a few developing countries. A group of senior experts conducted a study of the existing constraints on nuclear power in developing countries, the requirements to be met for successful introduction of a nuclear power programme, and mechanisms to assist developing countries in overcoming the identified constraints. Financing represents one (but not the only) major constraint to nuclear power development in developing countries. The present schemes of export credits and commercial financing are seen as not adequately meeting the needs of nuclear power financing in terms of repayment periods and profiles, or in terms of flexibility to meet delays and cost overruns. Innovative and workable arrangements to share the economic and financial risks would be helpful in obtaining financing for a nuclear power project. All possible efforts should be made by all parties involved in the development of nuclear power to reduce as far as possible the uncertainties surrounding the cost and schedule of a nuclear power project, as an essential step to improve the overall climate for financing the project. Government commitment, soundly based and thorough planning, development of qualified manpower and other key infrastructures, and good project management are important mechanisms to achieve greater predictability in project schedule and cost. Technical assistance provided by the IAEA can be very helpful in building these capabilities in developing countries. (author). 1 tab

The community's research and development programme on decommissioning of nuclear power plants. Third annual progress report (year 1982)

International Nuclear Information System (INIS)

1984-01-01

This is the third progress report of the European Community's programme (1979-83) of research on the decommissioning of nuclear power plants. It covers the year 1982 and follows the 1980 and 1981 reports (EUR 7440, EUR 8343). Since 1982 was a very active year of research under the programme, this report contains a large amount of results. Besides, the work programmes of some additional research contracts, awarded through 1982, are described

Complex programmable logic device based alarm sequencer for nuclear power plants

International Nuclear Information System (INIS)

Khedkar, Ravindra; Solomon, J. Selva; KrishnaKumar, B.

2001-01-01

Complex Programmable Logic Device based Alarm Sequencer is an instrument, which detects alarms, memorizes them and displays the sequences of occurrence of alarms. It caters to sixteen alarm signals and distinguishes the sequence among any two alarms with a time resolution of 1 ms. The system described has been designed for continuous operation in process plants, nuclear power plants etc. The system has been tested and found to be working satisfactorily. (author)

Competitiveness through cooperation between electricity and information technology. TESLA - Information technology and electric power systems technology programme 1998-2002

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-11-01

The electricity markets are being opened up to competition all round the world. To succeed in competition electricity sellers want new information technology tools to use in managing the sale of electricity. The network companies are aiming to step up utilization of their distribution capacity and to optimize power quality and the reliability of supply. Consumers need solutions with which they can manage their own power consumption and tendering sellers. The Nordic countries have been the first to deregulate their electricity markets. This head start in time is being made use of to generate a head start in technology. Tekes has initiated a technology programme for the years 1998 to 2002, named TESLA - Information Technology and Electric Power Systems, to promote the competitiveness of the Finnish electricity industry in changing conditions. The objective of the programme is to adapt information technology extensively to power distribution and thus develop the potential for Finland`s electricity industry to succeed on world markets. At the moment power distribution technology forms about one third of Finland`s energy technology exports. The programme is also aimed at developing new data transfer and data processing applications for companies in information technology clusters. For Finnish parties in the electricity markets the programme will produce ways and means of (1) improving management and use of distribution networks, (2) implementing competition in electricity sales, and (3) increasing the efficiency of electricity use

Stepwise classification of cancer samples using clinical and molecular data

Directory of Open Access Journals (Sweden)

Obulkasim Askar

2011-10-01

Full Text Available Abstract Background Combining clinical and molecular data types may potentially improve prediction accuracy of a classifier. However, currently there is a shortage of effective and efficient statistical and bioinformatic tools for true integrative data analysis. Existing integrative classifiers have two main disadvantages: First, coarse combination may lead to subtle contributions of one data type to be overshadowed by more obvious contributions of the other. Second, the need to measure both data types for all patients may be both unpractical and (cost inefficient. Results We introduce a novel classification method, a stepwise classifier, which takes advantage of the distinct classification power of clinical data and high-dimensional molecular data. We apply classification algorithms to two data types independently, starting with the traditional clinical risk factors. We only turn to relatively expensive molecular data when the uncertainty of prediction result from clinical data exceeds a predefined limit. Experimental results show that our approach is adaptive: the proportion of samples that needs to be re-classified using molecular data depends on how much we expect the predictive accuracy to increase when re-classifying those samples. Conclusions Our method renders a more cost-efficient classifier that is at least as good, and sometimes better, than one based on clinical or molecular data alone. Hence our approach is not just a classifier that minimizes a particular loss function. Instead, it aims to be cost-efficient by avoiding molecular tests for a potentially large subgroup of individuals; moreover, for these individuals a test result would be quickly available, which may lead to reduced waiting times (for diagnosis and hence lower the patients distress. Stepwise classification is implemented in R-package stepwiseCM and available at the Bioconductor website.

Finnish experiences on licensing and using of programmable digital systems in nuclear power plants

International Nuclear Information System (INIS)

Haapanen, P.; Maskuniitty, M.; Heimburger, H.; Hall, L.E.; Manninen, T.

1993-01-01

Finnish utility companies, Imatran Voima Oy (IVO) and Teollisuuden Voima (TVO), and the licensing authority, the Finnish Centre for Radiation and Nuclear Safety (STUK), are preparing for a new nuclear power plant in Finland. Plant vendors are proposing programmable digital automation systems for both the safety-related and the operational I and C (instrumentation and control) systems in this new unit. Also in existing plant units the replacement of certain old analog systems with state-of-the-art digital ones will become necessary in the years to come. Licensing of programmable systems for safety critical applications requires a new approach due to the special properties and failure modes of these systems. The major difficulties seem to be in the assessment and quantification of software reliability. The Technical Research Centre of Finland has in co-operation with the authority and the utilities conducted a project (AJA) to develop domestically applicable licensing requirements, guidelines and practices. International standards, guidelines and licensing practices have been analyzed in order to specify national licensing requirements. The paper describes and discusses the findings and experiences of the AJA project so far. The experience in introducing advanced programmable digital control and computer systems in the operating nuclear power plants will be covered briefly. Although these systems are not safety-related but systems of more general interest regarding nuclear safety, some routines regarding the licensing of safety- related systems have been followed. In these backfitting and replacement projects some experience have been gained in how to license safety-related programmable systems. (Author) 31 refs., 2 figs

RATU2 - The Finnish research programme on the structural integrity of nuclear power plants. Synthesis of achievements 1995-1998

International Nuclear Information System (INIS)

Solin, J.; Sarkimo, M.; Asikainen, M.; Aavall, Aa.

1998-01-01

The symposium summarises the scientific and technical achievements within the Finnish Research programme on the structural integrity of nuclear power plants (RATU2). The programme began in 1995 and will be accomplished at the end of 1998. The annual volume of this programme represented approximately 6 % of the total nuclear energy R and D in Finland. The research programme was mainly publicly funded and supplied impartial expertise for the regulation of nuclear energy. It also played an important role in the education of new experts, technology transfer and the international exchange of scientific results. (orig.)

Cushing′s syndrome: Stepwise approach to diagnosis

Directory of Open Access Journals (Sweden)

Anurag R Lila

2011-01-01

Full Text Available The projected prevalence of Cushing′s syndrome (CS inclusive of subclinical cases in the adult population ranges from 0.2-2% and it may no longer be considered as an orphan disease (2-3 cases/million/year. The recognition of CS by physicians is important for early diagnosis and treatment. Late-night salivary cortisol, dexamethasone suppressiontesti, or 24-h urine free cortisol are good screening tests. Positively screened cases need stepwise evaluation by an endocrinologist. This paper discusses the importance of screening for CS and suggests a stepwise diagnostic approach to a case of suspected hypercortisolism.

Dangers associated with civil nuclear power programmes: weaponization and nuclear waste.

Science.gov (United States)

Boulton, Frank

2015-07-24

The number of nuclear power plants in the world rose exponentially to 420 by 1990 and peaked at 438 in 2002; but by 2014, as closed plants were not replaced, there were just 388. In spite of using more renewable energy, the world still relies on fossil fuels, but some countries plan to develop new nuclear programmes. Spent nuclear fuel, one of the most dangerous and toxic materials known, can be reprocessed into fresh fuel or into weapons-grade materials, and generates large amounts of highly active waste. This article reviews available literature on government and industry websites and from independent analysts on world energy production, the aspirations of the 'new nuclear build' programmes in China and the UK, and the difficulties in keeping the environment safe over an immense timescale while minimizing adverse health impacts and production of greenhouse gases, and preventing weaponization by non-nuclear-weapons states acquiring civil nuclear technology.

COPD: A stepwise or a hit hard approach?

Directory of Open Access Journals (Sweden)

A.J. Ferreira

2016-07-01

Full Text Available Current guidelines differ slightly on the recommendations for treatment of Chronic Obstructive Pulmonary Disease (COPD patients, and although there are some undisputed recommendations, there is still debate regarding the management of COPD. One of the hindrances to deciding which therapeutic approach to choose is late diagnosis or misdiagnosis of COPD. After a proper diagnosis is achieved and severity assessed, the choice between a stepwise or “hit hard” approach has to be made. For GOLD A patients the stepwise approach is recommended, whilst for B, C and D patients this remains debatable. Moreover, in patients for whom inhaled corticosteroids (ICS are recommended, a step-up or “hit hard” approach with triple therapy will depend on the patient's characteristics and, for patients who are being over-treated with ICS, ICS withdrawal should be performed, in order to optimize therapy and reduce excessive medications.This paper discusses and proposes stepwise, “hit hard”, step-up and ICS withdrawal therapeutic approaches for COPD patients based on their GOLD group. We conclude that all approaches have benefits, and only a careful patient selection will determine which approach is better, and which patients will benefit the most from each approach. Keywords: COPD, Stepwise, Hit hard, Step-up, ICS withdrawal, Bronchodilators, ICS

Manpower development for nuclear power programme. China. Project findings and recommendations

International Nuclear Information System (INIS)

Csik, B.J.

1992-01-01

The United Nations Development Program (UNDP) project was conceived in April 1985, implementation was started on preliminary authorization by summer 1986, and it was approved and signed in early 1987. The duration was originally planned for three years with a UNDP input of US$ 1,657.500 (including Government cost sharing of US$ 280,000). The project is now essentially completed with a few items still pending, though committed as firmly planned, and the current cost estimate is US$ 1,707.617. The objective of the project was to assist in establishing long-term training programmes in two training centres in the People's Republic of China (Qinshan and Suzhou) and strengthen the training capabilities at these centres. The two centres are intended to provide specialized comprehensive training in basic and applied nuclear power engineering disciplines as well as in construction, operation and maintenance of nuclear power plants to technical personnel assigned to the nuclear power plants in the People's Republic of China

Melanin fluorescence spectra by step-wise three photon excitation

Science.gov (United States)

Lai, Zhenhua; Kerimo, Josef; DiMarzio, Charles A.

2012-03-01

Melanin is the characteristic chromophore of human skin with various potential biological functions. Kerimo discovered enhanced melanin fluorescence by stepwise three-photon excitation in 2011. In this article, step-wise three-photon excited fluorescence (STPEF) spectrum between 450 nm -700 nm of melanin is reported. The melanin STPEF spectrum exhibited an exponential increase with wavelength. However, there was a probability of about 33% that another kind of step-wise multi-photon excited fluorescence (SMPEF) that peaks at 525 nm, shown by previous research, could also be generated using the same process. Using an excitation source at 920 nm as opposed to 830 nm increased the potential for generating SMPEF peaks at 525 nm. The SMPEF spectrum peaks at 525 nm photo-bleached faster than STPEF spectrum.

Design and development of microcontroller based programmable ramp generator for AC-DC converter for simulating decay power transient in experimental facility for nuclear power plants

International Nuclear Information System (INIS)

Srivastava, Gaurava Deep; Kulkarni, R.D.

2015-01-01

In nuclear power plants, fuel is subjected to a wide range of power and temperature transients during normal and abnormal conditions. The reactor setback and step-back power pattern, fast temperature profile occurred during Loss of Coolant Accident and decay power followed by shutdown of power plant are the typical transients in nuclear power plant. For a variety of reactor engineering and reactor safety related study, one needs to simulate these transients in experimental facility. In experimental facilities, high response AC-DC converters are used to handle these power and temperature transients safely in a controlled manner for generating a database which is utilized for design of thermal hydraulic system, development of computer codes, study of reliability of reactor safety system, etc. for nuclear power plants. The paper presents the methodology developed for simulating the typical reactor decay power transient in an experimental facility. The design and simulation of AC-DC power electronic converter of 3 MW capacity is also presented. The microcontroller based programmable ramp generator is designed and hardware implemented for feeding reference voltage to the closed loop control system of AC-DC converter for obtaining the decay power profile at the converter output. The typical decay power transient of the nuclear power plant is divided into several small power ramps for simulating the transient. The signal corresponding to each power ramp is generated by programmable ramp generator and fed to the comparator for generating control signal for the converter. The actual decay power transient obtained from the converter is compared with the theoretical decay power transient. (author)

Results of the desulfurization programme at coal-fired power plants operated by CEZ a.s

International Nuclear Information System (INIS)

Anon.

1996-01-01

The Czech utility CEZ, which is the major power plant operator in the Czech Republic, is running an extensive coal-fired power plant desulfurization programme to improve the environmental situation in the region. Flue gas desulfurization is achieved in 2 ways: by augmenting the existing units with desulfurization equipment, and by replacing old boilers with new, fluidized-bed combustion facilities. Both wet limestone scrubbing and the dry limestone method are applied. A survey of the power plants, desulfurized power, desulfurization equipment suppliers, and contract prices is presented in a tabular form. Plots showing the contribution of CEZ's power plants to sulfur dioxide emissions in the Czech Republic are reproduced. (P.A.). 1 tab., 3 figs

Programmable Low-Power Low-Noise Capacitance to Voltage Converter for MEMS Accelerometers.

Science.gov (United States)

Royo, Guillermo; Sánchez-Azqueta, Carlos; Gimeno, Cecilia; Aldea, Concepción; Celma, Santiago

2016-12-30

In this work, we present a capacitance-to-voltage converter (CVC) for capacitive accelerometers based on microelectromechanical systems (MEMS). Based on a fully-differential transimpedance amplifier (TIA), it features a 34-dB transimpedance gain control and over one decade programmable bandwidth, from 75 kHz to 1.2 MHz. The TIA is aimed for low-cost low-power capacitive sensor applications. It has been designed in a standard 0.18-μm CMOS technology and its power consumption is only 54 μW. At the maximum transimpedance configuration, the TIA shows an equivalent input noise of 42 fA/ Hz at 50 kHz, which corresponds to 100 μg/ Hz .

Programmable Low-Power Low-Noise Capacitance to Voltage Converter for MEMS Accelerometers

Directory of Open Access Journals (Sweden)

Guillermo Royo

2016-12-01

Full Text Available In this work, we present a capacitance-to-voltage converter (CVC for capacitive accelerometers based on microelectromechanical systems (MEMS. Based on a fully-differential transimpedance amplifier (TIA, it features a 34-dB transimpedance gain control and over one decade programmable bandwidth, from 75 kHz to 1.2 MHz. The TIA is aimed for low-cost low-power capacitive sensor applications. It has been designed in a standard 0.18-μm CMOS technology and its power consumption is only 54 μW. At the maximum transimpedance configuration, the TIA shows an equivalent input noise of 42 fA/ Hz at 50 kHz, which corresponds to 100 μg/ Hz .

Best Practices in the Management of an Operating Experience Programme at Nuclear Power Plants

International Nuclear Information System (INIS)

2010-08-01

The IAEA Fundamental Safety Principles (IAEA Safety Standards Series No. SF-1) state the need for operating organizations to establish a programme for the feedback and analysis of operating experience in nuclear power plants. Such a programme ensures that operating experience is analysed, events important to safety are reviewed in depth, lessons learned are disseminated to the staff of the organization and to the relevant national and international organizations and corrective actions are effectively implemented. In IAEA Operational Safety Review Team (OSART) and Peer Review of the effectiveness of the Operational Safety Performance Experience Review (PROSPER) missions, weaknesses in the management of operating experience (OE) programmes have been identified as one of the root causes of the recurrence of events. This publication has been developed to provide advice and assistance to nuclear installation managers and related institutions, including contractors and support organizations, to strengthen and enhance the management of their OE processes. In this publication, a number of barriers to the successful management of an OE programme have been identified. Managers are encouraged to review and evaluate these barriers with a view to identifying and eliminating them within their own organizations

The French nuclear programme

International Nuclear Information System (INIS)

Bacher, Pierre

1987-01-01

France has a civil nuclear power generation programme second only to the USA with 49 nuclear units in operation and 13 under construction. The units in service are described. These include 33 PWR 900 MW and 9 PWR 1300 MW units. The electricity consumption and generation in France is illustrated. The absence of a powerful anti-nuclear lobby and two main technical options have contributed to the success of the French nuclear programme. These are the PWR design and the plant standardization policy which allows the setting up of an effective industrial complex (eg for analysis of operating conditions and of safety and reliability information). The programme and the reasons for its success are reviewed. Research programmes and future plans are also discussed. (UK)

Consideration of the legal system required for achievement of current nuclear power plant construction programmes

International Nuclear Information System (INIS)

Castellon Fernandez, E.; Forum Atomico Espanol, Madrid)

1976-01-01

The extensive nuclear power plant construction programmes currently in progress in western countries require updating of the legislation in force in this field, especially as regards the following: acquisition of the sites necessary by means of a national planning programme of available sites; simplification of formalities concerning issuance of administrative licenses; revision of the principle of absolute and exclusive liability of the nuclear operator which forms the basis of the third party liability system for nuclear damage; radioactive waste management and decommissioning of nuclear plants. Furthermore, this new legislation should be harmonized between the different countries concerned. (N.E.A.) [fr

ELF - An experimental programme to quantify the effects of load follow and perturbated power histories

International Nuclear Information System (INIS)

Bairiot, H.; Hass, D.; Stora, J.P.

1984-01-01

Most of the ramp tests performed in national or international programmes have as main objective to define the fuel rod failure/survival limits, as a function of various parameters. Only a few of these experiments are sufficiently instrumented. The main feature of the ELF programme, described in this paper, consists in continuously measuring the cladding diameter during irradiation in OSIRIS of pre-irradiated PWR fuel rods, in order to provide strain relaxation data under various operating conditions. Power fluctuations during these OSIRIS irradiations are defined in order to obtain the conditioning and deconditioning kinetics of the fuel rods. (author)

Stepwise introduction of laparoscopic liver surgery: validation of guideline recommendations.

Science.gov (United States)

van der Poel, Marcel J; Huisman, Floor; Busch, Olivier R; Abu Hilal, Mohammad; van Gulik, Thomas M; Tanis, Pieter J; Besselink, Marc G

2017-10-01

Uncontrolled introduction of laparoscopic liver surgery (LLS) could compromise postoperative outcomes. A stepwise introduction of LLS combined with structured training is advised. This study aimed to evaluate the impact of such a stepwise introduction. A retrospective, single-center case series assessing short term outcomes of all consecutive LLS in the period November 2006-January 2017. The technique was implemented in a stepwise fashion. To evaluate the impact of this stepwise approach combined with structured training, outcomes of LLS before and after a laparoscopic HPB fellowship were compared. A total of 135 laparoscopic resections were performed. Overall conversion rate was 4% (n = 5), clinically relevant complication rate 13% (n = 18) and mortality 0.7% (n = 1). A significant increase in patients with major LLS, multiple liver resections, previous abdominal surgery, malignancies and lesions located in posterior segments was observed after the fellowship as well as a decrease in the use of hand-assistance. Increasing complexity in the post fellowship period was reflected by an increase in operating times, but without comprising other surgical outcomes. A stepwise introduction of LLS combined with structured training reduced the clinical impact of the learning curve, thereby confirming guideline recommendations. Copyright © 2017 International Hepato-Pancreato-Biliary Association Inc. Published by Elsevier Ltd. All rights reserved.

Research plan on programmable automation systems in nuclear power plants (OHA) in 1995-1998

International Nuclear Information System (INIS)

Haapanen, P.; Pulkkinen, U.; Korhonen, J.

1995-05-01

The main purpose of nuclear energy research is to ensure the safety and continued development of Finnish nuclear power plants - a task which places high demands on expertise needed to support the work of public authorities and power companies. A factor necessarily influencing the orientation of the research is the Parliament's decision of late 1993 against further nuclear capacity in the country. Therefore the main emphasis of research shall be directed towards the ensuring the safety of existing plants and the continuous development of their safety along the progress of the science and technology. Anyhow, the preparedness for constructing new plants shall also be preserved. The utilization of programmable digital automation technology for the safety critical functions is the most significant change in the new plants, but also in existing plants this technology will be used for replacing and complementing the ageing automation systems. The safety evaluation of programmable digital systems can not be based on methods applied to conventional analog systems but new evaluation methods and tools must be developed for the assessing of their acceptability. (5 refs., 1 fig., 2 tabs.)

Thailand: Infrastructure Development and Challenges to Launch Nuclear Power Programme

International Nuclear Information System (INIS)

Keinmeesuke, Sirichai

2011-01-01

In June 2007, the cabinet passed a resolution for Thailand's Power Development Plan (PDP 2007). It was mentioned in the plan that Thailand will have 2 x 1,000 MWe nuclear power plants in 2020 and another 2 x 1,000 MWe in 2021. The PDP 2007 was revised in March 2009 and it was agreed to change the nuclear power generation to only 1 x 1,000 MWe in 2020 and 2021 respectively due to the large excess capacity at present. Many activities related to development of infrastructures in order to support electricity generation using nuclear power are being executed. Milestones for nuclear power program implementation has been developed using the IAEA document 'Milestones in the Development of a National Infrastructure for Nuclear Power' with some amendment/additions to suit the country situation. According to the schedule, a lot of activities related to infrastructure establishment, feasibility study, utility preparation and public education and participation are being performed. Within the year 2011, various issues such as legal and regulatory systems and international commitment, industrial and commercial infrastructure, technology transfer and human resource development, safety and environmental protection, public information and public acceptance, preparation of the nuclear power utility establishment, etc. must be solved out and undertaken to assure the cabinet to make final decision to go nuclear. There are many challenges for Thailand embarking of the nuclear power programme. It is essential to plan for the establishment of a regulatory body at the national level to support and regulate the nuclear power plant industry. Currently, the application for a license and the monitoring of a power plant are administered by the authorities of various agencies under different ministries; hence the process is very time-consuming and overlaps with one another. The approach that the regulatory body and the authorities to issue licenses relevant to the nuclear power plant operation

A stepwise model to predict monthly streamflow

Science.gov (United States)

Mahmood Al-Juboori, Anas; Guven, Aytac

2016-12-01

In this study, a stepwise model empowered with genetic programming is developed to predict the monthly flows of Hurman River in Turkey and Diyalah and Lesser Zab Rivers in Iraq. The model divides the monthly flow data to twelve intervals representing the number of months in a year. The flow of a month, t is considered as a function of the antecedent month's flow (t - 1) and it is predicted by multiplying the antecedent monthly flow by a constant value called K. The optimum value of K is obtained by a stepwise procedure which employs Gene Expression Programming (GEP) and Nonlinear Generalized Reduced Gradient Optimization (NGRGO) as alternative to traditional nonlinear regression technique. The degree of determination and root mean squared error are used to evaluate the performance of the proposed models. The results of the proposed model are compared with the conventional Markovian and Auto Regressive Integrated Moving Average (ARIMA) models based on observed monthly flow data. The comparison results based on five different statistic measures show that the proposed stepwise model performed better than Markovian model and ARIMA model. The R2 values of the proposed model range between 0.81 and 0.92 for the three rivers in this study.

Inevitability of atomic energy in India's power programme

International Nuclear Information System (INIS)

Ramanna, R.

1977-01-01

The case for atomic energy as the inevitable answer to the energy problem of India has been emphatically put up and supported with data. Hydroelectric power is costly to develop and moreover its potential is not enough to meet India's growing energy requirements. On the grounds of economics and safety, nuclear power has been shown to be superior to power from coal-based power plants. India's proved reserves of coal are 21 billion tonnes out of which 80% has ash content more than 20% and in order to reach only half of the present per capita energy consumption in Europe, the present output of 90 million tonnes/year of coal will have to be increased by a factor of 10, which in addition raises the problem of its transportation to the plant sites. Secondly, total energy from the available coal is estimated at 160 x 10 12 kwh, while that from known reserves of 52,000 tonnes of uranium is 7.2 x 10 12 kwh if used in thermal reactors and 208 x 10 12 kwh if used in fast reactors. Thorium with its known reserves of 320,000 tonnes would give another 1280 x 10 12 kwh. As for safety and ecology, it has been pointed out that : (1) in U.S., the number of coal miners dying of black cancer is 1000 per 10 12 kwh of electricity generated, whereas the fatality rate of uranium miners due to lung cancer is 20 per 10 12 kwh of electricity generated and (2) safety has been the primary concern in all aspects of nuclear technology - mining, fuel production, reactor operation and radioactive waste processing. It has also been explained how the fear of any terrorist getting possession of plutonium for spreading it into atmosphere or making a nuclear bomb is highly improbable, because at any point throughout the fuel cycle plutonium is under strict security surveillance and it is impossible to make a nuclear device without the back-up of powerful laboratory facilities. Finally, India's three stage atomic power programme is described in brief. (M.G.B.)

REGSTEP - stepwise multivariate polynomial regression with singular extensions

International Nuclear Information System (INIS)

Davierwalla, D.M.

1977-09-01

The program REGSTEP determines a polynomial approximation, in the least squares sense, to tabulated data. The polynomial may be univariate or multivariate. The computational method is that of stepwise regression. A variable is inserted into the regression basis if it is significant with respect to an appropriate F-test at a preselected risk level. In addition, should a variable already in the basis, become nonsignificant (again with respect to an appropriate F-test) after the entry of a new variable, it is expelled from the model. Thus only significant variables are retained in the model. Although written expressly to be incorporated into CORCOD, a code for predicting nuclear cross sections for given values of power, temperature, void fractions, Boron content etc. there is nothing to limit the use of REGSTEP to nuclear applications, as the examples demonstrate. A separate version has been incorporated into RSYST for the general user. (Auth.)

15 years of information and educational programme of Czech Power Company CEZ

International Nuclear Information System (INIS)

Dufkova, M.

2007-01-01

The education program is the most important long-term communication programme of CEZ. It was established in 1992 shortly after an establishment of Czech Power Company. The support of education and talented students is doubtless a positive activity bringing a benefit to the company, especially in the field of nuclear energy. Students, who have been currently addressed with this program, are future consumers of electricity and as voters and politicians they shall decide on further development of power industry and nuclear installations. We care for them to make qualified decisions. CEZ has so far been the only Czech industrial company, which offers such program to schools. Education is the most important activity in the gaining support for nuclear energy. (author)

Building Technical Capability for the Development of Nuclear Power Programme: Uganda's Experience

International Nuclear Information System (INIS)

Jagenu, A.

2012-01-01

The Republic of Uganda is a landlocked country in East Africa with a population of about 33 million. It lies along the equator and is bordered on the east by Kenya, north by Sudan, west by the Democratic Republic of the Congo, southwest by Rwanda, and south by Tanzania. Uganda has continued to suffer power shortage, mainly due to slow investment in the power sector as well as unreliable rainfall. To supplement the power supply, it has contracted independent power producers to supply electricity from fossil fuels. The Thermal power is expensive and contributes to emission of large amount of carbon dioxide - a major greenhouse gas causing global warming. The total estimated electricity generation potential is in the long term will be about 5300MW. In view of the increasingly energy needs and urgent environmental concerns related to power production using fossil fuels, the government recognizes that nuclear technology will play important role in future sustainable energy systems. The Government is therefore considering nuclear energy as part of the future energy mix. However, Uganda is not yet having the capacity to build a nuclear power plant, but is making earnest efforts to prepare for nuclear power programme. These include putting in place appropriate legislation and capacity building in nuclear power technology, implementing human resources development plan, which involves recruiting fresh graduate and sending them abroad for further studies in nuclear science and technology for power generation and regulations, and infrastructure requirement.

Considerations in Emergency Preparedness and Response for a State Embarking on a Nuclear Power Programme (Arabic Edition)

International Nuclear Information System (INIS)

2014-01-01

The aim of this publication is to provide a practical tool for emergency planning for States embarking on a nuclear power programme and to fulfil, in part, functions assigned to the IAEA in the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency ('Assistance Convention'). Under Article 5.a (ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to State Parties and Member States information concerning methodologies, techniques and available results of research relating to such emergencies. As established in the publication Preparedness and Response for a Nuclear or Radiological Emergency (IAEA Safety Standards Series No. GS-R-2), the practical goal of emergency response is 'to ensure that arrangements are in place for a timely, managed, controlled, coordinated and effective response at the scene, and at the local, regional, national and international level, to any nuclear or radiological emergency'. In 2011 the IAEA General Conference, in resolution GC(55)/RES/9, encouraged States 'embarking on new nuclear power programmes to take timely and proactive steps, based upon gradual and systematic application of IAEA safety standards, to establish and sustain a strong safety culture'. It also 'emphasizes the importance for all Member States to implement emergency preparedness and response mechanisms and develop mitigation measures at a national level, consistent with the IAEA's Safety Standards, for improving emergency preparedness and response, facilitating communication in an emergency and contributing to harmonization of national criteria for protective and other actions'. This publication, issued in the IAEA Emergency Preparedness and Response Series, is intended to assist on steps to be taken by States embarking on a nuclear power programme to establish effective national capabilities and arrangements of preparedness for and response to a nuclear or radiological emergency (hereinafter referred to as

Considerations in Emergency Preparedness and Response for a State Embarking on a Nuclear Power Programme (Russian Edition)

International Nuclear Information System (INIS)

2013-01-01

The aim of this publication is to provide a practical tool for emergency planning for States embarking on a nuclear power programme and to fulfil, in part, functions assigned to the IAEA in the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency ('Assistance Convention'). Under Article 5.a (ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to State Parties and Member States information concerning methodologies, techniques and available results of research relating to such emergencies. As established in the publication Preparedness and Response for a Nuclear or Radiological Emergency (IAEA Safety Standards Series No. GS-R-2), the practical goal of emergency response is 'to ensure that arrangements are in place for a timely, managed, controlled, coordinated and effective response at the scene, and at the local, regional, national and international level, to any nuclear or radiological emergency'. In 2011 the IAEA General Conference, in resolution GC(55)/RES/9, encouraged States 'embarking on new nuclear power programmes to take timely and proactive steps, based upon gradual and systematic application of IAEA safety standards, to establish and sustain a strong safety culture'. It also 'emphasizes the importance for all Member States to implement emergency preparedness and response mechanisms and develop mitigation measures at a national level, consistent with the IAEA's Safety Standards, for improving emergency preparedness and response, facilitating communication in an emergency and contributing to harmonization of national criteria for protective and other actions'. This publication, issued in the IAEA Emergency Preparedness and Response Series, is intended to assist on steps to be taken by States embarking on a nuclear power programme to establish effective national capabilities and arrangements of preparedness for and response to a nuclear or radiological emergency (hereinafter referred to as

Considerations in Emergency Preparedness and Response for a State Embarking on a Nuclear Power Programme (Spanish Edition)

International Nuclear Information System (INIS)

2014-01-01

The aim of this publication is to provide a practical tool for emergency planning for States embarking on a nuclear power programme and to fulfil, in part, functions assigned to the IAEA in the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency ('Assistance Convention'). Under Article 5.a (ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to State Parties and Member States information concerning methodologies, techniques and available results of research relating to such emergencies. As established in the publication Preparedness and Response for a Nuclear or Radiological Emergency (IAEA Safety Standards Series No. GS-R-2), the practical goal of emergency response is 'to ensure that arrangements are in place for a timely, managed, controlled, coordinated and effective response at the scene, and at the local, regional, national and international level, to any nuclear or radiological emergency'. In 2011 the IAEA General Conference, in resolution GC(55)/RES/9, encouraged States 'embarking on new nuclear power programmes to take timely and proactive steps, based upon gradual and systematic application of IAEA safety standards, to establish and sustain a strong safety culture'. It also 'emphasizes the importance for all Member States to implement emergency preparedness and response mechanisms and develop mitigation measures at a national level, consistent with the IAEA's Safety Standards, for improving emergency preparedness and response, facilitating communication in an emergency and contributing to harmonization of national criteria for protective and other actions'. This publication, issued in the IAEA Emergency Preparedness and Response Series, is intended to assist on steps to be taken by States embarking on a nuclear power programme to establish effective national capabilities and arrangements of preparedness for and response to a nuclear or radiological emergency (hereinafter referred to as

Development of control system for multi-converter high voltage power supply using programmable SoC

International Nuclear Information System (INIS)

Dave, Rasesh; Singh, N.P.; Thakar, Aruna; Dhola, Hitesh; Gajjar, Sandip; Parmar, Darshan Kumar; Baruah, Ujjwal Kumar; Dharangutti, Jagruti; Zaveri, Tanish

2015-01-01

Multi-converter based High Voltage Power Supplies (HVPSs) find application in multi-megawatt accelerators, RF systems. Control system for HVPS must be a combination of superior parallel processing, real time performance, fast computation and versatile connectivity. The hardware platform is expected to be robust, easily scalable for future developments without any cost overhead. Typical HVPS control mechanism involves communication, generation of precise control signals/pulses for few hundred Nos of chopper and closed loop control in microsecond range for regulated output. Such kind of requirements can be met with Zynq All Programmable SoC, which is a combination of Dual core ARM Cortex A-9 Processing System (PS) and Xilinx 7 series FPGA based Programmable Logic (PL). Deterministic functions of power supply control system such as generation of control signals with precise inter-channel delay of nanosecond range and communication with individual chopper at 100kbps can be implemented on PL. PS should implement corrective tasks based on field feedback received from individual chopper, user interface and OS management that allows to take full advantage of system capabilities. PS and PL are connected with on-chip AXI-4 interface with low latency and higher bandwidth through 9 AXI ports. Typically PS boots first, this ensures secure booting and prevents external environment from tampering PL. This paper describes development of control system on Zynq All Programmable SoC for HVPS. (author)

Development of control system for multi-converter High voltage Power supply using programmable SoC

Science.gov (United States)

Dave, Rasesh; Dharangutti, Jagruti; Singh, N. P.; Thakar, Aruna; Dhola, Hitesh; Gajjar, Sandip; Parmar, Darshan; Zaveri, Tanish; Baruah, Ujjwal

2017-04-01

Multi-converter based High Voltage Power Supplies (HVPSs) find application in multi-megawatt accelerators, RF systems. Control system for HVPS must be a combination of superior parallel processing, real time performance, fast computation and versatile connectivity. The hardware platform is expected to be robust, easily scalable for future developments with minimal overheads. This paper describes development of control system on Zynq All Programmable SoC (System on Chip) for HVPS. Typical HVPS control mechanism involves communication, generation of precise control signals/pulses for few hundred numbers of chopper and closed loop control in microsecond range for regulated output. Such kind of requirements can be met with Zynq All Programmable SoC, which is a combination of Dual core ARM Cortex A-9 Processing System (PS) and Xilinx 7 series FPGA based Programmable Logic (PL). Deterministic functions of power supply control system such as generation of control signals with precise inter-channel delay of nanosecond range and communication with individual chopper at 100kbps can be implemented on PL. PS should implement corrective tasks based on field feedback received from individual chopper, user interface and OS management that allows to take full advantage of system capabilities. PS and PL are connected with on-chip AXI-4 interface with low latency and higher bandwidth through 9 AXI ports. Typically PS boots first, this ensures secure booting and prevents external environment from tampering PL.

Stepwise Decision Making for Long-Term Radioactive Waste Management

International Nuclear Information System (INIS)

Pescatore, Claudio; Vari, Anna

2003-01-01

Consideration is increasingly being given, in radioactive waste management (RWM), to concepts such as 'stepwise decision making' and 'adaptive staging' in which the public, and especially the local communities, are also meaningfully involved in the review and planning of developments. The key feature of these concepts is development by steps or stages that are reversible, within the limits of practicability and provided they meet the requirements of an acceptable safety case. Stepwise decisions are designed to provide reassurance that actions can be reversed if experience shows them to have adverse or unwanted effects. Stepwise decision making has thus come to the fore as being especially important for making progress for radioactive waste management in a manner which is acceptable to large sectors of society. Despite its early identification within the RWM community as an important means for reaching decision in which there is broad-based confidence, stepwise decision making has not been widely debated. Accepted guiding principles of any such process have not yet been formulated, its roots in empirical social science research have not been fully reviewed, nor the difficulties of its implementation analysed. This paper reviews the current developments regarding stepwise decision making in RWM with the aim to pinpoint where it stands, to highlight its societal dimension, to analyse its roots in social sciences, and to identify guiding principles and issues in implementation. It is observed that there is convergence between the approach taken by the practitioners of RWM and the indications received from field studies in social research, and that general guiding principles can be proposed at least as a basis for further discussion. A strong basis for dialogue across disciplines thus exists. General methodological issues are also identified. This paper was developed in the framework of the activities of the NEA Forum on Stakeholder Confidence, which is presented in a

IRIS guidelines. 2014 ed. Integrated Review of Infrastructure for Safety (IRIS) for self-assessment when establishing the safety infrastructure for a nuclear power programme

International Nuclear Information System (INIS)

2014-01-01

The IAEA safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment, and therefore represent what all Member States should achieve, whilst recognizing the ultimate responsibility of each State to ensure safety when implementing a nuclear power programme. IAEA Safety Standards Series No. SSG-16, entitled Establishing the Safety Infrastructure for a Nuclear Power Programme was published in order to provide recommendations, presented in the form of sequential actions, on meeting safety requirements progressively during the initial three phases of the development of safety, as described in INSAG-22, Nuclear Safety Infrastructure for a National Nuclear Power Programme Supported by the IAEA Fundamental Safety Principles. To that end, the 200 safety related actions, which are proposed by SSG-16, constitute a roadmap to establish a foundation for promoting a high level of safety over the entire lifetime of the nuclear power plant. These actions reflect international consensus on good practice in order to achieve full implementation of IAEA safety standards. The IAEA has developed a methodology and tool, the Integrated Review of Infrastructure for Safety (IRIS), to assist States in undertaking self-assessment with respect to SSG-16 recommendations when establishing the safety infrastructure for a nuclear power programme, and to develop an action plan for improvement. The IRIS methodology and the associated tool are fully compatible with the IAEA safety standards and are also used, when appropriate, in the preparation of review missions, such as the Integrated Regulatory Review Service and advisory missions. The present guidelines describe the IRIS methodology for self-assessment against SSG-16 recommendations. Through IRIS implementation, every organization concerned with nuclear safety may gain proper awareness and engage in a continuous progressive process to develop the effective national

Problems faced by Bangladesh in introduction of nuclear power programme

International Nuclear Information System (INIS)

Nurul Islam, A.B.M.; Quaiyum, M.A.; Hasnat, K.A.

1977-01-01

Bangladesh has one of the lowest per capita energy resources and consumption of energy. The per capita GDP of Bangladesh is also one of the lowest in the world. In view of this situation, the need and importance of nuclear power in providing cheaper and reliable energy for economic development of the country is discussed. Constraints being faced by the Bangladesh Atomic Energy Commission (BAEC) in the initiation and development of a national nuclear power programme are dealt with. Following liberation of the country in 1971, its financial resources were mainly channelled for rehabilitation and restoration of its economy. As the size of the national grid has remained relatively small, unit sizes in the range of 100-200 MWe only could be considered for commissioning during the next decade. Lack of vendor interest in such small sizes and the difficulty of arranging long-term investment for nuclear station are the main constraints being faced by the BAEC. Other bottlenecks are due to the uncertainty about the nature and extent of future economic development, pricing policy for available indigenous fossil fuel, national energy planning criteria which are mainly influenced by financial resource constraint, drainage of trained man-power, national priority for various essential non-development expenditures which use up most of the country's own earnings and foreign aid, etc. The effect of the growth of opposition to nuclear power in developed countries on the public acceptability of nuclear power in Bangladesh is analysed. The paper also examines the prospective growth of a cartel of nuclear-exporting countries and its possible effect upon Bangladesh

The discharge of radioactive effluents from the nuclear power programme into western waters of Great Britain

International Nuclear Information System (INIS)

Allday, C.

1977-01-01

A brief account is presented of the British nuclear power programme and the types of radioactive effluent that arise from the power stations and from the Windscale reprocessing plant. Routes by which these effluents could affect human populations, and radiation dose limits which have been laid down, are discussed. The discharge of permitted amounts of activity into western coastal waters of Great Britain, and the requirements for monitoring the discharges, are described. (U.K.)

Options for Management of Spent Fuel and Radioactive Waste for Countries Developing New Nuclear Power Programmes

International Nuclear Information System (INIS)

2013-01-01

One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world.' One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property'. The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. Today, numerous countries are considering construction of their first nuclear power plant or the expansion of a small nuclear power programme, and many of these countries have limited experience in managing radioactive waste and spent nuclear fuel. They often have limited information about available technologies and approaches for safe and long term management of radioactive waste and spent nuclear fuel arising from power reactors. The lack of basic know-how and of a credible waste management strategy could present a major challenge or even an obstruction for countries wishing to

Stepwise transformation behavior of the strain-induced martensitic transformation in a metastable stainless steel

International Nuclear Information System (INIS)

Hedstroem, Peter; Lienert, Ulrich; Almer, Jon; Oden, Magnus

2007-01-01

In situ high-energy X-ray diffraction during tensile loading has been used to investigate the evolution of lattice strains and the accompanying strain-induced martensitic transformation in cold-rolled sheets of a metastable stainless steel. At high applied strains the transformation to α-martensite occurs in stepwise bursts. These stepwise transformation events are correlated with stepwise increased lattice strains and peak broadening in the austenite phase. The stepwise transformation arises from growth of α-martensite embryos by autocatalytic transformation

The development of an integrated nuclear fuel-cycle industry to meet the needs of the Italian nuclear power programme

International Nuclear Information System (INIS)

Angelini, A.M.; Badolato, G.; Clementel, E.

1977-01-01

The paper summarizes the Italian nuclear power station programme, recently approved by the Government, and illustrates the main reasons for the programme, which are in line with those presented at the Geneva Conference in 1971, and which lead to the consideration that nuclear energy is the main source for meeting practically all new electric power requirements in Italy. The implementation of this programme involves considerable nuclear fuel-cycle services, ranging from uranium supply to waste disposal. The industrial strategy to meet these needs is discussed. Technical and economic factors affecting such strategy, both for the fuel cycle as a whole and for its individual phases, are considered. Attention is focused on problems typical of the Italian situation and on various ways of solving them. A prominent feature of the Italian situation is the lack of sizeable domestic uranium resources, which makes it even more important to try, by local industrial efforts, to cover the phases of the cycle subsequent to uranium supply, so as to increase as much as possible the fraction of added value produced inside the country. The present status of the Italian nuclear fuel-cycle industry is reviewed in detail, and its capability of supporting the nuclear programme is analysed. Future development plans are discussed, taking into account the possibility of European co-operation. While the focus is on short- and medium-term programmes, the long-term nuclear programmes are discussed, such as those based on fast breeders, and stress is laid on the need to build up as quickly as possible a strong nuclear fuel-cycle industry. (author)

Outlines of RTE's R and D programme for 2017-2020

International Nuclear Information System (INIS)

2017-01-01

RTE is publishing the outlines of its R and D programme for the 2017-2020 period. The programme is aimed at strengthening RTE's capacity for anticipating the major disruptive transformations with which it will be confronted. RTE is therefore pursuing the efforts initiated during the first roadmap over the 2013-2016 period and is embarking on new efforts. Thus, RTE's R and D efforts for the 2017-2020 period will be structured into six programmes: - The 'asset management' programme. This programme continues on with activities undertaken to reach the use phase for research initiated during the first roadmap. - The 'grid infrastructure evolution' programme. This programme continues the efforts initiated under the 'Grid of the future' programme with a reinforcement of the equipments' eco-design dimension and increased use of digital technologies to implement the equipments' control systems, protection devices and associated defence plans. - The 'environment and society' programme. This programme will be strengthened in relation to the existing programme, particularly as regards the eco-design and biodiversity dimensions. - The 'power system functioning and operation' programme. Firstly, this programme continues on from a large part of the 'Power system' programme with the dual objective of ensuring that the system remains secure with all the major physical transformations leading to a true power system 2.0 (i.e. based on power electronics) and, secondly, it aims to substantially upgrade the system's operating tools through the integration of big data processing and visualisation capabilities. - The 'optimal grid development for the energy transition' programme. This programme is aimed at rethinking grid development study methods and tools in the context of the energy, societal and digital transitions currently underway, with a view to: better integrating cross-functionality with respect to operation / maintenance and asset management / development, and to proposing the

Nuclear power programmes and medium term projections in the OECD area

International Nuclear Information System (INIS)

Miida, J.; Haeussermann, W.; Mankin, S.

1977-01-01

The paper describes nuclear power growth forecasts up to 1985 on an individual country basis for the OECD area, based on present nuclear programmes. For the period between 1985 and the year 2000, no individual countries' estimates are given. The projections for this period are subdivided into three main areas: OECD Europe, North America and OECD Pacific Region. These projections are derived from the presently prevailing estimates concerning total energy growth, the increasing share of electricity requirements in total energy requirements and the growth of the nuclear share in electrical installed capacity. The basic assumptions are discussed and the combination of various possibilities results in upper and lower growth limits, which should include the most likely development. An attempt is also made to describe probable scenarios of nuclear reactor strategies, taking into account developments under way in the OECD area. Finally, the factors liable to influence nuclear power growth in a positive or negative way are briefly analysed

Five years of partnership programme between German and East European nuclear power plant operators

International Nuclear Information System (INIS)

Kraemer, P.

1995-01-01

In a jointly adopted communique in August 1992 the regulations governing the partnerships were laid down. The following principles are given priority: bilateral exchange of operating experience on the basis of equal partnership; the knowledge gained from the exchange of experience is used to improve the operation and safety of the respective partner plant; the partnership programme is free from commercial interests and does not include transfer of funds. Since the establishment of the first partnership relations (Biblis) with an east european nuclear power plant (Balakowo) late in April 1990, a total of 126 reciprocal visits was paid, 82 of which to German nuclear power plants. The balance of the efforts made by German nuclear power plant operators to integrate east european nuclear plant operators can be considered positive. (orig./HP) [de

A generic miniature multi-feature programmable wireless powering headstage ASIC for implantable biomedical systems.

Science.gov (United States)

Kubendran, Rajkumar; Krishnan, Harish; Manola, Bhupendra; John, Simon W M; Chappell, William J; Irazoqui, Pedro P

2011-01-01

Wireless powering holds immense promise to enable a variety of implantable biomedical measurement systems with different power supply and current budget requirements. Effective power management demands more functionality in the headstage design like power level detection for range estimation and power save modes for sleep-wake operation. This paper proposes a single chip ASIC solution that addresses these problems by incorporating digitally programmable features and thus has the potential to enable wireless powering for many implantable systems. The ASIC includes an RF rectifier which has a peak efficiency of 17.9% at 900 MHz and 11.0% at 2.4 GHz, a robust 1 V bandgap reference and LDO voltage regulator whose output can be programmed in the range of 1 V-1.5 V, and can drive upto 4 mA of load current. The input RF power level detector has a threshold of 1.6 V and the power management block can be programmed to give a 6%, 12.5% or 25% duty cycle power line to the transmitter resulting in upto 60% reduction in average power. The ASIC was fabricated using the TSMC 65 nm process, occupies 1mm(2) die area and the headstage consumes ~300 μA at 1.2V regulated supply.

Analysis of replies to an IAEA questionnaire on regulatory practices in Member States with nuclear power programmes

International Nuclear Information System (INIS)

1988-10-01

The survey of regulatory practices in Member States with nuclear power programmes by means of a questionnaire is the first stage of the programme developed by the IAEA to assist the Member States in the enhancement of their regulatory practices. The questionnaire, drafted by IAEA staff members and consultants, consisted of 120 detailed questions and its structure corresponds approximately to the Structure of Code on the Safety of Nuclear Power Plants: Governmental Organizations (IAEA Safety Series No. 50-C-G-Rev.1). The questionnaire was sent to 64 Member States on 7 July 1987 and the replies received from 44 Member States have been analysed by IAEA staff members with the assistance of two consultants in order to identify the main differences in approach and the important features of regulatory practices in Member States. This technical document is the summary report of this analysis

Use of the stepwise progression return-to-play protocol following concussion among practicing athletic trainers

Directory of Open Access Journals (Sweden)

Jessica Wallace

2018-04-01

Full Text Available Purpose: The purpose of this study was to determine whether practicing athletic trainers (ATs were using the stepwise progression to make return-to-play (RTP decisions after concussion and to determine what factors influenced their decision to use the stepwise progression. Methods: A total of 166 ATs (response rate = 16.6% completed a 21-item questionnaire that evaluated participant demographics, methods of concussion management, and RTP decision-making using the stepwise progression. Descriptive statistics and a logistic regression were completed to analyze data. Results: Factors such as education level (p = 0.05 and number of concussions treated (p = 0.05 predicted use of the stepwise progression, whereas sex (p = 0.17, employment setting (p = 0.17, state law (p = 0.86, and years practicing (p = 0.17 did not predict whether ATs were following the stepwise progression. Conclusion: The majority of the ATs from this study are employing the stepwise progression to safely return athletes to play after sustaining a concussion. This demonstrates that ATs are providing a standard of care for concussed athletes across various athletic training settings; however, having a graduate degree and treating more concussions per year are predictors of whether an AT follows all steps of the stepwise progression. Keywords: Athletic trainers, Concussion, Concussion management, Graduate degree, Return to play, Sports medicine, Stepwise progression

EFEKTIVITAS METODE NEW STEPWISE DALAM PEMILIHAN VARIABEL PADA MODEL REGRESI GANDA

Directory of Open Access Journals (Sweden)

Thamrin Tayeb

2017-12-01

Full Text Available New stepwise method is a method of selecting predictor variables in a linear reg- ression model. This method is an extension of the principal component regressi- on, and consists of the selection of the original predictor variables iteratively at the same time, a group of main subset component is selected repeatedly. This me- thod has also the basic properties of the stepwise method. Thus we will get the best combination of stepwise selection and principal component selection me- thods. Model that is obtained by using this method characterizes a low-valued PRESS. The application of this method is not only for linear model, but also can  be expanded to generalized linear models. The comparison of both methods are based on the R2 criteria in the variable selection, obtained R2 value results which are almost the same as those models in the case of solid waste of data, so having payed fully attention to the number of predictor variables entered into the mo- dels, it can be said that the new stepwise method tends to be better than the prin- cipal component regression.

Financial aspects of nuclear power programmes from the experience of the Foratom Member Countries

International Nuclear Information System (INIS)

Riverola Pelayo, R.

1977-01-01

This paper reviews the financial aspects of the nuclear power programme from the experience of the Foratom Member countries. To appreciate the magnitude of the financial requirement the investments for the nuclear programme over the period 1976-85 are related to gross national product and gross capital formation. An examination is made of the sources and systems of financing for nuclear power stations and for all stages of the fuel cycle. The importance of interest during construction of the nuclear plant is considered in detail as, with the lengthening of construction times, this has now become a major factor in the total cost of a nuclear station. The possible accounting conventions under which interest during construction can be treated are examined and a study is made of the investment profile, the cost of money and the effect of inflation. The fiscal aspects of nuclear finance are studied with reference to national regulations and amortization rules. The amortization of nuclear installations also presents certain problems associated with their dismantling once their useful life is over, and this raises the question of the need to create a reserve fund which can commence with the startup of the power plant. For the fuel cycle a distinction can be made between areas of high (economic) risk such as in the prospecting and mining of uranium and the reprocessing of irradiated fuel, and those areas of normal risk such as the manufacture of fuel elements. The difficulties of obtaining credit for the first phase should be considered. (author)

Financial aspects of nuclear power programmes from the experience of the FORATOM member countries

International Nuclear Information System (INIS)

Riverola-Pelayo, R.

1977-01-01

This paper reviews the financial aspects of nuclear power programme from the experience of the FORATOM member countries. To appreciate the magnitude of the financial requirement, the investments for the nuclear programme over the period 1976-85 are related to gross national product and gross capital formation. An examination is made of the sources and systems of financing for nuclear power stations and for all stages of the fuel cycle. The importance of interest during construction of nuclear plant is considered in detail as, with the lengthening of construction times, this has now become a major factor in the total cost of a nuclear station. The possible accounting conventions under which interest during construction can be treated are examined and a study is made of the investment profile, the cost of money and the effect of inflation. The fiscal aspects of nuclear finance are studied with reference to national regulations and amortization rules. The amortization of nuclear installations also presents certain problems associated with their dismantling once their useful life is over and this raises the question of the need to create a reserve fund which can commence with the startup of the power plant. For the fuel cycle, a distinction can be made between phases of high (economic) risk such as in the prospection and mining of uranium and the reprocessing of irradiated fuel, and those areas of normal risk such as the manufacture of fuel elements. The difficulties of obtaining credit for the first phase should be considered

Nine-channel mid-power bipolar pulse generator based on a field programmable gate array

Energy Technology Data Exchange (ETDEWEB)

Haylock, Ben, E-mail: benjamin.haylock2@griffithuni.edu.au; Lenzini, Francesco; Kasture, Sachin; Fisher, Paul; Lobino, Mirko [Centre for Quantum Dynamics, Griffith University, Brisbane (Australia); Queensland Micro and Nanotechnology Centre, Griffith University, Brisbane (Australia); Streed, Erik W. [Centre for Quantum Dynamics, Griffith University, Brisbane (Australia); Institute for Glycomics, Griffith University, Gold Coast (Australia)

2016-05-15

Many channel arbitrary pulse sequence generation is required for the electro-optic reconfiguration of optical waveguide networks in Lithium Niobate. Here we describe a scalable solution to the requirement for mid-power bipolar parallel outputs, based on pulse patterns generated by an externally clocked field programmable gate array. Positive and negative pulses can be generated at repetition rates up to 80 MHz with pulse width adjustable in increments of 1.6 ns across nine independent outputs. Each channel can provide 1.5 W of RF power and can be synchronised with the operation of other components in an optical network such as light sources and detectors through an external clock with adjustable delay.

Novel Programmable Shape Memory Polystyrene Film: A Thermally Induced Beam-power Splitter.

Science.gov (United States)

Li, Peng; Han, Yu; Wang, Wenxin; Liu, Yanju; Jin, Peng; Leng, Jinsong

2017-03-09

Micro/nanophotonic structures that are capable of optical wave-front shaping are implemented in optical waveguides and passive optical devices to alter the phase of the light propagating through them. The beam division directions and beam power distribution depend on the design of the micro/nanostructures. The ultimate potential of advanced micro/nanophotonic structures is limited by their structurally rigid, functional singleness and not tunable against external impact. Here, we propose a thermally induced optical beam-power splitter concept based on a shape memory polystyrene film with programmable micropatterns. The smooth film exhibits excellent transparency with a transmittance of 95% in the visible spectrum and optical stability during a continuous heating process up to 90 °C. By patterning double sided shape memory polystyrene film into erasable and switchable micro-groove gratings, the transmission light switches from one designed light divided directions and beam-power distribution to another because of the optical diffraction effect of the shape changing micro gratings during the whole thermal activated recovery process. The experimental and theoretical results demonstrate a proof-of-principle of the beam-power splitter. Our results can be adapted to further extend the applications of micro/nanophotonic devices and implement new features in the nanophotonics.

Power estimation on functional level for programmable processors

Directory of Open Access Journals (Sweden)

M. Schneider

2004-01-01

Full Text Available In diesem Beitrag werden verschiedene Ansätze zur Verlustleistungsschätzung von programmierbaren Prozessoren vorgestellt und bezüglich ihrer Übertragbarkeit auf moderne Prozessor-Architekturen wie beispielsweise Very Long Instruction Word (VLIW-Architekturen bewertet. Besonderes Augenmerk liegt hierbei auf dem Konzept der sogenannten Functional-Level Power Analysis (FLPA. Dieser Ansatz basiert auf der Einteilung der Prozessor-Architektur in funktionale Blöcke wie beispielsweise Processing-Unit, Clock-Netzwerk, interner Speicher und andere. Die Verlustleistungsaufnahme dieser Bl¨ocke wird parameterabhängig durch arithmetische Modellfunktionen beschrieben. Durch automatisierte Analyse von Assemblercodes des zu schätzenden Systems mittels eines Parsers können die Eingangsparameter wie beispielsweise der erzielte Parallelitätsgrad oder die Art des Speicherzugriffs gewonnen werden. Dieser Ansatz wird am Beispiel zweier moderner digitaler Signalprozessoren durch eine Vielzahl von Basis-Algorithmen der digitalen Signalverarbeitung evaluiert. Die ermittelten Schätzwerte für die einzelnen Algorithmen werden dabei mit physikalisch gemessenen Werten verglichen. Es ergibt sich ein sehr kleiner maximaler Schätzfehler von 3%. In this contribution different approaches for power estimation for programmable processors are presented and evaluated concerning their capability to be applied to modern digital signal processor architectures like e.g. Very Long InstructionWord (VLIW -architectures. Special emphasis will be laid on the concept of so-called Functional-Level Power Analysis (FLPA. This approach is based on the separation of the processor architecture into functional blocks like e.g. processing unit, clock network, internal memory and others. The power consumption of these blocks is described by parameter dependent arithmetic model functions. By application of a parser based automized analysis of assembler codes of the systems to be estimated

Power estimation on functional level for programmable processors

Science.gov (United States)

Schneider, M.; Blume, H.; Noll, T. G.

2004-05-01

In diesem Beitrag werden verschiedene Ansätze zur Verlustleistungsschätzung von programmierbaren Prozessoren vorgestellt und bezüglich ihrer Übertragbarkeit auf moderne Prozessor-Architekturen wie beispielsweise Very Long Instruction Word (VLIW)-Architekturen bewertet. Besonderes Augenmerk liegt hierbei auf dem Konzept der sogenannten Functional-Level Power Analysis (FLPA). Dieser Ansatz basiert auf der Einteilung der Prozessor-Architektur in funktionale Blöcke wie beispielsweise Processing-Unit, Clock-Netzwerk, interner Speicher und andere. Die Verlustleistungsaufnahme dieser Bl¨ocke wird parameterabhängig durch arithmetische Modellfunktionen beschrieben. Durch automatisierte Analyse von Assemblercodes des zu schätzenden Systems mittels eines Parsers können die Eingangsparameter wie beispielsweise der erzielte Parallelitätsgrad oder die Art des Speicherzugriffs gewonnen werden. Dieser Ansatz wird am Beispiel zweier moderner digitaler Signalprozessoren durch eine Vielzahl von Basis-Algorithmen der digitalen Signalverarbeitung evaluiert. Die ermittelten Schätzwerte für die einzelnen Algorithmen werden dabei mit physikalisch gemessenen Werten verglichen. Es ergibt sich ein sehr kleiner maximaler Schätzfehler von 3%. In this contribution different approaches for power estimation for programmable processors are presented and evaluated concerning their capability to be applied to modern digital signal processor architectures like e.g. Very Long InstructionWord (VLIW) -architectures. Special emphasis will be laid on the concept of so-called Functional-Level Power Analysis (FLPA). This approach is based on the separation of the processor architecture into functional blocks like e.g. processing unit, clock network, internal memory and others. The power consumption of these blocks is described by parameter dependent arithmetic model functions. By application of a parser based automized analysis of assembler codes of the systems to be estimated the input

The Wind Energy programme - SFOE Research Programme 2000 - 2003; Programm Wind. Konzept BFE-Forschungsprogramm 'Wind' 2000 - 2003

Energy Technology Data Exchange (ETDEWEB)

Horbaty, R.

2001-07-01

This document, issued by the Swiss Federal Office of Energy (SFOE) describes the concept behind the Swiss wind energy programme. The first part of the report discusses the origins and development of the wind energy programme in Switzerland, discussing the importance of wind energy and policy matters associated with its promotion. The experience gained during the previous research programmes is reviewed. The degree to which targets were reached, promotional activities, the central government's own wind energy activities and the results of a programme evaluation are discussed. Lists of projects that have been realised and activities that have been carried out are presented and positive and negative influences on development are noted. A second part is dedicated to the goals of the wind energy programme in terms of target figures for the year 2010 and the strategies chosen to reach these goals, including pilot and demonstration projects (P and D) and promotional activities. Details of the P and D programme including lists of wind-power projects to be supported, the priorities that have been set and information and further education that is to be provided, are given. New activities in the wind power area such as the development of new type of wind turbine especially suited to alpine conditions are discussed. The role of the Swiss Association for Wind Energy 'Suisse Eole' as a network-partner in the wind energy programme is discussed. An appendix provides details of wind energy projects in Switzerland, market partners and customers. The results of a survey made of wind energy activities at Swiss institutes of higher education are presented.

The development and implementation of a public information programme at the Kozloduy nuclear power plant, Bulgaria

International Nuclear Information System (INIS)

Parker, Keith

1998-01-01

This paper proposes to examine the aims, approach and evaluation of a Public Information Programme currently being undertaken by the British Nuclear Industry Forum. The Kozloduy Nuclear Power Plant has awarded a contract to the British Nuclear Industry Forum to carry out a Public Information Programme with the objective of informing the people of Bulgaria about the content of the Nuclear Safety Account Grant Agreement, the role of the NSA, the role of EBRD and the donor countries in providing the necessary funding, the safety improvement programme being undertaken and the progress being made. The overall aim of the Programme is to build a consensus among energy consumers of the principal issues to be faced in the development and implementation of a Bulgarian energy strategy. There are a number of key elements of the Programme which include: 1) To carry out a communications audit in order to assess current structures and methods of information dissemination. This is to establish the Programme's requirements and provide a detailed operational plan. 2) To assess public opinion and general levels of awareness of the general public, workforce, press, government and industry regarding Kozloduy in order to establish priority messages and create and produce the necessary information material. 3) To review the plant's existing information centre and to provide training and support to facilitate the handling of public and press enquiries and also presentation training for the centre's personnel. 4) To create bespoke outreach programmes which will inform local and national Government, the workforce and local communities, women and schools of safety improvement processes. 5) To implement a media programme which will enable staff at the plant to deal effectively with inquiries and to enable them to anticipate media interest in a range of issues including the safety upgrade. 6) To organise a workshop on issue management so that participants can create and communicate an issue

Targets and criteria for the effective participation of national industry in a domestic nuclear power programme

International Nuclear Information System (INIS)

Py, J.P.

1986-01-01

The interest in maximum use of national resource is common to all countries, the highly industrialized as well as the developing ones. Although benefits can be expected from national participation in a domestic nuclear power programme and may not be limited to this programme, such national participation is restricted by constraining factors: economic, financial, technical and political. Considering the various natures of activities - design, procurement, manufacturing, erection -, their technical difficulties, their potential spin-off effects on the overall industrial development of a country, the paper reviews the materials and components of a nuclear power plants which can be selected as targets for domestic production. The paper also reviews criteria which must be considered in setting these Target materials and components in order to overcome restricting factors to national participation such as cost of national products, financing, investment capability, adequate market size, availability of qualified manpower, industrial capability and quality standards, availability of technology and know-how, conflicts of interests. Some concrete examples drawn from previous experience will illustrate France efforts to overcome these limiting factors [fr

Considerations in Emergency Preparedness and Response for a State Embarking on a Nuclear Power Programme. Publication Date: August 2012

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-09-15

The aim of this publication is to provide a practical tool for emergency planning for States embarking on a nuclear power programme and to fulfil, in part, functions assigned to the IAEA in the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency ('Assistance Convention'). Under Article 5.a (ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to State Parties and Member States information concerning methodologies, techniques and available results of research relating to such emergencies. As established in the publication Preparedness and Response for a Nuclear or Radiological Emergency (IAEA Safety Standards Series No. GS-R-2), the practical goal of emergency response is 'to ensure that arrangements are in place for a timely, managed, controlled, coordinated and effective response at the scene, and at the local, regional, national and international level, to any nuclear or radiological emergency'. In 2011 the IAEA General Conference, in resolution GC(55)/RES/9, encouraged States 'embarking on new nuclear power programmes to take timely and proactive steps, based upon gradual and systematic application of IAEA safety standards, to establish and sustain a strong safety culture'. It also 'emphasizes the importance for all Member States to implement emergency preparedness and response mechanisms and develop mitigation measures at a national level, consistent with the IAEA's Safety Standards, for improving emergency preparedness and response, facilitating communication in an emergency and contributing to harmonization of national criteria for protective and other actions'. This publication, issued in the IAEA Emergency Preparedness and Response Series, is intended to assist on steps to be taken by States embarking on a nuclear power programme to establish effective national capabilities and arrangements of preparedness for and response to a nuclear or radiological emergency (hereinafter referred to as

Considerations in Emergency Preparedness and Response for a State Embarking on a Nuclear Power Programme. Publication Date: August 2012

International Nuclear Information System (INIS)

2012-01-01

The aim of this publication is to provide a practical tool for emergency planning for States embarking on a nuclear power programme and to fulfil, in part, functions assigned to the IAEA in the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency ('Assistance Convention'). Under Article 5.a (ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to State Parties and Member States information concerning methodologies, techniques and available results of research relating to such emergencies. As established in the publication Preparedness and Response for a Nuclear or Radiological Emergency (IAEA Safety Standards Series No. GS-R-2), the practical goal of emergency response is 'to ensure that arrangements are in place for a timely, managed, controlled, coordinated and effective response at the scene, and at the local, regional, national and international level, to any nuclear or radiological emergency'. In 2011 the IAEA General Conference, in resolution GC(55)/RES/9, encouraged States 'embarking on new nuclear power programmes to take timely and proactive steps, based upon gradual and systematic application of IAEA safety standards, to establish and sustain a strong safety culture'. It also 'emphasizes the importance for all Member States to implement emergency preparedness and response mechanisms and develop mitigation measures at a national level, consistent with the IAEA's Safety Standards, for improving emergency preparedness and response, facilitating communication in an emergency and contributing to harmonization of national criteria for protective and other actions'. This publication, issued in the IAEA Emergency Preparedness and Response Series, is intended to assist on steps to be taken by States embarking on a nuclear power programme to establish effective national capabilities and arrangements of preparedness for and response to a nuclear or radiological emergency (hereinafter referred to as

Modernization programme for nuclear power plant units with VVER-1000 in Ukraine

International Nuclear Information System (INIS)

Shenderovich, V.

1997-01-01

All Ukrainian nuclear power plants with WWER type reactors are briefly described from the safety point of view. Information is given on the design and construction of the units. The main goals of upgrading are: elimination of incompliances with current safety standards, improvement of the reliability of safety significant systems, equipment and elements, and implementation of IAEA recommendations. A list of actions making up the large upgrading programme is given; it includes 181 measures to be taken. At present the measures are being designed in order to find appropriate engineering solutions, to develop technical specifications for new equipment, and to ensure precise cost estimation. (M.D.)

Concerted and stepwise mechanisms in cycloaddition reactions: potential surfaces and isotope effects

International Nuclear Information System (INIS)

Houk, K.N.; Yi Li; Storer, Joey; Raimondi, Laura; Beno, Brett

1994-01-01

CASSCF/6-31G * calculations have been performed on concerted and stepwise Diels-Alder reactions of butadiene with ethene, the dimerization of butadiene, and the dimerization of cyclobutadiene. The relative energies of concerted and stepwise mechanisms are compared, and the factors influencing these ''energies of concert'' are discussed. The comparison of calculated isotope effects to experimental data provides support for theoretical results. (Author)

High performance yellow organic electroluminescent devices by doping iridium(III) complex into host materials with stepwise energy levels

Energy Technology Data Exchange (ETDEWEB)

Cui, Rongzhen; Zhou, Liang, E-mail: zhoul@ciac.ac.cn; Jiang, Yunlong; Li, Yanan; Zhao, Xuesen; Zhang, Hongjie, E-mail: hongjie@ciac.ac.cn

2015-10-15

In this work, we aim to further improve the electroluminescent (EL) performances of a yellow light-emitting iridium(III) complex by designing double light-emitting layers (EMLs) devices having stepwise energy levels. Compared with single-EML devices, these designed double-EML devices showed improved EL efficiency and brightness attributed to better balance in carriers. In addition, the stepwise distribution in energy levels of host materials is instrumental in broadening the recombination zone, thus delaying the roll-off of EL efficiency. Based on the investigation of carriers' distribution, device structure was further optimized by adjusting the thickness of deposited layers. Finally, yellow EL device (Commission Internationale de l'Eclairage (CIE) coordinates of (0.446, 0.542)) with maximum current efficiency, power efficiency and brightness up to 78.62 cd/A (external quantum efficiency (EQE) of 21.1%), 82.28 lm/W and 72,713 cd/m{sup 2}, respectively, was obtained. Even at the high brightness of 1000 cd/m{sup 2}, EL efficiency as high as 65.54 cd/A (EQE=17.6%) can be retained. - Highlights: • Yellow electroluminescent devices were designed and fabricated. • P-type and n-type materials having stepwise energy levels were chosen as host materials. • Better balance of holes and electrons causes the enhanced efficiencies. • Improved carriers' trapping suppresses the emission of host material.

Developing a Science and Technology Centre for Supporting the Launching of a Nuclear Power Programme

International Nuclear Information System (INIS)

Badawy, I.

2013-01-01

The present investigation aims at developing a science and technology centre for supporting the launching of a nuclear power [NP] programme in a developing country with a relatively high economic growth rate. The development approach is based on enhancing the roles and functions of the proposed centre with respect to the main pillars that would have effect on the safe, secure and peaceful uses of the nuclear energy -particularly- in the field of electricity generation and sea-water desalination. The study underlines the importance of incorporating advanced research and development work, concepts and services provided by the proposed centre to the NP programme, to the regulatory systems of the concerned State and to the national nuclear industry in the fields of nuclear safety, radiation safety, nuclear safeguards, nuclear security and other related scientific and technical fields including human resources and nuclear knowledge management.

The French nuclear programme

Energy Technology Data Exchange (ETDEWEB)

Feger, M [Ecole Nationale Superieure d' Electrotechnique de Grenoble, Institute National des Sciences et Techniques Nucleaires (Saclay), Gif-sur-Yvette, Electricite de France (France)

1990-06-01

EDF has long been interested in the use of nuclear energy for thermal power generation. After a period of apprenticeship and experiments, EDF launched a major PWR plant programme so as to reduce France's energy dependence and master generation costs. This programme, based on standardization, has achieved the desired results. It must now be adapted to suit the needs of the 21st century. For this programme, all those involved (Governmental authorities, EDF, manufacturers) were mobilized to an unprecedented extent and rigorous working methods were imposed. Experience feedback has been used to make improvements both to the installations themselves and to procedures. Results have proved satisfactory as regards nuclear safety but vigilance must be maintained. Public opinion on nuclear power is reserved we are sentenced to achieving a 'fault-free' track record, all the while mastering costs, so as to ensure the continuing use of nuclear energy. (author)

The French nuclear programme

International Nuclear Information System (INIS)

Feger, M.

1990-01-01

EDF has long been interested in the use of nuclear energy for thermal power generation. After a period of apprenticeship and experiments, EDF launched a major PWR plant programme so as to reduce France's energy dependence and master generation costs. This programme, based on standardization, has achieved the desired results. It must now be adapted to suit the needs of the 21st century. For this programme, all those involved (Governmental authorities, EDF, manufacturers) were mobilized to an unprecedented extent and rigorous working methods were imposed. Experience feedback has been used to make improvements both to the installations themselves and to procedures. Results have proved satisfactory as regards nuclear safety but vigilance must be maintained. Public opinion on nuclear power is reserved we are sentenced to achieving a 'fault-free' track record, all the while mastering costs, so as to ensure the continuing use of nuclear energy. (author)

The role of the nuclear programme in the development of the Romanian power system

International Nuclear Information System (INIS)

Dobos, I.; Popescu, A.; Popovici, D.

2000-01-01

The power system, major component of the Romanian development, is strictly related to the social-economic and technological policy and to the external factors influencing this development. Taking into consideration the future evolution of the electricity demand in Romania over the period 2000-2020, it is necessary to devise an optimized strategy for electricity generation in order to ensure the economic development of the country and to achieve a high standard of living. For these reasons presented are the role of the nuclear programme for different patterns of electricity consumption evolution, taking into account the present situation of Romanian power system, the evolution of the domestic primary energy resources, the fuel prices evolution, the technologies of the electric and thermal power generation and the environmental requirements. The analysis is achieved in the context of the new political and economic trends facing European countries, related to the Joint Agreement with European Community and to the requirements of the single energy market. (author)

Problems faced by Bangladesh in introducing a nuclear power programme

International Nuclear Information System (INIS)

Nurul Islam, A.B.M.; Quaiyum, M.A.; Hasnat, K.A.

1977-01-01

The per capita energy resources and consumption of energy in Bangladesh are among the lowest in the world as in the per capita GDP of the country. The need for and importance of nuclear power in providing cheaper and reliable energy for economic development of the country is discussed in the light of this situation. The constraints faced by the Bangladesh Atomic Energy Commission (BAEC) in the initiation and development of a national nuclear power programme are detailed. Following the liberation of the country in 1971 its financial resources were mainly channelled to the rehabilitation and restoration of the economy. As the size of the national grid has remained relatively small, unit sizes in the range of 50-200MW(e) only could be considered for commissioning. Lack of vendor interest in such small sizes and the difficulty of arranging long-term investment for nuclear stations are the main constraints faced by the BAEC. Other bottlenecks are due to the uncertainty about the nature and extent of future economic development, pricing policy for available indigenous fossil fuel, and national energy planning criteria, which are mainly influenced by the limited financial resources, national priority for various essential non-development expenditures, which use up most of the country's own earnings and foreign aid, etc. Problems that are likely to be faced in future are discussed. These include public acceptability of nuclear power in Bangladesh, the obstacles to the transfer of nuclear technology that may be erected through the prospective growth of a cartel of nuclear-exporting countries, drainage of trained manpower, etc. (author)

Sustainable Industrial Development Programmes of International ...

African Journals Online (AJOL)

However, more insightful corporate entrepreneurship programmes with improved infrastructural and electric power facilities should be encouraged. Increasing support to firms through diverse channels would boost rapid economic development of the sub region. Key words: Sustainable programmes, economic development, ...

A programme in transition

International Nuclear Information System (INIS)

Dean, S.O.

1992-01-01

Fusion is beginning its transition from a scientific research programme to that of an engineering development programme aimed at practical applications. This transition is likely to last a decade or more because many scientific questions remain and because of the magnitude and cost of the engineering issues. This article reviews briefly the encouraging results produced at the Joint European Torus (JET) where 1.7 MW of fusion power was generated for 2 seconds in experiments in November 1991, the remaining scientific issues, the role of near-term experimental reactors like the International Thermonuclear Experimental reactor (ITER) and other approaches to a demonstration power plant. (author)

Cooperation with the Soviet Union in the development of the fuel and power base and in the implementation of the nuclear programme in Czechoslovakia

International Nuclear Information System (INIS)

Harvanek, Z.

1976-01-01

One of the decisive chapters of the long-term programme of international cooperation with the Soviet Union is the solution of the problems of the development of the Czechoslovak fuel and power base, i.e., by the implementation of the nuclear programme. Cooperation in the solution of these tasks is oriented to the following spheres of activity: the realization of and cooperation in research and development tasks, the implementation of project designs based on basic and applied research, and cooperation in the production and assembly of technological equipment for nuclear power production. (J.P.)

Efficient Design of OFDMA-Based Programmable Wireless Radios

Directory of Open Access Journals (Sweden)

Shah SFA

2008-01-01

Full Text Available With the increasing demand for efficient spectrum management, programmable wireless radios can potentially play a key role in shaping our future spectrum use. In this paper, we consider the design of low-power programmable wireless radios based on orthogonal frequency division multiple access (OFDMA. To meet the demands of higher data rate communications, we split OFDMA symbols carrying multiuser data across several noncontiguous bands of available spectrum. To relax power consumption in analog-to-digital and digital-to-analog converters, we use a programmable narrowband RF front end comprising of programmable synthesizers and fixed low-pass filters. To perform digital baseband signal processing in an energy efficient manner, we propose efficient designs for the fast Fourier transform (FFT and inverse FFT (IFFT modules. Our designs of the FFT/IFFT modules reduce power consumption and chip area, and are capable of handling the dynamic nature of spectrum in programmable radios. To recover data that falls within the transition band of the filters, we propose a combiner similar to maximal ratio combiner. We also present the complete design of programmable wireless radios in accordance with the IEEE 802.22 (draft standard.

Efficient Design of OFDMA-Based Programmable Wireless Radios

Directory of Open Access Journals (Sweden)

A. H. Tewfik

2008-03-01

Full Text Available With the increasing demand for efficient spectrum management, programmable wireless radios can potentially play a key role in shaping our future spectrum use. In this paper, we consider the design of low-power programmable wireless radios based on orthogonal frequency division multiple access (OFDMA. To meet the demands of higher data rate communications, we split OFDMA symbols carrying multiuser data across several noncontiguous bands of available spectrum. To relax power consumption in analog-to-digital and digital-to-analog converters, we use a programmable narrowband RF front end comprising of programmable synthesizers and fixed low-pass filters. To perform digital baseband signal processing in an energy efficient manner, we propose efficient designs for the fast Fourier transform (FFT and inverse FFT (IFFT modules. Our designs of the FFT/IFFT modules reduce power consumption and chip area, and are capable of handling the dynamic nature of spectrum in programmable radios. To recover data that falls within the transition band of the filters, we propose a combiner similar to maximal ratio combiner. We also present the complete design of programmable wireless radios in accordance with the IEEE 802.22 (draft standard.

Experience gained in Hungary on the role and responsibility of the public health authority in the nuclear power programme

International Nuclear Information System (INIS)

Sztanyik, L.B.

1983-01-01

The public health service of every country has a basic responsibility for maintaining and continuously improving the standard of health of its population. A significant part of this general responsibility, which has grown in importance in recent years, is radiation protection. While substantial economic, social, medical and scientific benefits are derived from various applications of nuclear energy, health authorities must insist on adequate control to protect the population from excessive exposure to radiation. Safety in the nuclear power industry means the assurance that all operational activities are carried out without undue radiation hazard to the general public and to the persons on-site. It is essential, therefore, that national public health authorities give immediate attention to their responsibilities for radiation protection and ensure the development of an adequate system of control as soon as initiation of a nuclear power programme has been decided. The role and responsibility assigned in Hungary to the public health authority by the government, the development of its organizational structure and of its control system and the actions taken to assert radiation protection requirements in the nuclear power programme of the country from the very beginning of its institution till the commissioning of the first 440 MW(e) unit of the nuclear power plant at Paks are reviewed. (author)

Principals, agents and research programmes

OpenAIRE

Elizabeth Shove

2003-01-01

Research programmes appear to represent one of the more powerful instruments through which research funders (principals) steer and shape what researchers (agents) do. The fact that agents navigate between different sources and styles of programme funding and that they use programmes to their own ends is readily accommodated within principal-agent theory with the help of concepts such as shirking and defection. Taking a different route, I use three examples of research programming (by the UK, ...

In vitro production of buffalo embryos from stepwise vitrified immature oocytes.

Science.gov (United States)

Abd-Allah, Saber Mohammed

2009-01-01

This study was conducted to produce buffalo embryos in vitro from stepwise vitrified immature oocytes. Cumulus oocyte complexes (COCs) were obtained from the ovaries of slaughtered buffalo and were collected from the local abattoir. Selected COCs were exposed to a vitrification solution consisting of 40% ethylene glycol (EG) plus 0.3 M trehalose and 20% polyvinyl pyrrolidone (PVP) for 1 min and loaded in 0.25 ml plastic mini-straws containing 100 microl of 10% sucrose. The loaded cryostraws were cryopreserved by stepwise vitrification and were stored in liquid nitrogen for 4 to 6 months. Data analysis revealed a high percentage of post-thawing morphologically normal immature oocytes (80.7%) with a low percentage of damaged oocytes. There were no significant differences in the maturation (82.1%), cleavage (47.6%) and buffalo embryo development (15.4%) produced by the stepwise vitrified immature oocytes in comparison to the three observations in fresh oocytes (88.3%, 50.4% and 19.4%, respectively, p<0.05).

In vitro production of buffalo embryos from stepwise vitrified immature oocytes

Directory of Open Access Journals (Sweden)

Saber Mohammed Abd-Allah

2009-09-01

Full Text Available This study was conducted to produce buffalo embryos in vitro from stepwise vitrified immature oocytes. Cumulus oocyte complexes (COCs were obtained from the ovaries of slaughtered buffalo and were collected from the local abattoir. Selected COCs were exposed to a vitrification solution consisting of 40% ethylene glycol (EG plus 0.3 M trehalose and 20% polyvinyl pyrrolidone (PVP for 1 min and loaded in 0.25 ml plastic mini-straws containing 100 µl of 10% sucrose. The loaded cryostraws were cryopreserved by stepwise vitrification and were stored in liquid nitrogen for 4 to 6 months. Data analysis revealed a high percentage of post-thawing morphologically normal immature oocytes (80.7% with a low percentage of damaged oocytes. There were no significant differences in the maturation (82.1%, cleavage (47.6% and buffalo embryo development (15.4% produced by the stepwise vitrified immature oocytes in comparison to the three observations in fresh oocytes (88.3%, 50.4% and 19.4%, respectively, p<0.05.

A Data Forward Stepwise Fitting Algorithm Based on Orthogonal Function System

Directory of Open Access Journals (Sweden)

Li Han-Ju

2017-01-01

Full Text Available Data fitting is the main method of functional data analysis, and it is widely used in the fields of economy, social science, engineering technology and so on. Least square method is the main method of data fitting, but the least square method is not convergent, no memory property, big fitting error and it is easy to over fitting. Based on the orthogonal trigonometric function system, this paper presents a data forward stepwise fitting algorithm. This algorithm takes forward stepwise fitting strategy, each time using the nearest base function to fit the residual error generated by the previous base function fitting, which makes the residual mean square error minimum. In this paper, we theoretically prove the convergence, the memory property and the fitting error diminishing character for the algorithm. Experimental results show that the proposed algorithm is effective, and the fitting performance is better than that of the least square method and the forward stepwise fitting algorithm based on the non-orthogonal function system.

Stepwise Analysis of Differential Item Functioning Based on Multiple-Group Partial Credit Model.

Science.gov (United States)

Muraki, Eiji

1999-01-01

Extended an Item Response Theory (IRT) method for detection of differential item functioning to the partial credit model and applied the method to simulated data using a stepwise procedure. Then applied the stepwise DIF analysis based on the multiple-group partial credit model to writing trend data from the National Assessment of Educational…

Questions for considerations in context of launch a nuclear energy programme

International Nuclear Information System (INIS)

2008-01-01

The main problems to be considered at the beginning of a nuclear power programme were presented . This is polish translation of '' Considerations to launch a nuclear programme '' IAEA 2007, printed by National Atomic Agency - Document of Nuclear Power Support Group coordinated by IAEA Department of Nuclear Energy. Strategy elements influencing the political decision, the main programme factors concerning the first nuclear power plant, IAEA support and reference documents are included

Development of the scheme of stepwise combustion of coal in the inverter firebox of a power unit of 1000 MW power

Science.gov (United States)

Prokhorov, V. B.; Chernov, S. L.; Kirichkov, V. S.

2017-09-01

The desire to increase the efficiency of using the heat of burned solid fuel leads to the significant growth of the initial steam parameter at steam-turbine plants. At the maximum temperatures of fresh and secondary steam of 700-720°C, the price of connecting of steam pipelines between the boiler and turbine is up to 20% of the price of a power plant unit, which dictates the necessity to decrease their length. One of the methods to achieve this is the application of an inverter firebox. An M-shaped profile of boiler, allowing one to decrease the length of heat-resistant steam pipelines, was developed at NRU MPEI. A distinctive feature of the profile is two inclined connecting gas flues between the firebox and convective shaft, starting from the gas windows located in the lower third of the firebox height. The boiler was designed for the steam production of 2493 t/h with the parameters of fresh steam of 35 MPa and 710°C. Thermal and aerodynamic calculations made it possible to get the sizes of boiler and dimensions of heating surfaces, and they also allow one to get the values of temperatures in the characteristic points along the gas path. On the basis of the results of calculations, the coefficient of efficiency of the boiler was 93.07% and the fuel consumption was 91.13 kg/s. For this boiler, the technology of effective stepwise burning of coal in a direct-flow-vortex torch (DFVT) in a system of vertical and horizontal tangential torches in the mode of solid slag removal, previously successively used in boilers with a traditional profile and upgraded to an inverter firebox, is proposed. The layouts of the direct-flow burners and nozzles for even and odd vertical sections of the firebox and also in a horizontal section were proposed. Organization of staged air supply in the vertical direction with a high fraction of in-firebox recycle of hot gases leads to low concentration of nitrogen oxides.

Overview on international experimental programmes on power ramping and fission gas release

International Nuclear Information System (INIS)

Knaab, H.; Lang, P.M.; Mogard, H.

1983-01-01

During the last years a number of internationally sponsored experimental programmes were initiated to study the LWR fuel behaviour during ramping and fission gas release at higher burnup levels. Common interest and the limited availability of experimental facilities and appropriate test fuel rods have led to valuable cooperation of many organizations throughout the nuclear community. These programmes are performed by the experimental staff from research centers with their experimental facilities. Fuel vendors and several utilities contribute by supply and irradiation of test fuel rods. The aim of this paper is to provide a synopsis of the following programmes: Studsvik Projects: Interramp, Overramp, Superramp, Demoramp I and II; Petten, High Burnup PWR Ramp Test Programme; Mol, Tribulation Programme; BNWL, High Burnup Effects Programme; Risoe Fission Gas Project; Related tasks within the OECD Halden Reactor Project. The objectives of the programme, their work scope and main results will be summarized on the basis of presently available information. An outlook to future proposed programmes will be given. (author)

Overview on international experimental programmes on power ramping and fission gas release

International Nuclear Information System (INIS)

Knaab, H.; Lang, P.M.

1985-01-01

During the last few years a number of internationally sponsored experimental programmes have been initiated to study LWR fuel behaviour during ramping and fission gas release at high burnup levels. Common interest and the limited availability of experimental facilities and appropriate test fuel rods have led to valuable cooperation between many organizations throughout the nuclear community. These programmes are carried out by experienced staff from research centres using the centres' experimental facilities. Fuel vendors and several utilities contribute by supplying and irradiating the test fuel rods. The aim of this paper is to provide a synopsis of the following programmes: (a) Studsvik Projects: Interramp, Demoramp I and II, Overramp, Superramp; (b) Petten, High Burnup PWR Ramp Test Programme; (c) Mol, Tribulation Programme; (d) BNWL, High Burnup Effects Programme; (e) Riso Fission Gas Project; and (f) related tasks within the OECD Halden Reactor Project. The objectives of the programmes, their scope and the main results will be summarized. An overview of proposed future programmes will be given. (author)

Super-resolution fluorescence microscopy by stepwise optical saturation

Science.gov (United States)

Zhang, Yide; Nallathamby, Prakash D.; Vigil, Genevieve D.; Khan, Aamir A.; Mason, Devon E.; Boerckel, Joel D.; Roeder, Ryan K.; Howard, Scott S.

2018-01-01

Super-resolution fluorescence microscopy is an important tool in biomedical research for its ability to discern features smaller than the diffraction limit. However, due to its difficult implementation and high cost, the super-resolution microscopy is not feasible in many applications. In this paper, we propose and demonstrate a saturation-based super-resolution fluorescence microscopy technique that can be easily implemented and requires neither additional hardware nor complex post-processing. The method is based on the principle of stepwise optical saturation (SOS), where M steps of raw fluorescence images are linearly combined to generate an image with a M-fold increase in resolution compared with conventional diffraction-limited images. For example, linearly combining (scaling and subtracting) two images obtained at regular powers extends the resolution by a factor of 1.4 beyond the diffraction limit. The resolution improvement in SOS microscopy is theoretically infinite but practically is limited by the signal-to-noise ratio. We perform simulations and experimentally demonstrate super-resolution microscopy with both one-photon (confocal) and multiphoton excitation fluorescence. We show that with the multiphoton modality, the SOS microscopy can provide super-resolution imaging deep in scattering samples. PMID:29675306

Outlook for the IAEA's technical co-operation programme

International Nuclear Information System (INIS)

Samiei, Massoud

1998-01-01

This is a slide presentation dealing with the following subjects: - the IAEA's programmes; - the technical co-operation programme; - past trends in the TC programme; - new initiatives in TC; - TC programme profile; - perspectives for the future. The major programmes conducted by IAEA are concerning: - nuclear power and fuel cycle; - nuclear applications; - nuclear, radiation and waste safety, nuclear verification and security material; - management of technical co-operation; - policy making, coordination and support. In relation with the IAEA role in development process the author presents the legal framework for TC, the programme structure, and programme areas, resources, budgets, cycle, approval and implementation. Two plots regarding the recipients with and without NPP's are displayed for the period 1980-1994. Also, according to the status of the member states (without and with nuclear power programme) the programme priorities are presented. For the first case these are: radiation and waste safety, food and agriculture, water resources management human health and nutrition, human resources development, environmental protection and industrial applications. For the second case there are mentioned: radiation and nuclear safety, nuclear power operation and maintenance management, radioactive waste management, environment protection and sustainable energy options. Concerning the regional distribution the following figures are given for 1997: West Asia, 9%; Europe, 18%; Inter-regional, 11%; Africa, 24%; Latin America, 21%; East Asia and Pacific, 17%. In conclusion, the hope is expressed that the value of Technical Co-operation Programme would be seen not only in the successful transfer of technology but also, in the way that the nuclear technologies may satisfy demands for sustainable development by having a lasting impact on the life of the majority in a cost effective and environmentally sound manner

Cushing's syndrome: Stepwise approach to diagnosis

OpenAIRE

Lila, Anurag R.; Sarathi, Vijaya; Jagtap, Varsha S.; Bandgar, Tushar; Menon, Padmavathy; Shah, Nalini S.

2011-01-01

The projected prevalence of Cushing′s syndrome (CS) inclusive of subclinical cases in the adult population ranges from 0.2-2% and it may no longer be considered as an orphan disease (2-3 cases/million/year). The recognition of CS by physicians is important for early diagnosis and treatment. Late-night salivary cortisol, dexamethasone suppressiontesti, or 24-h urine free cortisol are good screening tests. Positively screened cases need stepwise evaluation by an endocrinologist. This paper disc...

Broader utilization of programmable automation equipment in French nuclear power plants: Reflections on the choices made by Electricite de France and French designers

International Nuclear Information System (INIS)

Baudry, Y.; Varaldi, G.

1983-01-01

More than 1000 microprocessors and more than 10,000 data memories in each of the twenty or so 1300 MW units in the French nuclear programme: that was the decision taken by Electricite de France (EDF) in conjunction with the designers in 1974, with the intention of introducing programmable automata on a wide scale in French nuclear power plants. This programme was carried out with the assistance of advanced research services such as the universities, the Commissariat a l'energie atomique (CEA), EDF's design and research service and the designers, most of whom were already EDF suppliers for the 900 MW range. Having used computers for linking sequences (themselves carried out with electromagnetic technology) for its latest natural-uranium gas-cooled graphite-moderated power plants, EDF decided to call a temporary halt, in the case of its 900 MW light-water range, to the use of digital techniques for the control and automation of power plants although it continued to employ such techniques widely in data processing. Thus, the widespread introduction of programmable automata, which was decided upon in 1974/75 at a time when no equivalent existed at the international level, led EDF and French designers to undertake a major development effort in order to meet the requirements - particularly safety and reliability requirements - for such automata to be incorporated into the nuclear field. How does this choice fit in with the logical evolution of the digitalization of French nuclear power plants. What problems has it caused for EDF and French industry. How have these problems been tackled. How have they been overcome. These are the questions dealt with in this paper. (author)

Stepwise adsorption of phenanthrene at the fly ash-water interface as affected by solution chemistry: experimental and modeling studies.

Science.gov (United States)

An, Chunjiang; Huang, Guohe

2012-11-20

Fly ash (FA) is predominantly generated from coal-fired power plants. Contamination during disposal of FA can cause significant environmental problems. Knowledge about the interaction of FA and hydrophobic organic pollutants in the environment is very limited. This study investigated the adsorption of phenanthrene at the interface of FA and water. The performance of phenanthrene adsorption on FA and the effects of various aqueous chemistry conditions were evaluated. The adsorption isotherms exhibited an increasing trend in the adsorbed amounts of phenanthrene, while a stepwise pattern was apparent. A stepwise multisite Langmuir model was developed to simulate the stepwise adsorption process. The adsorption of phenanthrene onto FA was noted to be spontaneous at all temperatures. The thermodynamic results indicated that the adsorption was an exothermic process. The adsorption capacity gradually decreased as pH increased from 4 to 8; however, this trend became less significant when pH was changed from 8 to 10. The binding affinity of phenanthrene to FA increased after the addition of humic acid (HA). The pH variation was also responsible for the changes of phenanthrene adsorption on FA in the presence of HA. High ionic strength corresponded to low mobility of phenanthrene in the FA-water system. Results of this study can help reveal the migration patterns of organic contaminants in the FA-water system and facilitate environmental risk assessment at FA disposal sites.

China: the long wait. [Developments in the nuclear power programme

Energy Technology Data Exchange (ETDEWEB)

1990-03-01

The repercussions of Tiananmen Square coupled with worse than expected balance of payments problems have been made it even more difficult than usual to discern the likely future direction of China's nuclear power programme. Currently there are three power reactors under construction, an indigenously designed 300MWe PWR at Qinsham and the two 900MWe Framatome units at Daya Bay, Guang-dong. Prior to the events of June the most likely way forward, beyond these units under construction, appeared to be development of 600MWe units for Chinese conditions in a joint venture with Western companies. There are strong pressures to ''go indigenous'', and attempt to develop a home grown 600MWe design or, perhaps more likely, go for repeats of the 300 MWe plant - assuming it can be operated successfully, a point on which some factions of the Chinese nuclear industry have their doubts. Nuclear district heating still has strong advocates, as an environmentally sound way of meeting the country's huge projected increases in primary energy consumption over the coming years. Construction of a 5MWt district heating reactor at Tsinghua University, Beijing, started in 1986, entered operation at the end of 1989 following a test phase and is now supplying 3MWt to heating of university buildings. (author).

Considerations in Emergency Preparedness and Response for a State Embarking on a Nuclear Power Programme. Publication Date: June 2013 (French Edition)

International Nuclear Information System (INIS)

2013-01-01

The aim of this publication is to provide a practical tool for emergency planning for States embarking on a nuclear power programme and to fulfil, in part, functions assigned to the IAEA in the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency ('Assistance Convention'). Under Article 5.a (ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to State Parties and Member States information concerning methodologies, techniques and available results of research relating to such emergencies. As established in the publication Preparedness and Response for a Nuclear or Radiological Emergency (IAEA Safety Standards Series No. GS-R-2), the practical goal of emergency response is 'to ensure that arrangements are in place for a timely, managed, controlled, coordinated and effective response at the scene, and at the local, regional, national and international level, to any nuclear or radiological emergency'. In 2011 the IAEA General Conference, in resolution GC(55)/RES/9, encouraged States 'embarking on new nuclear power programmes to take timely and proactive steps, based upon gradual and systematic application of IAEA safety standards, to establish and sustain a strong safety culture'. It also 'emphasizes the importance for all Member States to implement emergency preparedness and response mechanisms and develop mitigation measures at a national level, consistent with the IAEA's Safety Standards, for improving emergency preparedness and response, facilitating communication in an emergency and contributing to harmonization of national criteria for protective and other actions'. This publication, issued in the IAEA Emergency Preparedness and Response Series, is intended to assist on steps to be taken by States embarking on a nuclear power programme to establish effective national capabilities and arrangements of preparedness for and response to a nuclear or radiological emergency (hereinafter referred to as

Nuclear power. Its development in the United Kingdom

International Nuclear Information System (INIS)

Pocock, R.F.

1977-01-01

The subject is covered chronologically in chapters, entitled: from war to peace; the Atomic Energy Authority and the first nuclear power station; a civil power programme; Windscale - the need for caution; research for the future; the new (Magnox) power stations; revision of the nuclear power programme; supply of nuclear fuels; nuclear power for ship propulsion; completion of first programme; Dungeness B and second programme, political assessment of (nuclear) industry's structure; reorganization of the industry; nuclear power in the environment; completion of second programme; the energy crisis; decision on third programme. (U.K.)

Development of the national nuclear programme and preparations for the introduction of nuclear power in Hungary

International Nuclear Information System (INIS)

Szili, G.; Erdoesi, N.; Varga, I.; Ocsai, M.; Szabo, B.

1977-01-01

The paper describes Hungary's energy situation, energy policy and interest in nuclear energy; main targets of the medium-term (by 1990) and long-term (by 2000) nuclear power programme; and preparatory steps for the introduction of nuclear energy. A short technical description is given of the Paks Nuclear Power Station, and of the preparations for construction and erection of Hungary's first nuclear power plant. Fuel supply, basic technical safety aspects and social consequences arising from the plant's erection are discussed. The problems posed by the introduction of nuclear energy which will have to be solved by state administration are summarized. Earlier legislation on projects and works representing radiation danger are described, together with the responsibilities of the various state administrative bodies. Anticipated legal problems are discussed. The participation of Hungarian R and D and design resources in the joint nuclear power development efforts of the CMEA countries is explained and division of design and R and D tasks between various institutes is shown. (author)

Biomass programme: Overview of the 2006 Swiss research programme; Programm Biomasse. Ueberblicksbericht zum Forschungsprogramm 2006

Energy Technology Data Exchange (ETDEWEB)

Binggeli, D.; Guggisberg, B.

2007-07-01

This report for the Swiss Federal Office of Energy (SFOE) reviews work done within the framework of the Swiss biomass research programme in 2006. The programme concentrates on the efficient conversion of biomass into heat, electrical power and motor fuels. Projects concerned with the optimisation of processes are reported on, including low-particle-emission systems, control systems for bivalent heating installations, use of demanding biomass fuels, combined pellets and solar heating systems and the elimination of ammonia emissions. In the material flow area, measurement campaigns, organic pollutants in compost, the effects of fermented wastes in agriculture and methane losses in biogas conditioning are reported on. New conversion technologies are reviewed, including hydro-thermal gasification, plant-oil fuelled combined heat and power units, flameless burners and catalytic direct liquefaction. In the area of basics, studies and concepts, eco-balances and life-cycle analyses are reported on; the production of synthetic natural gas and the influence of combustion particles are discussed and decentralised power generation from solid biomass is reported on. National and international co-operation is reviewed. The report is concluded with a review of eight pilot and demonstration projects, a review of work to be done in 2007 and a list of research and demonstration projects.

NNP Life Management Programmes

International Nuclear Information System (INIS)

Hervia Ruperez, F.

1996-01-01

Around the world, power station owners are increasingly concerned to optimise Plant Life Management. In response, they are setting up Life Management programmes, of more or less ambitious scope and depth. Strategic, economic and security concerns and the close link between life extension work and the improved maintenance practices that are so important today, will increase and global these programmes for monitoring and conservation or mitigation of ageing. These programmes are all based on knowledge of the precise condition of all components and population with the greatest effect on the economics and safety of the plant, and trends in changes in their condition. (Author)

Evaluation tests on controbloc, a programmable automaton for nuclear power plants

International Nuclear Information System (INIS)

Pralus, B.; Bourassin, J.L.; Varaldi, G.

1983-01-01

Controbloc is the programmable automaton used by Electricite de France (EDF) to equip its 1300 MW range of power plants. EDF and the designer CGEE Alsthom have conducted a large number of tests on prototype series equipment to determine whether it matches its specifications. These tests were performed in various laboratories in the Paris area and were concerned with: (1) verifying performance (acquisition, processing and retrieval cycle times - multiplexed exchange performance); (2) the robustness of equipment and its behaviour in industrial conditions (climatic tests in line with IEC regulations - earthquake resistance in particularly severe conditions - resistance to industrial interference); (3) behaviour when internal faults occur, an aspect of particular importance in view of the role played by Controbloc in nuclear power plants; in the event of a failure, safety (incorrect commands must not be given) and availability (resumption of operation) must be guaranteed. A large number of checks have been carried out both by the designer and EDF, the latter having put into operation an original method which is described in the paper. Controbloc has been thoroughly tested and its modular construction has facilitated the performance of these tests. Some shortcomings have been revealed which the designer or EDF has remedied. (author)

The EC-ASEAN COGEN programme

Energy Technology Data Exchange (ETDEWEB)

Pennington, M.; Lacrosse, L. [Asian Institute of Technology (Thailand); Schenkel, Y. [Centre de Recherches Agronomiques (Belgium)

1996-12-31

The EC-ASEAN COGEN Programme is a co-operation programme between the European Commission (EC) and the Association of South East Asian Nations (ASEAN) co-ordinated by the Asian Institute of Technology (AIT), Bangkok, Thailand. Its aim is to accelerate the implementation of proven technologies generating heat and/or power from wood and agroindustrial residues through partnerships between European and ASEAN companies. (orig.)

The EC-ASEAN COGEN programme

Energy Technology Data Exchange (ETDEWEB)

Pennington, M; Lacrosse, L [Asian Institute of Technology (Thailand); Schenkel, Y [Centre de Recherches Agronomiques (Belgium)

1997-12-31

The EC-ASEAN COGEN Programme is a co-operation programme between the European Commission (EC) and the Association of South East Asian Nations (ASEAN) co-ordinated by the Asian Institute of Technology (AIT), Bangkok, Thailand. Its aim is to accelerate the implementation of proven technologies generating heat and/or power from wood and agroindustrial residues through partnerships between European and ASEAN companies. (orig.)

Iran plans world's fourth biggest nuclear programme

International Nuclear Information System (INIS)

Anon.

1977-01-01

Power requirements of projected power generation to 1992, and fuel reserves, in Iran are submitted. The current nuclear programme is outlined. 34000 MWe of nuclear power is planned for the end of the century. (U.K.)

Stepwise Diagnosis for Rotating Machinery Using Force Identification Approach

Directory of Open Access Journals (Sweden)

Shozo Kawamura

2012-01-01

Full Text Available Machine condition monitoring and diagnosis have become increasingly important, and the application of these processes has been widely investigated. The authors previously proposed a stepwise diagnosis method for a beam structure. In that method, the location of the abnormality is first estimated using the force identification approach, and then the cause of the abnormality is identified. In this study, the stepwise diagnosis method was improved specifically for rotating machinery. The applicability of the proposed method was checked by using the experimental data. In the case of a rotor system with unbalance, it was shown that the location of the abnormality and its severity could be identified, and, in the case of a rotor system with stationary rubbing, the location of the abnormality could be accurately identified. Therefore, it was confirmed that the proposed diagnostic method is feasible for actual application.

Multiple-Objective Stepwise Calibration Using Luca

Science.gov (United States)

Hay, Lauren E.; Umemoto, Makiko

2007-01-01

This report documents Luca (Let us calibrate), a multiple-objective, stepwise, automated procedure for hydrologic model calibration and the associated graphical user interface (GUI). Luca is a wizard-style user-friendly GUI that provides an easy systematic way of building and executing a calibration procedure. The calibration procedure uses the Shuffled Complex Evolution global search algorithm to calibrate any model compiled with the U.S. Geological Survey's Modular Modeling System. This process assures that intermediate and final states of the model are simulated consistently with measured values.

Manpower development for nuclear power

International Nuclear Information System (INIS)

1980-01-01

This Guidebook provides policy-makers and managers of nuclear power programmes with information and guidance on the role, requirements, planning and implementation of manpower development programmes. It presents and discusses the manpower requirements associated with the activities of a nuclear power programme, the technical qualifications of this manpower and the manpower development corresponding to these requirements and qualifications. The Guidebook also discusses the purpose and conditions of national participation in the activities of a nuclear power programme

Multi-channel programmable power supply with temperature compensation for silicon sensors

International Nuclear Information System (INIS)

Shukla, R. A.; Achanta, V. G.; Dugad, S. R.; Kurup, A. M.; Lokhandwala, S. S.; Prabhu, S. S.; Freeman, J.; Los, S.; Garde, C. S.; Khandekar, P. D.; Gupta, S. K.; Rakshe, P. S.

2016-01-01

Silicon Photo-Multipliers (SiPMs) are increasingly becoming popular for discrete photon counting applications due to the wealth of advantages they offer over conventional photo-detectors such as photo-multiplier tubes and hybrid photo-diodes. SiPMs are used in variety of applications ranging from high energy physics and nuclear physics experiments to medical diagnostics. The gain of a SiPM is directly proportional to the difference between applied and breakdown voltage of the device. However, the breakdown voltage depends critically on the ambient temperature and has a large temperature co-efficient in the range of 40-60 mV/°C resulting in a typical gain variation of 3%-5%/°C [Dinu et al., in IEEE Nuclear Science Symposium, Medical Imaging Conference and 17th Room Temperature Semiconductor Detector Workshop (IEEE, 2010), p. 215]. We plan to use the SiPM as a replacement for PMT in the cosmic ray experiment (GRAPES-3) at Ooty [Gupta et al., Nucl. Instrum. Methods Phys. Res., Sect. A 540, 311 (2005)]. There the SiPMs will be operated in an outdoor environment subjected to temperature variation of about 15 °C over a day. A gain variation of more than 50% was observed for such large variations in the temperature. To stabilize the gain of the SiPM under such operating conditions, a low-cost, multi-channel programmable power supply (0-90 V) was designed that simultaneously provides the bias voltage to 16 SiPMs. The programmable power supply (PPS) was designed to automatically adjust the operating voltage for each channel with a built-in closed loop temperature feedback mechanism. The PPS provides bias voltage with a precision of 6 mV and measures the load current with a precision of 1 nA. Using this PPS, a gain stability of 0.5% for SiPM (Hamamatsu, S10931-050P) has been demonstrated over a wide temperature range of 15 °C. The design methodology of the PPS system, its validation, and the results of the tests carried out on the SiPM is presented in this

Multi-channel programmable power supply with temperature compensation for silicon sensors

Energy Technology Data Exchange (ETDEWEB)

Shukla, R. A.; Achanta, V. G.; Dugad, S. R., E-mail: dugad@cern.ch; Kurup, A. M.; Lokhandwala, S. S.; Prabhu, S. S. [Tata Institute of Fundamental Research, Mumbai 400005 (India); Freeman, J.; Los, S. [Fermi National Accelerator Laboratory, Batavia, Illinois 60510 (United States); Garde, C. S.; Khandekar, P. D. [Vishwakarma Institute of Information Technology, Pune 411048 (India); Gupta, S. K. [Tata Institute of Fundamental Research, Mumbai 400005 (India); GRAPES-3 Experiment, Cosmic Ray Laboratory, Raj Bhavan, Ooty 643001 (India); Rakshe, P. S. [Vishwakarma Institute of Information Technology, Pune 411048 (India); GRAPES-3 Experiment, Cosmic Ray Laboratory, Raj Bhavan, Ooty 643001 (India)

2016-01-15

Silicon Photo-Multipliers (SiPMs) are increasingly becoming popular for discrete photon counting applications due to the wealth of advantages they offer over conventional photo-detectors such as photo-multiplier tubes and hybrid photo-diodes. SiPMs are used in variety of applications ranging from high energy physics and nuclear physics experiments to medical diagnostics. The gain of a SiPM is directly proportional to the difference between applied and breakdown voltage of the device. However, the breakdown voltage depends critically on the ambient temperature and has a large temperature co-efficient in the range of 40-60 mV/°C resulting in a typical gain variation of 3%-5%/°C [Dinu et al., in IEEE Nuclear Science Symposium, Medical Imaging Conference and 17th Room Temperature Semiconductor Detector Workshop (IEEE, 2010), p. 215]. We plan to use the SiPM as a replacement for PMT in the cosmic ray experiment (GRAPES-3) at Ooty [Gupta et al., Nucl. Instrum. Methods Phys. Res., Sect. A 540, 311 (2005)]. There the SiPMs will be operated in an outdoor environment subjected to temperature variation of about 15 °C over a day. A gain variation of more than 50% was observed for such large variations in the temperature. To stabilize the gain of the SiPM under such operating conditions, a low-cost, multi-channel programmable power supply (0-90 V) was designed that simultaneously provides the bias voltage to 16 SiPMs. The programmable power supply (PPS) was designed to automatically adjust the operating voltage for each channel with a built-in closed loop temperature feedback mechanism. The PPS provides bias voltage with a precision of 6 mV and measures the load current with a precision of 1 nA. Using this PPS, a gain stability of 0.5% for SiPM (Hamamatsu, S10931-050P) has been demonstrated over a wide temperature range of 15 °C. The design methodology of the PPS system, its validation, and the results of the tests carried out on the SiPM is presented in this

Research and development efforts in the implementation of nuclear power programme in Indonesia

International Nuclear Information System (INIS)

Suhaemi, T.

1986-04-01

Research and development efforts in the implementation of nuclear power programme in Indonesia are presented. According to Indonesia Law, the National Atomic Energy Agency (BATAN) is an official body which is reponsible for all aspects of nuclear development. In implementing the nuclear power, BATAN together with the State Electricity Corporation (PLN) have pioneered the introduction of nuclear power plant in Indonesia by carrying out various activities, studies, seminars, workshops and report writings. A nuclear power planning study was carried out jointly with the International Atomic Energy Agency. The feasibility studies were also carried out by NIRA, an Italian consultant firm in cooperation with BATAN and PLN. To improve research and development, BATAN has established 5 research nuclear centres which function as centres of basic and applied research, isotope and radiation application, standardization and calibration and uranium exploration. Nowadays BATAN is constructing a sophisticated and multidisciplinary complex at Serpong near Jakarta. It is hoped that the participation of the national industry can be synchronized to the construction of the first nuclear power in Indonesia. To endorse the movement towards the industrial and technological future, the National Centre for Research, Science and Technology (known as PUSPITEK) has been established. There will be 12 different laboratories providing facilities for research and development of all aspects of technology. For training manpower, BATAN has established the Education and Training Centre (PUSDIKLAT). BATAN has also collaborated with universities, such as Gadjahmada University in Yogyakarta, in establishing Nuclear Engineering Division in the School of Engineering. 6 refs, 3 figs

Overview on recent results of the VTT's research programme on assuring nuclear power plant structural safety

International Nuclear Information System (INIS)

Rintamaa, R.; Aaltonen, P.; Kauppinen, P.; Keinaenen, H.; Talja, H.; Valo, M.; Wallin, K.; Toerroenen, K.

1994-01-01

An overview of the Finnish national research programme on the Nuclear Power Plant Structural Safety, being carried out from 1990 to 1994, is presented. The focus of this paper is on recent results in the areas of experimental and computational fracture mechanics, material deterioration due to neutron irradiation, corrosion and water chemistry, nondestructive testing methods and procedures, and verification of structural integrity assessment methods by large scale component tests. (author). 21 refs, 21 figs, 2 tabs

Strengthening Technical Specialist Training for an Expanding Nuclear Power Programme in the UK

International Nuclear Information System (INIS)

Robertson, John L.

2014-01-01

NTSTS: Future Plans: • Introduce new pathway in Nuclear Reactor Operations into FD/BEng (Plant Engineering) programmes. • Outline curriculum based on INPOs Nuclear Uniform Curriculum for Power Plant Technician, Maintenance and Non-licensed Operations Personnel. • Procurement of generic Pressurised Water Reactor Simulation Suite – due for delivery/commissioning by Sep 2014 • Gen 2 has established a partnership with Tecnatom SA of Spain – experienced in operator training for PWR and BWR. • Proposals to establish a bespoke Reactor Operations Training Centre (ROTC) close to NuGen’s planned AP1000 new build at Moorside, West Cumbria. • In longer term, ROTC could house full scope AP1000 simulator for licensed operator training

RBMK nuclear power plants: Generic safety issues. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

International Nuclear Information System (INIS)

1996-05-01

This report has been prepared on the basis of above mentioned report and it is intended to provide information on RBMK NPPs generic safety issues. As all other insights, recommendations and conclusions resulting from the IAEA Programme, this report is intended to assist national decision makers, who have sole responsibility for the regulation and safe operation of their nuclear power plants. It also serves to focus national and international projects on priority of the RBMK safety improvements. 23 refs, 10 figs, 3 tabs

External man-induced events in relation to nuclear power plant design. A Safety Guide. A publication within the NUSS programme

International Nuclear Information System (INIS)

1996-01-01

In order to take account of lessons learned since the first publication of the NUSS programme was issued, it was decided in 1986 to revise and reissue the Codes and Safety Guides. During the original development of these publications, as well as during the revision process, care was taken to ensure that all Member States, in particular those with active nuclear power programmes, could provide their input. Several independent reviews took place including a final one by the Nuclear Safety Standards Advisory Group (NUSSAG). The revised Codes were approved by the Board of Governors in June 1988. In the revision process new developments in technology and methods of analysis have been incorporated on the basis of international consensus. It is hoped that the revised Codes will be used, and that they will be accepted and respected by Member States as a basis for regulation of the safety of power reactors within the national legal and regulatory framework. 28 refs, 9 figs, 1 tab

Radioecological studies tied to the French nuclear power station programme: aims, nature and mode of execution

International Nuclear Information System (INIS)

Delile, G.

1980-01-01

Under present French practice, assessing the effects of radioactive discharges due to the various likely accident situations comes under 'L'Analyse de Surete Nucleaire' (Nuclear Safety Analysis). The assessment of radioactive discharges relating to normal working comes within the framework of radioecologic studies. Radioecology studies are undertkaen for every power station project. They consist in: - studying what is to be done with radioelements discharged as liquids or gases, - estimating their impact on the populations in the areas of influence of the power station and checking that this impact is permissible, - establishing a surveillance measuring programme for checking against the predictions made and, if required, determining the modifications to be made to the facilities or to their method of operation [fr

Co-ordinated research programme on operator support systems in nuclear power plants. Working material

International Nuclear Information System (INIS)

1993-01-01

In September 1991 the Co-ordinated Research Programme (CRP) on ''Operator Support Systems (OSSs) in Nuclear Power Plants'' was approved in the framework of the Project ''Man-Machine Interface Studies''. The main objective of the programme is to provide guidance and technology transfer in the development and implementation of OSSs. This includes the experience with man-machine interfaces and closely related issues such as control and instrumentation, the use of computers, and operator qualification. The first Co-ordinated Research Meeting held in Vienna, 13-16 October 1992, prepared a summary report which defined the tasks and the responsibilities of the CRP participants. A time schedule and future actions were also agreed upon at this meeting. The second meeting was held in Budapest, Hungary, from 5 to 8 October 1993 and was sponsored by the KFKI Atomic Energy Research Institute. The meeting reviewed the progress of the tasks defined by the first meeting, considered reports on national activities in the subject area, and agreed on time schedule and future actions. The present volume contains: (1) report prepared by the CRP meeting, (2) reports presented by the national delegates, and (3) CRP background and working plan. Refs, figs and tabs

Planning and development of nuclear power programmes in the Federal Republic of Germany

International Nuclear Information System (INIS)

Haunschild, H.H.

1983-01-01

The development of the peaceful utilization of nuclear science and technology in the Federal Republic of Germany started in 1955. It concentrated on the development of nuclear energy with its important potential for energy supply, in order to cover the growing energy demand of the recovering economy, and on the application of nuclear radiation and radioactive isotopes in various areas of science and technology such as biology, medicine, chemistry, physics, materials research and development. From the beginning, the nuclear energy programme was a joint undertaking of government, industry and science. To achieve the necessary impetus and to supplement the activities of industry and universities, several nuclear research centres, in particular at Juelich and Karlsruhe, were founded. This comprehensive approach was the basis for the following rapid development of nuclear technology, as well as for its competitive structure and its safety record. With regard to nuclear energy utilization for electricity generation, heat supply, and ship propulsion a broad range of reactor concepts such as light- and heavy-water reactors, high-temperature reactors, and fast-breeder reactors was examined. Today, nuclear energy meets about 17% of the country's electricity demand. Fifteen nuclear power plants with a capacity of about 10,000 MW(e) are in operation; 11 plants with a total capacity of about 12,000 MW(e) are under construction, and the construction of another 10 plants is definitely planned. Activities in uranium enrichment, fuel element fabrication, and reprocessing have reached the industrial stage. The paper indicates possible future trends of the nuclear programme. The successful development of a national nuclear energy programme goes in parallel with broad international co-operation. Therefore the efforts to re-establish a stable system for co-operation in nuclear commerce and technology, based on international safeguards, should be strengthened

Stepwise magnetic-geochemical approach for efficient assessment of heavy metal polluted sites

Science.gov (United States)

Appel, E.; Rösler, W.; Ojha, G.

2012-04-01

Previous studies have shown that magnetometry can outline the distribution of fly ash deposition in the surroundings of coal-burning power plants and steel industries. Especially the easy-to-measure magnetic susceptibility (MS) is capable to act as a proxy for heavy metal (HM) pollution caused by such kind of point source pollution. Here we present a demonstration project around the coal-burning power plant complex "Schwarze Pumpe" in eastern Germany. Before reunification of West and East Germany huge amounts of HM pollutants were emitted from the "Schwarze Pumpe" into the environment by both fly ash emission and dumped clinker. The project has been conducted as part of the TASK Centre of Competence which aims at bringing new innovative techniques closer to the market. Our project combines in situ and laboratory MS measurements and HM analyses in order to demonstrate the efficiency of a stepwise approach for site assessment of HM pollution around point sources of fly-ash emission and deposition into soil. The following scenario is played through: We assume that the "true" spatial distribution of HM pollution (given by the pollution load index PLI comprising Fe, Zn, Pb, and Cu) is represented by our entire set of 85 measured samples (XRF analyses) from forest sites around the "Schwarze Pumpe". Surface MS data (collected with a Bartington MS2D) and in situ vertical MS sections (logged by an SM400 instrument) are used to determine a qualitative overview of potentially higher and lower polluted areas. A suite of spatial HM distribution maps obtained by random selections of 30 out of the 85 analysed sites is compared to the HM map obtained from a targeted 30-sites-selection based on pre-information from the MS results. The PLI distribution map obtained from the targeted 30-sites-selection shows all essential details of the "true" pollution map, while the different random 30-sites-selections miss important features. This comparison shows that, for the same cost

A review from the regulatory position of the control of occupational exposure associated with the first 20 years of the United Kingdom commercial nuclear power programme

International Nuclear Information System (INIS)

Emmerson, B.W.

1980-01-01

Experience gained by the Nuclear Installations Inspectorate (NII) during the past 20 years in the regulatory control of the nuclear power programme is discussed. After discussing control objectives, the principle sources of occupational exposure associated with the nuclear power programme are tabulated from 1962 to 1979. The fuel reprocessing plants give rise to the highest contribution to radiation dose. It is concluded that there is an improving trend in the radiological exposure pattern despite increasing power generation, fuel burn-up and processing plant throughput. The objective of ensuring that individuals do not exceed the statutory dose limits has largely been achieved. However, optimization procedures will probably be used in the future to optimise procedures and thus exposure data for various tasks will be required. (UK)

MULGRES: a computer program for stepwise multiple regression analysis

Science.gov (United States)

A. Jeff Martin

1971-01-01

MULGRES is a computer program source deck that is designed for multiple regression analysis employing the technique of stepwise deletion in the search for most significant variables. The features of the program, along with inputs and outputs, are briefly described, with a note on machine compatibility.

Chemistry Programme for Water Cooled Nuclear Power Plants. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-01-15

This publication provides guidance on establishing a high standard chemistry programme in accordance with plant safety policy and regulatory requirements. It will be useful to managers of operating organizations and other staff responsible for supporting or monitoring plant activities and for oversight of the plant chemistry programme, as well as to regulatory bodies. Contents: 1. Introduction; 2. Functions, responsibilities and interfaces; 3. Chemistry programme; 4. Chemistry control; 5. Chemistry aspects of radiation exposure optimization; 6. Chemistry surveillance; 7. Management of chemistry data; 8. Training and qualification; 9. Quality control of chemicals and other substances.

Chemistry Programme for Water Cooled Nuclear Power Plants. Specific Safety Guide

International Nuclear Information System (INIS)

2011-01-01

This publication provides guidance on establishing a high standard chemistry programme in accordance with plant safety policy and regulatory requirements. It will be useful to managers of operating organizations and other staff responsible for supporting or monitoring plant activities and for oversight of the plant chemistry programme, as well as to regulatory bodies. Contents: 1. Introduction; 2. Functions, responsibilities and interfaces; 3. Chemistry programme; 4. Chemistry control; 5. Chemistry aspects of radiation exposure optimization; 6. Chemistry surveillance; 7. Management of chemistry data; 8. Training and qualification; 9. Quality control of chemicals and other substances

Progress of China's nuclear power programme

International Nuclear Information System (INIS)

Cai Jianping

1997-01-01

From a long-term point of view, nuclear power is the only solution for the shortage of energy resource. Nuclear power development strategy has been specified in China according to national condition: The electricity development of nuclear power optimizes the national energy structure and ensure the power supply, particularly in east China. China's first self-designed and self-constructed nuclear power plant--Qinshan Nuclear Power Plant (300MWe PWR) is now well under commercial operation. China is willing to cooperate with IAEA, other countries and regions in the field of nuclear energy for peaceful use on basis of mutual benefit. (author)

A stepwise protocol for the treatment of refractory gastroesophageal reflux-induced chronic cough

Science.gov (United States)

Xu, Xianghuai; Lv, Hanjing; Yu, Li; Chen, Qiang; Liang, Siwei

2016-01-01

Background Refractory gastroesophageal reflux-induced chronic cough (GERC) is difficult to manage. The purpose of the study is to evaluate the efficacy of a novel stepwise protocol for treating this condition. Methods A total of 103 consecutive patients with suspected refractory reflux-induced chronic cough failing to a standard anti-reflux therapy were treated with a stepwise therapy. Treatment commences with high-dose omeprazole and, if necessary, is escalated to subsequent sequential treatment with ranitidine and finally baclofen. The primary end-point was overall cough resolution, and the secondary end-point was cough resolution after each treatment step. Results High-dose omeprazole eliminated or improved cough in 28.1% of patients (n=29). Further stepwise of treatment with the addition of ranitide yielded a favorable response in an additional 12.6% (n=13) of patients, and subsequent escalation to baclofen provoked response in another 36.9% (n=38) of patients. Overall, this stepwise protocol was successful in 77.6% (n=80) of patients. The diurnal cough symptom score fell from 3 [1] to 1 [0] (Z=6.316, P=0.000), and the nocturnal cough symptom score decreased from 1 [1] to 0 [1] (Z=–4.511, P=0.000), with a corresponding reduction in the Gastroesophageal Reflux Diagnostic Questionnaire score from 8.6±1.7 to 6.8±0.7 (t=3.612, P=0.000). Conversely, the cough threshold C2 to capsaicin was increased from 0.49 (0.49) µmol/L to 1.95 (2.92) µmol/L (Z=–5.892, P=0.000), and the cough threshold C5 was increased from 1.95 (2.92) µmol/L to 7.8 (5.85) µmol/L (Z=–5.171, P=0.000). Conclusions Sequential stepwise anti-reflux therapy is a useful therapeutic strategy for refractory reflux-induced chronic cough. PMID:26904227

Fourth-order Perturbed Eigenvalue Equation for Stepwise Damage Detection of Aeroplane Wing

Directory of Open Access Journals (Sweden)

Wong Chun Nam

2016-01-01

Full Text Available Perturbed eigenvalue equations up to fourth-order are established to detect structural damage in aeroplane wing. Complete set of perturbation terms including orthogonal and non-orthogonal coefficients are computed using perturbed eigenvalue and orthonormal equations. Then the perturbed eigenparameters are optimized using BFGS approach. Finite element model with small to large stepwise damage is used to represent actual aeroplane wing. In small damaged level, termination number is the same for both approaches, while rms errors and termination d-norms are very close. For medium damaged level, termination number is larger for third-order perturbation with lower d-norm and smaller rms error. In large damaged level, termination number is much larger for third-order perturbation with same d-norm and larger rms error. These trends are more significant as the damaged level increases. As the stepwise damage effect increases with damage level, the increase in stepwise effect leads to the increase in model order. Hence, fourth-order perturbation is more accurate to estimate the model solution.

Taking another look at the IAEA's OSART programme

International Nuclear Information System (INIS)

Franzen, F.L.

1990-01-01

The Operational Safety Review Team (OSART) programme of the International Atomic Energy Agency continues a high level of activity. In 1989 there were eleven OSART missions to nuclear power plants operating or approaching operation. The programme, now in its seventh year, has matured with its implementation. It reflects the principal change in operational safety that has occurred worldwide during these years: utilities operating nuclear power plants and industry organisations supporting the plants have become the spearhead in the international drive for excellence in operational safety. While this may reach beyond and supplement compliance with regulatory requirements, it also affects the IAEA's relation with regulatory authorities and utilities. Utilities have become the most important counterparts of the IAEA in implementing the OSART programme; in fact, the programme is now a special form of utility co-operation under the auspices of the IAEA. (author)

Mali. Challenges for a Developing Country in Building Human Resource Development for Nuclear Power Programmes: Case of Mali

International Nuclear Information System (INIS)

Kone, Nagantie

2014-01-01

Present situation: National Regulatory infrastructure of Radiation Protection: • A legislation and regulations, but not adapted to the case of Nuclear Power Programme; • A Regulatory Body as the sole nuclear institution - very few trained persons in the field of safety and security; - No E and T Institutions; - Lack of adopted system for the management of regulatory activities of practices and activities in NPP field

Porous media fracturing dynamics: stepwise crack advancement and fluid pressure oscillations

Science.gov (United States)

Cao, Toan D.; Hussain, Fazle; Schrefler, Bernhard A.

2018-02-01

We present new results explaining why fracturing in saturated porous media is not smooth and continuous but is a distinct stepwise process concomitant with fluid pressure oscillations. All exact solutions and almost all numerical models yield smooth fracture advancement and fluid pressure evolution, while recent experimental results, mainly from the oil industry, observation from geophysics and a very few numerical results for the quasi-static case indeed reveal the stepwise phenomenon. We summarize first these new experiments and these few numerical solutions for the quasi-static case. Both mechanical loading and pressure driven fractures are considered because their behaviours differ in the direction of the pressure jumps. Then we explore stepwise crack tip advancement and pressure fluctuations in dynamic fracturing with a hydro-mechanical model of porous media based on the Hybrid Mixture Theory. Full dynamic analyses of examples dealing with both hydraulic fracturing and mechanical loading are presented. The stepwise fracture advancement is confirmed in the dynamic setting as well as in the pressure fluctuations, but there are substantial differences in the frequency contents of the pressure waves in the two loading cases. Comparison between the quasi-static and fully dynamic solutions reveals that the dynamic response gives much more information such as the type of pressure oscillations and related frequencies and should be applied whenever there is a doubt about inertia forces playing a role - the case in most fracturing events. In the absence of direct relevant dynamic tests on saturated media some experimental results on dynamic fracture in dry materials, a fast hydraulic fracturing test and observations from geophysics confirm qualitatively the obtained results such as the type of pressure oscillations and the substantial difference in the behaviour under the two loading cases.

Technology Programme

Energy Technology Data Exchange (ETDEWEB)

Batistoni, Paola; De Marco, Francesco; Pieroni, Leonardo [ed.

2005-07-01

The technology activities carried out by the Euratom-ENEA Association in the framework of the European Fusion Development Agreement concern the Next Step (International Thermonuclear Experimental Reactor - ITER), the Long-Term Programme (breeder blanket, materials, International Fusion Materials Irradiation Facility - IFMIF), Power Plant Conceptual Studies and Socio-Economic Studies. The Underlying Technology Programme was set up to complement the fusion activities as well to develop technologies with a wider range of interest. The Technology Programme mainly involves staff from the Frascati laboratories of the Fusion Technical and Scientific Unit and from the Brasimone laboratories of the Advanced Physics Technologies Unit. Other ENEA units also provide valuable contributions to the programme. ENEA is heavily engaged in component development/testing and in design and safety activities for the European Fusion Technology Programme. Although the work documented in the following covers a large range of topics that differ considerably because they concern the development of extremely complex systems, the high level of integration and coordination ensures the capability to cover the fusion system as a whole. In 2004 the most significant testing activities concerned the ITER primary beryllium-coated first wall. In the field of high-heat-flux components, an important achievement was the qualification of the process for depositing a copper liner on carbon fibre composite (CFC) hollow tiles. This new process, pre-brazed casting (PBC), allows the hot radial pressing (HRP) joining procedure to be used also for CFC-based armour monoblock divertor components. The PBC and HRP processes are candidates for the construction of the ITER divertor. In the materials field an important milestone was the commissioning of a new facility for chemical vapour infiltration/deposition, used for optimising silicon carbide composite (SiCf/SiC) components. Eight patents were deposited during 2004

Technology Programme

International Nuclear Information System (INIS)

Batistoni, Paola; De Marco, Francesco; Pieroni, Leonardo

2005-01-01

The technology activities carried out by the Euratom-ENEA Association in the framework of the European Fusion Development Agreement concern the Next Step (International Thermonuclear Experimental Reactor - ITER), the Long-Term Programme (breeder blanket, materials, International Fusion Materials Irradiation Facility - IFMIF), Power Plant Conceptual Studies and Socio-Economic Studies. The Underlying Technology Programme was set up to complement the fusion activities as well to develop technologies with a wider range of interest. The Technology Programme mainly involves staff from the Frascati laboratories of the Fusion Technical and Scientific Unit and from the Brasimone laboratories of the Advanced Physics Technologies Unit. Other ENEA units also provide valuable contributions to the programme. ENEA is heavily engaged in component development/testing and in design and safety activities for the European Fusion Technology Programme. Although the work documented in the following covers a large range of topics that differ considerably because they concern the development of extremely complex systems, the high level of integration and coordination ensures the capability to cover the fusion system as a whole. In 2004 the most significant testing activities concerned the ITER primary beryllium-coated first wall. In the field of high-heat-flux components, an important achievement was the qualification of the process for depositing a copper liner on carbon fibre composite (CFC) hollow tiles. This new process, pre-brazed casting (PBC), allows the hot radial pressing (HRP) joining procedure to be used also for CFC-based armour monoblock divertor components. The PBC and HRP processes are candidates for the construction of the ITER divertor. In the materials field an important milestone was the commissioning of a new facility for chemical vapour infiltration/deposition, used for optimising silicon carbide composite (SiCf/SiC) components. Eight patents were deposited during 2004

Stepwise innovation adoption : a neglected concept in innovation research

NARCIS (Netherlands)

Huizingh, K.R.E.; Brand, M.J.

2009-01-01

Most innovation researchers tend to consider innovation adoption as a binary process, implying that companies have either adopted an innovation or not. In this paper we focus on e-commerce as an innovation that can be adopted stepwise. We distinguish between two levels of e-commerce, basic and

Technique of ICP monitored stepwise intracranial decompression effectively reduces postoperative complications of severe bifrontal contusion

Directory of Open Access Journals (Sweden)

Guan eSun

2016-04-01

Full Text Available Background Bifrontal contusion is a common clinical brain injury. In the early stage, it is often mild, but it progresses rapidly and frequently worsens suddenly. This condition can become life threatening and therefore requires surgery. Conventional decompression craniectomy is the commonly used treatment method. In this study, the effect of ICP monitored stepwise intracranial decompression surgery on the prognosis of patients with acute severe bifrontal contusion was investigated. Method A total of 136 patients with severe bifrontal contusion combined with deteriorated intracranial hypertension admitted from March 2001 to March 2014 in our hospital were selected and randomly divided into two groups, i.e., a conventional decompression group and an intracranial pressure (ICP monitored stepwise intracranial decompression group (68 patients each, to conduct a retrospective study. The incidence rates of acute intraoperative encephalocele, delayed hematomas, and postoperative cerebral infarctions and the Glasgow outcome scores (GOSs 6 months after the surgery were compared between the two groups.Results (1 The incidence rates of acute encephalocele and contralateral delayed epidural hematoma in the stepwise decompression surgery group were significantly lower than those in the conventional decompression group; the differences were statistically significant (P < 0.05; (2 6 months after the surgery, the incidence of vegetative state and mortality in the stepwise decompression group were significantly lower than those in the conventional decompression group (P < 0.05; the rate of favorable prognosis in the stepwise decompression group was also significantly higher than that in the conventional decompression group (P < 0.05.Conclusions The ICP monitored stepwise intracranial decompression technique reduced the perioperative complications of traumatic brain injury through the gradual release of intracranial pressure and was beneficial to the prognosis of

Nuclear safety. Improvement programme

International Nuclear Information System (INIS)

2000-01-01

In this brochure the improvement programme of nuclear safety of the Mochovce NPP is presented in detail. In 1996, a 'Mochovce NPP Nuclear Safety Improvement Programme' was developed in the frame of unit 1 and 2 completion project. The programme has been compiled as a continuous one, with the aim to reach the highest possible safety level at the time of commissioning and to establish good preconditions for permanent safety improvement in future. Such an approach is in compliance with the world's trends of safety improvement, life-time extension, modernisation and nuclear station power increase. The basic document for development of the 'Programme' is the one titled 'Safety Issues and their Ranking for WWER 440/213 NPP' developed by a group of IAEA experts. The following organisations were selected for solution of the safety measures: EUCOM (Consortium of FRAMATOME, France, and SIEMENS, Germany); SKODA Prague, a.s.; ENERGOPROJEKT Prague, a.s. (EGP); Russian organisations associated in ATOMENERGOEXPORT; VUJE Trnava, a.s

Step-wise pulling protocols for non-equilibrium dynamics

Science.gov (United States)

Ngo, Van Anh

The fundamental laws of thermodynamics and statistical mechanics, and the deeper understandings of quantum mechanics have been rebuilt in recent years. It is partly because of the increasing power of computing resources nowadays, that allow shedding direct insights into the connections among the thermodynamics laws, statistical nature of our world, and the concepts of quantum mechanics, which have not yet been understood. But mostly, the most important reason, also the ultimate goal, is to understand the mechanisms, statistics and dynamics of biological systems, whose prevailing non-equilibrium processes violate the fundamental laws of thermodynamics, deviate from statistical mechanics, and finally complicate quantum effects. I believe that investigations of the fundamental laws of non-equilibrium dynamics will be a frontier research for at least several more decades. One of the fundamental laws was first discovered in 1997 by Jarzynski, so-called Jarzynski's Equality. Since then, different proofs, alternative descriptions of Jarzynski's Equality, and its further developments and applications have been quickly accumulated. My understandings, developments and applications of an alternative theory on Jarzynski's Equality form the bulk of this dissertation. The core of my theory is based on stepwise pulling protocols, which provide deeper insight into how fluctuations of reaction coordinates contribute to free-energy changes along a reaction pathway. We find that the most optimal pathways, having the largest contribution to free-energy changes, follow the principle of detailed balance. This is a glimpse of why the principle of detailed balance appears so powerful for sampling the most probable statistics of events. In a further development on Jarzynski's Equality, I have been trying to use it in the formalism of diagonal entropy to propose a way to extract useful thermodynamic quantities such temperature, work and free-energy profiles from far

An Original Stepwise Multilevel Logistic Regression Analysis of Discriminatory Accuracy

DEFF Research Database (Denmark)

Merlo, Juan; Wagner, Philippe; Ghith, Nermin

2016-01-01

BACKGROUND AND AIM: Many multilevel logistic regression analyses of "neighbourhood and health" focus on interpreting measures of associations (e.g., odds ratio, OR). In contrast, multilevel analysis of variance is rarely considered. We propose an original stepwise analytical approach that disting...

Monitoring during the stepwise implementation of the Swedish deep repository for spent fuel

International Nuclear Information System (INIS)

Baeckblom, Goeran; Almen, Karl-Erik

2004-03-01

Monitoring in this report is defined as 'Continuous or repeated observations or measurements of parameters to increase the scientific understanding of the site and the repository, to show compliance with requirements or for adaptation of plans in light of the monitoring results.' The international outlook from IAEA, OECD/NEA, CEC and some country-specific reviews presented in the report forms a necessary background to the Swedish monitoring framework. The implementation of the deep repository in Sweden is executed in phases where monitoring is an inherently integrated activity in the programme. The first phase is the site investigations when Primary Baseline conditions are established. During the following construction phase of the repository, detailed site characterisation continues in conjunction with construction of the access to the deposition area, construction of parts of the deposition area and the central service area. Monitoring is then used to track the changes to the previously established Primary Baseline conditions and distinguishing these imposed changes from natural variations or from other man-made influences. During the initial operation phase, around 200-400 canisters of spent fuel is emplaced and deposition tunnels backfilled. After up-dated evaluations, the phase of regular operation begin, where detailed characterisation, construction of the repository and waste emplacement are concurrent activities. The closure of the repository will take place when all spent fuel has been emplaced, i.e. in the latter part of this century. Monitoring during the stepwise implementation of the repository is executed of several reasons mainly to: describe the Primary Baseline conditions of the repository site, develop and demonstrate understanding of the repository site and the behaviour of engineered barriers, assist in the decision-making process, show compliance with international and national guidelines and regulations. Specific rationales for monitoring are

Experience with respect to dose limitation in nuclear fuel service operations in the United Kingdom supporting civil nuclear power programmes

International Nuclear Information System (INIS)

Kennedy, J.W.

1983-01-01

Within the United Kingdom, the nuclear power generation programme is supported by nuclear fuel services including uranium enrichment, fuel fabrication and reprocessing, operated by British Nuclear Fuels Limited (BNFL). These have entailed the processing of large quantities of uranium and of plutonium and fission products arising in the course of irradiation of fuel in nuclear power stations and have necessitated substantial programmes for the radiological protection of the public and of the workers employed in the industry. This paper presents and reviews the statistics of doses recorded in the various sectors of nuclear fuel services operations against the background of the standards to which the industry is required to operate. A description is given of the development of BNFL policy in keeping with the objective of being recognized as among those industries regarded as safe and the resource implications of measures to reduce doses received by workers are reviewed in the light of experience. Finally, the paper reviews the epidemiological data which have been, and continue to be, collected for workers who have been employed in these nuclear fuel services. (author)

The Community's research and development programme on decommissioning of nuclear power plants. Fourth annual progress report (year 1983)

International Nuclear Information System (INIS)

Anon.

1985-01-01

This is the fourth progress report of the European Community's program. (1979-83) of research on decommissioning of nuclear power plants. It covers the year 1983 and follows the 1980, 1981 and 1982 reports (EUR 7440, EUR 8343, EUR 8962). The present report describes the further progress of research and contains a large amount of results. For a majority of the 51 research contracts composing the 1979-83 programme, work was completed by the end of 1983; the conclusions drawn from this work are in this report. The European Community's program deals with the following fields: long-term integrity of buildings and systems; decontamination for decommissioning purposes; dismantling techniques; treatment of specific wastes materials (steel, concrete and graphite); large transport containers for radioactive waste produced in the dismantling of nuclear power plants; estimation of the quantities of radioactive waste arising from the decommissioning of nuclear power plants in the Community; influence of nuclear power plant design features on decommissioning

Developing the necessary infrastructure. Chapter 1; IAEA activities in support of countries considering embarking on Nuclear Power Programme

International Nuclear Information System (INIS)

Akira, O.

2010-01-01

The IAEA supports in a variety of ways in establishing an appropriate infra-structure necessary to secure safe and reliable operation and still maintaining the international safeguards regime, especially in developing countries which are considering introduction of nuclear power programme. The TC projects to support introduction of nuclear power has been formulated and its number increased significantly recently. Various guidance documents have been published by the IAEA recently to enable progressive development of national infrastructure. The IAEA guidance documents constitute a basis of advises to newcomer countries. The recently formulated important mission is INIR mission to review the status of national infrastructure in the context of measuring the distance to the expected milestone. Finally, it is expected that the newcomers would make informed decision-making on going to nuclear power by fully understanding the necessary obligations and national long-term commitment, by confirming viability of nuclear power options in the country's energy plan through Energy Planning and long-term strategic assessment using IAEA guidance and tools

NOKIA - nuclear power plant monitoring system

International Nuclear Information System (INIS)

Anon.

The monitoring system is described developed specially for the LOVIISA-1 and -2 nuclear power plants with two WWER-440 units. The multiprocessor system of the WWER-440 contains 3 identical main computers. The in core instrumentation is based on stationary self-powered neutron detectors and on thermocouples for measuring the coolant temperature. The system has equipment for the automatic control of the insulation resistance of the self-powered detectors. It is also equipped with a wide range of standard and special programmes. The standard programmes permit the recording of analog and digital data at different frequencies depending on the pre-set requirements. These data are processed and form data files which are accessible from all programmes. The heart of the special programme is a code for the determination of the power distribution in the core of the WWER-440 reactor. The main part of the programme is the algorithm for computing measured neutron fluxes derived from the signals of the self-powered detectors and the algorithm for deriving the global distribution of the neutron flux in the core. The computed power distribution is used for the determination of instantaneous thermal loads and the distribution of burnup in the core. The production programme of the FINNATOM company for nuclear power plants is listed. (B.S.)

Status of nuclear power in India

International Nuclear Information System (INIS)

Srinivasan, M.R.

1976-01-01

The article traces the history of Indian atomic energy programme and deals with the various nuclear power reactors operating commercially and under construction. Development of atomic energy in India is firmly committed to the installation of PHWR's as the mainstay of the country's immediate nuclear power programme. Indian nuclear power programme upto 1982 and major efforts at indigenisation, as reflected by the diminishing foreign exchange component in capital cost of different projects are discussed. Operational highlights of Tarapur atomic power station and Rajasthan atomic power station are reported. (S.K.K.)

RD and D steering of a geological disposal programme in poorly indurated clays

International Nuclear Information System (INIS)

Capouet, M.; Depaus, C.; Van Geet, M.; Lalieux, P.

2014-01-01

and other interested stakeholders in Belgium on a number of aspects, including the regulatory framework and guidance on how to proceed with siting and with the associated decision making. These issues pointed in the direction to urge ONDRAF/NIRAS to develop the frame and tools to embed its national programme in a stepwise decision-making plan with key milestones supported by successive safety cases stretching over the next decades towards the licensing process. The development of the first safety case of its kind (SFC1) led ONDRAF/NIRAs to re-orient the geological disposal programme towards a multifaceted development programme, bringing together technical, regulatory and societal aspects, each of these having their own weights and priorities. To serve these ends, ONDRAF/NIRAS has reassessed the organisation of its geological disposal programme. In recent years ONDRAF/NIRAS has elaborated a safety and feasibility strategy to frame and formalise the stepwise and iterative development of geological disposal in a coherent and integrating manner, able to fulfil all identified management requirements. The strategy sets out in broad terms how it is envisaged that safe disposal will be achieved. It is mainly based on safety principles established by the IAEA which are, among others, passive safety, defence-in-depth, robustness, best available technology and optimisation. The safety and feasibility strategy also includes the boundary conditions to be met and the requirements to be satisfied. Boundary conditions include, for example, relevant international and national regulatory frameworks, institutional policy and conditions required by other stakeholders. Within this strategic frame and along the same safety principles, a safety assessment methodology was also developed for a comprehensive and consistent treatment of uncertainties in order to steer the RD and D. (authors)

Development of domestic capabilities for the Indian nuclear programme

International Nuclear Information System (INIS)

Kakodkar, A.; Sinha, R.K.; Chetal, S.C.; Bhoje, S.B.

2000-01-01

India, has an extensive programme for nuclear power that is self reliant to achieve long term energy security. This paper describes the Indian experience in structuring and implementing the national nuclear programme turned to its natural resources. (author)

The European community's programme of research on the decommissioning of nuclear power plants: objectives, scope and implementation

International Nuclear Information System (INIS)

Huber, B.

1984-01-01

The European Community's research activities on the decommissioning of nuclear installations are aimed at developing effective techniques and procedures for ensuring the protection of man and his environment against the potential hazards from nuclear installations that have been withdrawn from service. The first five-year (1979-1983) programme of research on the decommissioning of nuclear power plants has comprised seven R and D projects concerning the following areas: maintaining disused plants in safe condition; surface decontamination for decommissioning purposes; dismantling techniques; treatment of the main waste materials arising in decommissioning, i.e. steel, concrete and graphite; large containers for decommissioning waste; arisings and characteristics of decommissioning waste; plant design features facilitating decommissioning. The research work was carried out by organizations and companies in the Member States under 51 research contracts, most of them cost-sharing. The Commission is now launching a new five-year (1984-1988) programme of research on the decommissioning of nuclear installations. (author)

Programmable, automated transistor test system

Science.gov (United States)

Truong, L. V.; Sundburg, G. R.

1986-01-01

A programmable, automated transistor test system was built to supply experimental data on new and advanced power semiconductors. The data will be used for analytical models and by engineers in designing space and aircraft electric power systems. A pulsed power technique was used at low duty cycles in a nondestructive test to examine the dynamic switching characteristic curves of power transistors in the 500 to 1000 V, 10 to 100 A range. Data collection, manipulation, storage, and output are operator interactive but are guided and controlled by the system software.

A stepwise approach to stroke surveillance in Brazil: the EMMA (Estudo de Mortalidade e Morbidade do Acidente Vascular Cerebral) study.

Science.gov (United States)

Goulart, Alessandra C; Bustos, Iara R; Abe, Ivana M; Pereira, Alexandre C; Fedeli, Ligia M; Benseñor, Isabela M; Lotufo, Paulo A

2010-08-01

Stroke mortality rates in Brazil are the highest in the Americas. Deaths from cerebrovascular disease surpass coronary heart disease. To verify stroke mortality rates and morbidity in an area of São Paulo, Brazil, using the World Health Organization Stepwise Approach to Stroke Surveillance. We used the World Health Organization Stepwise Approach to Stroke Surveillance structure of stroke surveillance. The hospital-based data comprised fatal and nonfatal stroke (Step 1). We gathered stroke-related mortality data in the community using World Health Organization questionnaires (Step 2). The questionnaire determining stroke prevalence was activated door to door in a family-health-programme neighbourhood (Step 3). A total of 682 patients 18 years and above, including 472 incident cases, presented with cerebrovascular disease and were enrolled in Step 1 during April-May 2009. Cerebral infarction (84.3%) and first-ever stroke (85.2%) were the most frequent. In Step 2, 256 deaths from stroke were identified during 2006-2007. Forty-four per cent of deaths were classified as unspecified stroke, 1/3 as ischaemic stroke, and 1/4 due to haemorrhagic subtype. In Step 3, 577 subjects over 35 years old were evaluated at home, and 244 cases of stroke survival were diagnosed via a questionnaire, validated by a board-certified neurologist. The population demographic characteristics were similar in the three steps, except in terms of age and gender. By including data from all settings, World Health Organization stroke surveillance can provide data to help plan future resources that meet the needs of the public-health system.

Stepwise radical cation Diels-Alder reaction via multiple pathways.

Science.gov (United States)

Shimizu, Ryo; Okada, Yohei; Chiba, Kazuhiro

2018-01-01

Herein we disclose the radical cation Diels-Alder reaction of aryl vinyl ethers by electrocatalysis, which is triggered by an oxidative SET process. The reaction clearly proceeds in a stepwise fashion, which is a rare mechanism in this class. We also found that two distinctive pathways, including "direct" and "indirect", are possible to construct the Diels-Alder adduct.

Lower-power, high-linearity class-AB current-mode programmable gain amplifier

International Nuclear Information System (INIS)

Wu Yiqiang; Wang Zhigong; Wang Junliang; Ma Li; Xu Jian; Tang Lu

2014-01-01

A novel class-AB implementation of a current-mode programmable gain amplifier (CPGA) including a current-mode DC offset cancellation loop is presented. The proposed CPGA is based on a current amplifier and provides a current gain in a range of 40 dB with a 1 dB step. The CPGA is characterized by a wide range of current gain variation, a lower power dissipation, and a small chip size. The proposed circuit is fabricated using a 0.18 μm CMOS technology. The CPGA draws a current of less than 2.52 mA from a 1.8 V supply while occupying an active area of 0.099 μm 2 . The measured results show an overall gain variation from 10 to 50 dB with a gain error of less than 0.40 dB. The OP 1dB varies from 11.80 to 13.71 dBm, and the 3 dB bandwidth varies from 22.2 to 34.7 MHz over the whole gain range. (semiconductor integrated circuits)

Electricity research programme - Overview report on activities in 2005; Programm Elektrizitaet. Ueberblicksbericht zum Forschungsprogramm 2005

Energy Technology Data Exchange (ETDEWEB)

Brueniger, R.

2006-07-01

This overview-report for the Swiss Federal Office of Energy (SFOE) summarises the work done in 2005 in the various research areas covered by the Swiss Electricity Research programme. Work done in the programme's two main areas - technologies and efficient applications - is reviewed. In the technologies area, high-temperature superconductivity - and especially its use in power-generation facilities - is looked at, as are the topics of energy conversion and thermo-electric power generation. Further, energy storage using compressed-air is discussed. Power distribution and the use of controllable storage in the low-voltage mains is briefly commented on, as is distributed power generation. Information and communications technologies are reviewed, as is work done in the electrical drives area. Work in other areas summarised includes lighting and uninterruptible power-supplies. Co-operation with Swiss institutions and international organisations such as the IEA is reviewed. Implementation work in the pilot and demonstration area is commented on. This includes work in various areas ranging from set-top boxes through to the optimisation of compressed-air systems and electrical drives as well as codes of conduct and agreements for water-dispensers and cooling systems in retail applications and the optimisation of wastewater treatment plant. The report is completed with a list of current research and development projects.

Country Nuclear Power Profiles. 2016 Edition

International Nuclear Information System (INIS)

2016-12-01

The Country Nuclear Power Profiles compile background information on the status and development of nuclear power programmes in Member States. The publication summarizes organizational and industrial aspects of nuclear power programmes and provides information about the relevant legislative, regulatory and international framework in each State. Its descriptive and statistical overview of the overall economic, energy and electricity situation in each State and its nuclear power framework is intended to serve as an integrated source of key background information about nuclear power programmes throughout the world. This 2016 edition, issued on CD-ROM, contains updated country information for 51 States.

Country Nuclear Power Profiles - 2015 Edition

International Nuclear Information System (INIS)

2015-08-01

The Country Nuclear Power Profiles compile background information on the status and development of nuclear power programmes in Member States. The publication summarizes organizational and industrial aspects of nuclear power programmes and provides information about the relevant legislative, regulatory and international framework in each State. Its descriptive and statistical overview of the overall economic, energy and electricity situation in each State and its nuclear power framework is intended to serve as an integrated source of key background information about nuclear power programmes throughout the world. This 2015 edition, issued on CD-ROM, contains updated country information for 51 States

Application of stepwise multiple regression techniques to inversion of Nimbus 'IRIS' observations.

Science.gov (United States)

Ohring, G.

1972-01-01

Exploratory studies with Nimbus-3 infrared interferometer-spectrometer (IRIS) data indicate that, in addition to temperature, such meteorological parameters as geopotential heights of pressure surfaces, tropopause pressure, and tropopause temperature can be inferred from the observed spectra with the use of simple regression equations. The technique of screening the IRIS spectral data by means of stepwise regression to obtain the best radiation predictors of meteorological parameters is validated. The simplicity of application of the technique and the simplicity of the derived linear regression equations - which contain only a few terms - suggest usefulness for this approach. Based upon the results obtained, suggestions are made for further development and exploitation of the stepwise regression analysis technique.

Opening Address [International Conference on Human Resource Development for Introducing and Expanding Nuclear Power Programmes, Abu Dhabi (United Arab Emirates), 14-18 March 2010

Energy Technology Data Exchange (ETDEWEB)

Amano, Y [International Atomic Energy Agency, Vienna (Austria)

2012-10-15

Full text: It is a pleasure for me to open this IAEA conference on Human Resource Development for Introducing and Expanding Nuclear Power Programmes. I am very grateful to the Government of the United Arab Emirates for hosting this important event. As you know, the world is witnessing a resurgence of interest in nuclear power. The IAEA has projects on introducing nuclear power with no fewer than 58 of our Member States. We expect between 10 and 25 new countries to bring their first nuclear power plants on line by 2030. These are momentous changes. However, some countries are concerned about a possible shortage of skilled professionals in the nuclear field in the coming decades. The generation of professionals who built and led the nuclear power industry for much of the past 50 years is approaching retirement and in some countries not enough students are coming up through the educational system to take their place. Naturally, we, at the IAEA, want to do all we can to help Member States address this issue. That is why we have organized this conference. The situation is different in each country. For countries with expanding nuclear power programmes, the challenge is to scale up their existing education and training in order to have the required qualified workforce on time. Countries planning to supply nuclear technology to others must not only meet their national human resource needs, but also be able to transfer education and training capacity together with the technology they provide. Finally, countries embarking on nuclear power cannot become too dependent on their technology supplier and need to develop their own home grown expertise and skills base. The IAEA would be happy to help interested States to formulate country specific policies on human resource development, education, training and knowledge management in support of nuclear power programmes. We could also help countries make better use of training facilities, research reactors and other educational

Termo technology programme. Final report 1993-1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-31

The TERMO-technology programme was realised in 1993-1997. The aim of the programme was to promote the profitability and sustainable development of district heating by means of research and development actions. The programme included 36 research projects that were distributed to four research areas. These included heat distribution, metering, information and control systems, the economy of district heating as well as system development. The costs totaled to FIM 12 million. The programme was financed by the participating companies and the Technology Development Centre TEKES. Around eighty Finnish companies and institutions participated in the programme. In addition, the programme participated in international research cooperation in the framework of the Nordic Council of Ministers and the International Energy Agency programmes. The research area Heat Distribution included projects on rehabilitation and status control of district heating networks, pumping, thermal stresses in district heating pipes, material questions, water treatment, steam pipe systems as well as drag reducing additives in district heating water. The research area Metering, Information and Control Systems included projects on forecasts of district heating load, calibration of flow meters, heat cost allocation in buildings, control systems and their qualifications in buildings and improved cooling of district heating water in the consumer equipment. The research area Economy included projects on determination of subscribed heat demand, pricing methods of district heating, success factors of energy companies as well as long term prospects of district heating in Finland. The research area System Development included projects on changing heat loads, district cooling as well as combined heat and power production. After the TERMO programme joint efforts will be continued for the development of district heating technology. The emphasis will be to improve the feasibility of combined heat and power

Molecular Fingerprinting Approach in Plant Species Evaluation for a Nuclear Power Programme

International Nuclear Information System (INIS)

Azhar Mohamed

2011-01-01

Deoxyribonucleic acid (DNA) as a tool for marker technology is found to be remarkable, advanced and exciting in recent years. DNA markers are valuable tools and important in various plant breeding analyses for identification, gene mapping, marker systems and mutagenesis response. As gene expression is related to concurrent cellular activities and is mobilised in the adaptation of plants to adverse environmental conditions, changes at the DNA levels can be detected simultaneously. The changes also reflect response onto plant traits in which selection for better quality plant materials can be made and/or used as bio-indicator response in tracking any environmental change. The objective of the present study is to show Inter Simple Sequence Repeat (ISSR) markers as an important technique in differentiating plant DNA genomic in various species for the evaluation of their diversity and radiation effects in population. The technique has been found to be rapid, simple, reliable and robust in generating molecular fingerprinting database in bio surveillance for a nuclear power programme. (author)

Stepwise dehydrogenation of ammonia on Fcc-Co surfaces: A DFT study

Energy Technology Data Exchange (ETDEWEB)

Ma, F.F.; Ma, S.H., E-mail: mash.phy@htu.edu.cn; Jiao, Z.Y.; Dai, X.Q.

2017-05-31

Highlights: • On Co surfaces, oxygen atom not only strengthens ammonia-substrate interaction but also facilitates ammonia dissociation on the Co surfaces. • Pre-adsorbed O atom significantly promotes the stepwise dehydrogenation of ammonia on Co(110), giving rise to N atom strongly binding with the surface. • The dissociation of NH appears to be the rate-determining step on O-covered Co(111) and Co(100) surfaces. • The species N and NH produced in ammonia dehydrogenation are likely responsible for cobalt catalyst deactivation in the excess of oxygen atom. - Abstract: The stepwise dehydrogenation of ammonia on clean and O-covered Co surfaces have been studied by performing density functional theory (DFT) calculations. It is found that the interaction of species NH{sub x} (x = 0–3) with the Co surfaces become stronger with its further dehydrogenation, and oxygen atom not only strengthens ammonia-substrate interaction but also facilitates ammonia dissociation. Specifically, pre-adsorbed O atom significantly promotes the stepwise dehydrogenation of ammonia on Co(110), giving rise to N atom strongly binding with the surface. In contrast, the dissociation of NH appears to be the rate-determining step on O-covered Co(111) and Co(100) surfaces, due to the high energy barriers. And present results demonstrate that the species N and NH produced in ammonia dehydrogenation are likely responsible for cobalt catalyst deactivation in the excess of oxygen atom.

Stepwise dehydrogenation of ammonia on Fcc-Co surfaces: A DFT study

International Nuclear Information System (INIS)

Ma, F.F.; Ma, S.H.; Jiao, Z.Y.; Dai, X.Q.

2017-01-01

Highlights: • On Co surfaces, oxygen atom not only strengthens ammonia-substrate interaction but also facilitates ammonia dissociation on the Co surfaces. • Pre-adsorbed O atom significantly promotes the stepwise dehydrogenation of ammonia on Co(110), giving rise to N atom strongly binding with the surface. • The dissociation of NH appears to be the rate-determining step on O-covered Co(111) and Co(100) surfaces. • The species N and NH produced in ammonia dehydrogenation are likely responsible for cobalt catalyst deactivation in the excess of oxygen atom. - Abstract: The stepwise dehydrogenation of ammonia on clean and O-covered Co surfaces have been studied by performing density functional theory (DFT) calculations. It is found that the interaction of species NH x (x = 0–3) with the Co surfaces become stronger with its further dehydrogenation, and oxygen atom not only strengthens ammonia-substrate interaction but also facilitates ammonia dissociation. Specifically, pre-adsorbed O atom significantly promotes the stepwise dehydrogenation of ammonia on Co(110), giving rise to N atom strongly binding with the surface. In contrast, the dissociation of NH appears to be the rate-determining step on O-covered Co(111) and Co(100) surfaces, due to the high energy barriers. And present results demonstrate that the species N and NH produced in ammonia dehydrogenation are likely responsible for cobalt catalyst deactivation in the excess of oxygen atom.

Technology transfer in the Spanish nuclear programme

International Nuclear Information System (INIS)

Perez-Naredo, F.

1983-01-01

The paper describes the process of technology transfer under the Spanish nuclear programme and its three generations of nuclear power plants during the last 20 years, with special reference to the nine new plants equipped with Westinghouse pressurized water reactors and the rising level of national involvement in these stations. It deals with the development of Westinghouse Nuclear's organization in Spain, referring to its staff and to the manufacturers who supply equipment for the programme, going into particular detail where problems of quality assurance are concerned. In conclusion, it summarizes the present capacity of Spanish industry in various areas connected with the design, manufacture and construction of nuclear power plants. (author)

Tidal energy UK Government R and D programme. Final report

International Nuclear Information System (INIS)

Craig, J.W.; Davies, L.M.; Allington, M.A.

1996-05-01

The United Kingdom Government's research programme into the feasibility of exploiting tidal power for electricity generation in Britain's estuaries is described in this document. The history of the research is included from the Severn Barrage Committee in 1978 to the conclusion of the tidal energy barrages programme in 1994. The programme sought to reduce uncertainty on costs, technical performance and environmental and regional effects, in order to firm up on decisions on whether to construct certain specific barrages. It was concluded that, while technically feasible, tidal power from barrages, was and will continue to be uneconomic compared with other energy sources. Other renewable technologies would receive further research. (UK)

An Inter-Networking Mechanism with Stepwise Synchronization for Wireless Sensor Networks

Directory of Open Access Journals (Sweden)

Masayuki Murata

2011-08-01

Full Text Available To realize the ambient information society, multiple wireless networks deployed in the region and devices carried by users are required to cooperate with each other. Since duty cycles and operational frequencies are different among networks, we need a mechanism to allow networks to efficiently exchange messages. For this purpose, we propose a novel inter-networking mechanism where two networks are synchronized with each other in a moderate manner, which we call stepwise synchronization. With our proposal, to bridge the gap between intrinsic operational frequencies, nodes near the border of networks adjust their operational frequencies in a stepwise fashion based on the pulse-coupled oscillator model as a fundamental theory of synchronization. Through simulation experiments, we show that the communication delay and the energy consumption of border nodes are reduced, which enables wireless sensor networks to communicate longer with each other.

Investigation and evaluation of erosion-corrosion status of the secondary side steam-water system at Paks Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Schunk, J.; Patek, G.; Pinter, T.; Baracska Varju, I.; Doma, A.; Kovacs, A.; Nemeth, P.; Tilky, P. [Paks Nuclear Power Plant Ltd (Hungary); Osz, J. [Budapest Univ. of Science and Economy (Hungary)

2009-07-01

There were four identical VVER-440 type units installed at Paks Nuclear Power Plant with 440 MW electrical capacity of each, between 1982 and 1987. Based on inherent reserve capacity of these units, the operational and maintenance experiences and examples of power upgrading abroad it was decided to increase the power of our units in a stepwise way. Presently, this upgrading project is close to finalization resulting in 500 MW electrical capacity of each unit. To realize the planned electrical power increase it was necessary to increase the primary and secondary heat power, which requested the increase of mass flow, temperature and pressure of secondary coolant flowing through the steam generators. According to the preliminary expert evaluations these increased parameters would not cause such an increase in humidity of steam leaving the turbine houses that could adversely impair our long term power upgrading plans. The steam humidity was determined on our units and the values did not even exceed the original design values. In spite of these preliminary investigations, significant accumulation of erosion-corrosion products at different places of secondary circuit was found and erosion damages of some secondary side equipment were discovered as a probable consequence of power upgrading. An extensive evaluation programme has been started involving experts and institutes of material testing, chemistry and hydrodynamics. Results and details of that work are given in our presentation. (authors)

Spinoffs from radiological emergency preparedness programmes to generic emergency management

International Nuclear Information System (INIS)

Sanders, M.E.

1986-01-01

In the USA, the radiological emergency preparedness (REP) programme for nuclear power plants is being used to enhance emergency management programmes for other types of emergencies. The REP programme is particularly useful in developing plans and preparedness measures for chemical accidents. The Integrated Emergency Management System (IEMS) approach provides a means for maximizing relationships between the REP programme and other programmes. IEMS essentially involves applying common elements of planning and preparedness to all types of emergencies, while recognizing that unique characteristics of specific natural and man-made emergencies require special planning and preparedness considerations. Features of the REP programme that make it compatible with the IEMS approach and useful in coping with other types of emergencies are: (1) the close co-operation between the national nuclear regulatory and emergency management organizations; (2) the programme integration among all levels of government, the nuclear power industry, public interest groups and the general public and (3) the comprehensiveness and sophistication of the programme. The REP programme in the USA represents a state-of-the-art emergency management capability. Some of its elements are readily transferrable to most other types of emergency preparedness programmes, while other elements can be adapted more readily to other hazard-specific programmes. The Bhopal accident has been a catalyst for this adaptation to chemical accidents, in such areas as furnishing hazard-specific information to the public, alert and notification systems, definition of the hazards and risks involved, establishing planning zones and developing close working relationships among the industry, the public and government

Large-scale road safety programmes in low- and middle-income countries: an opportunity to generate evidence.

Science.gov (United States)

Hyder, Adnan A; Allen, Katharine A; Peters, David H; Chandran, Aruna; Bishai, David

2013-01-01

The growing burden of road traffic injuries, which kill over 1.2 million people yearly, falls mostly on low- and middle-income countries (LMICs). Despite this, evidence generation on the effectiveness of road safety interventions in LMIC settings remains scarce. This paper explores a scientific approach for evaluating road safety programmes in LMICs and introduces such a road safety multi-country initiative, the Road Safety in 10 Countries Project (RS-10). By building on existing evaluation frameworks, we develop a scientific approach for evaluating large-scale road safety programmes in LMIC settings. This also draws on '13 lessons' of large-scale programme evaluation: defining the evaluation scope; selecting study sites; maintaining objectivity; developing an impact model; utilising multiple data sources; using multiple analytic techniques; maximising external validity; ensuring an appropriate time frame; the importance of flexibility and a stepwise approach; continuous monitoring; providing feedback to implementers, policy-makers; promoting the uptake of evaluation results; and understanding evaluation costs. The use of relatively new approaches for evaluation of real-world programmes allows for the production of relevant knowledge. The RS-10 project affords an important opportunity to scientifically test these approaches for a real-world, large-scale road safety evaluation and generate new knowledge for the field of road safety.

The Czech Republic programme and experiences on training and qualification for NPPs personnel

International Nuclear Information System (INIS)

Kovar, P.

1993-01-01

The nuclear power programme in Czech Republic is based on commercial use of WWER-type reactors. This document discusses future scope of nuclear programme in Czech Republic and status of training programme for NPP personnel

Application of Field Programmable Gate Arrays in Instrumentation and Control Systems of Nuclear Power Plants

International Nuclear Information System (INIS)

2016-01-01

Field programmable gate arrays (FPGAs) are gaining increased attention worldwide for application in nuclear power plant (NPP) instrumentation and control (I&C) systems, particularly for safety and safety related applications, but also for non-safety ones. NPP operators and equipment suppliers see potential advantages of FPGA based digital I&C systems as compared to microprocessor based applications. This is because FPGA based systems can be made simpler, more testable and less reliant on complex software (e.g. operating systems), and are easier to qualify for safety and safety related applications. This publication results from IAEA consultancy meetings covering the various aspects, including design, qualification, implementation, licensing, and operation, of FPGA based I&C systems in NPPs

Fusion - the programme in the UK - and other thoughts

International Nuclear Information System (INIS)

Carruthers, R

1978-01-01

The Fusion Programme in the Euratom--UKAEA Fusion Association is mainly one of plasma confinement studies in four major experimental areas. Conceptual studies of fusion reactors have been based upon the tokamak and the reversed field pinch. Particular attention has been given to the potential operating problems of toroidal fusion reactors in order to establish design principles which take note of the high availability essential in a power plant. Future plans for fusion power programmes are discussed and it is suggested that they are not obviously the quickest or most cost effective ways to establishing the credibility of fusion. It is proposed that a more aggressive programme which involved taking calculated risks could be quicker and cheaper. An additional, important advantage would be to attract into the fusion programme good engineers who feel the need to be motivated by action on a time scale less than the 30 to 50 years of much present planning

Outcomes in knowledge, attitudes and confidence of nursing staff working in nursing and residential care homes following a dementia training programme.

Science.gov (United States)

Scerri, Anthony; Scerri, Charles

2017-11-08

Dementia training programmes for staff working in long-term care settings have been found to be effective in improving staff outcomes. This study investigated the impact of a dementia training programme for all Maltese nursing staff working in public nursing/residential homes on their knowledge, attitudes and confidence. Additionally, we identified the predictors of these domains before and after the programme. A 14-hour training programme focusing on dementia management, care and policy was developed for all nursing staff working in public nursing and residential homes in Malta. A pretest-posttest design was used to evaluate the participants' knowledge of dementia, attitudes and confidence in working with residents with dementia using validated tools. Demographic variables were measured and compared with each staff domain. The majority of nursing staff attended the training programme with 261 fully completed questionnaires being collected pre-training and 214 post-training. The programme significantly improved nursing staff knowledge, attitudes and confidence. Stepwise regression analysis of each staff domain showed that the strongest predictor in all models at pre-training was the intensity of previous training programmes. Furthermore, staff who attended previous training continued to improve in their attitudes and confidence following programme completion. The study continues to shed further evidence on the impact of dementia training programs on staff outcomes. It also indicated that the intensity of previous participation in dementia training programmes was related to the participants' knowledge, attitudes and confidence and that continual exposure to training had a cumulative effect.

FY 1998 Report on development of technologies for commercialization of photovoltaic power systems. International co-operative project (IEA implementing agreement for a co-operative programme on photovoltaic power systems); 1998 nendo taiyoko hatsuden system jitsuyoka gijutsu kaihatsu kokusai kyoryoku jigyo. IEA taiyoko hatsuden system kenkyu kyoryoku program jisshi kyotei

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

Described herein are outline of the International Energy Agency/Co-operative programme on Photovoltaic Power Systems (IEA/PVPS). Japan signed the IEA Implementing Agreement for a co-operative programme on Photovoltaic Power Systems in April 1993, and has been participating in the programme for research and development, demonstration, analysis, information exchange and introduction promotion, among others. This programme is managed by Executive Committee composed of the representatives, one nominated by each participating country, and each task is managed by each Operating Agency. There are 9 tasks (Tasks 1 to 9), and Executive Committee deliberates and approves the plans, and manages the progresses, budgetary plans and budgets for each task. IEA implementing agreement for a co-operative programme on PVPS, originally set effective for 5 years, has been extended for another 5 years to 2002, and the second phase activities have been started. The 9th to 11th Executive Committee meetings were held during the 1997-1998 period in Denmark, ROK, Spain, Austria and Australia, respectively. (NEDO)

Safety case development in the Japanese programme for geological disposal of HLW: Evolution in the generic stage

International Nuclear Information System (INIS)

Ueda, Hiroyoshi; Ishiguro, Katsuhiko; Takeuchi, Mitsuo; Fujihara, Hiroshi; Takeda, Seietsu

2014-01-01

In the Japanese programme for nuclear power generation, the safe management of the resulting radioactive waste, particularly vitrified high-level waste (HLW) from fuel reprocessing, has been a major concern and a focus of R and D since the late 70's. According to the specifications in a report issued by an advisory committee of the Japan Atomic Energy Commission (JAEC, 1997), the Second Progress Report on R and D for the Geological Disposal of HLW (H12 report) (JNC, 2000) was published after two decades of R and D activities and showed that disposal of HLW in Japan is feasible and can be practically implemented at sites which meet certain geological stability requirements. The H12 report supported government decisions that formed the basis of the 'Act on Final Disposal of Specified Radioactive Waste' (Final Disposal Act), which came into force in 2000. The Act specifies deep geological disposal of HLW at depths greater than 300 metres, together with a stepwise site selection process in three stages. Following the Final Disposal Act, the supporting 'Basic Policy for Final Disposal' and the 'Final Disposal Plan' were authorised in the same year. (authors)

Working toward a sustainable laboratory quality improvement programme through country ownership: Mozambique's SLMTA story.

Science.gov (United States)

Masamha, Jessina; Skaggs, Beth; Pinto, Isabel; Mandlaze, Ana Paula; Simbine, Carolina; Chongo, Patrina; de Sousa, Leonardo; Kidane, Solon; Yao, Katy; Luman, Elizabeth T; Samogudo, Eduardo

2014-01-01

Launched in 2009, the Strengthening Laboratory Management Toward Accreditation (SLMTA) programme has emerged as an innovative approach for the improvement of laboratory quality. In order to ensure sustainability, Mozambique embedded the SLMTA programme within the existing Ministry of Health (MOH) laboratory structure. This article outlines the steps followed to establish a national framework for quality improvement and embedding the SLMTA programme within existing MOH laboratory systems. The MOH adopted SLMTA as the national laboratory quality improvement strategy, hired a dedicated coordinator and established a national laboratory quality technical working group comprising mostly personnel from key MOH departments. The working group developed an implementation framework for advocacy, training, mentorship, supervision and audits. Emphasis was placed on building local capacity for programme activities. After receiving training, a team of 25 implementers (18 from the MOH and seven from partner organisations) conducted baseline audits (using the Stepwise Laboratory Quality Improvement Process Towards Accreditation [SLIPTA] checklist), workshops and site visits in six reference and two central hospital laboratories. Exit audits were conducted in six of the eight laboratories and their results are presented. The six laboratories demonstrated substantial improvement in audit scores; median scores increased from 35% at baseline to 57% at exit. It has been recommended that the National Tuberculosis Reference Laboratory apply for international accreditation. Successful implementation of SLMTA requires partnership between programme implementers, whilst effectiveness and long-term viability depend on country leadership, ownership and commitment. Integration of SLMTA into the existing MOH laboratory system will ensure durability beyond initial investments. The Mozambican model holds great promise that country leadership, ownership and institutionalisation can set the stage for

The power of PowerPoint.

Science.gov (United States)

Niamtu , J

2001-08-01

Carousel slide presentations have been used for academic and clinical presentations since the late 1950s. However, advances in computer technology have caused a paradigm shift, and digital presentations are quickly becoming standard for clinical presentations. The advantages of digital presentations include cost savings; portability; easy updating capability; Internet access; multimedia functions, such as animation, pictures, video, and sound; and customization to augment audience interest and attention. Microsoft PowerPoint has emerged as the most popular digital presentation software and is currently used by many practitioners with and without significant computer expertise. The user-friendly platform of PowerPoint enables even the novice presenter to incorporate digital presentations into his or her profession. PowerPoint offers many advanced options that, with a minimal investment of time, can be used to create more interactive and professional presentations for lectures, patient education, and marketing. Examples of advanced PowerPoint applications are presented in a stepwise manner to unveil the full power of PowerPoint. By incorporating these techniques, medical practitioners can easily personalize, customize, and enhance their PowerPoint presentations. Complications, pitfalls, and caveats are discussed to detour and prevent misadventures in digital presentations. Relevant Web sites are listed to further update, customize, and communicate PowerPoint techniques.

Stepwise withdrawal of inhaled corticosteroids in COPD patients receiving dual bronchodilation

DEFF Research Database (Denmark)

Magnussen, Helgo; Watz, Henrik; Kirsten, Anne

2014-01-01

-controlled fashion, one group of patients continues to receive tiotropium, salmeterol and fluticasone, while the second group initiates stepwise withdrawal of fluticasone. The primary end point is time to first moderate or severe exacerbation following randomized treatment over 52 weeks. Lung function, symptoms...

Discrimination of Geographical Origin of Asian Garlic Using Isotopic and Chemical Datasets under Stepwise Principal Component Analysis.

Science.gov (United States)

Liu, Tsang-Sen; Lin, Jhen-Nan; Peng, Tsung-Ren

2018-01-16

Isotopic compositions of δ 2 H, δ 18 O, δ 13 C, and δ 15 N and concentrations of 22 trace elements from garlic samples were analyzed and processed with stepwise principal component analysis (PCA) to discriminate garlic's country of origin among Asian regions including South Korea, Vietnam, Taiwan, and China. Results indicate that there is no single trace-element concentration or isotopic composition that can accomplish the study's purpose and the stepwise PCA approach proposed does allow for discrimination between countries on a regional basis. Sequentially, Step-1 PCA distinguishes garlic's country of origin among Taiwanese, South Korean, and Vietnamese samples; Step-2 PCA discriminates Chinese garlic from South Korean garlic; and Step-3 and Step-4 PCA, Chinese garlic from Vietnamese garlic. In model tests, countries of origin of all audit samples were correctly discriminated by stepwise PCA. Consequently, this study demonstrates that stepwise PCA as applied is a simple and effective approach to discriminating country of origin among Asian garlics. © 2018 American Academy of Forensic Sciences.

Report of a consultants` meeting to review the IAEA programme on operational safety services as part of the programme performance assessment system (PPAS) within the IAEA

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-09-01

The consultants consider that the ASCOT (Assessment of Safety Culture in Organizations Team), ASSET (Assessment of Safety Significant Events Team), and OSART (Operational Safety Review Team) programmes contribute to enhancing safe performance of Member States nuclear power plants. Continued co-ordination with the World Association of Nuclear Operators and national programmes in addition to continued emphasis on developing self assessment capabilities at the power plants will contribute to continuing improvement. International performance indicators clearly portray improvements in almost all areas. For example, the incidence of unplanned scrams and the unavailability of systems important to safety reduced. All three programmes ASCOT, ASSET and OSART may be improved by: tailoring them to meet the requested need. This includes not only the use of the OSART modular concepts but also the mixing and matching of the programmes. All three programmes can be enhanced by the sharing and use of their individual current techniques. The balance between assistance for conducting self assessment and direct assessment activities must be carefully considered. Country profiles could assist the Agency staff in advising Member States on request in the technique; power plant assistance or direct assessment, that would yield the best result. It is therefore recommended that the Agency go forward with the effort to develop these profiles. Figs, tabs.

Report of a consultants' meeting to review the IAEA programme on operational safety services as part of the programme performance assessment system (PPAS) within the IAEA

International Nuclear Information System (INIS)

1996-09-01

The consultants consider that the ASCOT (Assessment of Safety Culture in Organizations Team), ASSET (Assessment of Safety Significant Events Team), and OSART (Operational Safety Review Team) programmes contribute to enhancing safe performance of Member States nuclear power plants. Continued co-ordination with the World Association of Nuclear Operators and national programmes in addition to continued emphasis on developing self assessment capabilities at the power plants will contribute to continuing improvement. International performance indicators clearly portray improvements in almost all areas. For example, the incidence of unplanned scrams and the unavailability of systems important to safety reduced. All three programmes ASCOT, ASSET and OSART may be improved by: tailoring them to meet the requested need. This includes not only the use of the OSART modular concepts but also the mixing and matching of the programmes. All three programmes can be enhanced by the sharing and use of their individual current techniques. The balance between assistance for conducting self assessment and direct assessment activities must be carefully considered. Country profiles could assist the Agency staff in advising Member States on request in the technique; power plant assistance or direct assessment, that would yield the best result. It is therefore recommended that the Agency go forward with the effort to develop these profiles. Figs, tabs

Nuclear programme in Indonesia

International Nuclear Information System (INIS)

Ahimsa, Djali

1994-01-01

Implementation of the energy policy covers several aspects such as issuance of regulations, standards, energy pricing incentives and disincentives, and the application of appropriate technologies. The policies and implementation of the technologies can fully be supported by the use of nuclear technology, especially toward the now popular issue concerning the environment. In view of these policies and the need to implement these policies. i.e. for the diversification of energy and environmental concern, the Department of Mines and Energy has established an Indonesian Energy Coordination Board (BAKOREN). This board has realised the importance of considering nuclear as a source of energy, which has led to a decision in September 1989, for The National Atomic Energy Agency (BATAN) to conduct a feasibility study to introduce nuclear power plants in Indonesia. The establishment of an authority for the construction and operation of Nuclear Power Plants in Indonesia, which is primarily related to the safe and efficient operation of nuclear power plants, must also be prepared. This authority is still under considerations by the Indonesian Government. In implementing the Indonesia Nuclear Programme, it is important that cooperation exists among countries of the world, Korea, in this respect, as learning from experiences of other countries are very necessary to plan for a successful Nuclear Programme

Programmable high power beam damper for the Tevatron

International Nuclear Information System (INIS)

Crisp, J.; Goodwin, R.; Gerig, R.

1985-06-01

A bunch-by-bunch beam damper has been developed for the Fermilab Tevatron. The system reduces betatron oscillation amplitudes and incorporates some useful machine diagnostics. The device is programmable via look-up tables so the output is an arbitrary function, on a bunch-by-bunch basis, of the beam displacement. We are presently using this feature to measure the betatron tune throughout the acceleration cycle. 4 refs

The current wind energy programme in Italy

International Nuclear Information System (INIS)

Ambrosini, G.; Foli, U.; Sesto, E.; Vigotti, R.

1991-01-01

In Italy, the main activities in the field of wind energy are carried out by two state-owned organizations, ENEA (Italian National Agency for New Technologies, Energy and the Environment) and ENEL (Italian National Electricity Board), and two major wind turbine generator manufacturers, Alenia/WEST and Riva Calzoni, within the framework of a national programme which is supervized by the Ministry of Industry and Commerce. The work currently under way concerns both wind power plant siting and the development and testing of Italian-made wind turbine generators ranging from 5 to 1500 kW in power. In addition, programmes aimed at constructing wind-farms made up of medium-sized machines (200-400 kW) have recently been launched

Stepwise commissioning of a steam boiler with stability guarantees

DEFF Research Database (Denmark)

Johansen, Simon Vestergaard; Kallesøe, Carsten Skovmose; Bendtsen, Jan Dimon

2016-01-01

This paper aims to make the commissioning of an industrial MIMO controller more straightforward by gradually commissioning it from a set of SISO controllers, after the system has been started. For this purpose a stepwise commissioning strategy based on the Youla-Kucera parametrization has been de...... been commissioned from a SISO controller using the developed method on a real steam boiler and measurements show a clear performance improvement after transition....

Step-wise and punctuated genome evolution drive phenotype changes of tumor cells

International Nuclear Information System (INIS)

Stepanenko, Aleksei; Andreieva, Svitlana; Korets, Kateryna; Mykytenko, Dmytro; Huleyuk, Nataliya; Vassetzky, Yegor; Kavsan, Vadym

2015-01-01

Highlights: • There are the step-wise continuous and punctuated phases of cancer genome evolution. • The system stresses during the different phases may lead to very different responses. • Stable transfection of an empty vector can result in genome and phenotype changes. • Functions of a (trans)gene can be opposite/versatile in cells with different genomes. • Contextually, temozolomide can both promote and suppress tumor cell aggressiveness. - Abstract: The pattern of genome evolution can be divided into two phases: the step-wise continuous phase (step-wise clonal evolution, stable dominant clonal chromosome aberrations (CCAs), and low frequency of non-CCAs, NCCAs) and punctuated phase (marked by elevated NCCAs and transitional CCAs). Depending on the phase, system stresses (the diverse CIN promoting factors) may lead to the very different phenotype responses. To address the contribution of chromosome instability (CIN) to phenotype changes of tumor cells, we characterized CCAs/NCCAs of HeLa and HEK293 cells, and their derivatives after genotoxic stresses (a stable plasmid transfection, ectopic expression of cancer-associated CHI3L1 gene or treatment with temozolomide) by conventional cytogenetics, copy number alterations (CNAs) by array comparative genome hybridization, and phenotype changes by cell viability and soft agar assays. Transfection of either the empty vector pcDNA3.1 or pcDNA3.1-CHI3L1 into 293 cells initiated the punctuated genome changes. In contrast, HeLa-CHI3L1 cells demonstrated the step-wise genome changes. Increased CIN correlated with lower viability of 293-pcDNA3.1 cells but higher colony formation efficiency (CFE). Artificial CHI3L1 production in 293-CHI3L1 cells increased viability and further contributed to CFE. The opposite growth characteristics of 293-CHI3L1 and HeLa-CHI3L1 cells were revealed. The effect and function of a (trans)gene can be opposite and versatile in cells with different genetic network, which is defined by

Step-wise and punctuated genome evolution drive phenotype changes of tumor cells

Energy Technology Data Exchange (ETDEWEB)

Stepanenko, Aleksei, E-mail: a.a.stepanenko@gmail.com [Department of Biosynthesis of Nucleic Acids, Institute of Molecular Biology and Genetics, National Academy of Sciences of Ukraine, Kyiv 03680 (Ukraine); Andreieva, Svitlana; Korets, Kateryna; Mykytenko, Dmytro [Department of Biosynthesis of Nucleic Acids, Institute of Molecular Biology and Genetics, National Academy of Sciences of Ukraine, Kyiv 03680 (Ukraine); Huleyuk, Nataliya [Institute of Hereditary Pathology, National Academy of Medical Sciences of Ukraine, Lviv 79008 (Ukraine); Vassetzky, Yegor [CNRS UMR8126, Université Paris-Sud 11, Institut de Cancérologie Gustave Roussy, Villejuif 94805 (France); Kavsan, Vadym [Department of Biosynthesis of Nucleic Acids, Institute of Molecular Biology and Genetics, National Academy of Sciences of Ukraine, Kyiv 03680 (Ukraine)

2015-01-15

Highlights: • There are the step-wise continuous and punctuated phases of cancer genome evolution. • The system stresses during the different phases may lead to very different responses. • Stable transfection of an empty vector can result in genome and phenotype changes. • Functions of a (trans)gene can be opposite/versatile in cells with different genomes. • Contextually, temozolomide can both promote and suppress tumor cell aggressiveness. - Abstract: The pattern of genome evolution can be divided into two phases: the step-wise continuous phase (step-wise clonal evolution, stable dominant clonal chromosome aberrations (CCAs), and low frequency of non-CCAs, NCCAs) and punctuated phase (marked by elevated NCCAs and transitional CCAs). Depending on the phase, system stresses (the diverse CIN promoting factors) may lead to the very different phenotype responses. To address the contribution of chromosome instability (CIN) to phenotype changes of tumor cells, we characterized CCAs/NCCAs of HeLa and HEK293 cells, and their derivatives after genotoxic stresses (a stable plasmid transfection, ectopic expression of cancer-associated CHI3L1 gene or treatment with temozolomide) by conventional cytogenetics, copy number alterations (CNAs) by array comparative genome hybridization, and phenotype changes by cell viability and soft agar assays. Transfection of either the empty vector pcDNA3.1 or pcDNA3.1-CHI3L1 into 293 cells initiated the punctuated genome changes. In contrast, HeLa-CHI3L1 cells demonstrated the step-wise genome changes. Increased CIN correlated with lower viability of 293-pcDNA3.1 cells but higher colony formation efficiency (CFE). Artificial CHI3L1 production in 293-CHI3L1 cells increased viability and further contributed to CFE. The opposite growth characteristics of 293-CHI3L1 and HeLa-CHI3L1 cells were revealed. The effect and function of a (trans)gene can be opposite and versatile in cells with different genetic network, which is defined by

Regulatory inspection of the implementation of quality assurance programmes

International Nuclear Information System (INIS)

1989-01-01

This Manual provides guidance to Member States in the organization and performance of their regulatory inspection functions regarding the implementation of nuclear power plant quality assurance programmes. It addresses the interface between, and is consistent with, the IAEA Nuclear Safety Standards (NUSS programme) documents on quality assurance and governmental organization. The Manual offers a practical model and examples for performing regulatory inspections to ensure that the quality assurance programme is operating satisfactorily in the siting, design, manufacturing, construction, commissioning, operation and decommissioning of nuclear power plants. The primary objective is to confirm that the licensee has the capability to manage and control the effective performance of all quality assurance responsibilities during all phases of a nuclear power project. The guidance provided through this Manual for proper establishment and execution of the regulatory inspections helps to enforce the effective implementation of the quality assurance programme as a management control system that the nuclear industry should establish and use in attaining the safety and reliability objectives for nuclear installations. This enforcement action by national regulatory bodies and the emphasis on the purposes and advantages of quality assurance as an important management tool integrated within the total project task have been recommended by the IAEA International Nuclear Safety Advisory Group (INSAG). The primary intended users of this Manual are the management personnel and high level staff from regulatory bodies but it will also be helpful to management personnel from nuclear utilities and vendors. They all are inevitable partners in a nuclear power project and this document offers all of them valuable information on the better accomplishment of quality assurance activities to ensure the common objective of safe and reliable nuclear power production

RTE - Assessment of the R and D programme for 2014

International Nuclear Information System (INIS)

2015-01-01

After a synthetic overview (R and D context, brief presentations of R and D programmes, programme progress indicators, financial assessment for 2014, evolution of expenses for each programme from 2013 to 2016, highlights for each programme during 2014), this report first describes R and D projects associated with the different R and D programmes (tomorrow's grid, asset management, electric power system, environment, smart grids). It gives a list of current and future projects with their expected results for 2015 and 2016. It presents financial aspects for 2014 (expenses, subsidies, expense evolution), and presents the different indicators used for the follow-up of the R and D assessment of each programme

Is there a step-wise migration in Nigeria? A case study of the migrational histories of migrants in Lagos.

Science.gov (United States)

Afolayan, A A

1985-09-01

"The paper sets out to test whether or not the movement pattern of people in Nigeria is step-wise. It examines the spatial order in the country and the movement pattern of people. It then analyzes the survey data and tests for the validity of step-wise migration in the country. The findings show that step-wise migration cannot adequately describe all the patterns observed." The presence of large-scale circulatory migration between rural and urban areas is noted. Ways to decrease the pressure on Lagos by developing intermediate urban areas are considered. excerpt

Fusion power

International Nuclear Information System (INIS)

Hancox, R.

1981-01-01

The principles of fusion power, and its advantages and disadvantages, are outlined. Present research programmes and future plans directed towards the development of a fusion power reactor, are summarized. (U.K.)

A novel peak-hopping stepwise feature selection method with application to Raman spectroscopy

International Nuclear Information System (INIS)

McShane, M.J.; Cameron, B.D.; Cote, G.L.; Motamedi, M.; Spiegelman, C.H.

1999-01-01

A new stepwise approach to variable selection for spectroscopy that includes chemical information and attempts to test several spectral regions producing high ranking coefficients has been developed to improve on currently available methods. Existing selection techniques can, in general, be placed into two groups: the first, time-consuming optimization approaches that ignore available information about sample chemistry and require considerable expertise to arrive at appropriate solutions (e.g. genetic algorithms), and the second, stepwise procedures that tend to select many variables in the same area containing redundant information. The algorithm described here is a fast stepwise procedure that uses multiple ranking chains to identify several spectral regions correlated with known sample properties. The multiple-chain approach allows the generation of a final ranking vector that moves quickly away from the initial selection point, testing several areas exhibiting correlation between spectra and composition early in the stepping procedure. Quantitative evidence of the success of this approach as applied to Raman spectroscopy is given in terms of processing speed, number of selected variables, and prediction error in comparison with other selection methods. In this respect, the procedure described here may be considered as a significant evolutionary step in variable selection algorithms. (Copyright (c) 1999 Elsevier Science B.V., Amsterdam. All rights reserved.)

Responsibilities and capabilities of a nuclear energy programme implementing organization

International Nuclear Information System (INIS)

2009-01-01

An appropriate infrastructure is essential for the efficient, safe, reliable and peaceful use of nuclear power. The IAEA was encouraged by its Member States to provide assistance to those considering the introduction of nuclear power. These countries face the challenge of building a national nuclear infrastructure to support a first nuclear power plant. The IAEA is responding to their needs through increased technical assistance, missions and workshops, and with new and updated technical publications in the IAEA Nuclear Energy Series. Milestones in the Development of a National Infrastructure for Nuclear Power, an IAEA Nuclear Energy Series publication (NG-G-3.1), provides detailed guidance on a holistic approach to national nuclear infrastructure development, over three phases. Nineteen issues are identified in this guide, ranging from development of a government's national position on nuclear power to planning for procurement related to the first NPP. An important element of the holistic approach is an entity that can help prepare the decision makers in a country to make a knowledgeable commitment to nuclear power, and then to coordinate infrastructure development efforts among various implementing organizations so that they arrive at the point of readiness to issue a bid tender at the same time. In the Milestones guide, this entity is called a nuclear energy programme implementing organization (NEPIO). As a growing number of Member States started to consider the nuclear power option, they asked for guidance from the IAEA on how to launch a nuclear power programme. In particular, Member States requested additional information on how to establish a NEPIO, especially in the earliest phases of a programme. This report has been prepared to provide information on the responsibilities and capabilities of a NEPIO, as well as to give an indication on how it relates to other key national organizations in the implementation of a nuclear power programme, such as the owner

The energy crisis and Bonn's atomic energy programme

International Nuclear Information System (INIS)

Steinhaus, K.; Heimbrecht, J.

1979-01-01

What are the background and causes of the energy crisis. In whose interest and on whose back is energy policy made in our country. Will the lights go out without nuclear power. Which are the real goals and dangers of Bonn's atomic energy programme. Is coal a real alternative to nuclear power in the Federal Republic of Germany. What possibilities and requirements are there for a national and democratic energy policy in the Federal Republic of Germany. Which are the central problems of the protest movement against the government's atomic energy programme. These questions, which are still in the centre of political discussion, are investigated by the authors. (orig.) [de

Programmes design for Bohunice NPP personnel other than control room operators

International Nuclear Information System (INIS)

Kalincik, L.

2002-01-01

This paper deals with project development of training programmes for non-licenced NPP personnel-masters, field operators, maintenance and technical supporting personnel. The programme development focuses on the part stage and on the job training at NPP. Bohunice NPP belongs to plants with higher specific number of personnel per installed power capacity. This factor also influenced the choice of programmes design. Undermentioned procedure is one of various approaches to SAT exploitation for training programmes design. (author)

Chemistry Programme for Water Cooled Nuclear Power Plants. Specific Safety Guide (Russian Edition)

International Nuclear Information System (INIS)

2014-01-01

This publication provides guidance on establishing a high standard chemistry programme in accordance with plant safety policy and regulatory requirements. It will be useful to managers of operating organizations and other staff responsible for supporting or monitoring plant activities and for oversight of the plant chemistry programme, as well as to regulatory bodies. Contents: 1. Introduction; 2. Functions, responsibilities and interfaces; 3. Chemistry programme; 4. Chemistry control; 5. Chemistry aspects of radiation exposure optimization; 6. Chemistry surveillance; 7. Management of chemistry data; 8. Training and qualification; 9. Quality control of chemicals and other substances

Working toward a sustainable laboratory quality improvement programme through country ownership: Mozambique’s SLMTA story

Directory of Open Access Journals (Sweden)

Jessina Masamha

2014-11-01

Full Text Available Background: Launched in 2009, the Strengthening Laboratory Management Toward Accreditation (SLMTA programme has emerged as an innovative approach for the improvement of laboratory quality. In order to ensure sustainability, Mozambique embedded the SLMTA programme within the existing Ministry of Health (MOH laboratory structure. Objective: This article outlines the steps followed to establish a national framework for quality improvement and embed the SLMTA programme within existing MOH laboratory systems. Methods: The MOH adopted SLMTA as the national laboratory quality improvement strategy, hired a dedicated coordinator and established a national laboratory quality technical working group comprising mostly personnel from key MOH departments. The working group developed an implementation framework for advocacy, training, mentorship, supervision and audits. Emphasis was placed on building local capacity for programme activities. After receiving training, a team of 25 implementers (18 from the MOH and sevenfrom partner organisations conducted baseline audits (using the Stepwise Laboratory Quality Improvement Process Towards Accreditation [SLIPTA] checklist, workshops and site visits in six reference and two central hospital laboratories. Exit audits were conducted in six of the eight laboratories and their results are presented. Results: The six laboratories demonstrated substantial improvement in SLIPTA checklistscores; median scores increased from 35% at baseline to 57% at exit. It has been recommended that the National Tuberculosis Reference Laboratory apply for international accreditation. Conclusion: Successful implementation of SLMTA requires partnership between programme implementers, whilst effectiveness and long-term viability depend on country leadership, ownership and commitment. Integration of SLMTA into the existing MOH laboratory system will ensure durability beyond initial investments. The Mozambican model holds great promise that

RD and D-Programme 2004. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste, including social science research

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-09-01

SKB (the Swedish Nuclear Fuel and Waste Management Co), which is owned by the companies that operate the Swedish nuclear power plants, has been assigned the task of managing and disposing of the spent nuclear fuel from the reactors. The Nuclear Activities Act requires a programme of comprehensive research and development and other measures that are needed to manage and dispose of nuclear waste in a safe manner and to decommission and dismantle the nuclear power plants. SKB is now presenting RD and D-Programme 2004 in fulfilment of this requirement. The programme describes SKB's plans for the period 2005-2010. The period of immediate concern is 2005-2007. The level of detail for the three subsequent years is naturally lower.The programme provides a basis for designing systems for safe management and disposal of the radioactive waste from the nuclear power plants. SKB's plan is to implement deep disposal of the spent fuel in accordance with the KBS-3 method. In the RD and D-Programme we describe our activities and planning for this line of action and the work that is being conducted on alternative methods. Review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they look upon different parts of the programme and stipulate guidelines for the future. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government.The goal for the period up to the end of 2008 is to be able to submit permit applications for the encapsulation plant and the deep repository. This RD and D-Programme therefore differs from the preceding ones in that it concentrates on questions relating to technology development for these facilities. The programmes for safety assessment and research on the long-term processes that take place in the deep repository are then linked together with the programmes for technology development. Another new

RD and D-Programme 2004. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste, including social science research

International Nuclear Information System (INIS)

2004-09-01

SKB (the Swedish Nuclear Fuel and Waste Management Co), which is owned by the companies that operate the Swedish nuclear power plants, has been assigned the task of managing and disposing of the spent nuclear fuel from the reactors. The Nuclear Activities Act requires a programme of comprehensive research and development and other measures that are needed to manage and dispose of nuclear waste in a safe manner and to decommission and dismantle the nuclear power plants. SKB is now presenting RD and D-Programme 2004 in fulfilment of this requirement. The programme describes SKB's plans for the period 2005-2010. The period of immediate concern is 2005-2007. The level of detail for the three subsequent years is naturally lower.The programme provides a basis for designing systems for safe management and disposal of the radioactive waste from the nuclear power plants. SKB's plan is to implement deep disposal of the spent fuel in accordance with the KBS-3 method. In the RD and D-Programme we describe our activities and planning for this line of action and the work that is being conducted on alternative methods. Review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they look upon different parts of the programme and stipulate guidelines for the future. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government.The goal for the period up to the end of 2008 is to be able to submit permit applications for the encapsulation plant and the deep repository. This RD and D-Programme therefore differs from the preceding ones in that it concentrates on questions relating to technology development for these facilities. The programmes for safety assessment and research on the long-term processes that take place in the deep repository are then linked together with the programmes for technology development. Another new

Effects of stepwise gas combustion on NOx generation

International Nuclear Information System (INIS)

Woperane Seredi, A.; Szepesi, E.

1999-01-01

To decrease NO x emission from gas boilers, the combustion process of gas has been modified from continuous combustion to step-wise combustion. In this process the combustion temperature, the temperature peaks in the flame, the residence time of combustion products in the high-temperature zone and the oxygen partial pressure are changed advantageously. Experiments were performed using multistage burners, and the NO x emission was recorded. It was found that the air factor of the primary combustion space has a determining effect on the NO x reduction. (R.P.)

The Swedish Nuclear Power Inspectorate's Review Statement and Evaluation of the Swedish Nuclear Fuel and Waste Management Co's RD and D Programme 2001

International Nuclear Information System (INIS)

2002-09-01

According to the Act on Nuclear Activities, the holder of a licence to operate a nuclear reactor must adopt all necessary measures to manage and dispose of spent nuclear fuel and nuclear waste. The Act stipulates requirements on a research programme which is to be submitted to the competent regulatory authority once every three years. The Swedish Nuclear Power Inspectorate (SKI) is the competent authority that evaluates and reviews the programme. SKI distributes the programme to a wide circle of reviewing bodies for comment, including authorities, municipalities, universities and NGOs. The Swedish programme for final disposal of spent nuclear fuel started about 25 years ago. According to the Swedish Nuclear Waste Management Co. (SKB), the planned repository will not be closed until sometime in the 2050's. A series of decisions must be made before this goal is attained. The decision process can therefore be described as a multi-stage process. During each stages, safety will be evaluated and there is a possibility of taking additional time for development work or of selecting improved solutions. SKI's task is to ensure safety compliance throughout all of these stages. In its decision in January 2000, the Government explained that the Programme for Research, Development and Demonstration for the Treatment and Final Disposal of Nuclear Waste (RD and D Programme 98) complied with legislative requirements but that certain supplementary reporting should be conducted by SKB and submitted no later than when the next programme, in accordance with paragraph 12 of the Act on Nuclear Activities, was prepared (September 2001). The supplementary reporting requested by the Government, and which was submitted by SKB to SKI in December 2000, dealt with issues relating to method selection, site selection and the site investigation programme. SKI submitted its review of the supplement to the Government in June 2001 and the Government made a decision on the matter on November 1, 2001

The TACIS Nuclear Programme: Assistance in Upgrading Russian Nuclear Power Stations - An Overview of the Individual Projects in the Internet

International Nuclear Information System (INIS)

Bieth, Michel; Schoels, Hubert

2006-01-01

The European Union' TACIS1 programme has been established for the New Independent States (NIS), among them in the Russian Federation since 1991. One priority of TACIS funding is Nuclear Safety. The European Commission has made available a total of 944 Million Euros for nuclear safety programmes covering the period 1991-2003. The TACIS nuclear safety programme is devoted to the improvement of the safety of Soviet designed nuclear installations in providing technology and safety culture transfer. JRC is carrying out works in the following areas: On-Site Assistance for TACIS operating Nuclear Power Plants; Design Safety and Dissemination of TACIS results; Reactor Pressure Vessel Embrittlement for VVER; Regulatory Assistance; Industrial Waste Management; Nuclear Safeguards; All TACIS projects, dealing with these areas of activity are now available in so called Project Description Sheets (PDS) or Project Results Sheets (PRS) in the Internet for everybody. JRC has created in the Internet an easy to open and to browse database which contains the result of works in relation to the above mentioned nuclear activities. This presentation gives an on-line overview of the app. 430 projects which have been implemented so far since the outset of the TACIS Nuclear Programme in the Russian Federation, which is representative to the other CIS countries, benefiting from the TACIS. The presentation will mainly consist of an on-line-demonstration of the TACIS Nuclear WEB Page, created by JRC. (authors)

modelling of directed evolution: Implications for experimental design and stepwise evolution

OpenAIRE

Wedge , David C.; Rowe , William; Kell , Douglas B.; Knowles , Joshua

2009-01-01

In silico modelling of directed evolution: Implications for experimental design and stepwise evolution correspondence: Corresponding author. Tel.: +441613065145. (Wedge, David C.) (Wedge, David C.) Manchester Interdisciplinary Biocentre, University of Manchester - 131 Princess Street--> , Manchester--> , M1 7ND--> - UNITED KINGDOM (Wedge, David C.) UNITED KINGDOM (Wedge, David C.) Man...

A leadership programme for critical care.

Science.gov (United States)

Crofts, Linda

2006-08-01

This paper describes the genesis, design and implementation of a leadership programme for critical care. This was an initiative funded by the National Health Service (NHS) Nursing Leadership Project and had at the core of its design flexibility to meet the needs of the individual hospitals, which took part in it. Participation was from the multi-disciplinary critical care team. Six NHS hospitals took part in the programme which was of 20 days duration and took place on hospital sites. The programme used the leadership model of as its template and had a number of distinct components; a baseline assessment, personal development, principles of leadership and critical case reviews. The programme was underpinned by three themes; working effectively in multi-professional teams to provide patient focussed care, managing change through effective leadership and developing the virtual critical care service. Each group set objectives pertinent to their own organisation's needs. The programme was evaluated by a self-reporting questionnaire; group feedback and feedback from stakeholders. Programme evaluation was positive from all the hospitals but it was clear that the impact of the programme varied considerably between the groups who took part. It was noted that there was some correlation between the success of the programme and organisational 'buy in' as well as the organisational culture within which the participants operated. A key feature of the programme success was the critical case reviews, which were considered to be a powerful learning tool and medium for group learning and change management.

Quality assurance for safety in nuclear power plants and other nuclear installations. Code and safety guides Q1-Q14. A publication within the NUSS programme

International Nuclear Information System (INIS)

1996-01-01

The code provides the basic requirements for establishing and implementing quality assurance programmes for the stages of siting, design, construction, commissioning, operation and decommissioning of nuclear power plants. These basic requirements apply to all individuals and organizations, including designers, suppliers, constructors, manufacturers and operators. The basic quality assurance requirements presented in this Code also apply, with appropriate modifications, to nuclear installations other than nuclear power plants

Developing maximal neuromuscular power: part 2 - training considerations for improving maximal power production.

Science.gov (United States)

Cormie, Prue; McGuigan, Michael R; Newton, Robert U

2011-02-01

This series of reviews focuses on the most important neuromuscular function in many sport performances: the ability to generate maximal muscular power. Part 1, published in an earlier issue of Sports Medicine, focused on the factors that affect maximal power production while part 2 explores the practical application of these findings by reviewing the scientific literature relevant to the development of training programmes that most effectively enhance maximal power production. The ability to generate maximal power during complex motor skills is of paramount importance to successful athletic performance across many sports. A crucial issue faced by scientists and coaches is the development of effective and efficient training programmes that improve maximal power production in dynamic, multi-joint movements. Such training is referred to as 'power training' for the purposes of this review. Although further research is required in order to gain a deeper understanding of the optimal training techniques for maximizing power in complex, sports-specific movements and the precise mechanisms underlying adaptation, several key conclusions can be drawn from this review. First, a fundamental relationship exists between strength and power, which dictates that an individual cannot possess a high level of power without first being relatively strong. Thus, enhancing and maintaining maximal strength is essential when considering the long-term development of power. Second, consideration of movement pattern, load and velocity specificity is essential when designing power training programmes. Ballistic, plyometric and weightlifting exercises can be used effectively as primary exercises within a power training programme that enhances maximal power. The loads applied to these exercises will depend on the specific requirements of each particular sport and the type of movement being trained. The use of ballistic exercises with loads ranging from 0% to 50% of one-repetition maximum (1RM) and

Supervisory control system implemented in programmable logical controller web server

OpenAIRE

Milavec, Simon

2012-01-01

In this thesis, we study the feasibility of supervisory control and data acquisition (SCADA) system realisation in a web server of a programmable logic controller. With the introduction of Ethernet protocol to the area of process control, the more powerful programmable logic controllers obtained integrated web servers. The web server of a programmable logic controller, produced by Siemens, will also be described in this thesis. Firstly, the software and the hardware equipment used for real...

The JET project and the European fusion research programme

International Nuclear Information System (INIS)

Wuester, H.-O.

1984-01-01

The paper concerns the Joint European Torus (JET) project and the European Fusion Research Programme. Fusion as an energy source and commercial fusion power are briefly discussed. The main features of the JET apparatus and the tokamak magnetic field configuration are given. Also described are the specific aims of JET, and the proposed future fusion reactor programme. (U.K.)

A stepwise regression tree for nonlinear approximation: applications to estimating subpixel land cover

Science.gov (United States)

Huang, C.; Townshend, J.R.G.

2003-01-01

A stepwise regression tree (SRT) algorithm was developed for approximating complex nonlinear relationships. Based on the regression tree of Breiman et al . (BRT) and a stepwise linear regression (SLR) method, this algorithm represents an improvement over SLR in that it can approximate nonlinear relationships and over BRT in that it gives more realistic predictions. The applicability of this method to estimating subpixel forest was demonstrated using three test data sets, on all of which it gave more accurate predictions than SLR and BRT. SRT also generated more compact trees and performed better than or at least as well as BRT at all 10 equal forest proportion interval ranging from 0 to 100%. This method is appealing to estimating subpixel land cover over large areas.

Multi-type Step-wise group screening designs with unequal A-priori ...

African Journals Online (AJOL)

... design with unequal group sizes and obtain values of the group sizes that minimize the expected number of runs.. Keywords: Group Screening, Group factors, multi-type step-wise group screening, expected number of runs, Optimum group screening designs > East African Journal of Statistics Vol. 1 (1) 2005: pp. 49-67 ...

Quality assurance programme and quality control

International Nuclear Information System (INIS)

Alvarez de Buergo, L.

1979-01-01

The paper analyses the requirements for the quality assurance and control in nuclear power plant projects which are needed to achieve safe, reliable and economic plants. The author describes the structure for the establishment of a nuclear programme at the national level and the participation of the different bodies involved in a nuclear power plant project. The paper ends with the study of a specific case in Spain. (NEA) [fr

Stepwise Inquiry into Hard Water in a High School Chemistry Laboratory

Science.gov (United States)

Kakisako, Mami; Nishikawa, Kazuyuki; Nakano, Masayoshi; Harada, Kana S.; Tatsuoka, Tomoyuki; Koga, Nobuyoshi

2016-01-01

This study focuses on the design of a learning program to introduce complexometric titration as a method for determining water hardness in a high school chemistry laboratory. Students are introduced to the different properties and reactions of hard water in a stepwise manner so that they gain the necessary chemical knowledge and conceptual…

The Brazilian nuclear programme

International Nuclear Information System (INIS)

Forman, J.M.A.

1990-01-01

Developing an energy policy for a country the size of Brazil is a formidable task. Large differences between the regions in geography and economic development do not allow for a uniform plan. In the mid 1970s, Brazil started a nuclear energy programme to provide it with another option in its energy planning. The objective of the programme was gradually to build a technical and industrial base for nuclear power in the country, so that it would be available when it was needed. It was recognized that it would not be easy for a developing country to acquire the necessary high technology. The organization of the industry is outlined, demand projections are presented and domestic supplies of uranium assessed. (author)

Improved model of the retardance in citric acid coated ferrofluids using stepwise regression

Science.gov (United States)

Lin, J. F.; Qiu, X. R.

2017-06-01

Citric acid (CA) coated Fe3O4 ferrofluids (FFs) have been conducted for biomedical application. The magneto-optical retardance of CA coated FFs was measured by a Stokes polarimeter. Optimization and multiple regression of retardance in FFs were executed by Taguchi method and Microsoft Excel previously, and the F value of regression model was large enough. However, the model executed by Excel was not systematic. Instead we adopted the stepwise regression to model the retardance of CA coated FFs. From the results of stepwise regression by MATLAB, the developed model had highly predictable ability owing to F of 2.55897e+7 and correlation coefficient of one. The average absolute error of predicted retardances to measured retardances was just 0.0044%. Using the genetic algorithm (GA) in MATLAB, the optimized parametric combination was determined as [4.709 0.12 39.998 70.006] corresponding to the pH of suspension, molar ratio of CA to Fe3O4, CA volume, and coating temperature. The maximum retardance was found as 31.712°, close to that obtained by evolutionary solver in Excel and a relative error of -0.013%. Above all, the stepwise regression method was successfully used to model the retardance of CA coated FFs, and the maximum global retardance was determined by the use of GA.

RD and D-Programme 2004. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste, including social science research

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-09-01

SKB (the Swedish Nuclear Fuel and Waste Management Co), which is owned by the companies that operate the Swedish nuclear power plants, has been assigned the task of managing and disposing of the spent nuclear fuel from the reactors. The Nuclear Activities Act requires a programme of comprehensive research and development and other measures that are needed to manage and dispose of nuclear waste in a safe manner and to decommission and dismantle the nuclear power plants. SKB is now presenting RD and D-Programme 2004 in fulfilment of this requirement. The programme describes SKB's plans for the period 2005-2010. The period of immediate concern is 2005-2007. The level of detail for the three subsequent years is naturally lower.The programme provides a basis for designing systems for safe management and disposal of the radioactive waste from the nuclear power plants. SKB's plan is to implement deep disposal of the spent fuel in accordance with the KBS-3 method. In the RD and D-Programme we describe our activities and planning for this line of action and the work that is being conducted on alternative methods. Review of the programme can contribute valuable outside viewpoints. The regulatory authorities and the Government can clarify how they look upon different parts of the programme and stipulate guidelines for the future. Municipalities and other stakeholders can, after studying the programme, offer their viewpoints to SKB, the regulatory authorities or the Government.The goal for the period up to the end of 2008 is to be able to submit permit applications for the encapsulation plant and the deep repository. This RD and D-Programme therefore differs from the preceding ones in that it concentrates on questions relating to technology development for these facilities. The programmes for safety assessment and research on the long-term processes that take place in the deep repository are then linked together with the programmes for technology development. Another

AVLIS [Atomic Vapour Laser Isotope Separation] programme powers ahead in the United States

International Nuclear Information System (INIS)

Sewell, P.G.; Haberman, N.

1988-01-01

The accomplishments of the AVLIS programme during the past year are described and a development programme initiated by the U.S. designed to lead to a full-scale demonstration of AVLIS by 1992. A possible early deployment option involving the enrichment of reprocessed uranium (REPU) is also examined. (U.K.)

Dose management programmes at Kaiga Generating Station

International Nuclear Information System (INIS)

Vijayan, P.; Prabhakaran, V.; Managavi, Sadashiv B.; Danannavar, Veerendra; Biju, P.; Manoj Kumar, M.; Shrikrishna, U.V.

2001-01-01

Kaiga Generating Station (KGS) has two units of pressurized heavy water reactors of 220 MWe each capacity. KGS-2 started power generation since 1999 and KGS-1 since 2000. Several programmes such as assessment of radioactive condition, training on radiological safety aspects, job planning in radioactive areas, etc. are conducted periodically to implement an effective dose control programmes in KGS. These efforts are briefly discussed in this report. Facilities and techniques to implement ALARA programs are also highlighted in this report. (author)

Organization and development of the Brazilian nuclear programme

International Nuclear Information System (INIS)

Pinto, C.S.M.; Souza, J.A.M. de; Grinberg, M.; Alves, R.N.; Costa, H.M. da; Grimberg, M.

1977-01-01

The paper presents the Brazilian Nuclear Energy Programme, its development, the organizations and the distribution of responsibilities involved in its execution at the present time. The nuclear power policy is established at the Presidency of the Republic and is planned, executed and controlled through the Ministry of Mines and Energy. Directly subject to the Ministry is the Brazilian Nuclear Energy Commission (CNEN), which has regulatory, standardization, licensing, planning and surveillance functions. The nuclear fundamental research and manpower formation are also under CNEN responsibility. Also subject to the Ministry are two companies responsible for the execution of the Programme: the Centrais Eletricas Brasileiras S.A. - Eletrobras, which advises on the granting of permits for the construction and operation of nuclear power plants, and the Empresas Nucleares Brasileiras S.A. - Nuclebras, which holds the monopoly of the nuclear fuel cycle in the country, designs and builds nuclear power plants and provides assistance to the electric utilities and promotes the participation of Brazilian industry. Besides describing the new distribution of regulatory functions given by law to CNEN, the paper gives special emphasis to the large industrial complex in the process of being established through the setting-up of the many Nuclebras subsidiaries in joint venture with German firms under the Industrial Co-operation Agreement Between Brazil and the Federal Republic of Germany in the Field of the Peaceful Uses of Nuclear Energy. The programmes for these subsidiaries are presented and their participation in the Brazilian Nuclear Energy Programme is discussed. The technology transfer aspects of the industrial activities are also discussed. (author)

Recent Perspective on the Severe Accident Management Programme for Nuclear Power Plant

International Nuclear Information System (INIS)

Kim, Manwoong; Lee, Sukho; Lee, Jungjae; Chung, Kuyoung

2017-01-01

Severe Accident Management Guidelines (SAMGs), has been developed to help operators to prevent or mitigate the impacts of accidents at nuclear power plants. Severe accident management was first introduced in the 1990s with the creation of SAMGs following recognition that post-Three Mile Island Emergency Operating Procedures (EOPs) did not adequately address severe core damage conditions. Establishing and maintaining multiple layers of defence against any internal/external hazards is an important measure to reduce radiological risks to the public and environment. This study is intended to suggest future regulatory perspectives to strengthen the prevention and mitigation strategies for severe accidents by review of the current status of revision of IAEA Safety Standard on Severe Accident Management Programmes for Nuclear Power Plants and the combined PWR SAMG. This new IAEA Safety Guide will address guidelines for preparation, development, implementation and review of severe accident management programs during all operating conditions for both reactor and spent fuel pool. This Guide is used by operating organizations of nuclear power plants and their support organizations. It may also be used by national regulatory bodies and technical support organizations as a reference for developing their relevant safety requirements and for conducting reviews and safety assessments for SAMP including SAMG. The Pressurized Water Reactor Owner’s Group (PWROG) is upgrading the original generic Severe Accident Management Guidelines (SAMGs) into single Severe Accident Guidelines (SAGs) for the PWR SAMG aims to consolidate the advantages of each of the separate vendor severe accident (SA) mitigation methods. This new PWROG SAGs changes the SAMG process to be made that can improve SA response. Changes have been made that guidance is available for control room operators when the TSC is not activated thus allowing for timely accident response. Other changes were made to the guidance

Nuclear power training courses

International Nuclear Information System (INIS)

1977-01-01

The training of technical manpower for nuclear power projects in developing countries is now a significant part of the IAEA Technical Assistance Programme. Two basic courses are the cornerstones of the Agency's training programme for nuclear power: a course in planning and implementation, and a course in construction and operation management. These two courses are independent of each other. They are designed to train personnel for two distinct phases of project implementation. The nuclear power project training programme has proven to be successful. A considerable number of highly qualified professionals from developing countries have been given the opportunity to learn through direct contact with experts who have had first-hand experience. It is recognized that the courses are not a substitute for on-the-job training, but their purpose is achieved if they have resulted in the transfer of practical, reliable information and have helped developing countries to prepare themselves for the planning, construction and operation management of nuclear power stations

Guideline concerning financial aid by the state to '250 MW wind' wind power plants within the framework of the third programme 'Energy research and energy technologies'

International Nuclear Information System (INIS)

1994-01-01

An industrial-scale wind power experiment will receive financial aid for several years. An installed power of 250 MW is to be reached within a 5-year period if possible. The BMFT will grant financial aid on a per kWh basis up to a maximum sum, or - if desired by certain applicants - in the form of an investment aid, both for a maximum period of 10 years from the start-up of the wind power plant. The BMFT will also finance a scientific programme for measurement and evaluation. (orig.) [de

The year 2000 (Y2k) Programme at AECL

International Nuclear Information System (INIS)

Pauksens, J.; Jung, D.

1998-01-01

In the nuclear industry we make, in total, very extensive use of digital computers and equipment. While use of dates in our application may not be quite so extensive as in other businesses such as banking or insurance, dates are nonetheless employed, and are important in a variety of applications. Furthermore, date-related problems can sometimes propagate into overall system failures or computer crashes. Digital system or digital infrastructure failure can have serious potential consequences in a power plant, utility, or engineering design office. This in turn can have potential impact on public safety or the reliability of power production and delivery of electrical power to the public. A concerted effort is needed, and is underway by nuclear design organizations, and the nuclear utilities in order to identify and fix or avoid the problems in the short time that remains between now and the Year 2000. AECL have a substantial Year 2000 programme underway, addressing both the infrastructure systems at AECL, and AECL's products and services. High priority is placed, in the programme, on assisting AECL's customers with the Year 2000 issue. The programme, and some of the lesson learned to date, are described in this paper. The relationship to equipment vendors' and customers' Year 2000 programs is explained, and the importance of Year 2000 programmes conducted by the customers, to address systems and equipment which are under their control, is highlighted. (authors)

JYT - Publicly financed nuclear waste management research programme

International Nuclear Information System (INIS)

Vuori, S.

1992-07-01

The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

JYT - Publicly financed nuclear waste management research programme

International Nuclear Information System (INIS)

Vuori, S.

1993-06-01

The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

JYT - Publicly financed nuclear waste management research programme

International Nuclear Information System (INIS)

Vuori, S.

1991-07-01

The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

Nuclear power in developing countries

International Nuclear Information System (INIS)

Laue, H.J.; Bennett, L.L.; Skjoeldebrand, R.

1984-01-01

Experience clearly indicates that most developing countries actively planning and implementing nuclear power require broad-scope assistance if their use of nuclear technology is to be safe, economic, and reliable. The IAEA's assistance is directed both to general planning, and to the development of supporting structures and is based on an assessment of needs which cannot be satisfied by other means. The Agency's Division of Nuclear Power has the technical background and tools to support a comprehensive programme of assistance in nuclear power assessment, planning, and implementation. The overall objective of such a programme is to help strengthen national capabilities of executing the following tasks: Analysis of overall energy and electricity demand and supply projections; planning the possible role of nuclear power in electricity supply, through determining the economically optimal extent and schedule for the introduction of nuclear power plants; assessing the available infrastructures and the need, constraints, and possibilities for their development; and developing master schedules, programmes, and recommendations for action. Proposed programmes must be reviewed periodically, and one of the Agency's aims is to ensure that national competence to carry out such reviews exists or can be developed. Training of local staff is therefore one of the most important objectives

Stepwise fluorination - a useful approach for the isotopic analysis of hydrous minerals

Energy Technology Data Exchange (ETDEWEB)

Haimson, M; Knauth, L P [Arizona State Univ., Tempe (USA). Dept. of Geology

1983-09-01

Analytical uncertainties in oxygen isotopic studies of hydrous silica have been investigated using a partial fluorination procedure in which fractional oxygen yields are achieved by reducing the amount of fluorine. Stepwise reaction of opaline silica results in a set of sequential oxygen fractions which show a wide range of delta/sup 18/O values due to variable amounts of water, organic matter, and other impurities. Delta-values for successive fractions in non-biogenic opal systematically increase as water is reacted away and then remain constant to within +- 0.2 per thousand as the remaining silica reacts. Delta-values in biogenic silica increase similarly but then decrease when low /sup 18/O oxide impurities begin to react. The troublesome water component in opal is readily removed by stepwise fluorination. This technique allows more precise oxygen isotope analysis of non-biogenic opal-A, and may improve the analytical precision for biogenic silica and any silicate mineral containing a significant water component.

Stepwise Assembly and Characterization of DNA Linked Two-Color Quantum Dot Clusters.

Science.gov (United States)

Coopersmith, Kaitlin; Han, Hyunjoo; Maye, Mathew M

2015-07-14

The DNA-mediated self-assembly of multicolor quantum dot (QD) clusters via a stepwise approach is described. The CdSe/ZnS QDs were synthesized and functionalized with an amphiphilic copolymer, followed by ssDNA conjugation. At each functionalization step, the QDs were purified via gradient ultracentrifugation, which was found to remove excess polymer and QD aggregates, allowing for improved conjugation yields and assembly reactivity. The QDs were then assembled and disassembled in a stepwise manner at a ssDNA functionalized magnetic colloid, which provided a convenient way to remove unreacted QDs and ssDNA impurities. After assembly/disassembly, the clusters' optical characteristics were studied by fluorescence spectroscopy and the assembly morphology and stoichiometry was imaged via electron microscopy. The results indicate that a significant amount of QD-to-QD energy transfer occurred in the clusters, which was studied as a function of increasing acceptor-to-donor ratios, resulting in increased QD acceptor emission intensities compared to controls.

Field Programmable Gate Array-based I and C Safety System

International Nuclear Information System (INIS)

Kim, Hyun Jeong; Kim, Koh Eun; Kim, Young Geul; Kwon, Jong Soo

2014-01-01

Programmable Logic Controller (PLC)-based I and C safety system used in the operating nuclear power plants has the disadvantages of the Common Cause Failure (CCF), high maintenance costs and quick obsolescence, and then it is necessary to develop the other platform to replace the PLC. The Field Programmable Gate Array (FPGA)-based Instrument and Control (I and C) safety system is safer and more economical than Programmable Logic Controller (PLC)-based I and C safety system. Therefore, in the future, FPGA-based I and C safety system will be able to replace the PLC-based I and C safety system in the operating and the new nuclear power plants to get benefited from its safety and economic advantage. FPGA-based I and C safety system shall be implemented and verified by applying the related requirements to perform the safety function

Field Programmable Gate Array-based I and C Safety System

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyun Jeong; Kim, Koh Eun; Kim, Young Geul; Kwon, Jong Soo [KEPCO, Daejeon (Korea, Republic of)

2014-08-15

Programmable Logic Controller (PLC)-based I and C safety system used in the operating nuclear power plants has the disadvantages of the Common Cause Failure (CCF), high maintenance costs and quick obsolescence, and then it is necessary to develop the other platform to replace the PLC. The Field Programmable Gate Array (FPGA)-based Instrument and Control (I and C) safety system is safer and more economical than Programmable Logic Controller (PLC)-based I and C safety system. Therefore, in the future, FPGA-based I and C safety system will be able to replace the PLC-based I and C safety system in the operating and the new nuclear power plants to get benefited from its safety and economic advantage. FPGA-based I and C safety system shall be implemented and verified by applying the related requirements to perform the safety function.

Fault diagnosis of power transformer based on fault-tree analysis (FTA)

Science.gov (United States)

Wang, Yongliang; Li, Xiaoqiang; Ma, Jianwei; Li, SuoYu

2017-05-01

Power transformers is an important equipment in power plants and substations, power distribution transmission link is made an important hub of power systems. Its performance directly affects the quality and health of the power system reliability and stability. This paper summarizes the five parts according to the fault type power transformers, then from the time dimension divided into three stages of power transformer fault, use DGA routine analysis and infrared diagnostics criterion set power transformer running state, finally, according to the needs of power transformer fault diagnosis, by the general to the section by stepwise refinement of dendritic tree constructed power transformer fault

Smart Power Supply for Battery-Powered Systems

Science.gov (United States)

Krasowski, Michael J.; Greer, Lawrence; Prokop, Norman F.; Flatico, Joseph M.

2010-01-01

A power supply for battery-powered systems has been designed with an embedded controller that is capable of monitoring and maintaining batteries, charging hardware, while maintaining output power. The power supply is primarily designed for rovers and other remote science and engineering vehicles, but it can be used in any battery alone, or battery and charging source applications. The supply can function autonomously, or can be connected to a host processor through a serial communications link. It can be programmed a priori or on the fly to return current and voltage readings to a host. It has two output power busses: a constant 24-V direct current nominal bus, and a programmable bus for output from approximately 24 up to approximately 50 V. The programmable bus voltage level, and its output power limit, can be changed on the fly as well. The power supply also offers options to reduce the programmable bus to 24 V when the set power limit is reached, limiting output power in the case of a system fault detected in the system. The smart power supply is based on an embedded 8051-type single-chip microcontroller. This choice was made in that a credible progression to flight (radiation hard, high reliability) can be assumed as many 8051 processors or gate arrays capable of accepting 8051-type core presently exist and will continue to do so for some time. To solve the problem of centralized control, this innovation moves an embedded microcontroller to the power supply and assigns it the task of overseeing the operation and charging of the power supply assets. This embedded processor is connected to the application central processor via a serial data link such that the central processor can request updates of various parameters within the supply, such as battery current, bus voltage, remaining power in battery estimations, etc. This supply has a direct connection to the battery bus for common (quiescent) power application. Because components from multiple vendors may have

Status report on the PWR 900, 1,300 and 1,400 MW construction programme

International Nuclear Information System (INIS)

Tesseraud, M.; Regnier, P.

1986-01-01

Having recalled plant standardisation, this paper describes the general situation concerning the French nuclear power programme, current building projects and planning extensions. Then a status report on the plants being built is drawn up. Finally, one shows that the essential objective of the nuclear power programme launched in 1974 - to eliminate petroleum from electricity generating - has now been achieved [fr

Digitally Programmable High-Q Voltage Mode Universal Filter

Directory of Open Access Journals (Sweden)

D. Singh

2013-12-01

Full Text Available A new low-voltage low-power CMOS current feedback amplifier (CFA is presented in this paper. This is used to realize a novel digitally programmable CFA (DPCFA using transistor arrays and MOS switches. The proposed realizations nearly allow rail-to-rail swing capability at all the ports. Class-AB output stage ensures low power dissipation and high current drive capability. The proposed CFA/ DPCFA operates at supply voltage of ±0.75 V and exhibits bandwidth better than 95 MHz. An application of the DPCFA to realize a novel voltage mode high-Q digitally programmable universal filter (UF is given. Performances of all the proposed circuits are verified by PSPICE simulation using TSMC 0.25μm technology parameters.

Netherlands export country for electricity? New developments in power plants and the impact on the Clean and Efficient programme

International Nuclear Information System (INIS)

Seebregts, A.J.; Daniels, B.W.

2008-07-01

This report explores part of the effects of the Dutch Climate Programme 'Clean and Efficient - Opportunities for Tomorrow' on the emissions of air pollutants, as included in the National Emissions Ceilings. The starting point for the analysis is the ex ante evaluation of Clean and Efficient as published in September 2007. Specifically for the Netherlands, the role of the power generation sector is important. For the near future (up to 2015), about 11 to 15 GW of new fossil generation capacity is being planned. In combination with the Clean and Efficient Programme, this will have a large impact on the resulting national emissions of air pollutants. Strong climate policies and high CO2 prices are likely to result in a lower electricity demand than the original reference projection (the Global Economy High Oil Price scenario). In addition, more renewable electricity generation and more cogeneration are expected. These changes are likely to improve the international competitiveness of the Dutch electricity generation. As a result, electricity exports rise and part of the emission reductions materialize outside the Netherlands, rather than within its borders [nl

Scalable alcohol interventions - An online “Month off Booze” programme

Directory of Open Access Journals (Sweden)

Jussi Tolvi

2015-09-01

Club Soda has developed a scalable online intervention, supporting people who want to abstain from alcohol for a month, which will be piloted in October 2015. An evaluation of the programme is not possible at the time of writing this abstract, but will be completed in November 2015. Based on initial feedback and anecdotal evidence, however, the programme is expected to be a powerful tool helping people abstain for a set period of time, and in reducing their alcohol consumption after the programme as well.

An Efficient Stepwise Statistical Test to Identify Multiple Linked Human Genetic Variants Associated with Specific Phenotypic Traits.

Directory of Open Access Journals (Sweden)

Iksoo Huh

Full Text Available Recent advances in genotyping methodologies have allowed genome-wide association studies (GWAS to accurately identify genetic variants that associate with common or pathological complex traits. Although most GWAS have focused on associations with single genetic variants, joint identification of multiple genetic variants, and how they interact, is essential for understanding the genetic architecture of complex phenotypic traits. Here, we propose an efficient stepwise method based on the Cochran-Mantel-Haenszel test (for stratified categorical data to identify causal joint multiple genetic variants in GWAS. This method combines the CMH statistic with a stepwise procedure to detect multiple genetic variants associated with specific categorical traits, using a series of associated I × J contingency tables and a null hypothesis of no phenotype association. Through a new stratification scheme based on the sum of minor allele count criteria, we make the method more feasible for GWAS data having sample sizes of several thousands. We also examine the properties of the proposed stepwise method via simulation studies, and show that the stepwise CMH test performs better than other existing methods (e.g., logistic regression and detection of associations by Markov blanket for identifying multiple genetic variants. Finally, we apply the proposed approach to two genomic sequencing datasets to detect linked genetic variants associated with bipolar disorder and obesity, respectively.

Effects of constant and stepwise changes in temperature on the species abundance dynamics of four cladocera species

Directory of Open Access Journals (Sweden)

Verbitsky V. B.

2011-09-01

Full Text Available Laboratory experiments with natural zooplankton communities were carried out to study the effects of two contrasting temperature regimes: constant temperature (15, 20, and 25 °C and graded changes in temperature. The graded regime consisted of repeated sustained (three weeks controlled stepwise temperature changes of 5 or 10 °C within 15–25 °C on the population dynamics of four dominant species of lake littoral zooplankton, Daphnia longispina (Müller, 1785, Diaphanosoma brachyurum (Lievin, 1848, Simocephalus vetulus (Müller, 1776 and Chydorus sphaericus (Müller, 1785. The results show that controlled stepwise changes (positive or negative in temperature within the ranges of 15–20, 20–25, and 15–25 °C can exert either stimulating or inhibitory effect (direct or delayed on the development of D. longispina and S. vetulus populations. The development of D. brachyurum and Ch. sphaericus, both more steno-thermophile, was only stimulated by a stable elevated temperature (25 °C. These results support the previously formulated hypothesis that, in determining the ecological temperature optimum of a species within a natural community, it is not enough to define its optimum from constant, cyclic or random temperature fluctuations, but also from unidirectional stepwise changes in temperature. These stepwise changes may also induce prolonged or delayed effects.

Pakistan's Nuclear programme for peaceful purposes

International Nuclear Information System (INIS)

Hilali, A.Z.

1994-01-01

Pakistan's nuclear programme is peaceful purposes and as the foregoing analysis shows, it is essential for its economic development. Nuclear power provides affordable energy for development of Pakistan economy and for meeting the minimum requirements of the people. Growing conventional energy requirements reflect Pakistan's expanding industrial demand for energy intensive appliances. Prospects for developing domestic sources of oil, natural gas, coal and hydro power are limited and the search for natural resources is slow due to lack of foreign aid and capital. Nuclear technology is an immensely powerful factor in the achievement of socio-economic development and elimination of poverty. (Orig./A.B.)

Surveillance programme and upgrading of the High Flux Reactor Petten

International Nuclear Information System (INIS)

Bieth, Michel

1995-01-01

The High Flux Reactor (HFR) at Petten (The Netherlands), a 45 MW light water cooled and moderated research reactor in operation during more than 30 years, has been kept up to date by replacing ageing components. In 1984, the HFR was shut down for replacement of the aluminium. reactor vessel which had been irradiated during more than 20 years. The demonstration that the new vessel contains no critical defect requires knowledge of the material properties of the aluminium alloy Al 5154 with and without neutron irradiation and of the likely defect presence through the periodic in-service inspections. An irradiation damage surveillance programme has been started in 1985 for the new vessel material to provide information on fracture mechanics properties. After the vessel replacement, the existing process of continuous upgrading and replacement of ageing components was accelerated. A stepwise upgrade of the control room is presently under realization. (author)

Surveillance programme and upgrading of the High Flux Reactor Petten

Energy Technology Data Exchange (ETDEWEB)

Bieth, Michel [Commission of the European Communities, Joint Research Centre, Institute for Advanced Materials, High Flux Reactor Unit, Petten (Netherlands)

1995-07-01

The High Flux Reactor (HFR) at Petten (The Netherlands), a 45 MW light water cooled and moderated research reactor in operation during more than 30 years, has been kept up to date by replacing ageing components. In 1984, the HFR was shut down for replacement of the aluminium. reactor vessel which had been irradiated during more than 20 years. The demonstration that the new vessel contains no critical defect requires knowledge of the material properties of the aluminium alloy Al 5154 with and without neutron irradiation and of the likely defect presence through the periodic in-service inspections. An irradiation damage surveillance programme has been started in 1985 for the new vessel material to provide information on fracture mechanics properties. After the vessel replacement, the existing process of continuous upgrading and replacement of ageing components was accelerated. A stepwise upgrade of the control room is presently under realization. (author)

Selection of quality assurance programme levels for nuclear power plants. Present practice in Canada and future developments

International Nuclear Information System (INIS)

Thomas, R.A.

1982-01-01

According to the IAEA Code of Practice on the subject and also to numerous national standards, effective quality assurance (QA) for safety in nuclear power plants depends upon the application of a number of fundamental principles. One of these principles is that QA for systems, components and structures should be commensurate with the individual importance to safety of each item. Evidently, money spent on excessive QA may be partly or wholly wasted, while too little QA will provide insufficient confidence that an item will perform satisfactorily in service. To deal successfully with the requirement of 'importance to safety', a detailed methodology must be established, by means of which QA can be prescribed rationally and consistently. Set in the context of the Canadian nuclear power and nuclear standards programmes, two related methodologies which account for importance to safety as well as for some other specific factors have been developed and are in use. These related methodologies are applied to the manufacture and installation of safety-related items, and are based on the implementation of the fixed-step, graded standards of the Canadian Standards Association, CSA Z299. Information is presented on the main features of the methodologies and on Canadian nuclear power plant QA practice in general. (author)

Status of national gas cooled reactor programmes

International Nuclear Information System (INIS)

1991-08-01

This report has been compiled as a central source of summary-level information on the present status of High Temperature Gas-Cooled Reactor (HTGR) programmes in the world and on future plans for the continued development and deployment of HTGRs. Most of the information concerns the programmes in the United States, Germany, Japan and the Soviet Union, countries that have had large programmes related to HTGR technology for several years. Summary-level information is also provided in the report on HTGR-related activities in several other countries who either have an increasing interest in the technology and/or who are performing some development efforts related to HTGR technology. The report contains a summary-level update on the MAGNOX and AGR programmes. This is the twelfth issue of the document, the first of which was issued in March, 1979. The report has been prepared in the IAEA Nuclear Power Technology Development Section. Figs and tabs

Super-hierarchical porous carbons derived from mixed biomass wastes by a stepwise removal strategy for high-performance supercapacitors

Science.gov (United States)

Peng, Lin; Liang, Yeru; Dong, Hanwu; Hu, Hang; Zhao, Xiao; Cai, Yijing; Xiao, Yong; Liu, Yingliang; Zheng, Mingtao

2018-02-01

The synthesis and energy storage application of hierarchical porous carbons with size ranging from nano-to micrometres has attracted considerable attention all over the world. Exploring eco-friendly and reliable synthesis of hierarchical porous carbons for supercapacitors with high energy density and high power is still of ongoing challenge. In this work, we report the design and synthesis of super-hierarchical porous carbons with highly developed porosity by a stepwise removal strategy for high-rate supercapacitors. The mixed biomass wastes of coconut shell and sewage sludge are employed as raw material. The as-prepared super-hierarchical porous carbons present high surface areas (3003 m2 g-1), large pore volume (2.04 cm3 g-1), appropriate porosity, and outstanding electrochemical performance. The dependence of electrochemical performance on structural, textural, and functional properties of carbons engineered by various synthesis strategies is investigated in detail. Moreover, the as-assembled symmetrical supercapacitor exhibits high energy density of 25.4 Wh kg-1 at a power density of 225 W kg-1 and retains 20.7 Wh kg-1 even at a very high power of 9000 W kg-1. This work provides an environmentally benign strategy and new insights to efficiently regulate the porosity of hierarchical porous carbons derived from biomass wastes for energy storage applications.

Embracing the complexity of educational programmes

Directory of Open Access Journals (Sweden)

Elly Govers

2016-12-01

Full Text Available Systems of monitoring and control have left many educators and organisations in the field of post-compulsory education struggling to find ways to meet the needs of an increasingly diverse society. Education is complex. Many educators would agree that it is influenced by many, often contradictory, voices and power structures. Based on the findings of a case study involving multiple programmes in a post-compulsory education institution in Aotearoa/New Zealand, this paper aims to unravel this complexity for the case of educational programmes. It describes how programmes can be seen as complex systems, created by people and directed by discourses in society, some of which are more influential than others. If programmes are seen as complex systems, the experience of struggle as referred to above can be understood as a consequence of the attempt to control the complexity rather than work with it. This control limits the possibilities for development and innovation. Alternatively, as this paper will explain, acknowledging and embracing the complexity of programmes helps open up spaces for innovation that would otherwise remain hidden. It is argued that the ultimate space for change is educators’ personal and collective responsibility for the discourses in society they choose to follow.

The radiation exposure control programme - its effect on design

International Nuclear Information System (INIS)

Simmons, R.B.V.

1975-01-01

The paper discusses how the Power Projects design organization has responded to the problem of operational exposure. This response took the form of an organized formal Programme developed during the Bruce G.S. design phase. This Radiation Exposure Control Programme considered: radiation conditions, number of items requiring attention, number of occasions item requires attention and manhours involved on each occasion. Analysis of these factors and comparison with target values enabled worthwhile reductions to be made in estimated operating exposure. Activity transport studies, reliability and design detail improvements have all received an impetus from the Programme. The Programme which has value both from the economic and the health physics points of view is now a continuing feature of the CANDU plant design process. (author)

IAEA Reviews Niger’s Nuclear Power Infrastructure Development

International Nuclear Information System (INIS)

2018-01-01

An International Atomic Energy Agency (IAEA) team of experts has concluded an eight-day mission to Niger to review its infrastructure development for a nuclear power programme. The Integrated Nuclear Infrastructure Review (INIR) was carried out at the invitation of the Government of the Republic of Niger. Niger, whose economic development is hampered by a lack of consistent electricity supply, is considering a potential role for nuclear power in its energy mix. A country of about 21 million people in Western Africa, Niger is currently ranked as the world’s fourth largest producer of uranium ore. The INIR team observed a strong Government commitment to developing the infrastructure for a nuclear power programme. The Government has established a Strategic Orientation Committee for the Nuclear Power Programme chaired by the Prime Minister, and a National Technical Committee for the Nuclear Power Programme chaired by the President of the Nigerien High Authority for Atomic Energy (HANEA). Those two committees form the Nuclear Energy Programme Implementing Organization (NEPIO). Niger has already completed or initiated several studies related to nuclear infrastructure development, and prepared a comprehensive report summarizing the results.

The Mathematica programmer

CERN Document Server

Maeder, Roman E

1994-01-01

The Mathematica Programmer covers the fundamental programming paradigms and applications of programming languages. This book is organized into two parts encompassing 10 chapters. Part 1 begins with an overview of the programming paradigms. This part also treats abstract data types, polymorphism and message passing, object-oriented programming, and relational databases. Part 2 looks into the practical aspects of programming languages, including in lists and power series, fractal curves, and minimal surfaces.This book will prove useful to mathematicians and computer scientists.

Potential for sharing nuclear power infrastructure between countries

International Nuclear Information System (INIS)

2006-10-01

The introduction or expansion of a nuclear power programme in a country and its successful execution is largely dependent on the network of national infrastructure, covering a wide range of activities and capabilities. The infrastructure areas include legal framework, safety and environmental regulatory bodies, international agreements, physical facilities, finance, education, training, human resources and public information and acceptance. The wide extent of infrastructure needs require an investment that can be too large or onerous for the national economy. The burden of infrastructure can be reduced significantly if a country forms a sharing partnership with other countries. The sharing can be at regional or at multinational level. It can include physical facilities, common programmes and knowledge, which will reflect in economic benefits. The sharing can also contribute in a significant manner to harmonization of codes and standards in general and regulatory framework in particular. The opportunities and potential of sharing nuclear power infrastructure is determined by the objectives, strategy and scenario of the national nuclear power programme. A review of individual infrastructure items shows that there are several opportunities for sharing of nuclear power infrastructure between countries if they cooperate with each other. International cooperation and sharing of nuclear power infrastructure are not new. This publication provides criteria and guidance for analyzing and identifying the potential for sharing of nuclear power infrastructure during the stages of nuclear power project life cycle. The target users are decision makers, advisers and senior managers in utilities, industrial organizations, regulatory bodies and governmental organizations in countries adopting or extending nuclear power programmes. This publication was produced within the IAEA programme directed to increase the capability of Member States to plan and implement nuclear power

A stepwise approach for defining the applicability domain of SAR and QSAR models

DEFF Research Database (Denmark)

Dimitrov, Sabcho; Dimitrova, Gergana; Pavlov, Todor

2005-01-01

A stepwise approach for determining the model applicability domain is proposed. Four stages are applied to account for the diversity and complexity of the current SAR/QSAR models, reflecting their mechanistic rationality (including metabolic activation of chemicals) and transparency. General para...

Stepwise radiofrequency ablation of Barrett's esophagus preserves esophageal inner diameter, compliance, and motility

NARCIS (Netherlands)

Beaumont, H.; Gondrie, J. J.; McMahon, B. P.; Pouw, R. E.; Gregersen, H.; Bergman, J. J.; Boeckxstaens, G. E.

2009-01-01

Background and aim: Stepwise endoscopic circumferential and focal radiofrequency ablation is safe and effective for the eradication of Barrett's esophagus. In contrast to other techniques, radiofrequency ablation appears to avoid significant esophageal scarring or stenosis. Our aim was to evaluate

Critical heat flux phenomena in flow boiling during step wise and ramp wise power transients

International Nuclear Information System (INIS)

Celata, G.P.; Cumo, M.; D'Annibale, F.; Farello, G.E.; Abou Said, S.

1987-01-01

The present paper deals with the results of an experimental investigation of the forced flow critical heat flux during power transients in a vertically heated channel. Experiments were carried out with a Refrigerant-12 1oop employing a circular test section which was electrically and uniformly heated. The power transients were performed with the step-wise and ramp-wise increase of the power to the test section. The test parameters included several values of the initial power (before the transient) and the final power (at the end of the transient) in the case of step-wise transients and the slope of the ramp in the case of ramp-wise transients. The pressure and specific mass flow rate, which were kept constant during the power transient,were varied from 1.2 to 2.7 MPa and 850 to 1500 Kg/sm 2 , respectively. Correlations of the experimental data for the time-to-crisis in terms of the independent parameters of the system are also proposed and verified for different values of pressure,mass flow rate, and inlet subcooling

Comparisons of self-ratings on managerial competencies, research capability, time management, executive power, workload and work stress among nurse administrators.

Science.gov (United States)

Kang, Chun-Mei; Chiu, Hsiao-Ting; Hu, Yi-Chun; Chen, Hsiao-Lien; Lee, Pi-Hsia; Chang, Wen-Yin

2012-10-01

To assess the level of and the differences in managerial competencies, research capability, time management, executive power, workload and work-stress ratings among nurse administrators (NAs), and to determine the best predictors of managerial competencies for NAs. Although NAs require multifaceted managerial competencies, research related to NAs' managerial competencies is limited. A cross-sectional survey was conducted with 330 NAs from 16 acute care hospitals. Managerial competencies were determined through a self-developed questionnaire. Data were collected in 2011. All NAs gave themselves the highest rating on integrity and the lowest on both financial/budgeting and business acumen. All scores for managerial competencies, research capability, time management and executive power showed a statistically significant correlation. The stepwise regression analysis revealed that age; having received NA training; having completed a nursing project independently; and scores for research capability, executive power and workload could explain 63.2% of the total variance in managerial competencies. The present study provides recommendations for future administrative training programmes to increase NAs' managerial competency in fulfilling their management roles and functions. The findings inform leaders of hospitals where NAs need to develop additional competencies concerning the type of training NAs need to function proficiently. © 2012 Blackwell Publishing Ltd.

The socio-economic monitoring of the Ignalina Nuclear Power Plant region: methodology, programme, implementation

International Nuclear Information System (INIS)

Baubinas, R.; Burneika, D.; Daugirdas, V.

2002-01-01

The article is devoted to the argumentation of the main principles of socio-economic monitoring of the Ignalina NPP region. The programme and the territorial levels of the monitoring as well as the main results of the trial of the programme are presented. (author)

Implementing agreement on photovoltaic power systems - Annual report 2003

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

This annual report for the International Energy Agency (IEA) reports on the programme's activities in 2003. The IEA Photovoltaic Power Systems Programme (PVPS) is one of the collaborative research and development agreements established within the IEA. Its mission is to enhance international collaboration efforts which support the development and deployment of photovoltaic solar energy. In this annual report, the programme's mission and its strategies for reaching four objectives are reviewed. The programme's tenth anniversary is noted. Status reports on the programme's various tasks and sub-tasks are presented. The tasks include the exchange and dissemination of information on photovoltaic power systems, the operational performance, maintenance and sizing of photovoltaic systems, the use of photovoltaic power systems in stand-alone and island applications, grid interconnection of building integrated and other distributed photovoltaic power systems, photovoltaic power systems in the built environment, a study on very large scale photovoltaic power generation system, the deployment of photovoltaic technologies in developing countries and urban-scale PV applications. The status and prospects in the 20 countries and organisations participating in the programme are presented. Along with country-specific topics, industry activities, research, development and demonstration projects, applications, education and governmental activities as well as future activities are reviewed. The report is completed with a list of Executive Committee members and Operating Agents.

Contribution of International and Regional Networks in Developing and Maintaining Human Capacity Building for Nuclear Power Programmes

International Nuclear Information System (INIS)

Osman, O. E.

2015-01-01

Capacity is defined as; the ability of individuals and organizations or organizational units to perform functions effectively, efficiently and sustainably. Capacity building is an evidence-driven process of strengthening the abilities of individuals, organizations, and systems to perform core functions sustainably, and to continue to improve and develop over time. This article will explain the contributions of knowledge networks at the national, regional and international level in developing the existing capacity building and human resources for regulatory body in Sudan, to confront the future challenges regarding to nuclear power program- safety and security. The article will compare the advantages and effectiveness of these knowledge networks (IAEA, ANNuR, FNRBA) in capacity building and enhance the infrastructure of national regulatory body. And how these networks contribute to enable the regulatory bodies in Africa and Arab countries, to establish and strengthen their regulatory infrastructure for nuclear power programme consistent with international standards and recommendations. As well as the recommendations resulting and deduced from comparative study to promote the exchange of knowledge, experience and information among its members. (author)

Stepwise mechanism of oxidative ammonolysis of propane to acrylonitrile over gallium-antimony oxide catalysts

Energy Technology Data Exchange (ETDEWEB)

Osipova, Z.G.; Sokolovskii, V.D.

1979-03-01

The stepwise mechanism of oxidative ammonolysis of propane to acrylonitrile over gallium-antimony oxide catalysts GaSb/sub 19/O/sub x/, GaSb/sub 3/Ni/sub 1.5/0/sub x/, and GaSb/sub 2.5/Ni/sub 1.5/PW/sub 0//sub 0.25/O/sub x/ was studied at 450/sup 0/ and 550/sup 0/C by introducing alternating pulses of 0.5Vertical Bar3< propane/0.6Vertical Bar3< ammonia/helium (to reduce the steady-state catalytic surface) and 0.5Vertical Bar3< propane/0.6Vertical Bar3< ammonia/1.86Vertical Bar3< oxygen/helium mixtures into a fluidized-bed catalytic reactor. Over all the catalysts studied, the rates of acrylonitrile formation during the two types of pulses were very similar, but carbon dioxide was formed much faster during the reducing pulses, particularly at 450/sup 0/C. These findings suggested that acrylonitrile is formed by a stepwise redox mechanism involving consecutive interaction of propane and ammonia with the surface oxygen of the catalysts and oxidation of the reduced catalyst surface by gas-phase oxygen. The formation of carbon dioxide proceeds by both stepwise and associative mechanisms, the latter being more important at higher temperatures. The results are similar to published results for ammoxidation of propylene and olefins.

A review of the UK fast reactor programme

International Nuclear Information System (INIS)

Picker, C.; Ainsworth, K.F.

1998-01-01

The general position with regard to nuclear power and fast reactors in the UK during 1996 is described. The main UK Government-funded fast reactor research and development programme was concluded in 1993, to be replaced by a smaller programme which is mainly funded and managed by British Nuclear Fuels plc. The main focus of this programme sustains the UK participation in the European Fast Reactor (EFR) collaboration and the broader international links built-up over the previous decades. The status of fast reactor studies made in the UK in 1996 is outlined and, with respect to the Prototype Fast Reactor at Dounreay, a report of progress with the closure studies, fuel reprocessing and decommissioning activities is provided. (author)

Stepwise integral scaling method and its application to severe accident phenomena

International Nuclear Information System (INIS)

Ishii, M.; Zhang, G.

1993-10-01

Severe accidents in light water reactors are characterized by an occurrence of multiphase flow with complicated phase changes, chemical reaction and various bifurcation phenomena. Because of the inherent difficulties associated with full-scale testing, scaled down and simulation experiments are essential part of the severe accident analyses. However, one of the most significant shortcomings in the area is the lack of well-established and reliable scaling method and scaling criteria. In view of this, the stepwise integral scaling method is developed for severe accident analyses. This new scaling method is quite different from the conventional approach. However, its focus on dominant transport mechanisms and use of the integral response of the system make this method relatively simple to apply to very complicated multi-phase flow problems. In order to demonstrate its applicability and usefulness, three case studies have been made. The phenomena considered are (1) corium dispersion in DCH, (2) corium spreading in BWR MARK-I containment, and (3) incore boil-off and heating process. The results of these studies clearly indicate the effectiveness of their stepwise integral scaling method. Such a simple and systematic scaling method has not been previously available to severe accident analyses

The waste isolation safety assessment programme

International Nuclear Information System (INIS)

Brandstetter, A.; Harwell, M.A.

1980-01-01

Associated with commercial nuclear power production in the USA is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE), through the National Waste Terminal Storage (NWTS) Programme, is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectations of meeting that objective. The Waste Isolation Safety Assessment Programme (WISAP) has been established at the Pacific Northwest Laboratory (operated by Battelle Memorial Institute) for developing the capability of making those analyses. Among the analyses required for isolation system evaluation is the detailed assessment of the post-closure performance of nuclear waste repositories in geologic formations. This assessment is essential, since it is concerned with aspects of the nuclear power programme which previously have not been addressed. Specifically, the nature of the isolation systems (e.g. involving breach scenarios and transport through the geosphere), and the time-scales necessary for isolation, dictate the development, demonstration and application of novel assessment capabilities. The assessment methodology needs to be thorough, flexible, objective, and scientifically defensible. Further, the data utilized must be accurate, documented, reproducible, and based on sound scientific principles. (author)

The IAEA Accident Management Programme

Energy Technology Data Exchange (ETDEWEB)

Kabanov, L.; Jankowski, M.; Mauersberger, H. (International Atomic Energy Agency, Vienna (Austria))

1993-02-01

Accident prevention and mitigation programmes and the Emergency Response System (ERS) are important elements of the Agency's activities in the area of nuclear power plant (NPP) safety. Safety Codes and Guides on siting, design, quality assurance and the operation of NPPs have been produced and are used by NPP operating organizations. Nuclear safety evaluation services are provided by the IAEA. The Emergency Response System and the International Nuclear Event Scale (INES) have been developed. The framework for the development of an accident management programme has been set up. The main goal is to develop an Accident Management Manual to provide a systematic, structured approach to the development and implementation of an accident management programme at NPPs. An outline of the Manual has been distributed and the first draft is available. The component parts are: Co-ordinated research programmes (CRPs) on severe accident management and containment behaviour; the use of vulnerability analysis; mitigation of the effects of hydrogen, and generic symptom oriented emergency operating procedures. The IAEA provides guidance by the dissemination of information on methods for accident management; collates information on approaches in this field in different organizations and countries; and arranges exchange of experience and the promulgation of knowledge through the training of NPP managers and senior technical staff. (orig.).

The IAEA Accident Management Programme

International Nuclear Information System (INIS)

Kabanov, L.; Jankowski, M.; Mauersberger, H.

1993-01-01

Accident prevention and mitigation programmes and the Emergency Response System (ERS) are important elements of the Agency's activities in the area of nuclear power plant (NPP) safety. Safety Codes and Guides on siting, design, quality assurance and the operation of NPPs have been produced and are used by NPP operating organizations. Nuclear safety evaluation services are provided by the IAEA. The Emergency Response System and the International Nuclear Event Scale (INES) have been developed. The framework for the development of an accident management programme has been set up. The main goal is to develop an Accident Management Manual to provide a systematic, structured approach to the development and implementation of an accident management programme at NPPs. An outline of the Manual has been distributed and the first draft is available. The component parts are: Co-ordinated research programmes (CRPs) on severe accident management and containment behaviour; the use of vulnerability analysis; mitigation of the effects of hydrogen, and generic symptom oriented emergency operating procedures. The IAEA provides guidance by the dissemination of information on methods for accident management; collates information on approaches in this field in different organizations and countries; and arranges exchange of experience and the promulgation of knowledge through the training of NPP managers and senior technical staff. (orig.)

Design and implementation of high-precision and low-jitter programmable delay circuitry

International Nuclear Information System (INIS)

Gao Yuan; Cui Ke; Zhang Hongfei; Luo Chunli; Yang Dongxu; Liang Hao; Wang Jian

2011-01-01

A programmable delay circuit design which has characteristics of high-precision, low-jitter, wide-programmable-range and low power is introduced. The delay circuitry uses the scheme which has two parts: the coarse delay and the fine delay that could be controlled separately. Using different coarse delay chip can reach different maximum programmable range. And the fine delay programmable chip has the minimum step which is down to 10 ps. The whole circuitry jitter will be less than 100 ps. The design has been successfully applied in Quantum Key Distribution experiment. (authors)

Low Power S-Box Architecture for AES Algorithm using Programmable Second Order Reversible Cellular Automata: An Application to WBAN.

Science.gov (United States)

Gangadari, Bhoopal Rao; Ahamed, Shaik Rafi

2016-12-01

In this paper, we presented a novel approach of low energy consumption architecture of S-Box used in Advanced Encryption Standard (AES) algorithm using programmable second order reversible cellular automata (RCA 2 ). The architecture entails a low power implementation with minimal delay overhead and the performance of proposed RCA 2 based S-Box in terms of security is evaluated using the cryptographic properties such as nonlinearity, correlation immunity bias, strict avalanche criteria, entropy and also found that the proposed architecture is secure enough for cryptographic applications. Moreover, the proposed AES algorithm architecture simulation studies show that energy consumption of 68.726 nJ, power dissipation of 3.856 mW for 0.18- μm at 13.69 MHz and energy consumption of 29.408 nJ, power dissipation of 1.65 mW for 0.13- μm at 13.69 MHz. The proposed AES algorithm with RCA 2 based S-Box shows a reduction power consumption by 50 % and energy consumption by 5 % compared to best classical S-Box and composite field arithmetic based AES algorithm. Apart from that, it is also shown that RCA 2 based S-Boxes are dynamic in nature, invertible, low power dissipation compared to that of LUT based S-Box and hence suitable for Wireless Body Area Network (WBAN) applications.

Efficient and Mild Microwave-Assisted Stepwise Functionalization of Naphthalenediimide with α-Amino Acids

NARCIS (Netherlands)

Pengo, Paolo; Pantoş, G. Dan; Otto, Sijbren; Sanders, Jeremy K.M.

2006-01-01

Microwave dielectric heating proved to be an efficient method for the one-pot and stepwise syntheses of symmetrical and unsymmetrical naphthalenediimide derivatives of α-amino acids. Acid-labile side chain protecting groups are stable under the reaction conditions; protection of the α-carboxylic

Optimal Control of Wind Power Generation

Directory of Open Access Journals (Sweden)

Pawel Pijarski

2018-03-01

Full Text Available Power system control is a complex task, which is strongly related to the number and kind of generating units as well as to the applied technologies, such as conventional coal fired power plants or wind and photovoltaic farms. Fast development of wind generation that is considered as unstable generation sets new strong requirements concerning remote control and data hubs cooperating with SCADA systems. Considering specific nature of the wind power generation, the authors analyze the problem of optimal control for wind power generation in farms located over a selected remote-controlled part of the Operator grid under advantageous wind conditions. This article presents an original stepwise method for tracing power flows that makes possible to eliminate current (power overloading of power grid branches. Its core idea is to consider the discussed problem as an optimization task.

FY 1998 Report on development of technologies for commercialization of photovoltaic power systems. International co-operative project (IEA implementing agreement for a co-operative programme on photovoltaic power systems, 9th and 10th executive committee meetings); 1998 nendo taiyoko hatsuden system jitsuyoka gijutsu kaihatsu kokusai kyoryoku jigyo. IEA taiyoko hatsuden system kenkyu kyoryoku program jisshi kyotei dai 10 kai dai 9 kai iinkai

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

Described herein are outline of the International Energy Agency/Co-operative programme on Photovoltaic Power Systems (IEA/PVPS), and minutes of the 9th and 10th executive committee meetings. Japan signed the IEA Implementing Agreement for a co-operative programme on Photovoltaic Power Systems in April 1993, and has been participating in the programme for research and development, demonstration, analysis, information exchange and introduction promotion, among others. The tasks are composed of exchange and dissemination of information on PVPS, operational performance and design of PVPS, use of PVPS in stand alone and island applications, grid interconnection of building integrated and other dispersed PVPS, design and grid interconnection of dispersed PVPS, e.g., roof type, design and operation of modular PV plants for large scale power generation, PV in the built environment, and feasibility study on large scale PV power generation utilizing desert areas. The 9th and 10th executive committee meetings include the co-operative programme progress reports and technical tours. (NEDO)

Monitoring during the stepwise implementation of the Swedish deep repository for spent fuel

Energy Technology Data Exchange (ETDEWEB)

Baeckblom, Goeran [Conrox (Sweden); Almen, Karl-Erik [KEA Geokonsult AB (Sweden)

2004-03-01

Monitoring in this report is defined as 'Continuous or repeated observations or measurements of parameters to increase the scientific understanding of the site and the repository, to show compliance with requirements or for adaptation of plans in light of the monitoring results.' The international outlook from IAEA, OECD/NEA, CEC and some country-specific reviews presented in the report forms a necessary background to the Swedish monitoring framework. The implementation of the deep repository in Sweden is executed in phases where monitoring is an inherently integrated activity in the programme. The first phase is the site investigations when Primary Baseline conditions are established. During the following construction phase of the repository, detailed site characterisation continues in conjunction with construction of the access to the deposition area, construction of parts of the deposition area and the central service area. Monitoring is then used to track the changes to the previously established Primary Baseline conditions and distinguishing these imposed changes from natural variations or from other man-made influences. During the initial operation phase, around 200-400 canisters of spent fuel is emplaced and deposition tunnels backfilled. After up-dated evaluations, the phase of regular operation begin, where detailed characterisation, construction of the repository and waste emplacement are concurrent activities. The closure of the repository will take place when all spent fuel has been emplaced, i.e. in the latter part of this century. Monitoring during the stepwise implementation of the repository is executed of several reasons mainly to: describe the Primary Baseline conditions of the repository site, develop and demonstrate understanding of the repository site and the behaviour of engineered barriers, assist in the decision-making process, show compliance with international and national guidelines and regulations. Specific rationales for

Regressão múltipla stepwise e hierárquica em Psicologia Organizacional: aplicações, problemas e soluções Stepwise and hierarchical multiple regression in organizational psychology: Applications, problemas and solutions

Directory of Open Access Journals (Sweden)

Gardênia Abbad

2002-01-01

Full Text Available Este artigo discute algumas aplicações das técnicas de análise de regressão múltipla stepwise e hierárquica, as quais são muito utilizadas em pesquisas da área de Psicologia Organizacional. São discutidas algumas estratégias de identificação e de solução de problemas relativos à ocorrência de erros do Tipo I e II e aos fenômenos de supressão, complementaridade e redundância nas equações de regressão múltipla. São apresentados alguns exemplos de pesquisas nas quais esses padrões de associação entre variáveis estiveram presentes e descritas as estratégias utilizadas pelos pesquisadores para interpretá-los. São discutidas as aplicações dessas análises no estudo de interação entre variáveis e na realização de testes para avaliação da linearidade do relacionamento entre variáveis. Finalmente, são apresentadas sugestões para lidar com as limitações das análises de regressão múltipla (stepwise e hierárquica.This article discusses applications of stepwise and hierarchical multiple regression analyses to research in organizational psychology. Strategies for identifying type I and II errors, and solutions to potential problems that may arise from such errors are proposed. In addition, phenomena such as suppression, complementarity, and redundancy are reviewed. The article presents examples of research where these phenomena occurred, and the manner in which they were explained by researchers. Some applications of multiple regression analyses to studies involving between-variable interactions are presented, along with tests used to analyze the presence of linearity among variables. Finally, some suggestions are provided for dealing with limitations implicit in multiple regression analyses (stepwise and hierarchical.

SKI's Evaluation of SKB's RD and D Programme 95. Review Report

International Nuclear Information System (INIS)

1996-10-01

SKI (the Swedish Nuclear Power Inspectorate) has sent SKB's (the Swedish Nuclear Fuel and Waste Management Co.) RD and D Programme 95 to sixty authorities and organizations for review. 35 reviewing bodies have replied. In various ways, most of the comments are related to the decision-making process, both with regard to site selection and choice of method and only a small number of reviewing bodies have dealt with the more purely technical issues such as the function of the barriers and the safety assessment methodology. SKI's review of the programme is based on the premises of establishing whether and how the programme can fulfill its actual purpose to identify and implement solutions for the final disposal of the spent nuclear fuel from the Swedish nuclear power plants. SKI's statement to the Government includes a 'Summary and Conclusions' of the 'Review Report'. In (the present) 'Review Report' SKI reviews the programme and deals with comments from the other reviewing bodies. Furthermore, SKI has commissioned a separate report with the 'Comments of the Reviewing Bodies'. 32 refs

Programmable automated transistor test system

International Nuclear Information System (INIS)

Truong, L.V.; Sundberg, G.R.

1986-01-01

The paper describes a programmable automated transistor test system (PATTS) and its utilization to evaluate bipolar transistors and Darlingtons, and such MOSFET and special types as can be accommodated with the PATTS base-drive. An application of a pulsed power technique at low duty cycles in a non-destructive test is used to examine the dynamic switching characteristic curves of power transistors. Data collection, manipulation, storage, and output are operator interactive but are guided and controlled by the system software. In addition a library of test data is established on disks, tapes, and hard copies for future reference

Programme of CABRI start-up measurements with the Zircaloy loop

International Nuclear Information System (INIS)

Kussmaul, G.; Rongier, P.

1981-06-01

After installation and operational tests of the CABRI Zircaloy loop, a start-up test programme will be carried out to determine the new coupling value between the driver core and the test pin and the reactivity dependent driver core energy release for transients from different power levels and modified injection rates. The purpose of the tests and the test programme itself are described in the report

Radiation and Environmental Protection Programme for the First Upcoming Nuclear Power Plant in Indonesia

International Nuclear Information System (INIS)

Syahrir

2007-01-01

Indonesia plans to operate the first nuclear power plant (NPP) by 2016. A radiation and environmental protection arrangement for NPPs is part of the whole safety system which is embedded in every practice involved radiation exposure to workers and members of public. A radiation and environmental protection programme for the NPP should adhere to international standards and mainstream in order to be acceptable to the public and international communities. International Atomic Energy Agency (IAEA) has recommended a radiation protection standard for NPPs as studied in this paper. Focus is given to the operational aspects of radiation protection program and discharge control to the environment. Some documents related to Safety Analysis Reports were used as working examples on its implementation. The study includes the classification of working areas and access control; local rules and supervision of work; work planning and work permits; protective clothing and protective equipment; facilities, shielding and equipment; application of the principle of optimization of protection; and removal or reduction in intensity of sources of radiation. The radiological protection aspects blend together in the whole NPP practices, each individual has his/her own responsibility in association with the radiation protection program implementation. It also present in the whole steps of NPP preparation up to its decommissioning. Promise on safety improvement and significant dose reduction in the recent development in NPP technology should scrutinized so that the option of proven technology as required in commercial power reactor licensing considers this tendency. (author)

Implementing agreement on photovoltaic power systems - Annual report 2000

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

This annual report for the International Energy Agency (IEA) reports on the programme's activities in 2000. The IEA Photovoltaic Power Systems Programme (PVPS) is one of the collaborative research and development agreements established within the IEA. Its mission is to enhance international collaboration efforts which support the development and deployment of photovoltaic solar energy. In this annual report, the programme's mission and its strategies for reaching four objectives are reviewed. Status reports on the programme's various tasks and sub-tasks are presented. The tasks include the exchange and dissemination of information on photovoltaic power systems, the operational performance and design of photovoltaic systems, the use of photovoltaic power systems in stand-alone and island applications, the grid interconnection of building-integrated and other distributed photovoltaic power systems, photovoltaic power systems in the built environment, very large scale photovoltaic power generation systems and the deployment of photovoltaic technologies in developing countries. The status and prospects in the 20 countries participating in the programme are presented. Along with country-specific topics, industry activities, research, development and demonstration projects, applications, education and governmental activities as well as future activities are reviewed. The report is completed with a list of Executive Committee members and Operating Agents.

Implementing agreement on photovoltaic power systems - Annual report 2001

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

This annual report for the International Energy Agency (IEA) reports on the programme's activities in 2001. The IEA Photovoltaic Power Systems Programme (PVPS) is one of the collaborative research and development agreements established within the IEA. Its mission is to enhance international collaboration efforts which support the development and deployment of photovoltaic solar energy. In this annual report, the programme's mission and its strategies for reaching four objectives are reviewed. Status reports on the programme's various tasks and sub-tasks are presented. The tasks include the exchange and dissemination of information on photovoltaic power systems, the operational performance, maintenance and sizing of photovoltaic systems, the use of photovoltaic power systems in stand-alone and island applications, grid interconnection of building integrated and other distributed photovoltaic power systems, photovoltaic power systems in the built environment, a study on very large scale photovoltaic power generation system and the deployment of photovoltaic technologies in developing countries. The status and prospects in the 20 countries participating in the programme are presented. Along with country-specific topics, industry activities, research, development and demonstration projects, applications, education and governmental activities as well as future activities are reviewed. The report is completed with a list of Executive Committee members and Operating Agents.

Fracture mechanics investigations within the swiss surveillance programme for the pressure vessel of modern nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Ullrich, G; Krompholz, K [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

1994-12-31

In the frame of surveillance programmes of Swiss nuclear power plants, irradiation tests have been performed on tensile, impact and wedge opening load specimens as well as on three point bend-type specimens (for J-integral investigations) and pre-cracked Charpy impact specimens (for dynamical stress intensities K{sub ID}). An experimental method (potential drop technique) is used together with a mathematical procedure which allow for the determination of the stress intensity K{sub IC} for small CT-samples instead of large ones: agreement of these both methods is found excellent, and the mapping of both methods to fatigue pre-cracked small specimens (3 PB and Charpy) is possible. The application of the analysis method to dynamical tests is also possible. 15 refs., 9 figs., 1 tab.

Price signals in the power market

International Nuclear Information System (INIS)

2000-01-01

Which price signals should be given to the players in the power market to promote a socio-economic power supply in the short term and the long term? In a model with perfect competition, without problems involving delivery quality, and with free scalable capacity in both transmission and production, price signals that reflect marginal losses and shortage of transmission capacity are all that is needed. Stepwise investments create a need for measures that are specific to the situation. Price signals reflecting delivery reliability are probably too weak today. Market power may create a need for greater transmission capacity, but gives no reason for new price signals. Tariffs that reduce installed capacity weakens delivery quality and increases the probability of market power

Implementing agreement on photovoltaic power systems - Annual report 2004

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

This annual report for the International Energy Agency (IEA) reports on the programme's activities in 2004. The IEA Photovoltaic Power Systems Programme (PVPS) is one of the collaborative research and development agreements established within the IEA. Its mission is to enhance international collaboration efforts which support the development and deployment of photovoltaic solar energy. In this annual report, the programme's mission and its strategies for reaching four objectives are reviewed and status reports on the programme's various tasks and sub-tasks are presented. The tasks include the exchange and dissemination of information on photovoltaic power systems, the performance, reliability and analysis of photovoltaic systems, the use of photovoltaic power systems in stand-alone and island applications, a study on very large scale photovoltaic power generation system, photovoltaic services for developing countries and urban-scale PV applications. The status and prospects in the 21 countries and organisations participating in the programme are presented. Along with country-specific topics, industry activities, research, development and demonstration projects, applications, education and governmental activities as well as future activities are reviewed. Finally, completed tasks are reviewed. These include grid interconnection of building integrated and other distributed photovoltaic power systems, design and operation of modular photovoltaic plants for large scale power generation and photovoltaic power systems in the built environment. The report is completed with a list of Executive Committee members and Operating Agents.

Implementing agreement on photovoltaic power systems - Annual report 2005

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

This annual report for the International Energy Agency (IEA) reports on the programme's activities in 2005. The IEA Photovoltaic Power Systems Programme (PVPS) is one of the collaborative research and development agreements established within the IEA. Its mission is to enhance international collaboration efforts which support the development and deployment of photovoltaic solar energy. In this annual report, the programme's mission and its strategies for reaching four objectives are reviewed and status reports on the programme's various tasks and sub-tasks are presented. The tasks include the exchange and dissemination of information on photovoltaic power systems, the performance, reliability and analysis of photovoltaic systems, a study on very large scale photovoltaic power generation system, photovoltaic services for developing countries and urban-scale PV applications. The status and prospects in the 21 countries and organisations participating in the programme are presented. Along with country-specific topics, industry activities, research, development and demonstration projects, applications, education and governmental activities as well as future activities are reviewed. Finally, completed tasks are reviewed. These include the use of photovoltaic power systems in stand-alone and island applications, grid interconnection of building integrated and other distributed photovoltaic power systems, design and operation of modular photovoltaic plants for large scale power generation and photovoltaic power systems in the built environment. The report is completed with a list of Executive Committee members and Operating Agents.

Nuclear power and the environment

International Nuclear Information System (INIS)

Matthews, R.R.

1976-01-01

A brief statement is presented of the nuclear power reactor programme in the United Kingdom and of the statutory and other organisations for ensuring reactor safety. The possible effects of the programme on the environment are dealt with under three heads: (1) discharge of radioactive effluents during normal operation of the power plants; (2) storage and disposal of radioactive waste; (3) reactor safety. Radiological protection of operating staff is also described briefly. (U.K.)

An antarctic stratigraphic record of stepwise ice growth through the eocene-oligocene transition

NARCIS (Netherlands)

Passchier, Sandra; Ciarletta, Daniel J.; Miriagos, Triantafilo E.; Bijl, Peter K.; Bohaty, Steven M.

2017-01-01

Earth's current icehouse phase began ~34 m.y. ago with the onset of major Antarctic glaciation at the Eocene-Oligocene transition. Changes in ocean circulation and a decline in atmospheric greenhouse gas levels were associated with stepwise cooling and ice growth at southern high latitudes. The

The Programmer's Guide to iSeries Navigator

CERN Document Server

Touhy, Paul

2012-01-01

iSeries Navigator is a favorite tool of operators and administrators-who use it with great success-but many programmers have missed the great programming tools that is provides! This book introduces you to iSeries Navigator along with all the powerful tools and interfaces that will expand your programming horizons. As iSeries applications continue to move toward a graphical user interface (GUI), so does the development environment. Programs such as CODE and WDSC may fill the need for the programming environment, but iSeries Navigator fills the programmer's need for general system access as wel

Programmable neural processing on a smartdust for brain-computer interfaces.

Science.gov (United States)

Yuwen Sun; Shimeng Huang; Oresko, Joseph J; Cheng, Allen C

2010-10-01

Brain-computer interfaces (BCIs) offer tremendous promise for improving the quality of life for disabled individuals. BCIs use spike sorting to identify the source of each neural firing. To date, spike sorting has been performed by either using off-chip analysis, which requires a wired connection penetrating the skull to a bulky external power/processing unit, or via custom application-specific integrated circuits that lack the programmability to perform different algorithms and upgrades. In this research, we propose and test the feasibility of performing on-chip, real-time spike sorting on a programmable smartdust, including feature extraction, classification, compression, and wireless transmission. A detailed power/performance tradeoff analysis using DVFS is presented. Our experimental results show that the execution time and power density meet the requirements to perform real-time spike sorting and wireless transmission on a single neural channel.

Laboratory quality stepwise implementation tool: National reference TB laboratory of Iran

OpenAIRE

Ali Naghi Kebriaee; Donya Malekshahian; Mojtaba Ahmadi; Parissa Farnia

2015-01-01

Background and objective: During recent years, the World Health Organization (WHO) proposed new software for improving the tuberculosis (TB) laboratory services. The protocol is known as “quality stepwise implementation tool” and is based on enforcement of quality assurance services through accreditation by the International Organization for Standardization (ISO) 15189. As a national reference TB laboratory (NRL) of Iran, the benefit and challenges of implementing this standard were analyzed....

Lessons Learned in Performing and Implementing the Results of TNA in a Newly Developed Regulatory Body with a Mandate to Regulate the Country's Expanding Nuclear Power Programme: A Case Study of PNRA no. 97

International Nuclear Information System (INIS)

Shahzad, Moazzam

2014-01-01

Conclusion: → It is essential that regulatory bodies apply a systematic approach to training need assessment; → Education and training requires capital investment, time and effort; it must be planned long in advance to be effective; → It is essential for a country considering a nuclear power programme to establish and implement a corresponding manpower development programme for its regulatory body

ADS National Programmes: China

International Nuclear Information System (INIS)

2015-01-01

In China the conceptual study of an ADS concept which lasted for about five years ended in 1999. As one project of the National Basic Research Programme of China (973 Programme) in energy domain, which is sponsored by the China Ministry of Science and Technology (MOST), a five year programme of fundamental research of ADS physics and related technology was launched in 2000 and passed national review at the end of 2005. From 2007, another five year 973 Programme Key Technology Research of Accelerator Driven Subcritical System for Nuclear waste Transmutation started. The research activities were focused on HPPA physics and technology, reactor physics of external source driven subcritical assembly, nuclear data base and material study. For HPPA, a high current injector consisting of an ECR ion source, LEBT and an RFQ accelerating structure of 3.5 MeV has been built and were being improved. In reactor physics study, a series of neutron multiplication experimental study has been carrying out. The VENUS I facility has been constructed as the basic experimental platform for neutronics study in ADS blanket. VENUS I a zero power subcritical neutron multiplying assembly driven by external neutron produced by a pulsed neutron generator or 252Cf neutron source. The theoretical, experimental and simulation studies on nuclear data, material properties and nuclear fuel circulation related to ADS are carried out in order to provide the database for ADS system analysis. China Institute of Atomic Energy (CIAE), Institute of High Energy Physics (IHEP) and other Chinese institutes carried out the MOST project together. Besides CIAE, China Academy of Science (CAS) pays more and more attention to Advanced Nuclear Fuel Cycles (ANFC). A large programme of ANFC, including ADS and Th based nuclear fuel cycle, has been launched by CAS

Diversity and testing requirements of programmable automation systems

International Nuclear Information System (INIS)

Haapanen, P.; Maskuniitty, M.

1993-04-01

In the report programmable digital operation and safety automation systems for nuclear power plants are discussed. The programmable systems deviate by their properties and behaviour from the conventional non-programmable systems in such extent, that their verification and validation for safety critical applications requires new methods and practices. The safety assessment can not be based on conventional probabilistic methods due to the difficulties in the quantification of the reliability of the software and hardware. A safety critical programmable system shall include diverse redundant parts so that no residual program fault can not cause the failure of the intended function of the system. Although complete testing of a programmable system is impossible, different tests have a central role in the production and validation process of the system. Diversity is important also in confidence building measures for the implemented system. Independent analysis and testing of the system should use different methods and tools from those used in the production and validation process by the system vendor. Use of diversity and testing are concluded to be central issues in producing safe programmable system and in proving them to be safe enough. By combining functional and programming diversity in a suitable way one can produce a system that is safe enough without having a non-programmable back-up system. (48 refs., 10 figs., 2 tabs.)

Status of the HTR programme in France

International Nuclear Information System (INIS)

Ballot, B.; Gauthier, J.C.; Hittner, D.; Lebrun, J.Ph.; Lecomte, M.; Carre, F.; Delbecq, J.M.

2007-01-01

AREVA is convinced that HTR (High Temperature Reactor) is not in competition with large LWRs for electricity generation, and that its actual added value is its potential for addressing cogeneration and industrial process heat production. Therefore AREVA launched in 2004 the ANTARES programme for a pre-conceptual design study, with the support of EDF and together with a large research and development programme needed for the design in close collaboration with Cea. The pre-conceptual phase was finalized end of 2006. The specific feature of AREVA's concept, which distinguishes it from other ones, is its indirect cycle design powering a combined cycle power plant. Several reasons support this design choice, one of the most important being the design flexibility to adapt readily to combined heat and power applications, with a standardised nuclear heat source as independent as possible of the versatile process heat applications with which it is coupled. Standardisation should expedite licensing. In view of the volatility of the costs of fossil fuels, AREVA's choice brings to the large industrial heat applications the fuel cost predictability of nuclear fuel with the efficiency of a high temperature heat source free of greenhouse gases emissions. The reactor module produces 600 MWth which can be split into the required process heat, the remaining power driving an adapted prorated electric plant. Depending on the process heat temperature and power needs, up to 80 % of the nuclear heat is converted into useful energy

Using interlayer step-wise triplet transfer to achieve an efficient white organic light-emitting diode with high color-stability

Energy Technology Data Exchange (ETDEWEB)

Wang, Qi [State Key Laboratory of Polymer Physics and Chemistry, Changchun Institute of Applied Chemistry, Chinese Academy of Sciences, Changchun, Jilin 130022 (China); Department of Electrical Engineering and Computer Sciences, College of Engineering, South Dakota State University, Brookings, South Dakota 57007 (United States); Ma, Dongge, E-mail: mdg1014@ciac.jl.cn; Ding, Junqiao; Wang, Lixiang [State Key Laboratory of Polymer Physics and Chemistry, Changchun Institute of Applied Chemistry, Chinese Academy of Sciences, Changchun, Jilin 130022 (China); Leo, Karl [Tech. Univ. Dresden, Inst. Angew. Photophys., D-01062 Dresden (Germany); Qiao, Qiquan [Department of Electrical Engineering and Computer Sciences, College of Engineering, South Dakota State University, Brookings, South Dakota 57007 (United States); Jia, Huiping; Gnade, Bruce E. [Department of Materials Science and Engineering and Erik Jonsson School of Engineering and Computer Science, University of Texas at Dallas, Richardson, Texas 75083 (United States)

2014-05-12

An efficient phosphorescent white organic light emitting-diode with a red-green-blue tri-emitting-layer structure is reported. The host of the red dopant possesses a lower triplet-energy than the green dye. An interlayer step-wise triplet transfer via blue dye → green dye → red host → red dye is achieved. This mechanism allows an efficient triplet harvesting by the three dopants, thus maintaining a balanced white light and reducing energy loss. Moreover, the color stability of the device is improved significantly. The white device not only achieves a peak external quantum efficiency of 21.1 ± 0.8% and power efficiency of 37.5 ± 1.4 lm/W but shows no color shift over a wide range of voltages.

Results of research into nuclear power plant safety

International Nuclear Information System (INIS)

Polak, V.; Hladky, E.; Moravek, J.; Suchomel, J.; Stehlik, J.

1976-01-01

A survey is given of computer programmes for the safety analysis of nuclear power plants with WWER type reactors and with fast breeder reactors. The programmes solve accidents in the core, the primary circuit and the containment. A comparison is made of Czechoslovak and foreign computer programmes and their agreement proved. Also studied is the problem of radiation safety of nuclear power plants with regard to the leakage of radioactive isotopes and their detection. (J.B.)

The state and perspective of Belarus power engineering

International Nuclear Information System (INIS)

Mikhalevich, A.A.; Molochko, F.I.

1994-01-01

The economy of the Republic of Belarus has a high fuel and power resource deficit. In according to the National power engineering programme the power balance must be achieved by means of reconstruction and development of the energetics system on the basis of difference modern technologies, as well as carrying out power saving programme, It is suggested the building of a nuclear power plant in Belarus. The power engineering development directions for Belarus is discussed. The structure and dynamics of a power balance of the economy is described. It was shown the electric and heat energetics perspectives for Belarus by using of difference power sources. 3 tabs., 4 figs

The systemic management of cutaneous dermatomyositis: Results of a stepwise strategy

Directory of Open Access Journals (Sweden)

C.O. Anyanwu

2017-12-01

Full Text Available Treatment of dermatomyositis (DM is often achieved with a stepwise algorithm. However, the literature lacks quality evidence to support the use of this therapeutic strategy. The result of a stepwise therapeutic strategy in the management of skin-only DM is presented to better understand the clinical outcomes and allow for future studies. A cohort of 102 patients with DM, 41 of whom had skin-only disease, were seen between July 2009 and April 2013 at a referral-based connective tissue disease clinic. The Cutaneous Dermatomyositis Disease Area and Severity Index was used to prospectively assess disease severity and the outcomes in 41 adult patients with skin-only DM were analyzed. Of the 41 patients with skin-only DM, 23 patients (56.1% received antimalarial medications alone and 18 patients (43.9% received second- or third-line agents. Ten patients (24.4% remained at the first level of the treatment algorithm and received only hydroxychloroquine. Prednisone was included in the treatment regimen for 11 patients with skin-only disease (26.8%. The results show that management of cutaneous DM often requires second-line agents because antimalarial medications alone are insufficient to treat most patients with skin-only disease. Keywords: dermatomyositis, antimalarial, immunosuppressive, CDASI, outcome measures, treatment

A stepwise-cluster microbial biomass inference model in food waste composting

International Nuclear Information System (INIS)

Sun Wei; Huang, Guo H.; Zeng Guangming; Qin Xiaosheng; Sun Xueling

2009-01-01

A stepwise-cluster microbial biomass inference (SMI) model was developed through introducing stepwise-cluster analysis (SCA) into composting process modeling to tackle the nonlinear relationships among state variables and microbial activities. The essence of SCA is to form a classification tree based on a series of cutting or mergence processes according to given statistical criteria. Eight runs of designed experiments in bench-scale reactors in a laboratory were constructed to demonstrate the feasibility of the proposed method. The results indicated that SMI could help establish a statistical relationship between state variables and composting microbial characteristics, where discrete and nonlinear complexities exist. Significance levels of cutting/merging were provided such that the accuracies of the developed forecasting trees were controllable. Through an attempted definition of input effects on the output in SMI, the effects of the state variables on thermophilic bacteria were ranged in a descending order as: Time (day) > moisture content (%) > ash content (%, dry) > Lower Temperature (deg. C) > pH > NH 4 + -N (mg/Kg, dry) > Total N (%, dry) > Total C (%, dry); the effects on mesophilic bacteria were ordered as: Time > Upper Temperature (deg. C) > Total N > moisture content > NH 4 + -N > Total C > pH. This study made the first attempt in applying SCA to mapping the nonlinear and discrete relationships in composting processes.

The Nordic Research programme on nuclear safety

International Nuclear Information System (INIS)

1992-06-01

Only two of the five Nordic countries (Denmark, Iceland, Finland, Norway and Sweden) - Sweden and Finland - operate nuclear power plants, but there are a number of nuclear installations close to their borders. Regular 4-year programmes were initiated in 1977, designated NKS-programmes. (NKS: Nordisk KerneSikkerhedsforskning - Nordic nuclear-safety research). The current fourth NKS-programme is, influenced by the Chernobyl accident, dominated by the necessity for acquiring knowledge on unexpected events and release of radioactive material from nuclear installations. The present programme is divided into the areas of emergency preparedness, waste and decommissioning, radioecology and reactor safety. It comprises a total of 18 projects, the results of which will later be published in the form of handbooks for use in cases of emergency etc. The future of joint Nordic project work in the nuclear safety field must be seen in the light of changing conditions in and around the Nordic countries, such as the opening of relations to neighbours in the east, the move towards the European Communities and the need for training a new generation of specialists in the nuclear field etc. Each project is described in considerable detail and a list of reports resulting from the third NKS-programme 1985-1989 is given. (AB)

Radiation burden of population in nuclear power plant siting

International Nuclear Information System (INIS)

Navratil, J.

The significance is discussed of the determination of the radiobiological consequences of normal operation and design basis accidents in nuclear power plant siting. The basic diagram and brief description is given of the programme for calculating the radiation load of the population in the surroundings of the nuclear power plant. The programme consists of two subprogrammes, i.e., the dispersion of radioactive gases (for normal operation and for accidents), the main programme for the determination of biological consequences and one auxiliary programme (the distribution of the population in the surroundings of the power plant). The four most important types of exposure to ionizing radiation are considered, namely inhalation, external irradiation from a cloud, ingestion (water, milk, vegetables), external irradiation from the deposit. (B.S.)

Impact of statistical learning methods on the predictive power of multivariate normal tissue complication probability models.

Science.gov (United States)

Xu, Cheng-Jian; van der Schaaf, Arjen; Schilstra, Cornelis; Langendijk, Johannes A; van't Veld, Aart A

2012-03-15

To study the impact of different statistical learning methods on the prediction performance of multivariate normal tissue complication probability (NTCP) models. In this study, three learning methods, stepwise selection, least absolute shrinkage and selection operator (LASSO), and Bayesian model averaging (BMA), were used to build NTCP models of xerostomia following radiotherapy treatment for head and neck cancer. Performance of each learning method was evaluated by a repeated cross-validation scheme in order to obtain a fair comparison among methods. It was found that the LASSO and BMA methods produced models with significantly better predictive power than that of the stepwise selection method. Furthermore, the LASSO method yields an easily interpretable model as the stepwise method does, in contrast to the less intuitive BMA method. The commonly used stepwise selection method, which is simple to execute, may be insufficient for NTCP modeling. The LASSO method is recommended. Copyright © 2012 Elsevier Inc. All rights reserved.

Impact of Statistical Learning Methods on the Predictive Power of Multivariate Normal Tissue Complication Probability Models

Energy Technology Data Exchange (ETDEWEB)

Xu Chengjian, E-mail: c.j.xu@umcg.nl [Department of Radiation Oncology, University of Groningen, University Medical Center Groningen, Groningen (Netherlands); Schaaf, Arjen van der; Schilstra, Cornelis; Langendijk, Johannes A.; Veld, Aart A. van' t [Department of Radiation Oncology, University of Groningen, University Medical Center Groningen, Groningen (Netherlands)

2012-03-15

Purpose: To study the impact of different statistical learning methods on the prediction performance of multivariate normal tissue complication probability (NTCP) models. Methods and Materials: In this study, three learning methods, stepwise selection, least absolute shrinkage and selection operator (LASSO), and Bayesian model averaging (BMA), were used to build NTCP models of xerostomia following radiotherapy treatment for head and neck cancer. Performance of each learning method was evaluated by a repeated cross-validation scheme in order to obtain a fair comparison among methods. Results: It was found that the LASSO and BMA methods produced models with significantly better predictive power than that of the stepwise selection method. Furthermore, the LASSO method yields an easily interpretable model as the stepwise method does, in contrast to the less intuitive BMA method. Conclusions: The commonly used stepwise selection method, which is simple to execute, may be insufficient for NTCP modeling. The LASSO method is recommended.

Impact of Statistical Learning Methods on the Predictive Power of Multivariate Normal Tissue Complication Probability Models

International Nuclear Information System (INIS)

Xu Chengjian; Schaaf, Arjen van der; Schilstra, Cornelis; Langendijk, Johannes A.; Veld, Aart A. van’t

2012-01-01

Purpose: To study the impact of different statistical learning methods on the prediction performance of multivariate normal tissue complication probability (NTCP) models. Methods and Materials: In this study, three learning methods, stepwise selection, least absolute shrinkage and selection operator (LASSO), and Bayesian model averaging (BMA), were used to build NTCP models of xerostomia following radiotherapy treatment for head and neck cancer. Performance of each learning method was evaluated by a repeated cross-validation scheme in order to obtain a fair comparison among methods. Results: It was found that the LASSO and BMA methods produced models with significantly better predictive power than that of the stepwise selection method. Furthermore, the LASSO method yields an easily interpretable model as the stepwise method does, in contrast to the less intuitive BMA method. Conclusions: The commonly used stepwise selection method, which is simple to execute, may be insufficient for NTCP modeling. The LASSO method is recommended.

Country nuclear power profiles. 2003 ed

International Nuclear Information System (INIS)

2004-03-01

The preparation of Country Nuclear Power Profiles (CNPP) was initiated within the framework of the IAEA's programme on assessment and feedback of nuclear power plant performance. It responded to a need for a database and a technical publication containing a description of the energy and economic situation, the energy and the electricity sector, and the primary organizations involved in nuclear power in IAEA Member States. The CNPP covers background information on the status and development of nuclear power programmes in countries having nuclear plants in operation and/or plants under construction. It reviews the organizational and industrial aspects of nuclear power programmes in participating countries, and provides information about the relevant legislative, regulatory and international frameworks in each country. The CNPP compiles the current issues in the new environment within which the electricity and nuclear sector operates, i.e. energy policy, and privatization and deregulation in these sectors, the role of government, nuclear energy and climate change, and safety and waste management, which differ from country to country

Country nuclear power profiles. 2003 ed

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-03-01

The preparation of Country Nuclear Power Profiles (CNPP) was initiated within the framework of the IAEA's programme on assessment and feedback of nuclear power plant performance. It responded to a need for a database and a technical publication containing a description of the energy and economic situation, the energy and the electricity sector, and the primary organizations involved in nuclear power in IAEA Member States. The CNPP covers background information on the status and development of nuclear power programmes in countries having nuclear plants in operation and/or plants under construction. It reviews the organizational and industrial aspects of nuclear power programmes in participating countries, and provides information about the relevant legislative, regulatory and international frameworks in each country. The CNPP compiles the current issues in the new environment within which the electricity and nuclear sector operates, i.e. energy policy, and privatization and deregulation in these sectors, the role of government, nuclear energy and climate change, and safety and waste management, which differ from country to country.

Country nuclear power profiles. 2004 ed

International Nuclear Information System (INIS)

2005-12-01

The preparation of Country Nuclear Power Profiles (CNPP) was initiated within the framework of the IAEA's programme on assessment and feedback of nuclear power plant performance. It responded to a need for a database and a technical publication containing a description of the energy and economic situation, the energy and the electricity sector, and the primary organizations involved in nuclear power in IAEA Member States. The CNPP covers background information on the status and development of nuclear power programmes in countries having nuclear plants in operation and/or plants under construction. It reviews the organizational and industrial aspects of nuclear power programmes in participating countries, and provides information about the relevant legislative, regulatory and international frameworks in each country. The CNPP compiles the current issues in the new environment within which the electricity and nuclear sector operates, i.e. energy policy, and privatization and deregulation in these sectors, the role of government, nuclear energy and climate change, and safety and waste management, which differ from country to country

An overview of the need of manpower supply for a nuclear programme

International Nuclear Information System (INIS)

Palabrica, R.J.

1981-01-01

The present paper deals with the need for trained manpower and special features of nuclear power affecting manpower requirements and gives a manpower loading schedule for the different nuclear power activities and programmes for manpower development. (orig./RW)

Co-ordinated research programme on benchmark study for the seismic analysis and testing of WWER-type nuclear power plants. V. 4B. Paks NPP: Analysis/testing. Working material

International Nuclear Information System (INIS)

1995-01-01

The Co-ordinated research programme on the benchmark study for the seismic analysis and testing of WWER-type nuclear power plants was initiated subsequent to the request from representatives of Member States. The conclusions adopted at the Technical Committee Meeting on Seismic Issues related to existing nuclear power plants held in Tokyo in 1991 called for the harmonization of methods and criteria used in Member States in issues related to seismic safety. The Consulltants' Meeting which followed resulted in producing a working document for CRP. It was decided that a benchmark study is the most effective way to achieve the principal objective. Two types of WWER reactors (WWER-440/213 and WWER-1000) were selected as prototypes for the benchmark exercise to be tested on a full scale using explosions and/or vibration generators. The two prototypes are Kozloduy Units 5/6 for WWER-1000 and Paks for WWER-440/213 nuclear power plants. This volume of Working material contains reports on dynamic study of the main building of the Paks NPP; shake table investigation at Paks NPP and the Final report of the Co-ordinated Research Programme

A stepwise composite echocardiographic score predicts severe pulmonary hypertension in patients with interstitial lung disease.

Science.gov (United States)

Bax, Simon; Bredy, Charlene; Kempny, Aleksander; Dimopoulos, Konstantinos; Devaraj, Anand; Walsh, Simon; Jacob, Joseph; Nair, Arjun; Kokosi, Maria; Keir, Gregory; Kouranos, Vasileios; George, Peter M; McCabe, Colm; Wilde, Michael; Wells, Athol; Li, Wei; Wort, Stephen John; Price, Laura C

2018-04-01

European Respiratory Society (ERS) guidelines recommend the assessment of patients with interstitial lung disease (ILD) and severe pulmonary hypertension (PH), as defined by a mean pulmonary artery pressure (mPAP) ≥35 mmHg at right heart catheterisation (RHC). We developed and validated a stepwise echocardiographic score to detect severe PH using the tricuspid regurgitant velocity and right atrial pressure (right ventricular systolic pressure (RVSP)) and additional echocardiographic signs. Consecutive ILD patients with suspected PH underwent RHC between 2005 and 2015. Receiver operating curve analysis tested the ability of components of the score to predict mPAP ≥35 mmHg, and a score devised using a stepwise approach. The score was tested in a contemporaneous validation cohort. The score used "additional PH signs" where RVSP was unavailable, using a bootstrapping technique. Within the derivation cohort (n=210), a score ≥7 predicted severe PH with 89% sensitivity, 71% specificity, positive predictive value 68% and negative predictive value 90%, with similar performance in the validation cohort (n=61) (area under the curve (AUC) 84.8% versus 83.1%, p=0.8). Although RVSP could be estimated in 92% of studies, reducing this to 60% maintained a fair accuracy (AUC 74.4%). This simple stepwise echocardiographic PH score can predict severe PH in patients with ILD.

Peaceful nuclear programme and front end nuclear fuel cycle activities in Pakistan

International Nuclear Information System (INIS)

S. Mukhtar Ahmed

1999-01-01

Pakistan has a modest but broad based nuclear programme related to peaceful uses of atomic energy in nuclear power, agriculture, medicine and industry. While development projects in these areas form the major segment of Pakistan Atomic Energy Commission's work, complimentary activities in basic research and human resource development are also supported. PAEC through its activities has been moving towards the goal of achieving self-reliance for its existing programme in an international atmosphere of embargoes and restrictions and in pursuit of creating an infrastructure to help sustain an indigenous nuclear power programme. To solve the local needs and requirements, radioisotopes and nuclear techniques have been applied in agriculture, medicine, hydrology and industry. PAEC has one large research and development establishment in physical sciences, three R and D centers in agriculture, one in biotechnology, and ten nuclear medical centers for diagnostics and oncology treatment. Two research reactors form nucleus of research and development activities in nuclear sciences. In the power sector a 137 Mew CANDU power reactor is in operation in Karachi since 1971. Another 300 Mew PWR is under construction and is nearing completion. Front-end fuel cycle and engineering infrastructure facilities have been established to support continued operation of Karachi Nuclear Power Plant (KANUPP). To support the engineering activities it has established facilities for precision workshops, non-destructive testing center and a welding institute. (author)

Reactor Physics Programme

Energy Technology Data Exchange (ETDEWEB)

De Raedt, C

2000-07-01

The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

Reactor Physics Programme

International Nuclear Information System (INIS)

De Raedt, C.

2000-01-01

The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

Fast reactor programme

International Nuclear Information System (INIS)

Plakman, J.C.

1982-01-01

This progress report summarizes the fast reactor research carried out by ECN during the period covering the year 1980. This research is mainly concerned with the cores of sodium-cooled breeders, in particular the SNR-300, and its related safety aspects. It comprises six items: A programme to determine relevant nuclear data of fission- and corrosion-products; A fuel performance programme comprising in-pile cladding failure experiments and a study of the consequences of loss-of-cooling and overpower; Basic research on fuel; Investigation of the changes in the mechanical properties of austenitic stainless steel DIN 1.4948 due to fast neutron doses, this material has been used in the manufacture of the reactor vessel and its internal components; Study of aerosols which could be formed at the time of a fast reactor accident and their progressive behaviour on leaking through cracks in the concrete containment; Studies on heat transfer in a sodium-cooled fast reactor core. As fast breeders operate at high power densities, an accurate knowledge of the heat transfer phenomena under single-phase and two-phase conditions is sought. (Auth.)

SKIs evaluation of SKBs RD and D programme 92

International Nuclear Information System (INIS)

1993-07-01

Section 11 of the Act (1984:3) on Nuclear Activities stipulates that the holder of a licence to own or operate a nuclear power reactor shall ensure that the necessary comprehensive research and development work is conducted in order to safely handle and finally dispose of the nuclear waste produced and to safely decommission and dismantle installation where the nuclear activity is no longer carried out. According to section 12 of the Act on nuclear activities, the reactor owners shall, in consultation with each other, prepare or have prepared a programme for the necessary comprehensive research and development work and the other measures. The programme shall contain an overview of all measures that may be necessary and also specify, in detail, the measures that are intended to be taken within a period of at least six years. The programme shall be submitted to the Government or to the authority designated by the Government for examination and evaluation. According to section 22 of the ordinance on nuclear activities, the Swedish Nuclear Power Inspectorate (SKI) shall ensure that the research and development work which the reactor owners are responsible for undertaking according to sections 11 and 12 of the act of nuclear activities, is actually carried out. SKIs premise for evaluating the programme has been to examine it as an integrated R and D programme, which essentially focusses on structure, strategy and planning in order to effectively realize the defined goals of the programme, i.e. finding a safe, final solution to the disposal of spent nuclear fuel. Keeping to the time-schedule should not be the controlling factor in carrying out the research and development programme. The essential objective is to attain the goal without jeopardizing quality. SKIs examination has been documented in the form of the following: summary and conclusions, evaluation report, report of comments by reviewing bodies, and consultants reports. SKIs statement to the Government has been

Stepwise excavation may enhance pulp preservation in permanent teeth affected by dental caries

DEFF Research Database (Denmark)

Bjørndal, Lars

2011-01-01

ARTICLE TITLE AND BIBLIOGRAPHIC INFORMATION: Ways of enhancing pulp preservation by stepwise excavation-a systematic review. Hayashi M, Fujitani M, Yamaki C, Momoi Y. J Dent 2011;39(2):95-107. Epub 2010 Dec 3. REVIEWER: Lars Bjørndal, DDS, PhD, Dr Odont PURPOSE/QUESTION: To determine the clinical...

Nuclear power in developing countries

International Nuclear Information System (INIS)

Morrison, R.W.

1980-01-01

A few of the essential issues which arise when we consider nuclear power and development together in the context of energy policy are discussed. Ethical concerns must ultimately be expressed through policies and their impact on people. There are ethical issues associated with nuclear power in the developing countries which deserve our attention. Four aspects of the question of nuclear power in developing countries are considered: their energy situation; the characteristics of nuclear power which are relevant to them; whether developing countries will undertake nuclear power programmes; and finally the ethical implications of such programmes. It is concluded that what happens in developing countries will depend more on the ethical nature of major political decisions and actions than on the particular technology they use to generate their electricity. (LL)

Fuel R and D international programmes, a way to demonstrate future fuel performances

International Nuclear Information System (INIS)

Vanderborck, Y.; Mertens, L.; Dekeyser, J.; Sannen, L.

1997-01-01

As a MOX fuel manufacturer, BELGONUCLEAIRE have spent more than 15 years promoting and managing International R and D Programmes, many of them in close cooperation with SCK''centrdot'' CEN. Such programmes dedicated to MOX versus UO 2 fuel behaviour are most of the time based on irradiation in research reactors in which the investigated fuel is submitted to power variations and to ramp testing or are performed in commercial reactors. This paper is focused on recent programmes concerned by high and medium burn-up in BWR and PWR conditions for MOX fuel. It will present also the new opportunities for new programmes. The goals, the programmes descriptions and the expected data being part of these R and D programmes is presented. (author)

France without nuclear power

International Nuclear Information System (INIS)

Barre, B.; Charmant, A.; Devezeaux, J.G.; Ladoux, N.; Vielle, M.

1995-01-01

As environmental issues (particularly questions associated with the greenhouse effect) become a matter of increasing current concern, the French nuclear power programme can, in retrospect, be seen to have had a highly positive impact upon emissions of atmospheric pollutants. The most spectacular effect of this programme was the reduction of carbon dioxide emissions from 530 million tonnes per annum in 1973 to 387 million tonnes per annum today. Obviously, this result cannot be considered in isolation from the economic consequences of the nuclear power programme, which have been highly significant.The most obvious consequence of nuclear power has been the production of cheap electricity, while a further consequence has been the stability of electricity prices resulting from the increasing self-sufficiency of France in energy supplies (from 22% in 1973 to 49.% in 1992). Moreover, French nuclear industry exports. In 1993, 61.7 TW·h from nuclear production were exported, which contributed F.Fr. 14.2 billion to the credit side of the balance of payment. For the same year, Framatome exports are assessed at about F.Fr. 2 billion, corresponding to manufacturing and erection of heavy components, and maintenance services. Cogema, the French nuclear fuel operator, sold nuclear materials and services for F.Fr. 9.3 billion. Thus, nuclear activities contributed more than F.Fr. 25 billion to the balance of payment. Therefore, a numerical assessment of the macroeconomic impact of the nuclear power programme is essential for any accurate evaluation of the environmental consequences of that programme. For this assessment, which is presented in the paper, the Micro-Melodie macroeconomic and energy supply model developed by the Commissariat a l'energie atomique has been used. (author). 6 refs, 4 figs, 1 tab

Accelerator programme at CAT

International Nuclear Information System (INIS)

Ramamurthi, S.S.

1991-01-01

The Accelerator Programme at the Centre for Advanced Technology (CAT), Indore, has very broad based concept under which all types of accelerators are to be taken up for design and fabrication. This centre will be housing a wide variety of accelerators to serve as a common facility for the universities, national laboratories in addition to laboratories under the Department of Atomic Energy. In the first phase of the programme, a series of electron accelerators are designed and fabricated. They are synchrotron radiation sources of 450 MeV (INDUS-I) and of 2 GeV (INDUS-II), microtron upto energy of 20 MeV, linear accelerator upto 20 MeV, and DC Accelerator for industrial irradiation upto 750 KeV and 20 KW. A proton accelerator of 300 MeV with 20 MeV linac injector is also designed. CAT is also developing a strong base for support technologies like ultra high vacuum, radio frequency and microwaves, DC pulsed and superconducting magnets, power supplies and controls etc. These technologies are very useful for other industrial applications also. To develop user groups to utilise INDUS-II synchrotron radiation source, a batch production of rotating Anode X-ray generators with power supplies has been initiated. So also, the sputter ion pumps, electron guns, turbo molecular pumps are brought into batch production. (author)

Implementing agreement on photovoltaic power systems - Annual report 2008

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-07-01

This annual report for the International Energy Agency (IEA) reports on the programme's activities in 2008. The IEA Photovoltaic Power Systems Programme (PVPS) is one of the collaborative research and development agreements established within the IEA. Its mission is to enhance international collaboration efforts which support the development and deployment of photovoltaic solar energy. In this annual report, the programme's mission and its strategies for reaching four objectives are reviewed and status reports on the programme's various tasks and sub-tasks are presented. The tasks include the exchange and dissemination of information on photovoltaic power systems, a study on very large scale photovoltaic power generation system, photovoltaic services for developing countries, urban-scale PV applications, hybrid systems within mini-grids as well as health and safety activities. The status and prospects in the 23 countries and organisations participating in the programme are presented. Along with country-specific topics, industry activities, research, development and demonstration projects, applications, education and governmental activities as well as future activities are reviewed. Finally, completed tasks are reviewed. These include the performance, reliability and analysis of photovoltaic systems, the use of photovoltaic power systems in stand-alone and island applications, grid interconnection of building integrated and other distributed photovoltaic power systems, design and operation of modular photovoltaic plants for large scale power generation and photovoltaic power systems in the built environment. The report is completed with a list of Executive Committee members and Operating Agents.

Implementing agreement on photovoltaic power systems - Annual report 2007

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

This annual report for the International Energy Agency (IEA) reports on the programme's activities in 2007. The IEA Photovoltaic Power Systems Programme (PVPS) is one of the collaborative research and development agreements established within the IEA. Its mission is to enhance international collaboration efforts which support the development and deployment of photovoltaic solar energy. In this annual report, the programme's mission and its strategies for reaching four objectives are reviewed and status reports on the programme's various tasks and sub-tasks are presented. The tasks include the exchange and dissemination of information on photovoltaic power systems, the performance, reliability and analysis of photovoltaic systems, a study on very large scale photovoltaic power generation system, photovoltaic services for developing countries, urban-scale PV applications, hybrid systems within mini-grids and PV environmental health and safety activities. The status and prospects in the 22 countries and organisations participating in the programme are presented. Along with country-specific topics, industry activities, research, development and demonstration projects, applications, education and governmental activities as well as future activities are reviewed. Finally, completed tasks are reviewed. These include the use of photovoltaic power systems in stand-alone and island applications, grid interconnection of building integrated and other distributed photovoltaic power systems, design and operation of modular photovoltaic plants for large scale power generation and photovoltaic power systems in the built environment. The report is completed with a list of Executive Committee members and Operating Agents.

Implementing agreement on photovoltaic power systems - Annual report 2007

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

This annual report for the International Energy Agency (IEA) reports on the programme's activities in 2007. The IEA Photovoltaic Power Systems Programme (PVPS) is one of the collaborative research and development agreements established within the IEA. Its mission is to enhance international collaboration efforts which support the development and deployment of photovoltaic solar energy. In this annual report, the programme's mission and its strategies for reaching four objectives are reviewed and status reports on the programme's various tasks and sub-tasks are presented. The tasks include the exchange and dissemination of information on photovoltaic power systems, the performance, reliability and analysis of photovoltaic systems, a study on very large scale photovoltaic power generation system, photovoltaic services for developing countries, urban-scale PV applications, hybrid systems within mini-grids and PV environmental health and safety activities. The status and prospects in the 22 countries and organisations participating in the programme are presented. Along with country-specific topics, industry activities, research, development and demonstration projects, applications, education and governmental activities as well as future activities are reviewed. Finally, completed tasks are reviewed. These include the use of photovoltaic power systems in stand-alone and island applications, grid interconnection of building integrated and other distributed photovoltaic power systems, design and operation of modular photovoltaic plants for large scale power generation and photovoltaic power systems in the built environment. The report is completed with a list of Executive Committee members and Operating Agents.

Implementing agreement on photovoltaic power systems - Annual report 2008

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-07-01

This annual report for the International Energy Agency (IEA) reports on the programme's activities in 2008. The IEA Photovoltaic Power Systems Programme (PVPS) is one of the collaborative research and development agreements established within the IEA. Its mission is to enhance international collaboration efforts which support the development and deployment of photovoltaic solar energy. In this annual report, the programme's mission and its strategies for reaching four objectives are reviewed and status reports on the programme's various tasks and sub-tasks are presented. The tasks include the exchange and dissemination of information on photovoltaic power systems, a study on very large scale photovoltaic power generation system, photovoltaic services for developing countries, urban-scale PV applications, hybrid systems within mini-grids as well as health and safety activities. The status and prospects in the 23 countries and organisations participating in the programme are presented. Along with country-specific topics, industry activities, research, development and demonstration projects, applications, education and governmental activities as well as future activities are reviewed. Finally, completed tasks are reviewed. These include the performance, reliability and analysis of photovoltaic systems, the use of photovoltaic power systems in stand-alone and island applications, grid interconnection of building integrated and other distributed photovoltaic power systems, design and operation of modular photovoltaic plants for large scale power generation and photovoltaic power systems in the built environment. The report is completed with a list of Executive Committee members and Operating Agents.

Implementing agreement on photovoltaic power systems - Annual report 2006

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

This annual report for the International Energy Agency (IEA) reports on the programme's activities in 2006. The IEA Photovoltaic Power Systems Programme (PVPS) is one of the collaborative research and development agreements established within the IEA. Its mission is to enhance international collaboration efforts which support the development and deployment of photovoltaic solar energy. In this annual report, the programme's mission and its strategies for reaching four objectives are reviewed and status reports on the programme's various tasks and sub-tasks are presented. The tasks include the exchange and dissemination of information on photovoltaic power systems, the performance, reliability and analysis of photovoltaic systems, a study on very large scale photovoltaic power generation system, photovoltaic services for developing countries, urban-scale PV applications and hybrid systems within mini-grids. The status and prospects in the 21 countries and organisations participating in the programme are presented. Along with country-specific topics, industry activities, research, development and demonstration projects, applications, education and governmental activities as well as future activities are reviewed. Finally, completed tasks are reviewed. These include the use of photovoltaic power systems in stand-alone and island applications, grid interconnection of building integrated and other distributed photovoltaic power systems, design and operation of modular photovoltaic plants for large scale power generation and photovoltaic power systems in the built environment. The report is completed with a list of Executive Committee members and Operating Agents.

Implementing agreement on photovoltaic power systems - Annual report 2005

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

This annual report for the International Energy Agency (IEA) reports on the programme's activities in 2005. The IEA Photovoltaic Power Systems Programme (PVPS) is one of the collaborative research and development agreements established within the IEA. Its mission is to enhance international collaboration efforts which support the development and deployment of photovoltaic solar energy. In this annual report, the programme's mission and its strategies for reaching four objectives are reviewed and status reports on the programme's various tasks and sub-tasks are presented. The tasks include the exchange and dissemination of information on photovoltaic power systems, the performance, reliability and analysis of photovoltaic systems, a study on very large scale photovoltaic power generation system, photovoltaic services for developing countries and urban-scale PV applications. The status and prospects in the 21 countries and organisations participating in the programme are presented. Along with country-specific topics, industry activities, research, development and demonstration projects, applications, education and governmental activities as well as future activities are reviewed. Finally, completed tasks are reviewed. These include the use of photovoltaic power systems in stand-alone and island applications, grid interconnection of building integrated and other distributed photovoltaic power systems, design and operation of modular photovoltaic plants for large scale power generation and photovoltaic power systems in the built environment. The report is completed with a list of Executive Committee members and Operating Agents.

Implementing agreement on photovoltaic power systems - Annual report 2004

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

This annual report for the International Energy Agency (IEA) reports on the programme's activities in 2004. The IEA Photovoltaic Power Systems Programme (PVPS) is one of the collaborative research and development agreements established within the IEA. Its mission is to enhance international collaboration efforts which support the development and deployment of photovoltaic solar energy. In this annual report, the programme's mission and its strategies for reaching four objectives are reviewed and status reports on the programme's various tasks and sub-tasks are presented. The tasks include the exchange and dissemination of information on photovoltaic power systems, the performance, reliability and analysis of photovoltaic systems, the use of photovoltaic power systems in stand-alone and island applications, a study on very large scale photovoltaic power generation system, photovoltaic services for developing countries and urban-scale PV applications. The status and prospects in the 21 countries and organisations participating in the programme are presented. Along with country-specific topics, industry activities, research, development and demonstration projects, applications, education and governmental activities as well as future activities are reviewed. Finally, completed tasks are reviewed. These include grid interconnection of building integrated and other distributed photovoltaic power systems, design and operation of modular photovoltaic plants for large scale power generation and photovoltaic power systems in the built environment. The report is completed with a list of Executive Committee members and Operating Agents.

Implementing agreement on photovoltaic power systems - Annual report 2006

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

This annual report for the International Energy Agency (IEA) reports on the programme's activities in 2006. The IEA Photovoltaic Power Systems Programme (PVPS) is one of the collaborative research and development agreements established within the IEA. Its mission is to enhance international collaboration efforts which support the development and deployment of photovoltaic solar energy. In this annual report, the programme's mission and its strategies for reaching four objectives are reviewed and status reports on the programme's various tasks and sub-tasks are presented. The tasks include the exchange and dissemination of information on photovoltaic power systems, the performance, reliability and analysis of photovoltaic systems, a study on very large scale photovoltaic power generation system, photovoltaic services for developing countries, urban-scale PV applications and hybrid systems within mini-grids. The status and prospects in the 21 countries and organisations participating in the programme are presented. Along with country-specific topics, industry activities, research, development and demonstration projects, applications, education and governmental activities as well as future activities are reviewed. Finally, completed tasks are reviewed. These include the use of photovoltaic power systems in stand-alone and island applications, grid interconnection of building integrated and other distributed photovoltaic power systems, design and operation of modular photovoltaic plants for large scale power generation and photovoltaic power systems in the built environment. The report is completed with a list of Executive Committee members and Operating Agents.

Profitability of Qualified-Labour-Power Production

Science.gov (United States)

Baldino, Roberto Ribeiro; Cabral, Tânia Cristina Baptista

2015-01-01

In Baldino and Cabral (2013) we introduced the concept of qualified labour-power as the commodity produced by the school system. In the present article we outline a quantitative model to evaluate the profit rate of educational programmes. We compare a medical school programme with a teacher education programme at a public university in Brazil,…

Kenya National Presentation on Nuclear Power Infrastructure Evaluation

International Nuclear Information System (INIS)

Kinyanjui, B

2010-01-01

Kenya will factored 1200MW of nuclear energy in the period 2022-2023 of the national Least Cost Power Development Plan and 4200MW by 2030. A national nuclear power programme is now at inception. The National Economic and Social Council endorsed adoption of the nuclear programme in April 2010. Electricity demand is expected to rise from the current 1200 MW to over 15000 MW by 2030. The achievement of the Vision 2030 requires affordable and stable electricity tariffs. Formation of a Nuclear Power Committee to study and initially promote the development of the nuclear power program will be established e.g. Nuclear Power Committee - Kenyan version of Nuclear Energy Programme Implementing Organization formed. The Nuclear Power Committee is expected to precede formation of the NEPIO. There was proposal to review of current laws –e.g. Energy Act, Radiation Protection Act, Environmental Management and Control Act, Penal Code, etc. Potential sites proposed along the Indian Ocean Coastal areas, near Lake Victoria and the central region near the main national hydropower plants, based on power grid layout and water bodies. Kenya is in Phase 1 of milestones- Consideration before a decision is taken to start a NPP. Capacity Building towards Development of a Nuclear Power Programme (NPP) in Kenya is underway. To implement the national least cost power development plan so as to increase the capacity from current 1,300MW to 18,000MW by 2030 to support achievement of the ‘Vision 2030’

A Programmable Biopotential Aquisition Front-end with a Resistance-free Current-balancing Instrumentation Amplifier

Directory of Open Access Journals (Sweden)

FARAGO, P.

2018-05-01

Full Text Available The development of wearable biomedical equipment benefits from low-power and low-voltage circuit techniques for reduced battery size and battery, or even battery-less, operation. This paper proposes a fully-differential low-power resistance-free programmable instrumentation amplifier for the analog front-end of biopotential monitoring systems. The proposed instrumentation amplifier implements the current balancing technique. Low power consumption is achieved with subthreshold biasing. To reduce chip area and enable integration, passive resistances have been replaced with active equivalents. Accordingly, the instrumentation amplifier gain is expressed as the ratio of two transconductance values. The proposed instrumentation amplifier exhibits two degrees of freedom: one to set the desired range and the other for fine-tuning of the voltage gain. The proposed IA is employed in a programmable biopotential acquisition front-end. The programmable frequency-selective behavior is achieved by having the lower cutoff frequency of a Gm-C Tow-Thomas biquad varied in a constant-C tuning approach. The proposed solutions and the programmability of the operation parameters to the specifications of particular bio-medical signals are validated on a 350nm CMOS process.

Review of programmable systems associated with Fermilab experiments

International Nuclear Information System (INIS)

Nash, T.

1981-05-01

The design and application of programmable systems for Fermilab experiments are reviewed. The high luminosity fixed target environment at Fermilab has been a very fertile ground for the development of sophisticated, powerful triggering systems. A few of these are integrated systems designed to be flexible and to have broad application. Many are dedicated triggers taking advantage of large scale integrated circuits to focus on the specific needs of one experiment. In addition, the data acquisition requirements of large detectors, existing and planned, are being met with programmable systems to process the data. Offline reconstruction of data places a very heavy load on large general purpose computers. This offers a potentially very fruitful area for new developments involving programmable dedicated systems. Some of the present thinking at Fermilab regarding offline reconstruction processors will be described

Multi Carrier Modulation Audio Power Amplifier with Programmable Logic

DEFF Research Database (Denmark)

Christiansen, Theis; Andersen, Toke Meyer; Knott, Arnold

2009-01-01

While switch-mode audio power amplifiers allow compact implementations and high output power levels due to their high power efficiency, they are very well known for creating electromagnetic interference (EMI) with other electronic equipment. To lower the EMI of switch-mode (class D) audio power a...

Stepwise Procedure for Development and Validation of a Multipesticide Method

Energy Technology Data Exchange (ETDEWEB)

Ambrus, A. [Hungarian Food Safety Office, Budapest (Hungary)

2009-07-15

The stepwise procedure for development and the validation of so called multi-pesticide methods are described. Principles, preliminary actions, criteria for the selection of chromatographic separation, detection and performance verification of multi-pesticide methods are outlined. Also the long term repeatability and reproducibility, as well as the necessity for the documentation of laboratory work are highlighted. Appendix I hereof describes in detail the calculation of calibration parameters, whereas Appendix II focuses on the calculation of the significance of differences of concentrations obtained on two different separation columns. (author)

Stepwise crystallization and the layered distribution in crystallization kinetics of ultra-thin poly(ethylene terephthalate) film

Energy Technology Data Exchange (ETDEWEB)

Zuo, Biao, E-mail: chemizuo@zstu.edu.cn, E-mail: wxinping@yahoo.com; Xu, Jianquan; Sun, Shuzheng; Liu, Yue; Yang, Juping; Zhang, Li; Wang, Xinping, E-mail: chemizuo@zstu.edu.cn, E-mail: wxinping@yahoo.com [Department of Chemistry, Key Laboratory of Advanced Textile Materials and Manufacturing Technology of the Education Ministry, Zhejiang Sci-Tech University, Hangzhou 310018 (China)

2016-06-21

Crystallization is an important property of polymeric materials. In conventional viewpoint, the transformation of disordered chains into crystals is usually a spatially homogeneous process (i.e., it occurs simultaneously throughout the sample), that is, the crystallization rate at each local position within the sample is almost the same. Here, we show that crystallization of ultra-thin poly(ethylene terephthalate) (PET) films can occur in the heterogeneous way, exhibiting a stepwise crystallization process. We found that the layered distribution of glass transition dynamics of thin film modifies the corresponding crystallization behavior, giving rise to the layered distribution of the crystallization kinetics of PET films, with an 11-nm-thick surface layer having faster crystallization rate and the underlying layer showing bulk-like behavior. The layered distribution in crystallization kinetics results in a particular stepwise crystallization behavior during heating the sample, with the two cold-crystallization temperatures separated by up to 20 K. Meanwhile, interfacial interaction is crucial for the occurrence of the heterogeneous crystallization, as the thin film crystallizes simultaneously if the interfacial interaction is relatively strong. We anticipate that this mechanism of stepwise crystallization of thin polymeric films will allow new insight into the chain organization in confined environments and permit independent manipulation of localized properties of nanomaterials.

Developing National Capacity to Initiate Nuclear Power Programme

International Nuclear Information System (INIS)

Ndontchueng, M.M.

2014-01-01

Conclusion: ⇒ Nuclear power is needed for Developing Countries in the long term development strategy; ⇒ Developing Countries are lack of man power for both the NPP projects and the long term nuclear power program; ⇒ A long term HRD program (strategy) is needed to be established, in cooperation with Developed countries; ⇒ Education and training abroad is essential to the technology transfer; ⇒ Establishment of adequate infrastructure supporting HRD (nuclear engineering faculties, research groups, technical support centers) is indispensible for Developing Countries

The SGHWR programme together with memoranda submitted to the General Purposes sub-committee

International Nuclear Information System (INIS)

1976-01-01

The first part of the report sets out the arguments of those against, and those in favour of cancelling the SGHWR. Cost, as affected by more stringent safety standards and by reduced domestic power programme and export expectation, was the main centre of disagreement. The arguments of employee representatives, including sociological considerations, are also reported. Other possible strategies are then discussed: (a) no nuclear power; (b) a nuclear programme based on the FBR; (c) AGR; and (d) PWR. The PWR safety review, and the costs and size of

Choosing the nuclear power option: Factors to be considered

International Nuclear Information System (INIS)

1998-01-01

A need was expressed by Member States for guidance on policy issues to be addressed by decision makers considering the introduction of nuclear power programmes. This publication has been prepared by the IAEA, on the basis of past experience with nuclear power programmes in Member States and the current realities of the world nuclear regime, to provide information on political, governmental, economic, financial, technical and safety issues associated with planning and implementing a nuclear power programme. It highlights the main areas in which policies must be developed as well as the roles and responsibilities of the government, the plant owner and the national industry. For those interested in examining some of the issues in more depth, a list of related IAEA publications is provided in the bibliography. It is hoped that this guide will serve a useful purpose in assisting decision makers and governments in Member States considering the introduction of nuclear power programmes

Stepwise cyanation of naphthalene diimide for n-channel field-effect transistors

KAUST Repository

Chang, Jingjing

2012-06-15

Stepwise cyanation of tetrabromonaphthalenediimide (NDI) 1 gave a series of cyanated NDIs 2-5 with the monocyanated NDI 2 and dicyanated NDI 3 isolated. The tri- and tetracyano- NDIs 4 and 5 show intrinsic instability toward moisture because of their extremely low-lying LUMO energy levels. The partially cyanated intermediates can be utilized as air-stable n-type semiconductors with OFET electron mobility up to 0.05 cm 2 V -1 s -1. © 2012 American Chemical Society.

Five years of an educational programme - Results and experiences

International Nuclear Information System (INIS)

Dufkova, Marie

1998-01-01

Full text: School teachers and pupils constitute an important group having the ability to listen, Understand and help to create positive ties between the public and a utility. Therefore, CEZ spends a part of its revenue arising from the sales of electricity on education. CEZ's information and education programme named 'Energy for everybody' has been used by Czech schools for five years now. The main part of this educational programme is devoted to nuclear energy. CEZ materials for schools include: printed information, supplements to textbooks, videotapes, computer programmes, CD ROMs, an educational set for experiments with ionizing radiation, posters and other assorted materials. Schools are invited to visit Czech power plants and other facilities of the power sector (for example the experimental reactor at the Prague Technical University). Seminars and workshops are organised for teachers. CEZ offers objective information on all activities associated with energy generation and uses and the relationships between man and nature. The prices of our informational materials are rather symbolic, they come to one-tenth to one-third of the actual cost. CEZ is the only industrial company offering such a large-scale educational programme for schools in the Czech Republic. Materials are distributed to nearly 7 000 primary and secondary schools and 30 university departments. We have agreements with several schools which have committed themselves to testing our materials. Several dissertations and studies have demonstrated the usefulness of our materials for education and the contribution this information has made to the better understanding of nuclear energy. We have organised polls in order to ascertain how the schools liked the materials, what additional things they wished and what their view of nuclear power plants and CEZ was. The outcome has been unexpectedly favourable. In my contribution I will present the results of these polls and examples of successful activities

Status of power reactor fuel reprocessing in India

International Nuclear Information System (INIS)