WorldWideScience

Sample records for stepwise power programme

  1. Improvement of the Performance of Scheduled Stepwise Power Programme Changes within the European Power System

    DEFF Research Database (Denmark)

    Welfonder, E.; Weissbach, T.; Schulz, U.

    2008-01-01

    Since the deregulation of the electrical energy market, the technical realisation of power transactions based on energy market contracts often effects large stepwise power programme changes – especially at the change of the hour. Due to mainly economic reasons these stepwise power programme changes...... extended discussions with power plant and power system operators as well as with power plant dispatchers the described issues will be adopted into a VGB-recommendation which shall be published by VGB Powertech for Germany and Europe. Subsequently, it is intended to include the main elements of the VGB...

  2. Canada's nuclear power programme

    International Nuclear Information System (INIS)

    Peden, W.

    1976-01-01

    Although Canada has developed the CANDU type reactor, and has an ambitious programme of nuclear power plant construction, there has been virtually no nuclear controversy. This progress was seen as a means to bring Canada out of the 'resource cow' era, and onto a more equal footing with technologically elite nations. However the Indian nuclear explosion test, waste storage problems, contamination problems arising from use of uranium ore processing waste as land fill and subsidised sale of nuclear power plants to Argentina and South Korea have initiated public and parliamentary interest. Some economists have also maintained that Canada is approaching over-supply of nuclear power and over-investment in plant. Canada has no official overall energy production plan and alternative sources have not been evaluated. (JIW)

  3. Productivity Enhancement of Solar Still with PV Powered Heating Coil and Chamber Step-Wise Basin

    Directory of Open Access Journals (Sweden)

    Salah Abdallah

    2018-03-01

    Full Text Available There is a strong need to improve the productivity of single slope solar still. PV generator powered electrical heater and chamber step-wise design were introduced to the conventional solar still. An experimental study was performed to investigate the effect of adding the above mentioned modifications on the output parameters of the modified solar still. The inclusion of PV-powered heating coil and chamber step-wise design enhanced the productivity of distiller by up to 1098%.

  4. Iran's nuclear power programme revisited

    International Nuclear Information System (INIS)

    Mossavar-Rahmani, B.

    1980-01-01

    Iran's new government has not yet made a final decision about the fate of that country's once ambitious nuclear power programme. If the programme is kept alive, it will be limited to the completion of at most one or two of the reactors that were already well underway when the revolution broke out. The author traces the origins and growth of the Iranian nuclear power programme between 1974 and 1978, summarizes the principal economic, infrastructural, and political criticisms of the programme as originally planned, discusses the potential for greater use of natural gas as an alternative and, finally, recommends a long, detailed reassessment of Iran's energy options. (author)

  5. High-intensity stepwise conditioning programme for improved exercise responses and agility performance of a badminton player with knee pain.

    Science.gov (United States)

    Chen, Bob; Mok, Damon; Lee, Winson C C; Lam, Wing Kai

    2015-02-01

    To examine the effect of a high-intensity stepwise conditioning programme combined with multiple recovery measures on physical fitness, agility, and knee pain symptoms of an injured player. A single case study. University-based conditioning training laboratory. One 26-year-old male world-class badminton player (height, 190.0 cm; weight, 79.3 kg; left dominant hand; playing experience, 16 years; former world champion) with patellar tendinosis and calcification of his left knee. The player received seven conditioning sessions over three weeks. During the programme, there was a gradual increase in training duration and load across sessions while cold therapy, manual stretches and massage were administered after each session to minimise inflammation. The training outcome was evaluated with three different testing methods: standard step test, badminton-specific agility test, and tension-pain rating. The conditioning programme reduced knee pain symptoms and improved actual performance and cardiopulmonary fitness during the agility task. The player was able to return to sport and compete within a month. A high-intensity stepwise conditioning programme improved the physical fitness while sufficient recovery measures minimised any possible undesirable effects and promoted faster return to elite level competition. Copyright © 2014 Elsevier Ltd. All rights reserved.

  6. Research and development needs in a step-wise process for the nuclear waste programme in Sweden

    International Nuclear Information System (INIS)

    Ström, A.; Andersson, J.; Ekeroth, E.; Hedin, A.; Pers, K.

    2016-01-01

    Concluding remarks: • The SKB RD&D Programme 2016 − contains an overview of all the measures that may be necessary for treatment and final disposal of nuclear waste from Swedish nuclear reactors and SKB's facilities; − clarifies how research and technology development are justified and evaluated in a step-wise procedure on the basis of the measures planned; − presents a strategic plan for the research and development necessary to establish and implement future activities; − Published as SKB TR 16-15 in December 2016

  7. Power programmes review: Nuclear power in Italy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-07-15

    Several concrete measures have been initiated in Italy for the generation of nuclear power on a substantial scale. Two plants are already under construction and work will start soon on a third. Plans have also been announced for more stations. If the work already initiated is completed on schedule the installed capacity of nuclear power in Italy is likely to exceed 500 mw (electric) in the course of the next four years. This will constitute a sizeable proportion of the total electrical capacity in the country. After the Italian National Committee for Nuclear Research (Comitato Nazionale per le Ricerche Nucleari) was reorganized late in 1956, it prepared what can be described as a nuclear five-year plan for Italy. The plan, designed to cover the period 1957-1962, includes detailed schemes for a comprehensive development of the peaceful uses of nuclear energy, including a programme for the generation of power. The Comitato Nazionale per le Ricerche Nucleari (CNRN) promotes and co-ordinates the various activities in the field, and within the framework of its general programme certain industrial groups in Italy have formulated specific projects for nuclear power. At a Geneva conference (1958) it was disclosed that several companies were planning to build nuclear power stations in Italy. (1) SELNI (Societa Elettronucleare Italiana), pertaining to the Edison-Volta group, which plans to build a pressurized water reactor. (2) So.R.I.N. (Societa Ricerche Impianti Nucleari), a company founded by the Fiat and Montecatini groups, which is constructing a research centre, with a swimming pool reactor, and various laboratories for chemistry, physics and metallurgy. This centre will also be used for the training of specialized personnel, in view of the company's programme which envisages two 150 mw (e) plants: one operating with enriched uranium, the other with natural uranium. Such a programme will become effective only when the cost of power produced by these plants may actually

  8. Nuclear power programmes in developing countries

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    The paper on ''Nuclear power programmes in developing countries'' is a report to the IAEA by a Senior Expert Group. A description is given of the requirements for a successful nuclear power programme, including the constraints that developing countries might face in the introduction and execution of the programme. The group attempted to identify the main issues affecting the financing of nuclear power projects and suggested specific actions that could be undertaken in order to reduce economic and financial risks. The various issues were discussed under the topic headings:-programme-project-related factors, investment climate, financing plan, export credits and creditworthiness. (U.K.)

  9. 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

  10. 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

  11. Nuclear power programme planning: An integrated approach

    International Nuclear Information System (INIS)

    2001-12-01

    The International Atomic Energy Agency (IAEA) has published material on different policy considerations in the introduction of nuclear power, primarily addressed to top level decision makers in government and industry in Member States. Several Member States and experts recommended to the IAEA to address the aspects of an integrated approach to nuclear power programme planning and to serve as guidance to those countries wishing to embark on a nuclear power programme. As a follow-up, the present publication is primarily intended to serve as guidance for executives and managers in Member States in planning for possible introduction of nuclear power plants in their electricity generating systems. Nuclear power programme planning, as dealt with in this publication, includes all activities that need to be carried out up to a well-founded decision to proceed with a project feasibility study. Project implementation beyond this decision is not in the scope of this publication. Although it is possible to use nuclear energy as a heat source for industrial processes, desalination and other heat applications, it is assumed in this publication that the planning is aimed towards nuclear power for electricity generation. Much of the information given would, however, also be relevant for planning of nuclear reactors for heat production. The publication was prepared within the framework of the IAEA programme on nuclear power planning, implementation and performance as a joint activity of the Nuclear Power Engineering Section and the Planning and Economic Studies Section (Division of Nuclear Power)

  12. Building infrastructure for new nuclear power programmes

    International Nuclear Information System (INIS)

    Starz, A.; Aoki, M.

    2010-01-01

    In recent years, more than sixty countries have indicated that they are considering or launching nuclear power programmes. It has been more than a decade since a country commissioned its first nuclear power plant. In meantime, the global nuclear community has faced greater concerns about safety, security and non-proliferation, resulting in increased international obligations and a greater expectation for transparency and openness regarding nuclear power programmes. Many of these 'nuclear newcomers' are turning to International Atomic Energy Agency (IAEA) to understand the implications of the nuclear power option and to receive advice about how to proceed with implementing a national programme. In response to growing demand for assistance, the IAEA developed a comprehensive, phased approach to establishing the infrastructure necessary to support a national nuclear power programme. This 'Milestones' approach is described in Nuclear Energy Series Guide NG-G-3.1 'Milestones in the Development of a National Infrastructure for Nuclear Power' (2007). From establishing the national position and legal framework to nuclear safety, security and safeguards, the Milestones covers 19 issues that need to be addressed. This approach also places special emphasis on the need for involvement of the Government, utility, industry, academic, and other stakeholders in a national decision-making process. The IAEA is also helping 'newcomers' to better understand its Safety Standards, which were written from the perspective of operating nuclear power programmes. A new safety guide is in development which provides a Road-map to the safety standards and identifies the standards that are relevant for each phase consistent with the Milestones. Several countries in the Europe region are working with the IAEA to understand the issues associated with a nuclear power programme in preparation for making a knowledgeable commitment. The starting points and approaches vary widely: some are European

  13. Nuclear power programme: development and prospects

    International Nuclear Information System (INIS)

    Prasad, Y.S.R.

    1997-01-01

    The relevance of nuclear power in meeting the short and long term energy needs of India was recognised right at the beginning of the atomic energy programme. From the very beginning, as a long term strategy, the nuclear power programme, formulated by Dr Homi Jehangir Bhabha, embarked on a three stage process linking the fuel cycles of Pressurised Heavy Water Reactor (PHWR) and Fast Breeder Reactor (FBR), and was planned for judicious utilisation of the country's limited uranium ore (78,000 tonne) but vast thorium resources (>360,000 tonne). The emphasis of the programme was on self-reliance and thorium utilisation as a long term objective. India selected Pressurised Heavy Water Reactor (PHWR) because of several inherent advantages. (author)

  14. The Brazilian nuclear power manpower development programme

    International Nuclear Information System (INIS)

    Barbalho, A.R.; Spitalnik, J.; Machado, J.B.

    1983-01-01

    Since the early stages of decision making, manpower availability has been recognized to be a key factor for the implementation of Brazil's nuclear power programme. Though care has been given to securing an industrial base and financial resources, the consequences of a lack of sufficient qualified manpower could be critical for the success of the whole programme. The broad scope of the Brazilian nuclear power programme which, as a main concept, aimed at establishing in the country a complete fuel cycle industry together with the construction of nuclear power plants, added another burden to the already complex task of providing appropriate human resources when advanced technologies are introduced in a developing country. Thus, not only the work-force required for nuclear power plant operation but also that needed for plant design, component manufacture, fuel cycle plant design and operation, had to be made available in number and qualification in accordance with the standards of the nuclear industry. The feasibility of the Brazilian programme depended on a complete transfer of technology, essentially achieved through personnel training. Again, the process of manpower preparation for an efficient know-how transfer required careful planning, and the great difficulty in its implementation was the lack of reliable experience at the time. (author)

  15. 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.

  16. Workforce Planning for New Nuclear Power Programmes

    International Nuclear Information System (INIS)

    2011-01-01

    An appropriate infrastructure is essential for the efficient, safe, reliable and sustainable use of nuclear power. The IAEA continues to be encouraged by its Member States to provide assistance to those considering the introduction of nuclear power. Its response has been to increase technical assistance, organize more missions and hold workshops, as well as to issue new and updated 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 involving 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 nuclear power plant. One of these 19 issues upon which each of the other 18 depend is suitable human resources development. As a growing number of Member States begin to consider the nuclear power option, they ask for guidance from the IAEA on how to develop the human resources necessary to launch a nuclear power programme. The nuclear power field, comprising industry, government authorities, regulators, R and D organizations and educational institutions, relies on a specialized, highly trained and motivated workforce for its sustainability and continued success, quite possibly more than any other industrial field. This report has been prepared to provide information on the use of integrated workforce planning as a tool to effectively develop these resources for the spectrum of organizations that have a stake in such nuclear power programmes. These include, during the initial stages, a nuclear energy programme implementing organization (NEPIO), as well as the future operating organization, nuclear regulatory body, government authorities and technical support organizations if a decision is made to initiate a nuclear power

  17. Developing Infrastructure for New Nuclear Power Programmes

    International Nuclear Information System (INIS)

    2011-09-01

    Many countries are interested in introducing or expanding nuclear energy programmes because they regard nuclear power as a clean and stable source of electricity that can help to mitigate the impact of climate change. However, the March 2011 accident at the Fukushima Daiichi nuclear power plant in Japan - caused by an earthquake and tsunami of unprecedented proportions - demonstrated that there is a constant need to improve global nuclear safety, despite the great progress made in the previous 25 years. A 'safety first' approach needs to become fully entrenched among nuclear power plant operators, governments and regulators everywhere. Safety first must also be the watchword for Member States considering the introduction of nuclear power. I believe that all IAEA Member States should have access to nuclear power if they wish to add it their energy mix. While it is up to each country to decide whether or not to opt for nuclear power, the IAEA has a key role to play in ensuring that the development of nuclear power programmes takes place in a safe, efficient, responsible and sustainable manner. The IAEA has developed guidelines and milestones to help countries work in a systematic way towards the introduction of nuclear power. Use of the 'Milestones' approach can increase transparency both within a country introducing nuclear power, and between it and other States. This brochure summarizes the services which the IAEA offers to Member States considering introducing nuclear power. These include advice on proper planning, building the required human resources and infrastructure, establishing legal and regulatory frameworks, and ensuring the highest standards of safety and security, without increasing proliferation risks. The IAEA offers independent know-how on the construction, commissioning, startup and operation of nuclear reactors. Through the Technical Cooperation programme, we provide targeted support to 'newcomer' countries in response to national development needs

  18. 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

  19. 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)

  20. 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

  1. 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)

  2. Promotion and financing of nuclear power programmes in developing countries

    International Nuclear Information System (INIS)

    1987-01-01

    The Director General of the International Atomic Energy Agency established in February 1986 a Senior Expert Group (SEG) on Mechanisms to Assist Developing Countries in the Promotion and Financing of Nuclear Power Programmes, which was asked: (a) 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; (b) To 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 report summarizes the Senior Expert Group's study. It also presents a number of recommendations on mechanisms to assist developing countries in promoting and financing their nuclear power programmes. 1 fig., 3 tabs

  3. 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)

  4. Nigeria nuclear power generation programme: Suggested way forward

    International Nuclear Information System (INIS)

    Adesanmi, C.A.

    2007-01-01

    It has now been established worldwide that nuclear power generation is needed to meet growing energy demands. The gases emitted from fossil fuel have serious adverse effects on the environment. The message from the 50th Annual General Conference of the International Atomic Energy Agency (IAEA) held in Vienna, September 2006 was very clear on this issue. There was a unanimous support for more nuclear power generation to meet the world energy demand. All the member states that can afford the nuclear power technology and willing to abide by the international regulations and safeguards were encouraged to do so. The requirements to participate in the nuclear power generation programme are political will and organized diplomacy, legislative and statutory framework, international safety obligations, institutional framework, public acceptability, capacity building and technology transfer, environmental concern , waste management and financing. Nigeria's performance on all the criteria was evaluated and found satisfactory. All these coupled with Nigeria's dire need for more power and better energy mix, are sufficient and undisputable reasons for the whole world to support Nigeria nuclear power generation programme. Definitely the programme poses serious challenges to the Nigerian Physicists. Therefore, Departments of Physics should endeavour to include nuclear physics option in their programme and work in collaboration with the faculty of Engineering in their various tertiary institutions in order to attain the necessary critical human capacity that will be needed to man the nuclear power industry within the next 10 years

  5. Atucha I nuclear power plant surveillance programme

    Energy Technology Data Exchange (ETDEWEB)

    Jinchuk, D [Comision Nacional de Energia Atomica, Buenos Aires (Argentina)

    1994-12-31

    After a review of the main characteristics of the Atucha I nuclear power plant and its pressure vessel, the embrittlement surveillance capsules and the irradiation conditions are described; Charpy impact tests and tensile tests were performed on the irradiated samples, and results are discussed and compared to theoretical calculations: transition temperature shifts, displacement per atom values. 6 refs., 16 figs., 7 tabs.

  6. Atucha I nuclear power plant surveillance programme

    International Nuclear Information System (INIS)

    Jinchuk, D.

    1993-01-01

    After a review of the main characteristics of the Atucha I nuclear power plant and its pressure vessel, the embrittlement surveillance capsules and the irradiation conditions are described; Charpy impact tests and tensile tests were performed on the irradiated samples, and results are discussed and compared to theoretical calculations: transition temperature shifts, displacement per atom values. 6 refs., 16 figs., 7 tabs

  7. 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)

  8. 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

  9. MOX fuel for Indian nuclear power programme

    International Nuclear Information System (INIS)

    Kamath, H.S.; Anantharaman, K.; Purushotham, D.S.C.

    2000-01-01

    A sound energy policy and a sound environmental policy calls for utilisation of plutonium (Pu) in nuclear power reactors. The paper discusses the use of Pu in the form of mixed oxide (MOX) fuel in two Indian boiling water reactors (BWRs) at Tarapur. An industrial scale MOX fuel fabrication plant is presently operational at Tarapur which is capable of manufacturing MOX fuels for BWRs and in future for PHWRs. The plant can also manufacture mixed oxide fuel for prototype fast breeder reactor (PFBR) and development work in this regard has already started. The paper describes the MOX fuel manufacturing technology and quality control techniques presently in use at the plant. The irradiation experience of the lead MOX assemblies in BWRs is also briefly discussed. The key areas of interest for future developments in MOX fuel fabrication technology and Pu utilisation are identified. (author)

  10. 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

  11. 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

  12. Industrial infrastructure for the Indian nuclear power programme

    International Nuclear Information System (INIS)

    Srinivasan, M.R.

    1986-04-01

    For the inception of the Indian nuclear power programme, great emphasis has been laid on development of comprehensive indigenous capability in design, construction and operation of nuclear power plants. The choice of the pressurised heavy water reactor as the mainline for India's first generation nuclear power stations fitted into this perspective. Apart from the inherent advantages of high neutron economy, low fuelling costs and high capacity factors, this system offered significant opportunities for manufacture and design of all the components within the country. The development of indigenous capability has not been without its problems, namely cost overruns and delays. The main causes for these delays have been the developmental nature of the jobs involving learning process and continued tightening of the quality control requirements. The strategy of development to be pursued by any country is naturally dependent upon the size of the programme it wishes to embark upon and the state of industrial infrastructure in the country. The Indian experience has demonstrated that for development of a comprehensive capability, it is necessary to have a well formulated reactor policy, a good inter-disciplinary R and D base, a good base of conventional industrial infrastructure, a comprehensive manpower development programme and an innovative management. It is hoped that this experience will be of benefit to other developing countries embarking on their own nuclear programme

  13. 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.

  14. 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

  15. 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.

  16. 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)

  17. 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

  18. 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.

  19. 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

  20. 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

  1. 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)

  2. 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)

  3. 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

  4. 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)

  5. 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

  6. 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)

  7. 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)

  8. 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.

  9. 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

  10. 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)

  11. 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)

  12. 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)

  13. 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

  14. 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

  15. 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.

  16. 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

  17. 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).

  18. 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.)

  19. 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)

  20. 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

  1. 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...

  2. 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

  3. 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

  4. Programme

    OpenAIRE

    Hobday, E, fl. 1905, artist

    2003-01-01

    A photograph of an illustrated programme listing dances. The illustration shows a snake charmer playing to a snake while another man watches. Buildings and trees can be seen behind a wall in the distance. In the lower right-hand corner of the programme is the signature 'E. Hobday'. The programme is almost certainly related to the Punjab Ball, Lahore. It is placed next to the Punjab Ball Menu in the album and the Menu is also illustrated by 'E. Hobday'.

  5. 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)

  6. 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)

  7. 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.

  8. 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...

  9. 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.

  10. 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...

  11. 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...

  12. 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

  13. 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

  14. Implementation of accident management programmes in nuclear power plants

    International Nuclear Information System (INIS)

    2004-01-01

    good practices and developments in Member States and is intended as reference material for NPPs, as well as an information source for other organizations such as regulatory bodies. It is a follow-up to the IAEA report on Accident Management Programmes in Nuclear Power Plants, published in 1994, and reflects the considerable progress made since that time. The objective of this report is to provide a description of the elements to be addressed by the team responsible for developing and implementing a plant specific AMP at an NPP. Although it is intended primarily for use by NPP operators, utilities and their technical support organizations, it can also facilitate preparation of the relevant national regulatory requirements. Important event sequences that may lead to severe accidents shall be identified using a combination of probabilistic methods, deterministic methods and sound engineering judgement. These event sequences shall then be reviewed against a set of criteria aimed at determining which severe accidents should be addressed in the design. Potential design or procedural changes that could either reduce the likelihood of these selected events, or mitigate their consequences, should these selected events occur, shall be evaluated, and shall be implemented if reasonably practicable. Consideration shall be given to the plant full design capabilities, including the possible use of some systems (i.e. safety and non-safety systems) beyond their originally intended function and anticipated operating conditions, and the use of additional temporary systems to return the plant to a controlled state and/or to mitigate the consequences of a severe accident, provided that it can be shown that the systems are able to function in the environmental conditions to be expected. For multiunit plants, consideration shall be given to the use of available means and/or support from other units, provided that the safe operation of the other units is not compromised. Accident management

  15. 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)

  16. India's nuclear power programme and constraints encountered in its implementation

    International Nuclear Information System (INIS)

    Sethna, H.N.; Srinivasan, M.R.

    1977-01-01

    Nuclear power development in India is based on the natural uranium fuelled pressurised heavy water reactors. However, in order to acquire early experience in operation and maintenance of nuclear power stations, India's first atomic power station comprised of two units of boiling water reactors. Subsequent nuclear power stations currently in operation or under construction employ natural uranium heavy water reactors and each of the stations is a two reactor installation. While the first two nuclear power stations employ reactors with an output of 235 MW. 500 MW heavy water reactors are visualised for the period beyond 1985. The first nuclear power station was essentially fully imported; the second nuclear power station which employs heavy water reactors already has a significant contribution of equipment manufactured in India. For the third nuclear power station and the subsequent one, practically all equipment is being manufactured indigenously. The nuclear power station at Narora is in a seismic region and hence the design is substantially more advanced than the ones at the earlier sites and also employs concepts which will be used in the 500 MW reactors. Efforts are being made in the country to integrate power generation systems into larger regional grids and eventually into a national grid; however, the distributed nature of power generation at present and other infrastructural limitations still favour small and medium size plants only. The paper brings out the efforts put in over the last ten years in establishing capability for design and manufacture of all equipment and systems required for nuclear power plants. A major constraint in expanding the nuclear power capacity is naturally related to the competing demands on available national resources. The paper also discusses other constraints than purely technological and financial and describes how efforts are being made to overcome these contraints

  17. India's nuclear power programme and constraints encountered in its implementation

    International Nuclear Information System (INIS)

    Sethna, H.N.; Srinivasan, M.R.

    1977-01-01

    Nuclear power development in India is based on natural-uranium fuelled pressurized heavy-water reactors. However, to acquire early experience in operation and maintenance of nuclear power stations, India's first atomic power station comprised two units of boiling-water reactors. Subsequent nuclear power stations currently in operation or under construction employ natural-uranium heavy-water reactors and each is a two-reactor installation. While the first two nuclear power stations employ reactors of 200MW capacity, the subsequent stations employ reactors with an output of 235MW. Heavy-water reactors of 500-MW capacity are foreseen for the period beyond 1985. The first nuclear power station was essentially fully imported: the second, which employs heavy-water reactors, has already made a significant contribution of equipment manufactured in India. For the third nuclear power station and for the subsequent one, practically all equipment is being manufactured indigenously. The nuclear power station at Narora is in a seismic region and hence the design is substantially more advanced than those at the earlier sites and also employs concepts which will be used in the 500-MW reactors. Efforts are being made in India to integrate power generation systems into larger regional grids and eventually into a national grid; however, the distributed nature of power generation at present and other infrastructural limitations still favour small and medium-size plants only. The paper reports the efforts made since the mid-1960s in establishing capability for design and manufacture of all equipment and systems required for nuclear power plants. A major constraint in expanding the nuclear power capacity is naturally related to the competing demands on available national resources. The paper also discusses constraints other than purely technological and financial, and describes the efforts being made to overcome them. (author)

  18. 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

  19. 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.

  20. Nuclear Power Programme in India—Past, Present and Future

    Indian Academy of Sciences (India)

    India is poised for multifold growth in nuclear power generation to match the needs of sustained economic growth and improving the standard of living for masses. Nuclear power is currently the fourth-largest source of electricity in India after thermal, hydroelectric and renew- able sources of electricity. Thorium utilization for ...

  1. 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

  2. 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.

  3. The nuclear power safety programme of the International Atomic Energy Agency

    International Nuclear Information System (INIS)

    Rosen, M.

    1981-01-01

    The role of the International Atomic Energy Agency in the field of nuclear power safety is growing. In the period since the Three Mile Island accident, a significant expansion in its nuclear safety programme has taken place. To assure an acceptable safety level world-wide, new emphasis is being placed on the major effort to establish and foster the use of a comprehensive set of internationally agreed safety standards for nuclear power plants. New initiatives are in progress to intensify international co-operative safety efforts through the exchange of information on safety-related operating occurrences, and through a more open sharing of safety research results. Emergency accident assistance lends itself to international co-operation and steps are being taken to establish an emergency assistance programme so the Agency can aid in co-ordinating a timely response to provide, at short notice, help and advice in case of a nuclear power accident. There has been some strengthening of those advisory services which involve missions of international experts primarily to countries with less developed nuclear power programmes, and in conjunction with the Technical Assistance Programme there is a co-ordinated programme for developing countries, involving safety training courses and assistance aimed at promoting an effective national regulatory programme in all countries using nuclear power. This paper discusses the major features of the IAEA activities in nuclear power plant safety. An understanding of the programme and its limitations is essential to its more effective use. Additional initiatives may still be proposed, but the possibilities for international and regional co-operation to assure an adequate level of safety world-wide already exist. (author)

  4. 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.

  5. 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

  6. 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

  7. Infrastructure needs and organizational aspect of nuclear power programme

    International Nuclear Information System (INIS)

    Villanueva, M.S.

    1996-01-01

    I. Introduction. II. Infrastructure development for nuclear power program: a) pre-requisites and requirements for a nuclear power program; b) long-term national policy for a nuclear power (long-term policy reason; national commitment); c) manpower development (role of academic institutions; practical manpower training); d) laws and regulations (regulatory framework; main national laws and regulations); e) nuclear research and development implementation (researches in the university; long term nuclear R and D program; research reactors); f) functions of government organizations (Atomic Energy Commission (PNRI); Department of Science and Technology; Department of Energy; Department of Education and Culture); g) industrial infrastructure; h) technology transfer (recipients's preparedness); i) safeguards obligations; j) public acceptance activities. III. Stages of nuclear power development (stage 1: planning; stage 2: detailed study and procurement; stage 3: construction; stage 4: operation) IV. Conclusion/Recommendation. (author)

  8. Present status and prospects of nuclear power programme in Korea

    International Nuclear Information System (INIS)

    Wan-yong Chon; Byong-whi Lee; Chang-kun Lee

    1987-01-01

    The republic of Korea has made dramatic progress in her economic growth in the last twenty-five years, which had to be supported by annual power increase of typically fifteen (15) percent. The limited domestic energy resources available and also the bitter experience of two oil crises made it necessary that the nation pursue its national nuclear power projects vigourously. Throughout the project execution, however, problems related to nuclear safety have been given the top priority. In the forthcoming KNU Nos. 11 and 12 projects, steadily growing domestic nuclear industries will play major roles in plant design, construction, standardization, and technological self-independence. By the year 2001, the total number of nuclear power plants may reach fourteen, while construction of additional small nuclear power plants for combined cycle district heating may become a reality. Preparation for full-fledged fuel cycle is also underway and necessary amendment to the existing Atomic Energy Act has been enacted. (author)

  9. 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

  10. Human Resource Development for Nuclear Power Programme in Uganda

    International Nuclear Information System (INIS)

    Henry, Ovona

    2014-01-01

    Conclusions: Despite the effort by the Government to ensure reliable and available access to electricity which is crucial to the socio – economic development, the use of hydro power, biomass and oil, geothermal and peat alone would not meet the target of the vision 2040. There is need to identifies nuclear energy as a potential option for meeting the energy deficit. Development of nuclear energy for power generation needs decision making, preparation and preparatory work which involve human resource development process, strengthening the legislation and regulatory framework, stakeholders’ involvement and public acceptance campaign

  11. 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

  12. Indian nuclear power programme – Past, present and future

    Indian Academy of Sciences (India)

    and processing of uranium, construction of plants to produce heavy water and ... In May 1956, a decision was taken to set-up a pilot plant at AEET for ... The development of most of these reactor systems is an integrated result of detailed under- .... NPCIL has engineered the methodology and strategies for Nuclear Power ...

  13. Nuclear Power Programme in India—Past, Present and Future

    Indian Academy of Sciences (India)

    This is important due to its security in terms of fuel reserves; since India has one of the largest ... of advanced nuclear power systems for utilization of thorium. ... operating water cooled reactors, the country plans to build innovative nuclear ...

  14. RATU - Nuclear power plant structural safety research programme

    International Nuclear Information System (INIS)

    Rintamaa, R.

    1992-07-01

    Studies on the structural materials in nuclear power plants create the experimental data and background information necessary for the structural integrity assessments of mechanical components. The research is carried out by developing experimental fracture mechanics methods including statistical analysis methods of materials 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 measurement of loading and water chemistry parameters have been developed. The monitoring data obtained in real power plants has been used to simulate more precisely the real environment during laboratory tests. The research on structural analysis has focused on extending and verifying the analysis capabilities for structural assessments of nuclear power plants. A widely applicable system including various computational fracture assessment methods has been created with which different structural problems can be solved reliably and effectively. Research on reliability assessment of maintenance in nuclear power plants is directed to practical case studies on components and structures of safety importance, and to the development of models for maintenance related decision support. A systematic analysis of motor-operated valve has been performed

  15. 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

  16. 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.

  17. 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

  18. Indian nuclear power programme with pressurised heavy water reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-09-01

    This compilation is a part of ongoing efforts by Nuclear Power Corporation (NPC) to enable persons: to visit the plants under construction and operation to see for themselves adoption of new and advanced techniques; to have contact with the realities of NPC`s facilities; to familiarize themselves with the regulatory aspects on radiological and environmental protection; and assess for themselves the extent of thrust and importance given to overall safety. figs., tabs.

  19. Needs of countries with limited nuclear power programmes

    International Nuclear Information System (INIS)

    1978-01-01

    The main paper in this working group comes from Austria; it deals with the assurance of long-term supply of nuclear technology and nuclear fuel. Starting from an analysis of the structure of nuclear power programs of small industrialized countries, the paper discusses how supply of services can be assured in these countries during all steps of the fuel cycle. Detailed data and diagrams outline possible solutions under the aspect of production capacities and cost

  20. IAEA programme on water chemistry in nuclear power plants

    International Nuclear Information System (INIS)

    Nechaev, A.F.; Skjoeldebrand, R.

    1988-01-01

    The paper reviews the past future efforts of the IAEA, directed to ensure optimal water chemistry regimes in nuclear power plants. Corrosion of structural materials resulting from the interaction of the coolant with the internal surfaces comprising the primary heat transfer and auxiliary circuits of water reactors, creates two main problems. The first is an operational problem resulting in an increase in the core pressure drop or overheating of the fuel elements induced by crud buildup on the fuel cladding. The second problem is related to occupational radiation exposures arising from contamination of out-of-flux surfaces by corrosion products activated in the reactor core. These are the problems of reliability and safety which together with economics could be considered as the 'three whales' of nuclear power. The main goals of international cooperation in reactor water chemistry are: (1) to create a balanced and well-grounded methodological basis for corresponding regulatory and engineering solutions on a national level and (2) to improve 'the models and predictive capability of specialists for conditions that are different from or perhaps just beyond the realm of experience'. Continuing efforts are required to guarantee the highest reliability and safety standards under favorable economic indices of nuclear power plants, and to obtain understanding of such significant potential for solving the remaining problems. (Nogami, K.)

  1. Research programme on the conditioning of nuclear power waste

    International Nuclear Information System (INIS)

    Hultgren, Aa.

    1981-01-01

    Main parts of this programme have included the use of zeolites and titanates to improve reactor waste treatment, the fractionation of high level reprocessing waste by extraction, and a study of liquid partition chromotographic technique for the removal of impurities from reactor cooling circuits. Preparation of large crystal zeolites has been continued and refined. For titanate production new routes are tried to produce material of a form suitable for use in a sorption process. The possibility of lithium-7 recovery from spent PWR resins in the elution process is under study. Final products from different routes of heat treatment of loaded zeolites and titanates are characterized and compared. In parallell to this work a full-scale system is under study including transport, system design, integrated process flowsheets and cost estimates. The aim is to have basis early in 1982 to decide on the merits of a plant at the planned repository for low and medium level waste (SFR), to be commissioned around 1990. In the high level waste fractionation project, a demonstration of the developed process has been performed on a fission product solution from the reprocessing of low burn-up fuel. Disregarding some equipment malfunction the design goal of better than 99.99 % actinide removal from the high level waste waste solution was reached. The basic chemistry of the process seems to be quite tolerant against reasonable flow rate deviations in the extraction cycles. Also the concluding sorption step on mordenite-titanate worked quite well. The small scale experiments on liquid partition chromatographic techniques have included studies of the capacity of various carrier materials treated with NH 4 DEHP or Aliquat-336 to sorb radioactive impurities from reactor water, both in the laboratory and at the Ringhals-1 BWR. (author)

  2. 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)

  3. Human Resources Development for Rooppur Nuclear Power Programme in Bangladesh

    International Nuclear Information System (INIS)

    Hossain, Md. Kabir

    2014-01-01

    Conclusions: • Bangladesh faces a huge challenge in implementing the Rooppur NPP and its total nuclear power; • A preliminary assessment has been chalked out a plan to find out methods that can be applied to find out our gaps and then fill them up; • Bangladesh seeks cooperation from the Russian Federation in the form assistance package like National training courses, Seminar/Workshop, Expert Mission/Review and other form of bilateral arrangements in establishing infrastructure for “Rooppur NPP” building;

  4. Nuclear power plants seismic review programme in Spain

    International Nuclear Information System (INIS)

    Sanchez Cabanero, J.G.; Jimenez Juan, A.

    1995-01-01

    This presentation deals with seismic design and seismic reevaluation of Spanish operating nuclear power plants. The Spanish NPPs owners Probabilistic seismic hazard study requires an independent and deep review of methodology, modelling techniques, data management and method of eliciting in order to make decision on its acceptability. It reflects the opinion of only one expert tem and it would be necessary to involve more expert opinions to consider the uncertainties. It is proposed to evaluate the probabilistic seismic hazard study and the seismic categorisation

  5. 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

  6. 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

  7. 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

  8. 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)

  9. 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

  10. 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.)

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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)

  16. 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

  17. 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

  18. 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)

  19. Conceptual study of axial offset fluctuations upon stepwise power changes in a thorium–plutonium core to improve load-following conditions

    International Nuclear Information System (INIS)

    Lau, Cheuk Wah; Dykin, Victor; Nylén, Henrik; Björk, Klara Insulander; Sandberg, Urban

    2014-01-01

    Highlights: • Thorium–plutonium mixed oxide to improve nuclear reactors load-following capability. • SIMULATE-3 was the main calculation tool. • The Ringhals-3 PWR unit in Sweden was used as a reference. • Lower xenon poisoning and shorter reactor dead time. - Abstract: The increased share of renewable energy, such as wind and solar power, will increase the demand for load-following power sources, and nuclear reactors could be one option. However, during rapid load-following events, traditional UOX cores could be restricted by the volatile oscillation of the power distribution. Therefore, a conceptual study on stability properties of Th-MOX PWR concerning axial offset power excursion during load-following events are investigated and discussed. The study is performed in SIMULATE-3 for a realistic PWR core (Ringhals-3) at the end of cycle, where the largest amplitude of the axial offset oscillations is expected. It is shown that the Th-MOX core possesses much better stability characteristics and shorter reactor dead time compared with a traditional UOX core, and the main reasons are the lower sensitivity to perturbations in the neutron spectrum, lower xenon poisoning and lower thermal neutron flux

  20. 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).

  1. 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

  2. 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)

  3. 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.)

  4. 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.)

  5. 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)

  6. Waste to Energy Conversion by Stepwise Liquefaction, Gasification and "Clean" Combustion of Pelletized Waste Polyethylene for Electric Power Generation---in a Miniature Steam Engine

    Science.gov (United States)

    Talebi Anaraki, Saber

    The amounts of waste plastics discarded in developed countries are increasing drastically, and most are not recycled. The small fractions of the post-consumer plastics which are recycled find few new uses as their quality is degraded; they cannot be reused in their original applications. However, the high energy density of plastics, similar to that of premium fuels, combined with the dwindling reserves of fossil fuels make a compelling argument for releasing their internal energy through combustion, converting it to thermal energy and, eventually, to electricity through a heat engine. To minimize the emission of pollutants this energy conversion is done in two steps, first the solid waste plastics undergo pyrolytic gasification and, subsequently, the pyrolyzates (a mixture of hydrocarbons and hydrogen) are blended with air and are burned "cleanly" in a miniature power plant. This plant consists of a steam boiler, a steam engine and an electricity generator.

  7. 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

  8. 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.

  9. 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)

  10. 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

  11. 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)

  12. 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

  13. 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)

  14. 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)

  15. 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)

  16. 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.

  17. 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.

  18. 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

  19. 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

  20. 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

  1. The Spanish radioactive waste management programme

    International Nuclear Information System (INIS)

    Beceiro, A.R.

    1994-01-01

    All radioactive waste management activities in Spain are controlled by the Empresa Nacional de Residuos Radiactivos, installed by royal decree in 1984. The programme for low- and intermediate-level wastes is well advanced. A near-surface repository for these type of wastes has been in operation since October 1992. The programme for high-level wastes including spent fuel from the operating nuclear power plants is progressing stepwise. As the first step, effforts are made to secure the temporary storage of spent fuel. Final disposal is envisaged in an deep repository in one of the main geological media available in Spain, namely, granite, salt and clay. (orig.) [de

  2. 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.

  3. 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.

  4. 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.)

  5. 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.

  6. 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

  7. 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

  8. 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)

  9. 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)

  10. 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

  11. 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.)

  12. 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

  13. 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)

  14. 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

  15. 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

  16. 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 .

  17. 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 .

  18. 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.

  19. 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

  20. 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

  1. 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.)

  2. 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

  3. 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.)

  4. 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.

  5. 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.

  6. 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)

  7. 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

  8. 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)

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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.

  18. 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)

  19. 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)

  20. 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

  1. 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)

  2. 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

  3. 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

  4. 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

  5. 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)

  6. 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)

  7. 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

  8. The nuclear power stations of the French atomic energy programme (1960); Les centrales nucleaires de puissance du programme francais (1960)

    Energy Technology Data Exchange (ETDEWEB)

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

    1960-07-01

    After recalling the entry of nuclear energy into energy production in France, the paper emphasizes the evolution of techniques applied in the designing of French nuclear power plants and describes the means employed for reducing costs per kWh of EDF2 and EDF3 compared with EDF1: the electric power per ton of uranium varies from 493 kW/t for EDF1 to 970 kW/t for EDF3. For this purpose the thermal power and electric power of units are changed respectively from 290 MWt for EDF1 to 1200 or 1600 MWt for EDF3 and from 28 to 250 MW. The results are obtained by an improvement in neutronic characteristics, developments in nuclear fuel technology, and simplification of the system of charging the reactor, whose means of maintenance are increased; the EDF2 heat-exchangers have been so designed as to increase the unit power of the elements, which will attain 9 MWt, as against 3 for EDF1. For EDF3 an advance project forecasts a thermodynamic layout with only one pressure stage. The paper ends with a description of the burst-slug detection systems, and an appendix gives a detailed comparative table of EDF1, EDF2 and EDF3 plant characteristics. (author) [French] Apres avoir rappele l'integration de l'energie nucleaire parmi les moyens de production de l'energie en France, les auteurs se penchent surtout sur l'evolution des techniques appliquees dans l'equipement des centrales nucleaires francaises et decrivent les moyens mis en oeuvre pour reduire les prix de revient du kWh d'EDF2 et d'EDF3 par rapport a EDF1: la puissance electrique par tonne d'uranium varie de 493 kW/t pour EDF1 a 970 kW/t pour EDF3. C'est dans ce but que les puissances thermiques et la puissance unitaire des groupes turbo-alternateurs passent respectivement de 290 MWt pour EDF1 a 1200 ou 1600 MWt pour EDF3 et de 82 a 250 MW. Les resultats sont obtenus par une amelioration des caracteristiques neutroniques, des progres realises sur la technologie des elements combustibles, une simplification du systeme de

  9. 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

  10. Creation of nuclear power stations for export. Adapting a reference power station from the technical level of a national programme

    International Nuclear Information System (INIS)

    Marcaillou, J.; Haond, H.; Py, J.P.

    1977-01-01

    The recent evolution of primary energy supplies places those countries with a nuclear industry in an exporting role. Exporting countries have generally developed a limited number of national reactor types and attempt to extend their manufacture with as few changes as possible. The EDF in France is implementing an important 900-MW(e) PWR programme based on Framatome nuclear reactors, initially conceived by Westinghouse. Standardization imposes constraints, has limits, but offers incontestable advantages in terms of reliability, availability and security. These advantages were highly appreciated during the introduction into service of conventional thermal loads. Importing countries are all concerned to purchase a proven model. However, various local restrictions are often present, which are usually different from those accounted for in the export model, thus resulting in a need for modification. The different ways of considering the inescapable constraints can be analysed and their influence on the 'disfigurement' of the reactor model can be examined. Some of these constraints are connected with characteristics of the site. The nature of the soil and the seismicity influence the foundation and the depth of the installation and the choice between a foundation on antiseismic supports or structural reinforcement. The hydrology (risk of flooding or of deviation of the cold source) influences the choice between elevation of the installation and a protective dike, and also the stand-by coolant circuit. The atmospheric conditions and the temperature of cooling water influence the materials and their conditioning as well as the power level of the station. The surrounding demography influences the waste treatment systems. The characteristics of the electricity network influence the plan of the electric power supply and the conditions of operation. Finally, the characteristics of the personnel of the undertaking provide training problems. Other parameters to be taken into

  11. 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)

  12. 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.)

  13. 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)

  14. 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)

  15. 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)

  16. The development of radwaste policy and the Nirex programme

    International Nuclear Information System (INIS)

    Folger, M.

    1993-01-01

    Radwaste policy has had a chequered past in this country and although some of the blame has occasionally been laid at our door, three things sound be borne in mind, the context within which Nirex has worked and must continue to work, many of the ''myths'' about Nirex, and assurance that there is a well structured programme for stepwise investigation, and potential development, at Sellafield. Through that solution the waste producers will be paying real money to meet the requirement in the present generation. I aim to demonstrate that the United Kingdom (UK) programme for deep disposal is on track and compares well with the programmes which other nuclear nations have in place. Whatever the future investment decisions on nuclear power, government strategy does properly require safe disposal of the wastes we already have and the wastes which will come forward from the present nuclear programme. (Author)

  17. OSART programme highlights 1995-1996. Operational safety practices in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-01

    The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States in enhancing the operational safety of nuclear power plants. This report continues the practice of summarizing mission results so that all the aspects of OSART missions, Pre-OSART missions and good practices are to be found in one volume. It also includes results of follow-up visits. Attempts have been made in this report to highlight the most significant findings whilst retaining as much of the vital background information as possible. This report is in four parts: Part I summarizes the most significant observations made during the missions and follow-up visits during 1995-1996; Part II, in chronological order, is an overview of the major strengths and opportunities for improvement identified during each OSART mission and summaries of follow-up visits performed during the period; Part III lists good practices that were identified during 1995 and 1996; and Part IV presents the OSART mission results (OSMIR) database. Each part of the report is intended for different levels in operating and regulatory organizations but not exclusively so. Part I is primarily to the executive management level; Part II to middle managers; and Parts III and IV to those involved in operational experience feedback. Because of widely different plant designs, operating and management styles, cultural practices, and other factors affecting plant operations, no OSART findings were applicable to all of the plants visited in 1995 and 1996. Individual findings varied considerably in scope and significance. However, the findings do reflect some common strengths and opportunities for improvement

  18. 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

  19. 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

  20. 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.

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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)

  6. 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

  7. 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)

  8. 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

  9. 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.

  10. 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)

  11. 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)

  12. 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)

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. Transfer of radioactive waste management expertise from Switzerland to other countries with small nuclear power programmes

    International Nuclear Information System (INIS)

    McKinley, I.; Birkhaeuser, Ph.; Kickmaier, W.; Vomvoris, S.; Zuidema, P.

    2000-01-01

    A legal requirement which coupled demonstration of the feasibility of nuclear waste disposal to the extension of reactor operational licenses beyond 1985 acted to force rapid development of the Swiss radioactive waste management programme. Over a period of almost 30 years and at a cost of approximately 800 M CHF Nagra has become established as a centre of excellence in this field. Resources include highly experienced manpower, literature and databases supporting development of national repositories for L/ILW and HLW/TRU and state-of-the-art R and D infrastructure (including 2 underground laboratories, hot-laboratory facilities at PSI (Paul Scherrer Institute), modelling groups at universities etc.). This paper reviews Nagra's experience and considers various ways in which expertise can be transferred to other small countries to minimise duplication of effort and optimise development of their own national programmes. (author)

  20. RWE clean coal programme - IGCC power plant with CO{sub 2} capture & storage

    Energy Technology Data Exchange (ETDEWEB)

    Wolf, K.-J.; Ewers, J.; Renzenbrink, W. [RWE Power AG, Essen (Germany)

    2007-07-01

    In early 2006, RWE Power announced it was building a 450 MW gross commercial IGCC power plant with carbon capture. This paper sums up the key results of the project development phase concerning the IGCC power plant and shows the basis for the feasibility phase of the project. 10 figs.

  1. 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...

  2. 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.

  3. 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.

  4. 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)

  5. 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.

  6. 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

  7. Passively Powered and Programmable Sensor-RFID for ISHM Systems, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — To date there are several approaches for incorporating sensing capabilities into RFID. Active tags use batteries to power their communication circuitry, sensors, and...

  8. Passively Powered and Programmable Sensor-RFID for ISHM Systems, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — To date there are several approaches for incorporating sensing capabilities into RFID. Active tags use batteries to power their communication circuitry, sensors, and...

  9. Hydro-power installation on the Prascherbach, Nufenen, Switzerland; Wasserkraftwerk Prascherbach, Nufenen. Programm Kleinwasserkraftwerke - Schlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Marugg, R.

    2008-07-01

    This final report for the Swiss Federal Office of Energy (SFOE) describes project variants for the replacement of an 80-year old hydro-power plant in Nufenen, Switzerland. Details on the new power station, which is to produce 300 kilowatts of electrical power using a height difference of 340 metres is to provide 1.3 million kilowatt-hours of electricity per year. The report reviews the history of the project, which goes back to the 1990s and describes the project approved in 1999 as well as the updates made afterwards. The financial aspects of the project and remuneration for the power generated are examined. Environmental issues connected with the project are also discussed. The proposed course of events involved in taking further steps toward the realisation of the installation are discussed. An appendix includes copies of the various documents pertaining to cost estimation, water quantities, environmental protection and the granting of building permission.

  10. Fusion power in the E.E.C. - some considerations concerning the future programme

    International Nuclear Information System (INIS)

    Carruthers, R.

    1976-01-01

    The problems of fusion reactor technology, the assessment of potential reactor systems and an estimate of the overall investment of manpower likely to be needed to reach a practical fusion power reactor are presented. (U.K.)

  11. The nuclear power safety programme of the International Atomic Energy Agency

    International Nuclear Information System (INIS)

    Rosen, M.

    1981-01-01

    The expanded role of the IAEA in the field of nuclear power safety will be discussed. Emphasis will be given to the NUSS program (the letters being an acronym for Nuclear Safety Standards) to establish internationally accepted safety codes and guides for nuclear power plants dealing with governmental regulatory organizations, siting, design, operation and quality assurance. Other activities discussed will be advisory services, exchange of information and training, emergency accident assistance, and technical assistance. (orig./RW)

  12. Strategic International Cooperation of Fukui Prefectural Government in Human Resources Development for Nuclear Power Programmes

    International Nuclear Information System (INIS)

    Nishikawa, Issei

    2014-01-01

    Japan's new 'Basic Energy Plan': • Nuclear Energy is an important ”base load power supply”. • Restart NPPs that adhere to the world’s strictest regulation standards. • Reduce dependence on nuclear power as much as possible. • Ascertain the scale of steady supply, cost reduction, global warming, ensuring safety. • Decide the best mix of energy sources as soon as possible

  13. The ''controbloc'', a programmable automatic device for the 1,300 MW generation of power stations

    International Nuclear Information System (INIS)

    Pralus, B.; Winzelle, J.C.

    1983-01-01

    Technological progress in the field of microelectronics has led to the development of an automatic control device, the ''controbloc'', for operating and controlling nuclear power plants. The ''controbloc'' will be used in automatic systems with a high degree of safety and versatility and is now being installed in the first of the new generation 1,300 MW power stations. The main characteristics of the device and the evaluation tests which have been carried out are described [fr

  14. 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.

  15. 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.

  16. 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.

  17. The nuclear power stations of the French atomic energy programme (1960)

    International Nuclear Information System (INIS)

    Leduc, C.

    1960-01-01

    After recalling the entry of nuclear energy into energy production in France, the paper emphasizes the evolution of techniques applied in the designing of French nuclear power plants and describes the means employed for reducing costs per kWh of EDF2 and EDF3 compared with EDF1: the electric power per ton of uranium varies from 493 kW/t for EDF1 to 970 kW/t for EDF3. For this purpose the thermal power and electric power of units are changed respectively from 290 MWt for EDF1 to 1200 or 1600 MWt for EDF3 and from 28 to 250 MW. The results are obtained by an improvement in neutronic characteristics, developments in nuclear fuel technology, and simplification of the system of charging the reactor, whose means of maintenance are increased; the EDF2 heat-exchangers have been so designed as to increase the unit power of the elements, which will attain 9 MWt, as against 3 for EDF1. For EDF3 an advance project forecasts a thermodynamic layout with only one pressure stage. The paper ends with a description of the burst-slug detection systems, and an appendix gives a detailed comparative table of EDF1, EDF2 and EDF3 plant characteristics. (author) [fr

  18. 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

  19. Evaluation of fire hazard analyses for nuclear power plants. A publication within the NUSS programme

    International Nuclear Information System (INIS)

    1995-01-01

    The present publication has been developed with the help of experts from regulatory, operating and engineering organizations, all with practical experience in the field of fire safety of nuclear power plants. The publication supplements the broad concepts of Safety Series No. 50-SG-D2 (Rev.1), Fire Protection in Nuclear Power Plants, by providing a detailed list of the issues, and some of the limitations, to be considered when evaluating the adequacy and effectiveness of the fire hazard analysis of a nuclear power plant. The publication is intended for assessors of fire hazard analyses, including regulators, independent assessors or plant assessors, and gives a broad description of the methodology to be used by operators in preparing a fire hazard analysis for their own plant. 1 fig

  20. Drinking-water-driven power station in Weesen - Feasibility study; Machbarkeitsstudie Trinkwasserkraftwerk Waldrueti, Weesen. Programm Kleinwasserkraftwerke

    Energy Technology Data Exchange (ETDEWEB)

    Schalkowski, S.; Boelli, M.

    2006-07-01

    This final report published by the Swiss Federal Office of Energy (SFOE) takes a look at a project concerning the use of a drinking-water supply system in Weesen, Switzerland to generate electricity. The background behind efforts to use the differences in height between reservoirs to provide power are discussed. The report examines the potential of power generation and describes the installations and modifications to the system that are necessary. Various turbine types and their location are discussed and estimates of operating data and production are presented, as are the investments necessary and the operating costs to be expected.

  1. 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.

  2. Inspection and enforcement by the regulatory body for nuclear power plants. A safety guide. A publication within the NUSS programme

    International Nuclear Information System (INIS)

    1996-01-01

    The purpose of this Safety Guide is to provide guidance on fulfilling the requirements for inspection and enforcement by the regulatory body, as set out in the Code on the Safety of Nuclear Power Plants; Governmental Organization. This Safety Guide deals with the responsibilities of the regulatory body, the organization of inspection programmes, the inspection resources of the regulatory body, methods of inspection, requirements on the applicant/licensee in regard to regulatory inspection, inspection reports, and regulatory action and enforcement. It is recognized that many of the provisions of this Safety Guide may be applicable to the regulations of other nuclear facilities and related activities including research reactors, fuel processing and manufacturing plants, irradiated fuel processing plants and radioactive waste management facilities. This Safety Guide does not deal specifically with the functions of a regulatory body responsible for such matters; however, the guidance presented here may be applied as appropriate to these activities. 11 refs, 1 fig

  3. 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)

  4. Programmable Power-of-two RNS Scaler and its Application to a QRNS Polyphase Filter

    DEFF Research Database (Denmark)

    Cardarilli, Gian Carlo; Re, Andrea Del; Nannarelli, Alberto

    2005-01-01

    The scaling operation, i.e. the division by a constant factor followed by rounding, is a commonly used technique for reducing the dynamic range in Digital Signal Processing (DSP) systems. Usually, the constant is a power of two, and the implementation of the scaling is reduced to a right shift. T...

  5. Neutron dosimetry in EDF experimental surveillance programme for VVER-440 nuclear power plants

    International Nuclear Information System (INIS)

    Brumovsky, M.; Erben, O.; Novosad, P.; Zerola, L.; Hogel, J.; Trollat, C.

    2001-01-01

    Fourteen chains containing experimental surveillance material specimens of the VVER 440/213 nuclear power reactor pressure vessels were irradiated in the surveillance channels of the Nuclear Power Plant Dukovany in the Czech Republic. The irradiation periods were one, two or three cycles. The chains contained different number and types of containers, the omitted ones were replaced by chain elements. All of the containers were instrumented with wire neutron fluence detectors, some of the containers in the chain had spectrometric sets of neutron fluence monitors. For the absolute fluence values evaluation it was taken into account time history of the reactor power and local changes of the neutron flux along the reactor core height, correction factors due to the orientation of monitors with respect to the reactor core centre. Unfolding programs SAND-II or BASA-CF were used. The relative axial fluence distribution was obtained from the O-wire measurements. Neutron fluence values above 0.5 MeV energy and above 1.0 MeV energy in the container axis on the axial positions of the sample centres and fluence values in the geometric centre of the samples was calculated making use the exponential attenuation model of the incident neutron beam. Received fast neutron fluence values can be used as reference values to all VVER-440 type 213 nuclear power plant reactors. (author)

  6. YKAe - Research programme on nuclear power plant systems behaviour and operational aspects of safety

    International Nuclear Information System (INIS)

    Mattila, L.; Vanttola, T.

    1992-01-01

    The major part of nuclear energy research in Finland has been organised as five-year nationally coordinated research programs. The research programme on Systems Behaviour and Operational Aspects of Safety is under way during 1990-1994. Its annual volume has been about 35 person-years and its annual expenditure about FIM 18 million. Studies in the field on safe operational margins of nuclear fuel and reactor core concentrate on fuel high burn-up behaviour, VVER fuel experiments, and reactor core behaviour in complex reactivity transients such as 3-D phenomena and ATWS events. The PACTEL facility is used for the thermal hydraulic studies of the Loviisa type reactors (scaled 1:305). Validation of accident analysis codes is carried out by participation in international standard problems. Advanced foreign computer codes for severe reactor accidents are implemented, modified as needed and applied to level-2 PSAs and the improvement of accident management procedures. Fire simulation methods are tested using data from experiments in the German HDR facility. A nuclear plant analyzer for efficient safety analyses is being developed using the APROS process simulation environment. Computerized operator support systems are being studied in cooperation with the OECD Halden Project. The basic factors affecting plant operator activities and the development of their competence are being investigated. A comprehensive system for the control of plant operational safety is being developed by combining living PSA and safety indicators

  7. 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.)

  8. Using railway tunnel water for power generation; Vorprojekt. Programm Kleinwasserkraftwerke. Tunnelwasser BLS, 2540 Grenchen

    Energy Technology Data Exchange (ETDEWEB)

    Meier, A. [Armin Meier, Moesliweg 4, Wiler bei Utzenstorf (Switzerland); Hammer, J.; Fuerfanger, F. [ITECO Ingenieurunternehmung AG, Affoltern am Albis (Switzerland)

    2008-07-01

    This preliminary report for the Swiss Federal Office of Energy (SFOE) describes a project involving the use of drainage water from a railway tunnel in Grenchen, Switzerland. The installation is to be realised at the site of an earlier small hydro plant. Certain parts of the old installation still existing are to be reused. Figures on water flow and proposed power production are quoted. Variants for the water conduit construction including possible reuse of old piping are examined. The economic viability of the variants is discussed. The report is concluded with a recommendation for further work on the project. An appendix includes plan variants and hydrological data on the system a well as calculations concerning the cost-covering remuneration for the power generated.

  9. Special scientific programme on use of high energy accelerators for transmutation of actinides and power production

    International Nuclear Information System (INIS)

    1994-09-01

    Various techniques for the transmutation of radioactive waste through the use of high energy accelerators are reviewed and discussed. In particular, the present publication contains presentations on (i) requirements and the technical possibilities for the transmutation of long-lived radionuclides (background paper); (ii) high energy particle accelerators for bulk transformation of elements and energy generation; (iii) the resolution of nuclear energy issues using accelerator-driven technology; (iv) the use of proton accelerators for the transmutation of actinides and power production; (v) the coupling of an accelerator to a subcritical fission reactor (with a view on its potential impact on waste transmutation); (vi) research and development of accelerator-based transmutation technology at JAERI (Japan); and (vii) questions and problems with regard to accelerator-driven nuclear power and transmutation facilities. Refs, figs and tabs

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

    OpenAIRE

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

    2017-01-01

    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 th...

  11. Design assurance programme for modifications at the Ringhals Nuclear Power Plant

    International Nuclear Information System (INIS)

    Persson, K.

    1985-01-01

    The Engineering Department within the site organization is responsible for modifications and improvements of plant design. Internal and external specialists are also involved in the design activities. Modifications follow the procedures laid down in the Design Assurance Programme (DAP), according to the overall directions given in 10CFR50 APP B and the more detailed recommendations in American Nuclear Standard 3.2, and the United States Nuclear Regulatory Commission's Regulatory Guides 1.33 and 1.64. The site Quality Assurance Department has adapted these directions to Swedish conditions. All plant modifications are ordered from customers within the site organization. The design work is performed according to the following steps: priority of problems or requirements; overall analysis of problems or requirements; basic design (preliminary and final); detailed design (electrical, mechanical, civil); purchase of equipment; installation in plant; testing of installed equipment. The project engineer is responsible for modifications from the initiation of analysis until testing and documentation are finalized. For each step, procedures and checklists are available. Internal and external specialists as well as the Swedish Nuclear Inspectorate are involved when appropriate. Design engineers and QC/QE engineers are also involved. Special groups within the site organization handle purchase and installation. Testing the installed equipment is performed in co-operation with the operation staff. Deviations from DAP must be reported by all personnel, and corrective actions must be taken. Internal audits have to be done once a year for the entire DAP and the audit, with its findings and the corrective actions taken, must be reported to the QA group. (author)

  12. 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.)

  13. Fire protection programme during construction of the Chashma nuclear power plant

    International Nuclear Information System (INIS)

    Mian Umer, M.

    1998-01-01

    A clear view is given of several measures that have been taken with regard to fire prevention, protection and fire fighting during all phases of the construction, installation and commissioning of the Chasma nuclear power plant to protect personnel and equipment so that any delays in plant operation as a result of fire incident can be avoided. These measures include the precautions taken, the provisions made for fire extinguishers and hydrants, and the setting up of a fire brigade. An overview is also given of the fire incidents that have occurred. (author)

  14. Stepwise approach to myopathy in systemic disease.

    Science.gov (United States)

    Chawla, Jasvinder

    2011-01-01

    Muscle diseases can constitute a large variety of both acquired and hereditary disorders. Myopathies in systemic disease results from several different disease processes including endocrine, inflammatory, paraneoplastic, infectious, drug- and toxin-induced, critical illness myopathy, metabolic, and myopathies with other systemic disorders. Patients with systemic myopathies often present acutely or sub acutely. On the other hand, familial myopathies or dystrophies generally present in a chronic fashion with exceptions of metabolic myopathies where symptoms on occasion can be precipitated acutely. Most of the inflammatory myopathies can have a chance association with malignant lesions; the incidence appears to be specifically increased only in patients with dermatomyositis. In dealing with myopathies associated with systemic illnesses, the focus will be on the acquired causes. Management is beyond the scope of this chapter. Prognosis is based upon the underlying cause and, most of the time, carries a good prognosis. In order to approach a patient with suspected myopathy from systemic disease, a stepwise approach is utilized.

  15. Optimization of maintenance programme at Daya Bay Nuclear Power Station based on RCM analysis results

    International Nuclear Information System (INIS)

    Liu Min

    2003-01-01

    This paper begins with an introduction to Guangdong Daya Bay Nuclear Power Station (GNPS) and gives a simple introduction to the operations and maintenance documentation system at GNPS. It then will review the maintenance program guidelines base and the associated problems prior to the application of reliability centered maintenance (RCM). How RCM was implemented at GNPS, how the results of RCM analysis were used to optimize the maintenance program and test program, and what is the interface between RCM and the existing maintenance program will be shown. Next, it will show the successful implementation of RCM at GNPS resulted in the following changes: A new understanding of equipment failure challenges operations and maintenance beliefs, maintenance concepts undergo a large change, maintenance program and periodic testing program are continuously modified and optimized, new on-condition maintenance technologies are introduced, non-productive scheduled overhauls are discarded, maintenance costs are effectively controlled, maintenance appropriateness has improved, management of hidden failures is more effective and timely. It will show the benefit of greater equipment reliability brought about by all of these changes, which in turn increases the reliability and safety of the entire power station. (author)

  16. 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)

  17. Expanding Nuclear Power Programmes - Romanian experience: Master - Nuclear Materials and Technologies Educational Plan

    International Nuclear Information System (INIS)

    Valeca, S.; Valeca, M.

    2012-01-01

    The main objectives of the Master Nuclear Materials and Technologies Educational Plan are: 1. To deliver higher education and training in the following specific domains, such as: Powders Technology and Ceramic Materials, Techniques of Structural Analysis, Composite Materials, Semiconductor Materials and Components, Metals and Metallic Alloys, Optoelectronic Materials and Devices, Nuclear Materials, The Engineering of Special Nuclear Materials, 2. To train managers of the Nuclear Waste Products and Nuclear Safety, 3. To qualify in ICT Systems for Nuclear Process Guidance, 4. To qualify in Environmental Protection System at the Level of Nuclear Power Stations, 5. To train managers for Quality Assurance of Nuclear Energetic Processes, 6. To deliver higher education and training regarding the International Treatises, Conventions and Settlements in force in the field of nuclear related activities. (author)

  18. Infrastructure and Other Considerations to Launch Nuclear Power Programme: The Case of Sub-Sahara African Developing Countries like Ethiopia

    International Nuclear Information System (INIS)

    Meshesha, Atnatiwos Zeleke

    2011-01-01

    Trends in the world's population and energy use during the past decades show dramatic increases; and the demand for electricity, mainly from developing countries, is expected to increase more rapidly than the demand for other forms of energy. Besides, concern of climate change led to the need for production of significant amount of 'safe and clean' energy which in turn favours to nuclear option. Other alternative renewable sources like solar and wind can assist but currently they are short of supplying the required high energy demand either economically or/and in substantial amount. Nuclear option therefore remains a possible (developed) technology to fill this energy gap; and many countries including developing one show interest to make use of this energy source. In this paper the economic situations and energy production of six East Africa Sub-Saharan developing countries, with total population of 240 million were assessed, and 6.8% and 2.9% average GDP and population growth respectively registered in the last four years; however, their energy production in 2008 (est.) was 17.662 billion kWh, which is the least in the world. The contribution of inadequate energy and its poor coverage in hampering development, increase poverty and unstability were also analyzed. To come out of this cyclic challenge; it is recommended that countries based on regional economic cooperation should interconnect their electricity grid like EAPP and cooperate to invest commonly or unilaterally to launch Nuclear Power Programmes in relatively stable countries. Candid support of the international community is crucial, and IAEA should support and encourage such arrangements. It is also noted that the best candidate to start NP programme in these countries would be the worldwide dominant water cooled reactors. However, for countries with low grid capacity and to carry out projects in remote areas which are far-away from national grid systems or to desalinate water, considerations for smaller

  19. YKAe Research programme on nuclear power plant systems behaviour and operational aspects of safety 1990-1994, Final report

    International Nuclear Information System (INIS)

    Mattila, L.; Vanttola, T.

    1995-04-01

    The research programme on Nuclear Power Plant Systems Behaviour and Operational Aspects of Safety was carried out between 1990 and 1994. In the field of Safe operational margins of nuclear fuel and reactor core, an up-to-date steady-state fuel performance model was validated for higher burn-ups and well-characterized VVER fuel experiments were carried out. A comprehensive reactor analysis code system was extended and validated for complex 3-D phenomena, such as ATWS and boron dilution transients. Advanced hydraulics methods were added to the dynamics codes. Experiments were carried out with PACTEL, the most comprehensive thermal-hydraulic test facility for VVER-440-type reactors worldwide. For example, a series of natural circulation tests were provided for the first VVER-related international standard problem of the OECD/NEA. Advanced foreign computer codes for severe accidents were evaluated and modified for the needs of Finnish power plants. Specific progress was made in modelling the reflooding of an overheated core and in the structural analysis of a pressure vessel under corium load, as well as in experimental and theoretical studies of aerosol and hydrogen behaviour. Fire modelling was improved by implementing advanced calculation methods and by validating them against our own experiments and international test data. Techniques in living probabilistic safety assessment and risk decision-making were refined in pilot applications for continuous monitoring, follow-up and management of risks of an operating power plant. In the area of human reliability and organizational performance, factors important for the continuous development of the competence of control room operator teams and plant maintenance staff were identified. (237 refs., 75 figs., 13 tabs.)

  20. 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

  1. Regulatory evaluation of nuclear power plant on-the-job training programmes

    International Nuclear Information System (INIS)

    Wilkinson, J.

    1996-01-01

    It is now well recognized internationally in the nuclear industry that a Systematic Approach to Training (SAT), as described in IAEA-TECDOC-525, represents the currently most effective method of providing effective, efficient training to Nuclear Power Plant (NPP) personnel. For this reason the Canadian regulator, the Atomic Energy Control Board (AECB), has made SAT a requirement for the training of NPP personnel whose job activities could affect plant or public safety. In this respect the AECB recognizes that the SAT process will dictate on-the-job-training (OJT) and the prudent use of Job Performance Measures (JPMs) as the most effective method of providing parts of the required training to some work groups. The AECB has adopted a process of training program evaluation for NPP operations personnel which comprises methods to evaluate all types of training including OJT. This paper describes some variations which have been identified in the conduct of OJT at Canadian utilities. It then presents the three step process established by the AECB to effectively evaluate training programs expertise is required. The concept of utility self-evaluations is introduced. Finally, the importance of consistency on the part of the regulator in following a systematic approach to evaluation through the application of a viable standard is addressed. (author). 2 figs

  2. Statement to International Conference on Human Resource Development for Introducing and Expanding Nuclear Power Programmes

    International Nuclear Information System (INIS)

    Al Kaabi, H.

    2010-03-01

    United Arab Emirates is going through a rapid growth in its energy needs, projected to increase to three folds by the year 2020 compared to 2007, reflecting an annual growth rate of 9% from 2007 onward. In evaluating different options to meet the projected demand, Nuclear energy emerged as a proven, environmentally promising and commercially competitive option which could make a significant contribution to the UAE's economy and future energy security. A sustainable , materially-sized nuclear energy program could contribute substantially to the UAE's basic power needs for decades, retain the continued support of international investment partners, yield sufficient revenues to support a competent and fully-professionalized regulation and safety authority, and ensure the continual improvement of safety practices and security in accordance with best international standards. In conclusion, I would like to emphasize the importance that nuclear energy introduction plans are based on long term sustainable strategy to ensure its successful deployment in a safe and responsible manner, and through the adoption of plans and strategies that will ensure the availability of resources and efficiency of the sector through its long life. In the UAE, as we continue to develop our nuclear energy program , the actions outlined in the policy paper will continue to provide a framework which is robust, in line with international best practices, and which is an accurate demonstration of our commitments as a responsible member of the international community

  3. The Use of Prestressed Concrete Vessels in the French Power Reactor Programme

    International Nuclear Information System (INIS)

    Conte, F.; Dambrine, C.; Gaussot, D.

    1963-01-01

    This paper deals with the use of pre-stressed concrete for the G2 and G3 reactors at Marcoule and for the EDF3 reactor now under construction at Chinon. The first two reactors have been operating at power since 1959 and 1960 respectively. Messrs. Conte and Dambrine discuss the problems that arose during construction of the vessels for G2 and G3 and also deal with the experience gained in operation - experience which suggests that they are extremely safe- Work on the EDF3 vessel, begun at Chinon in the second half of 1961, is still under way and should be finished towards the end of 1963. Mr. Gaussot discusses the reasons for choosing this type of vessel, the results of calculations and mock-up tests, and the problems presented by the construction itself. A number of studies have been devoted to the future prospects of prestressed concrete structures for reactors. It would seem that working pressures could be increased, if desired, and, in any case, that dimensions could be considerably enlarged, thus offering the chance of integral-type solutions. (author) [fr

  4. 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

  5. India's nuclear power programme present status, future prospects and related issues

    International Nuclear Information System (INIS)

    Prasad, Y.S.R.

    1998-01-01

    India is poorly placed in terms of world energy resources, while 16% of world's population lives in India, only 6% of coal and 0.6% of oil and gas reserves exist in the country. Moreover, the distribution of primary commercial energy resources is quite skewed. However, India is endowed with vast reserves of thorium. The energy potential of our modest uranium resources and sizeable thorium resources has been estimated to be six times that of our total coal reserves. Though during last fifty years since independence, India has made tremendous progress in the energy sector where the use of commercial energy has increased by ten folds. Electricity used during the same period has increased by eighty times. In spite of such an impressive growth the country, due to population growth, finds itself in the almost lowest bracket with regard to per capita consumption which is many fold lower than the world average. India as of today is a net energy importing country. The demand for energy, in particular electricity that has established to be the most efficient and convenient source, is projected to grow at 7-8% per annum for coming two decades. In such a demand scenario it is imperative that all the resources of energy must be judiciously utilised. However, with the depletion of fossil fuels and resulting possible price shocks a long-term energy security is required for the country. The paper deals with the role nuclear power can play in meeting the country's short term and long term demands, progress made and related issues. (author)

  6. Armenian nuclear power plant: US NRC assistance programme for seismic upgrade and safety analysis

    International Nuclear Information System (INIS)

    Simos, N.; Perkins, K.; Jo, J.; Carew, J.; Ramsey, J.

    2003-01-01

    This paper summarizes the U.S. Nuclear Regulatory Commission's (US NRC) technical support program activities associated with the Armenian Nuclear Power Plant (ANPP) safety upgrade. The US NRC program, integrated within the overall IAEA-led initiative for safety re-evaluation of the WWER plants, has as its main thrust the technical support to the Armenian Nuclear Regulatory Authority (ANRA) through close collaboration with the scientific staff at Brookhaven National Laboratory (BNL). Several major technical areas of support to ANRA form the basis of the NRC program. These include the seismic re-evaluation and upgrade of the ANPP, safety evaluation of critical systems, and the generation of the Safety Analysis Report (SAR). Specifically, the seismic re-evaluation of the ANPP is part of a broader activity that involves the re-assessment of the seismic hazard at the site, the identification of the Safe Shutdown Equipment at the plant and the evaluation of their seismic capacity, the detailed modeling and analysis of the critical facilities at ANPP, and the generation of the Floor Response Spectra (FRS). Based on the new spectra that incorporate all new findings (hazard, site soil, structure, etc.), the overall capacity of the main structures and the seismic capacity of the critical systems are being re-evaluated. In addition, analyses of critical safe shutdown systems and safe shutdown processes are being performed to ensure both the capabilities of the operating systems and the enhancement of safety due to system upgrades. At present, one of the principal goals of the US NRC's regulatory assistance activities with ANRA is enhancing ANRA's regulatory oversight of high-priority safety issues (both generic and plant-specific) associated with operation of the ANPP. As such, assisting ANRA in understanding and assessing plant-specific seismic and other safety issues associated with the ANPP is a high priority given the ANPP's being located in a seismically active area

  7. Power capacity of the customers. A review of projects in the 'Market Design' programme

    International Nuclear Information System (INIS)

    Fritz, Peter

    2006-04-01

    An important discussion in later years has been whether the necessary reserves in the electricity market are to be generated through normal market mechanisms, i.e. with the price as the primary controlling parameter, or if it requires a collectively financed effect reserve and how regulations in such a case should be shaped. The issue is first and foremost a matter of where the line is drawn between that which 'the market' should handle and that which can be assured through regulation. Autumn 2002 Svenska Kraftnaet presented an investigation to the government in which it was suggested that the effect balance should primarily be managed through the use of normal pricing mechanisms, but that the state should strengthen responsibility for the nation's effect balance in the period up until 2008. When approaching an effect loss situation, spot prices and the price of balancing power will skyrocket. Today, most people are in agreement that a condition for maintained delivery safety is that normal pricing mechanisms are in place and that consumption actually is affected by high prices. The main reason for this conclusion is that it is very expensive to keep production facilities in reserve for situations that are expected to occur very seldom - it is cheaper to encourage large customers to reduce their consumption. The other reason is that increased price sensitivity creates conditions for a more stable and more predictable pricing development in strained situations. While being aware that a response to increased demand is needed, we see too little of that on the market today. The aim of this project is to present concrete measures that will awaken this slumbering resource. In order to judge how much effect reduction can reasonably be expected and if there is any financial gain for customers, electricity suppliers and grid operators; it has been necessary to cast a few predictions about future price peaks. We estimate price peaks in the 3-10 SEK/kWh interval for an

  8. Training simulators in nuclear power plants: Experience, programme design and assessment methodology. Proceedings of a specialists' meeting

    International Nuclear Information System (INIS)

    1997-11-01

    Simulators became an indispensable part of training world-wide. Therefore, international exchange of information is important to share the experience gained in different countries in order to assure high international standards. A second aspects is the tremendous evolution in the computing capacities of the simulator hardware and the increasing functionality of the simulator software. This background has let the IAEA to invite the simulator experts for an experience exchange. The German Simulator Centre in Essen, which is operated by the companies KSG and GfS, was asked to host this Specialists' Meeting. The Specialists' Meeting on ''Training Simulators in Nuclear Power Plants: Experience, Programme Design and Assessment Methodology'' was organized by IAEA in-cooperation with the German Simulator Centre operated by KSG Kraftwerks-Simulator-Gesellschaft mbH and GfS Gesellschaft fuer Simulatorschulung mbH and was held from 17 - 19 November 1997 in Essen, Germany. The meeting focused on developments in simulation technology, experiences with simulator upgrades, utilization of computerized tools as support and complement of simulator training, use of simulators for other purposes. The meeting was attended by 50 participants from 16 countries. In the course of four sessions 21 technical presentations were made. The present volume contains the papers by national delegates at the Specialists' Meeting

  9. Training simulators in nuclear power plants: Experience, programme design and assessment methodology. Proceedings of a specialists` meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

    Simulators became an indispensable part of training world-wide. Therefore, international exchange of information is important to share the experience gained in different countries in order to assure high international standards. A second aspects is the tremendous evolution in the computing capacities of the simulator hardware and the increasing functionality of the simulator software. This background has let the IAEA to invite the simulator experts for an experience exchange. The German Simulator Centre in Essen, which is operated by the companies KSG and GfS, was asked to host this Specialists` Meeting. The Specialists` Meeting on ``Training Simulators in Nuclear Power Plants: Experience, Programme Design and Assessment Methodology`` was organized by IAEA in-cooperation with the German Simulator Centre operated by KSG Kraftwerks-Simulator-Gesellschaft mbH and GfS Gesellschaft fuer Simulatorschulung mbH and was held from 17 - 19 November 1997 in Essen, Germany. The meeting focused on developments in simulation technology, experiences with simulator upgrades, utilization of computerized tools as support and complement of simulator training, use of simulators for other purposes. The meeting was attended by 50 participants from 16 countries. In the course of four sessions 21 technical presentations were made. The present volume contains the papers by national delegates at the Specialists` Meeting Refs, figs, tabs

  10. 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)

  11. The role of environmental survey laboratory at Nuclear Power Plants sites in India in environmental awareness and education programmes

    International Nuclear Information System (INIS)

    Hegde, A.G.; Singhal, R.K.; Sharma, R.M.

    2004-01-01

    Increased public awareness of nuclear power runs the gamut from immediate disengagement to whole-hearted approval of the use of and expansion of this energy source. The involved study carried out at different Environmental Survey Laboratories (ESL) is mainly responsible for the environment friendly attitudes of the large section of public. The scientists working in these laboratories collected vast data on different environmental issues related to releases of very low levels of radioactivity in the environment. The total dose received by a hypothetical individual member of public (critical group) evaluated at plant boundary i.e. 1.6 km zone is generally in the range of 2-50 mSv/y which is about two order of magnitude less compared to limits prescribed by the Atomic Energy Regulatory Board (AERB) and International Commission on Radiological Protection ICRP) suggested value of 1 mSv/y. The ESL staff give special attention to communicate to the public to clear their queries and dislodge, their misconception about the nuclear facilities operating at their site. At ESL, various environmental pathways responsible for radiation dose and their impact on different environmental matrices are nicely presented in the form of charts and posters. Site and off-site emergency exercise are conducted regularly in co-ordination with inter governmental agencies responsible for mass sheltering, medical facilities and transportation. During these exercises mass communication programme are conducted to educate the public in the vicinity of Nuclear Power Plants Sites. ESL also updates from time to time the population distribution data within 30 km radial zone and the dietary habit of the population within this zone. (author)

  12. 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

  13. 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

  14. 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

  15. 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)

  16. IAEA's technical co-operation programme and its role in assisting member states in the safe utilisation of nuclear power

    International Nuclear Information System (INIS)

    Reed, J.

    2000-01-01

    In this contribution the author deals with the technical co-operation projects of the IAEA. The Agency's technical co-operation programme is a most welcome mechanism for the transfer of nuclear technology, and to developing countries it is certainly the most attractive side of the Agency, since it is through this programme that the IAEA can contribute to the solution of their problems through the provision of know-how, technology and training. (authors)

  17. 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.

  18. 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

  19. 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

  20. 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

  1. 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

  2. Databases on safety issues for WWER and RBMK reactors. Users' manual. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-04-01

    At the beginning of the IAEA Extrabudgetary Programme on the safety of WWER reactors a great number of findings and recommendations (safety items) were collected as a result of design review and safety review missions of the WWER-440/230 type reactors. On the basis of these findings a technical database containing more than 1300 records was established to support the consolidation of the information obtained and to help in identification of safety issues. After the scope of the WWER extrabudgetary programme was extended similar data sets were prepared for the WWER-440/213, WWER-1000 and RBMK nuclear power plants. This publication describes the structure of the databases on safety issues of WWER and RBMK NPPs, the information sources used in the databases and interrogation capabilities for users to obtain the necessary information. 14 refs, 9 figs, 5 tabs

  3. 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

  4. 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

  5. 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.

  6. 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

  7. 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.

  8. 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.

  9. 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

  10. 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.

  11. Development of field programmable gate array–based encryption module to mitigate man-in-the-middle attack for nuclear power plant data communication network

    Directory of Open Access Journals (Sweden)

    Mohamed Abdallah Elakrat

    2018-06-01

    Full Text Available This article presents a security module based on a field programmable gate array (FPGA to mitigate man-in-the-middle cyber attacks. Nowadays, the FPGA is considered to be the state of the art in nuclear power plants I&C systems due to its flexibility, reconfigurability, and maintainability of the FPGA technology; it also provides acceptable solutions for embedded computing applications that require cybersecurity. The proposed FPGA-based security module is developed to mitigate information-gathering attacks, which can be made by gaining physical access to the network, e.g., a man-in-the-middle attack, using a cryptographic process to ensure data confidentiality and integrity and prevent injecting malware or malicious data into the critical digital assets of a nuclear power plant data communication system. A model-based system engineering approach is applied. System requirements analysis and enhanced function flow block diagrams are created and simulated using CORE9 to compare the performance of the current and developed systems. Hardware description language code for encryption and serial communication is developed using Vivado Design Suite 2017.2 as a programming tool to run the system synthesis and implementation for performance simulation and design verification. Simple windows are developed using Java for physical testing and communication between a personal computer and the FPGA. Keywords: AES-128, Cyber Security, Encryption, Field Programmable Gate Array, I&C

  12. The use of algae in monitoring discharges of radionuclides. Experiences from the 1992 and 1993 monitoring programmes at the Swedish nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Snoeijs, P. [Uppsala Univ. (Sweden). Dept. of Ecological Botany; Simenstad, P. [Swedish Radiation Protection Inst., Stockholm (Sweden)

    1995-01-01

    All four Swedish nuclear power plants (Forsmark, Oskarshamn, Barsebaeck and Ringhals) use brackish water as coolant (Baltic Sea and Swedish west coast). Radionuclides are discharged together with the cooling water. The gamma spectra of monthly algal samples harvested in 1992 and 1993 close to the discharge points of these power plants were determined within the routine monitoring programmes. The main radionuclides detected in the algal samples were {sup 54}Mn, {sup 58}Co, {sup 60}Co and {sup 137}Cs. Most {sup 137}Cs in the samples from the northern Baltic Sea (Forsmark) still originated from the 1986 Chernobyl accident. Other radionuclides, notably {sup 51}Cr, {sup 65}Zn, {sup 95}Zr, {sup 95}Nb, {sup 110m}Ag, {sup 124}b, {sup 125}Sb and {sup 134}Cs, were regularly detected at s of the sites. Transfer factors from discharge to algae were generally in the order of 0.3-3 Bq kg{sup -1} per MBq discharge. For the major discharged radionuclides, significant linear relationships were in most cases found between discharges and concentrations in algal samples. Differences in transfer factors and regression coefficients were explained by location of the sampling sites and type of radionuclide. It is concluded that algal samples provide useful complements to water and sediment samples in the monitoring programmes since radionuclide concentrations are much higher in algal samples and proportional to the discharges. 21 refs, figs.

  13. 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...

  14. 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.

  15. 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

  16. 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.

  17. 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

  18. 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

  19. Co-ordinated research programme on benchmark study for the seismic analysis and testing of WWER-type nuclear power plants. V. 5B. Experience data. Working material

    International Nuclear Information System (INIS)

    1996-01-01

    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 the effects of Armenia earthquakes on selected power, industry and commercial facilities and seismic functional qualification of active mechanical and electrical components tested on shaking table

  20. 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)

  1. Inspection of fire protection measures and fire fighting capability at nuclear power plants. A publication within the NUSS programme

    International Nuclear Information System (INIS)

    1994-01-01

    The present publication has been developed with the help of experts from regulatory, operating and engineering organizations, all with practical experience in the field of fire protection of nuclear power plants. The publication outlines practices for inspecting the fire protection measures at nuclear power plants in accordance with Safety Series No.50-SG-D2(Rev.1), Fire Protection in Nuclear Power Plants, and includes a comprehensive fire safety inspection checklist of the specific elements to be addressed when evaluating the adequacy and effectiveness of the fire protection measures and manual fire fighting capability available at operating nuclear power plants. The publication will be useful not only to regulators and safety assessors but also to operators and designers. The book addresses a specialized topic and it is recommended that it be used in conjunction with Safety Guide No.50-SG-D2(Rev.1)

  2. Opening remarks at the International Conference on Human Resource Development for Introducing and Expanding Nuclear Power Programmes

    International Nuclear Information System (INIS)

    Klein, D.E.

    2010-03-01

    The topic of this conference - human resources development and the expansion of nuclear power - is about the commitment and investment in people. The importance of this 'human side' of modern technology is sometimes forgotten or assumed to develop on its own once basic educational programs and institutions are put in place. In my view, the development and maintenance of a skilled national workforce is critical to the development of a stable, successful national nuclear power program

  3. 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)

  4. 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)

  5. Status of Nuclear Science Education and the Needs for Competency Based Education at the Beginning of Nuclear Power Programme in Turkey

    International Nuclear Information System (INIS)

    Yücel, H.

    2016-01-01

    Full text: In Turkey, in recent years, public opinion is mostly positive towards the establishment of NPPs because electricity demand is ever-increasing with a growing population and developing economy. For peaceful nuclear energy use, Turkey ratified the NPT in 1979 and has had a safeguards agreement, and its Additional Protocol since 2001. However, Turkey has not accumulated the essential nuclear knowledge and experience until now. The present nuclear education and training programmes are not focused on nuclear safety and power technology. There is lack of competencies concerned with measuring and monitoring, instrumentation and control for a safe operation of a reactor, and other specific nuclear equipment and facilities on site. The urgent needs should be determined to commence a competency based education in which the younger generations will instill confidence to nuclear technology. In nuclear training and education programs, it should be given a priority to nuclear safety and security culture. This should be a key requirement for newcomers to nuclear technology. In this presentation, the present status of nuclear science education in Turkey is discussed briefly and the fundamental arguments are dealt to focus on competency based nuclear education. Within international community, Turkey can seek collaborations and can consider the new challenges to tackle with the present difficulties in nuclear education programmes as a newcomer country. (author

  6. Plan for ecumenical hearing on the risks and potentialities of the further expansion of nuclear power programmes

    International Nuclear Information System (INIS)

    Francis, J.M.; Abrecht, P.

    1976-01-01

    The basis of the Hearing, initiated by the World Council of Churches, is explained. Some countries are planning a rapid development of nuclear power, but others are reluctant to follow this line. An outline is presented of the divergent views: those against refer to the political, social and technical problems which are being left with future generations (management of obsolete reactor systems, storage of radioactive wastes); restriction on free discussion on grounds of national security; need for international safeguards; economic questions; environmental impact; plutonium hazard of breeder reactors. Those for nuclear power argue that there is no obvious alternative way of meeting the world's power demands. Intermediate views are also presented. The Hearing received position papers prepared by specialists on the various aspects of the subject. The Hearing Group held a meeting at Sigtuna, Sweden, June 24 to 29, 1975. The text of the document they prepared and the position papers, are presented as separate papers in the present series. (U.K.)

  7. The Design and Implementation of Test System Based on Programmable Excitation Power Supply for Mining Comprehensive Protector

    Directory of Open Access Journals (Sweden)

    Zhi-jie Zhang

    2013-11-01

    Full Text Available As comprehensive protectors for coal mining (referred to comprehensive protectors in use are prone to fail, it can timely screen out the invalid comprehensive protector by periodic functional test when it is used (it is called test in use to ensure the production safety. The test in use needs the specialized test equipment, which is not used in delivery inspection by the manufacturers of comprehensive protectors. Thus, testing excitation power becomes a constraint for the improvement of the accuracy of test in use and the degree of automation. To solve the problem, this paper developed a power frequency programmed input-output testing excitation power supply, and on that basis it also realized the mining comprehensive protector test system in use with the excitation circuit and voltage program-controlled output.

  8. 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

  9. 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.

  10. Analysis of replies to an IAEA questionnaire on procedures for accreditation of training programmes and for authorization and licensing of nuclear power plant operations personnel

    International Nuclear Information System (INIS)

    1991-06-01

    The intent of this survey was to gather data and present results to facilitate the international exchange of information and experience in this field. This was accomplished using a questionnaire developed by the IAEA that was sent in September, 1989 to the thirty-one Member States having nuclear power plants operating or under construction. Of these, twenty-one responses were received. The questionnaire was constructed in two parts: (1) Accreditation of Training Programmes; and (2) Authorization and (Formal) Licensing of Operations Personnel. The analysis was conducted by IAEA staff with the assistance of consultants and resulted in an identification of the commonalities and differences in approach on these issues. An advisory group subsequently considered this analysis, interpreted the results relative to the original responses, and reached conclusions that are contained in this document

  11. Contribution of IAEA, FNRBA and ANNuR as Networking in Developing and Maintaining Capacity Building for a nuclear power programme: Comparative study

    International Nuclear Information System (INIS)

    Osman, Omer E.

    2014-01-01

    It is increasingly recognised that the mobilization and exchange of knowledge between different sectors (such as academia, policymakers, Regulators and practitioners) and regions or global can be of paramount importance in the field of Capacity Building for a nuclear power programme. As a result, the number of knowledge networks in this field has risen dramatically in recent years. Some of these networks bring together actors within a specific region, such as European Nuclear Safety Regulators Group (ENSREG), Western European Nuclear Regulators Association (WENRA), The Arab Network of Nuclear Regulators (ANNuR). Still others cover entire continents such as Asian Nuclear Safety Network (ANSN), Asia Pacific Safeguards Network (APSN) and Forum of Nuclear Regulatory Bodies in Africa (FNRBA). Or even operate worldwide and globally, like IAEA Special Support Services, Global Nuclear Safety and Security Network (GNSSN), World Organization of Nuclear Operators (WANO) and International Nuclear Regulators Association (INRA)

  12. Britain`s privatisation programme between government and powerful pressure groups; La privatizzazione inglese tra gruppi di pressione e forze politiche

    Energy Technology Data Exchange (ETDEWEB)

    Robinson, C [Institute of Economic Affairs, London (United Kingdom)

    1998-09-01

    There is an apparent paradox in Britain`s privatisation programme. It was carried out by an administration which proclaimed the virtues of market liberalisation, but its main feature was the ownership transfer, not liberalisation. The privatisation schemes, determined by the interplay between government and powerful pressure groups, are now leading to consequences in utility markets with some dangers of re-politicisation. [Italiano] Vi e` un evidente paradosso nella privatizzazione inglese: portata avanti da un`amministrazione che proclamava le virtu` del libero mercato, la sua principale caratteristica e` stata il cambiamento di proprieta`, non la liberalizzazione. Le modalita` della privatizzazione, determinate dall`interagire del governo con potenti gruppi di pressione, stanno ora ripercuotendosi sui mercati delle utility, con il pericolo di una loro ri-politicizzazione.

  13. Activity determination for neutron dosimetry in the vigilance programme for the pressure vessel in Atucha I nuclear power plant

    International Nuclear Information System (INIS)

    Furnari, J.C.; Cohen, I.M.; Ciriani, D.F.; Helzel Garcia, J.

    1993-01-01

    The methodologies for the activity determination of Co-60, Nb-93m and Nb-94 in flux monitors are presented. This was done in order to evaluate dose and damage caused by radiation received by pressure vessel materials of the Atucha I nuclear power plant for its surveillance program. (author)

  14. Power to change: Analysis of household participation in a renewable energy and energy efficiency programme in Central Australia

    International Nuclear Information System (INIS)

    Havas, Lisa; Ballweg, Julie; Penna, Chris; Race, Digby

    2015-01-01

    The Australian government funded a national Solar City program (2008–2013) to support communities to increase adoption of energy efficiency measures and renewable energy technology. One community was Alice Springs, a town with about 9000 households in the geographic centre of Australia. The programme offered a package of support: free energy audits, discounts for the purchase of renewable energy technology and energy efficiency measures, and ongoing information. Households that adopted solar hot water and photovoltaic systems reduced their electricity usage immediately after adoption by 10% and 34% respectively, and this was maintained in the long term. A small rebound effect of 15% was observed in the photovoltaic adopters. It was observed that, on average, households that adopted only energy efficiency measures did not have a significant reduction in their electricity usage over the long term. However, consistent with expectations, this study did show that there was a significant correlation between the number of energy efficiency measures adopted and the greatest household reduction in electricity usage. These contrary results indicate that there are additional factors involved. The connection between the effective use of measures, coincident behavioural change or increased energy awareness and greater energy reduction is discussed. - Highlights: • Households adopting solar hot water systems reduced total electricity usage by 10%. • Households adopting photovoltaic systems reduced total electricity usage by 34%. • 15% rebound effect in electricity usage by adopters of photovoltaic systems. • Excluding renewable energy no significant reduction in average electricity use.

  15. 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.

  16. 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....

  17. Technology programme

    International Nuclear Information System (INIS)

    2007-01-01

    The technology activities carried out by the EURATOM-ENEA Association concern the continuation of the European Fusion Development Agreement (EFDA) as well as the ITER activities coordinated by the ITER International Office and Fusion for Energy. Also included in the activities are design and RD under the Broader Approach Agreement between the EU and Japan. In order to better contribute to the programme a number of consortium agreements among the Associations are being signed. Collaboration with industries in view of their participation in the construction of ITER was further strengthened, mainly in the field of magnet and divertor components. The new European Test Blanket Facility at ENEA Brasimone was completed; the design of the ITER radial neutron camera was optimised and the performance achievable with the in-vessel viewing system was further assessed by experimental trials. Design activities for the JT-60SA magnet and power supply system as well as the design and experimental activities related to the target of the International Fusion Materials Irradiation Facility were continued. Significant work was done to define quality assurance for neutronics analyses. Mockups of the ITER pre-compression ring made in glass fibre epoxy were tested. The activities and results documented in the following illustrate ENEA's efforts to support fusion development

  18. No ''all clear'' signal yet. Although the West has set up support programmes for nuclear power plants in eastern Europe

    International Nuclear Information System (INIS)

    Roehrlich, D.

    1996-01-01

    During the first years after the catastrophic nuclear accident at Chernobyl, reports on Soviet nuclear power plants leaking to the west seldom contained hard facts. Now, after five years of a partnership between east and west in matters of reactor safety, things are clearer. What the commitment of the west to more reactor safety in eastern Europe means in practice was the subject of the winter meeting of the Deutsches Atomforum, Bonn. (orig.) [de

  19. 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)

  20. Safe and economic performance of nuclear power plant. Operation through meticulous Q/A programmes - a german example

    International Nuclear Information System (INIS)

    Schenk, H.J.

    1989-01-01

    Safe and reliable operation of a nuclear power plant over its life time of 40 to 60 years is the essential condition for an economic performance. This goal can be achieved by a qualified responsible staff realizing a high quality of operation and by maintaining high quality and technical standards in the plant in accordance with the status of science and technology. Quality assurance procedures have to verify this in detail, in close contact with the work to be performed. In this presentation I would like to describe our approach in Philippsburg to cope with this task

  1. Analysis of the potential of small hydro-power installations - Preliminary study on hydro-power schemes on rivers; Programm Kleinwasserkraftwerke. Potenzialanalyse Kleinwasserkraftwerke - Vorstudie zu Kraftwerken an Fliessgewaessern

    Energy Technology Data Exchange (ETDEWEB)

    Baur, M.; Dettli, R. [econcept AG, Zuerich (Switzerland); Weingartner, R.; Viviroli, D.; Imhof, P.; Faessler, M.; Gerhardinger, H. [University of Berne, Geographisches Institut, Gruppe fuer Hydrologie (GIUB), Berne (Switzerland)

    2006-07-01

    This final report for the Swiss Federal Office of Energy (SFOE) presents the results obtained from an analysis of the potential of small hydro-power installations in Switzerland. The current situation is reviewed and a 'bottom-up' analysis of the potential available is made. Data is presented on the potential of installations with power-ratings above and below 300 kW. Cantonal case-studies are examined. In a further 'top-down' examination, flow-rates and height-differences are looked at. The development of a 'potential-map' for Switzerland is described. The report is completed with the presentation of the conclusions made from the work. Suggestions for further work that could be done on the subject are made.

  2. 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, ...

  3. 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, ...

  4. 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)

  5. 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)

  6. 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)

  7. 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.)

  8. Guidelines for the review of accident management programmes in nuclear power plants. Reference document for the IAEA safety service missions on review of accident management programmes in nuclear power plants

    International Nuclear Information System (INIS)

    2003-01-01

    Similarly as for other IAEA safety services, the objectives of accident management safety service are to assist the Member States in ensuring and enhancing the safety of NPPs. In particular, the objective is to assist at the utility and NPP (i.e. licensee) level in effective plant specific AMP preparation, development and implementation. However, assistance can also be provided to the regulatory body in its reviewing of AMPs. Objectives of the safety service can be summarized as follows: To explain to licensee personnel principles and possible approaches in effective implementation of AMP based on experience world-wide; To give opportunities to experts from the host plant to broaden their experience and knowledge in the field; To perform an objective assessment of the status in various phases of AMP implementation, compared with international experience and practices; To provide the licensee with suggestions and assistance for improvements in various stages of AMP implementation. The objective of the IAEA safety services is to offer two options to respond to individual requirements. These options include missions to review accident analysis needed for accident management and missions to review the whole AMP. Review of accident analysis for accident management (RAAAM): this review is intended to check completeness and quality of accident analysis covering BDBA and severe accidents. The review should be typically performed prior to use of accident analysis for development of AMP. It is considered that 2 experts and 1 IAEA team leader in one-week mission can perform the review. Detailed guidelines for review of analysis are provided in Section 2. Reference is also made to another IAEA Safety Report (Safety Standards Series No. NS-R-1) which is devoted to guidance for accident analysis of nuclear power plants (NPPs). Review of AMP (RAMP): this review of AMP, which is in particular appropriate prior to its implementation, is intended to check its quality, consistency

  9. Human reliability analysis in probabilistic safety assessment for nuclear power plants. A Safety Practice. A publication within the NUSS programme

    International Nuclear Information System (INIS)

    1995-01-01

    Probabilistic safety assessment (PSA) is playing an increasingly important role in the safe operation of nuclear power plants throughout the world. In order to establish a consistent framework for conducting PSA studies, for promoting technology transfer of the state of the art, and for encouraging uniformity in the way PSA is carried out, the IAEA is preparing a set of publications which gives guidance on various aspects of PSA. This document presents a practical approach for incorporating human reliability analysis (HRA) into PSA. It describes the steps needed and the documentation that should be provided both to support the PSA itself and to ensure effective communication of important information arising from the studies. It also describes a framework for analysing those human actions which could affect safety and for relating such human influences to specific parts of a PSA. This Safety Practice also addresses the limitations of PSA in taking account of human factors in relation to safety and risk. Refs, figs and tabs

  10. Design of 50 MWe HTR-PBMR reactor core and nuclear power plant fuel using SRAC2006 programme

    International Nuclear Information System (INIS)

    Bima Caraka Putra; Yosaphat Sumardi; Yohannes Sardjono

    2014-01-01

    This research aims to assess the design of core and fuel of nuclear power plant type High Temperature Reactor-Pebble Bed Modular Reactor 50 MWe from the Beginning of Life (BOL) to Ending of life (EOL) with eight years operating life. The parameters that need to be analyzed in this research are the temperature distribution inside the core, quantity enrichment of U 235 , fuel composition, criticality, and temperature reactivity coefficient of the core. The research was conducted with a data set of core design parameters such as nuclides density, core and fuel dimensions, and the axial temperature distribution inside the core. Using SRAC2006 program package, the effective multiplication factor (k eff ) values obtained from the input data that has been prepared. The results show the value of the criticality of core is proportional to the addition of U 235 enrichment. The optimum enrichment obtained at 10.125% without the use of burnable poison with an excess reactivity of 3.1 2% at BOL. The addition Gd 2O3 obtained an optimum value of 12 ppm burnable poison with an excess reactivity 0.38 %. The use of Er 2O3 with an optimum value 290 ppm has an excess reactivity 1.24 % at BOL. The core temperature reactivity coefficient with and without the use of burnable poison has a negative values that indicates the nature of its inherent safety. (author)

  11. 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.)

  12. Open Pit Optimisation and Design: A Stepwise Approach*

    African Journals Online (AJOL)

    Michael

    2015-12-02

    Dec 2, 2015 ... The erstwhile Nkroful Mining Limited (NML) had a concession with an approximate area of 47.84 km2 ... exploration drilling programme executed by NML ..... Strategic Planning ... the Nkroful Gold Mining Project, Western.

  13. Fire hazard analysis for WWER nuclear power plants. Report of the IAEA extrabudgetary programme on the safety of WWER nuclear power plants

    International Nuclear Information System (INIS)

    1994-12-01

    This status report presents an overview of the different techniques available to carry out a fire hazard analysis, from qualitative criteria to quantitative methodologies of different purposes and basis; and then, it details a simplified methodology based on a screening approach which could be used in former Soviet designed nuclear power plants. The methodology presented in this report is an adequate means to identify fire related plant specific vulnerabilities to severe accidents, and it provides a useful tool for ranking the various plant fires according to their significances, as well as technical basis for prioritizing the implementation of plant improvements. The applicability of the methodology proposed to the former Soviet Union designed reactors has been evaluated. Its usefulness to the purpose defined above is conclusive. However, some aspects need further consideration, among others data sources and screening criteria. Computer codes for studying fire effects and fire spread in plant locations are also dealt with. Some computer codes are shortly described, from simplified models to more complex ones which allow more accurate modelling of geometries and accounting for additional phenomena. 10 refs, 5 tabs

  14. Safety assessment of proposed modifications of Ignalina nuclear power plant. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1995-09-01

    The objective of the meeting was to further discuss previous findings and recommendations and their application to the particular situation of the Ignalina NPP. Since design information and a series of proposed modifications for INPP had been prepared by the main RBMK designer, Research and Development Institute for Power Engineering (RDIPE), it was considered appropriate to conduct the meeting in two parts, the first from 17 to 22 October 1994, at RDIPE headquarters in Moscow and the second from 24 to 28 October 1994, at the plant site in Lithuania. Twelve international experts and IAEA staff participated in the meetings, together with a large group of RDIPE specialists and plant staff. The review covered five topical areas: core monitoring and control; pressure boundary integrity; accident migration; safety and support systems and instrumentation and control. A summary of the reviews in each technical areas is given in this report. Appendices 1 and 5 present the records of the reviews and detailed findings and recommendations in each topical area. The experts strongly supported the effort to develop a new extended safety analysis report. They also stressed the need for close monitoring of the fuel channel conditions and the need for an integrated approach for the upgrading of the control and safety systems. Refs, figs, tabs

  15. Crispv programme

    International Nuclear Information System (INIS)

    Marinkovicj, N.

    CRISPV (Criticality and Spectrum code) is a multigroup neutron spectrum code for homogeneous reactor cores and is actually a somewhat modified version of the original CRISP programme. It is a combination of DATAPREP-II and BIGG-II programmes. It is assumed that the reactor cell is a cylindrical fuel rod in the light or heavy water moderator. DATEPREP-II CODE forms the multigroup data for homogeneous reactor and prepares the input parameters for the BIGG-II code. It has its own nuclear data library on a separate tape in binary mode. BIGG-II code is a multigroup neutron spectrum and criticality code for a homogenized medium. It has as well its own separate data library. In the CRISPV programme the overlay structure enables automatic handling of data calculated in the DATAPREP-II programme and needed in the BIGG-II core. Both programmes are written in FORTRAN for CDC 3600. Using the programme is very efficient and simple

  16. WWER-1000 steam generator integrity. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1997-07-01

    Programme was initiated by IAEA in 1990 with the aim to assist the countries of Central and Eastern Europe and former Soviet Union in evaluating the safety of their first generation WWER-440/230 nuclear power plants. The main objectives were: to identify major design and operational safety issues; to establish international consensus on priorities for safety improvements; and to provide assistance in the review of the competence and and adequacy of safety improvement programs. The scope was extended in 1992 ro include RBMK, WWER-440/312 and WWER-1000 plants in operation and under construction. Based on the operational experience of more than 90 reactor years of WWER-1000 NPPs having 80 steam generators in operation or under construction the steam generator integrity was recognized as an important issue of high safety concern. The purpose of this report is to integrate available information on the issue of WWER-1000 steam generator integrity with the focus on the steam generator cold collector damage in particular. This information covers the status of stem generators at operating plants, cause analysis of collector cracking, the damage mechanisms involved, operational aspects and corrective measures developed and implemented. Consideration is given to material, design and fabrication related aspects, operational conditions, system solutions, and in-service inspection. Detailed conclusions and recommendations are provided for each of these aspects

  17. Design verification enhancement of field programmable gate array-based safety-critical I&C system of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Ahmed, Ibrahim [Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do 17104 (Korea, Republic of); Jung, Jaecheon, E-mail: jcjung@kings.ac.kr [Department of Nuclear Power Plant Engineering, KEPCO International Nuclear Graduate School, 658-91 Haemaji-ro, Seosang-myeon, Ulju-gun, Ulsan 45014 (Korea, Republic of); Heo, Gyunyoung [Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do 17104 (Korea, Republic of)

    2017-06-15

    Highlights: • An enhanced, systematic and integrated design verification approach is proposed for V&V of FPGA-based I&C system of NPP. • RPS bistable fixed setpoint trip algorithm is designed, analyzed, verified and discussed using the proposed approaches. • The application of integrated verification approach simultaneously verified the entire design modules. • The applicability of the proposed V&V facilitated the design verification processes. - Abstract: Safety-critical instrumentation and control (I&C) system in nuclear power plant (NPP) implemented on programmable logic controllers (PLCs) plays a vital role in safe operation of the plant. The challenges such as fast obsolescence, the vulnerability to cyber-attack, and other related issues of software systems have currently led to the consideration of field programmable gate arrays (FPGAs) as an alternative to PLCs because of their advantages and hardware related benefits. However, safety analysis for FPGA-based I&C systems, and verification and validation (V&V) assessments still remain important issues to be resolved, which are now become a global research point of interests. In this work, we proposed a systematic design and verification strategies from start to ready-to-use in form of model-based approaches for FPGA-based reactor protection system (RPS) that can lead to the enhancement of the design verification and validation processes. The proposed methodology stages are requirement analysis, enhanced functional flow block diagram (EFFBD) models, finite state machine with data path (FSMD) models, hardware description language (HDL) code development, and design verifications. The design verification stage includes unit test – Very high speed integrated circuit Hardware Description Language (VHDL) test and modified condition decision coverage (MC/DC) test, module test – MATLAB/Simulink Co-simulation test, and integration test – FPGA hardware test beds. To prove the adequacy of the proposed

  18. Design verification enhancement of field programmable gate array-based safety-critical I&C system of nuclear power plant

    International Nuclear Information System (INIS)

    Ahmed, Ibrahim; Jung, Jaecheon; Heo, Gyunyoung

    2017-01-01

    Highlights: • An enhanced, systematic and integrated design verification approach is proposed for V&V of FPGA-based I&C system of NPP. • RPS bistable fixed setpoint trip algorithm is designed, analyzed, verified and discussed using the proposed approaches. • The application of integrated verification approach simultaneously verified the entire design modules. • The applicability of the proposed V&V facilitated the design verification processes. - Abstract: Safety-critical instrumentation and control (I&C) system in nuclear power plant (NPP) implemented on programmable logic controllers (PLCs) plays a vital role in safe operation of the plant. The challenges such as fast obsolescence, the vulnerability to cyber-attack, and other related issues of software systems have currently led to the consideration of field programmable gate arrays (FPGAs) as an alternative to PLCs because of their advantages and hardware related benefits. However, safety analysis for FPGA-based I&C systems, and verification and validation (V&V) assessments still remain important issues to be resolved, which are now become a global research point of interests. In this work, we proposed a systematic design and verification strategies from start to ready-to-use in form of model-based approaches for FPGA-based reactor protection system (RPS) that can lead to the enhancement of the design verification and validation processes. The proposed methodology stages are requirement analysis, enhanced functional flow block diagram (EFFBD) models, finite state machine with data path (FSMD) models, hardware description language (HDL) code development, and design verifications. The design verification stage includes unit test – Very high speed integrated circuit Hardware Description Language (VHDL) test and modified condition decision coverage (MC/DC) test, module test – MATLAB/Simulink Co-simulation test, and integration test – FPGA hardware test beds. To prove the adequacy of the proposed

  19. Better Care Teams: A Stepwise Skill Reinforcement Model.

    Science.gov (United States)

    Christopher, Beth-Anne; Grantner, Mary; Coke, Lola A; Wideman, Marilyn; Kwakwa, Francis

    2016-06-01

    The Building Healthy Urban Communities initiative presents a path for organizations partnering to improve patient outcomes with continuing education (CE) as a key component. Components of the CE initiative included traditional CE delivery formats with an essential element of adaptability and new methods, with rigorous evaluation over time that included evaluation prior to the course, immediately following the CE session, 6 to 8 weeks after the CE session, and then subsequent monthly "testlets." Outcome measures were designed to allow for ongoing adaptation of content, reinforcement of key learning objectives, and use of innovative concordant testing and retrieval practice techniques. The results after 1 year of programming suggest the stepwise skill reinforcement model is effective for learning and is an efficient use of financial and human resources. More important, its design is one that could be adopted at low cost by organizations willing to work in close partnership. J Contin Educ Nurs. 2016;47(6):283-288. Copyright 2016, SLACK Incorporated.

  20. Randomised controlled trial and economic analysis of an internet-based weight management programme: POWeR+ (Positive Online Weight Reduction).

    Science.gov (United States)

    Little, Paul; Stuart, Beth; Hobbs, Fd Richard; Kelly, Jo; Smith, Emily R; Bradbury, Katherine J; Hughes, Stephanie; Smith, Peter Wf; Moore, Michael V; Lean, Mike Ej; Margetts, Barrie M; Byrne, Christopher D; Griffin, Simon; Davoudianfar, Mina; Hooper, Julie; Yao, Guiqing; Zhu, Shihua; Raftery, James; Yardley, Lucy

    2017-01-01

    maintained nearly 3 kg of weight loss per person (mean weight per person: baseline, 104.4 kg; 6 months, 101.9 kg; 12 months, 101.7 kg). Compared with the control group, the estimated additional weight reduction with POWeR+F was 1.5 kg [95% confidence interval (CI) 0.6 to 2.4 kg; p  = 0.001] and with POWeR+R was 1.3 kg (95% CI 0.34 to 2.2 kg; p  = 0.007). By 12 months the mean weight loss was not statistically significantly different between groups, but 20.8% of control participants, 29.2% of POWeR+F participants (risk ratio 1.56, 95% CI 0.96 to 2.51; p  = 0.070) and 32.4% of POWeR+R participants (risk ratio 1.82, 95% CI 1.31 to 2.74; p  = 0.004) maintained a clinically significant 5% weight reduction. The POWeR+R group had fewer individuals who reported doing another activity to help lose weight [control, 47.1% (64/136); POWeR+F, 37.2% (51/137); POWeR+R, 26.7% (40/150)]. The incremental cost to the health service per kilogram weight lost, compared with the control group, was £18 (95% CI -£129 to £195) for POWeR+F and -£25 (95% CI -£268 to £157) for POWeR+R. The probability of being cost-effective at a threshold of £100 per kilogram was 88% and 98% for POWeR+F and POWeR+R, respectively. POWeR+R was dominant compared with the control group. No harms were reported and participants using POWeR+ felt more enabled in managing their weight. The qualitative studies documented that POWeR+ was viewed positively by patients and that health-care professionals generally enjoyed supporting patients using POWeR+. Maintenance of weight loss after 1 year is unknown. Identifying strategies for longer-term engagement, impact in community settings and increasing physical activity. Clinically valuable weight loss (> 5%) is maintained in 20% of individuals using novel written materials with brief follow-up. A web-based behavioural programme and brief support results in greater mean weight loss and 10% more participants maintain valuable weight loss; it

  1. 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.

  2. 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.

  3. Monitoring programme

    International Nuclear Information System (INIS)

    1994-06-01

    Her Majesty's Inspectorate of Pollution's 1992 report on its programme of monitoring radioactive substances is presented. Site operators' returns are verified and the report provides independent data on the environmental impact of authorized disposal of radioactive wastes. Radiation doses which may have been received by members of the public, fall well below the International Commission for Radiological Protection's (ICRP) recommended annual doses. (UK)

  4. 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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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

  5. 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.)

  6. 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.

  7. 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

  8. Stillbirth evaluation: a stepwise assessment of placental pathology and autopsy.

    Science.gov (United States)

    Miller, Emily S; Minturn, Lucy; Linn, Rebecca; Weese-Mayer, Debra E; Ernst, Linda M

    2016-01-01

    The American Congress of Obstetricians and Gynecologists places special emphasis on autopsy as one of the most important tests for evaluation of stillbirth. Despite a recommendation of an autopsy, many families will decline the autopsy based on religious/cultural beliefs, fear of additional suffering for the child, or belief that no additional information will be obtained or of value. Further, many obstetric providers express a myriad of barriers limiting their recommendation for a perinatal autopsy despite their understanding of its value. Consequently, perinatal autopsy rates have been declining. Without the information provided by an autopsy, many women are left with unanswered questions regarding cause of death for their fetus and without clear management strategies to reduce the risk of stillbirth in future pregnancies. To avoid this scenario, it is imperative that clinicians are knowledgeable about the benefit of autopsy so they can provide clear information on its diagnostic utility and decrease potential barriers; in so doing the obstetrician can ensure that each family has the necessary information to make an informed decision. We sought to quantify the contribution of placental pathologic examination and autopsy in identifying a cause of stillbirth and to identify how often clinical management is modified due to each result. This is a cohort study of all cases of stillbirth from 2009 through 2013 at a single tertiary care center. Records were reviewed in a stepwise manner: first the clinical history and laboratory results, then the placental pathologic evaluation, and finally the autopsy. At each step, a cause of death and the certainty of that etiology were coded. Clinical changes that would be recommended by information available at each step were also recorded. Among the 144 cases of stillbirth examined, 104 (72%) underwent autopsy and these cases constitute the cohort of study. The clinical and laboratory information alone identified a cause of death

  9. The Technical Training Programme for Nuclear Power Station Personnel; Programme de formation technique du personnel des centrales nucleaires; Programma tekhnicheskoj podgotovki personala yadernoj ehlektrostantsii; El programa de formacion tecnica del personal de una central nucleoelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Howey, G. R. [Hydro-Electric Power Commission of Ontario, Toronto, Ontario (Canada)

    1963-10-15

    Canada's Nuclear Power Demonstration station (NPD), initiated by the federal agency Atomic Energy of Canada Limited, is operated and staffed by the Hydro-Electric Power Commission of Ontario, a provincial public utility. Obtaining and training staff for the station was hampered by the fact that until recently most of Ontario's electricity requirements were supplied by the abundant hydro-electric resources of the province. Increasing use of thermal-electric energy since 1950 created an extreme shortage of staff experienced in the operation of thermal stations. To meet this situation, trained manpower for nuclear generating stations was developed by the following steps: (1) An initial group of professional engineers was selected from among persons with considerable experience in nuclear work, thermal stations and electrical operation; (2) Another group of highly experienced operators and maintainers was selected; (3) The selected groups were given a rigorous training programme involving operation of both nuclear and coal-fired stations, instruction from the designers of NPD and training in the classroom and on the job; and (4) A nuclear training centre was established to select and train additional staff, conduct formal examinations and be generally responsible for personnel quality standards. Independent examinations of personnel were conducted by the Atomic Energy Control Board, a separate federal regulatory agency. Five general categories of personnel are being developed: (1) Supervisors: professional engineers responsible for operation, maintenance and administrative supervision, rotated periodically to increase their versatility; (2) Operators: four levels of qualification depending on the requirements of the job; (3) Control maintainers: four levels of qualification, responsible for maintenance of all instruments, control equipment and electrical equipment; (4) Mechanical maintainers: various levels and combinations of skills (welding, machining, fitting, etc

  10. Stepwise development of hematopoietic stem cells from embryonic stem cells.

    Directory of Open Access Journals (Sweden)

    Kenji Matsumoto

    Full Text Available The cellular ontogeny of hematopoietic stem cells (HSCs remains poorly understood because their isolation from and their identification in early developing small embryos are difficult. We attempted to dissect early developmental stages of HSCs using an in vitro mouse embryonic stem cell (ESC differentiation system combined with inducible HOXB4 expression. Here we report the identification of pre-HSCs and an embryonic type of HSCs (embryonic HSCs as intermediate cells between ESCs and HSCs. Both pre-HSCs and embryonic HSCs were isolated by their c-Kit(+CD41(+CD45(- phenotype. Pre-HSCs did not engraft in irradiated adult mice. After co-culture with OP9 stromal cells and conditional expression of HOXB4, pre-HSCs gave rise to embryonic HSCs capable of engraftment and long-term reconstitution in irradiated adult mice. Blast colony assays revealed that most hemangioblast activity was detected apart from the pre-HSC population, implying the early divergence of pre-HSCs from hemangioblasts. Gene expression profiling suggests that a particular set of transcripts closely associated with adult HSCs is involved in the transition of pre-HSC to embryonic HSCs. We propose an HSC developmental model in which pre-HSCs and embryonic HSCs sequentially give rise to adult types of HSCs in a stepwise manner.

  11. Pathways of DNA unlinking: A story of stepwise simplification.

    Science.gov (United States)

    Stolz, Robert; Yoshida, Masaaki; Brasher, Reuben; Flanner, Michelle; Ishihara, Kai; Sherratt, David J; Shimokawa, Koya; Vazquez, Mariel

    2017-09-29

    In Escherichia coli DNA replication yields interlinked chromosomes. Controlling topological changes associated with replication and returning the newly replicated chromosomes to an unlinked monomeric state is essential to cell survival. In the absence of the topoisomerase topoIV, the site-specific recombination complex XerCD- dif-FtsK can remove replication links by local reconnection. We previously showed mathematically that there is a unique minimal pathway of unlinking replication links by reconnection while stepwise reducing the topological complexity. However, the possibility that reconnection preserves or increases topological complexity is biologically plausible. In this case, are there other unlinking pathways? Which is the most probable? We consider these questions in an analytical and numerical study of minimal unlinking pathways. We use a Markov Chain Monte Carlo algorithm with Multiple Markov Chain sampling to model local reconnection on 491 different substrate topologies, 166 knots and 325 links, and distinguish between pathways connecting a total of 881 different topologies. We conclude that the minimal pathway of unlinking replication links that was found under more stringent assumptions is the most probable. We also present exact results on unlinking a 6-crossing replication link. These results point to a general process of topology simplification by local reconnection, with applications going beyond DNA.

  12. 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

  13. Report of a consultants' meeting on insights from PSA results on the programmes for safety upgrading of WWER NPPs. Extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-11-01

    The objective of the meeting was to compare the insight from plant specific PSA studies with the safety upgrading programme of WWER NPPs. The PSAs were reviewed considering the scope, level and detail of PSA models and results of IAEA peer reviews. Safety improvements which are not normally included in PSAs were also considered. The review specifically considers for each plant specific PSA: the dominant initiating events and accident sequences contributing to core damage; and, the importance of systems, components and human actions to be used for prioritizing actions. 4 refs, tabs

  14. 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

  15. Safety issues and their ranking for 'small series' WWER-1000 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-09-01

    This report presents the safety issues in 'small series' WWER-1000 nuclear power plants (NPPs). Safety issues are deviations from current recognized safety practices in design and operation judged to be safety significant by their impact on the plants' defence in depth. This report is intended to serve as reference for the development of plant specific safety improvement programmes and for the evaluation of measures proposed and/or implemented. The identification of safety issues is based on safety studies conducted by the operators of 'small series' WWER-1000 units and by organizations dealing with these reactors, on findings of IAEA safety missions to 'small series' WWER-1000 plants in South Ukraine, at Novovoronezh and Kalinin, and on information obtained from specialists from various countries during an IAEA consultants meeting, 8-12 September 1997 in Vienna, within the framework of the Extra budgetary Programme on the Safety of WWER and RBMK NPPs. Safety issues are first presented according to their impact on the main safety functions and are then described individually. The safety issues are characterized by issue title and specified by issue clarification. Safety issues connected with plant design are followed by the ranking of the issue and ranking justification. Altogether 85 safety issues have been identified, 12 of which are in Category III (defence in depth is insufficient, immediate corrective action is necessary), 38 in Category 11 (defence in depth is degraded, action is needed to resolve the issue) and 22 in Category I (departure from international practices, to be addressed as part of actions to resolve higher priority issues). In the case of operational safety issues (13 safety issues) no ranking is provided as the available material was considered insufficient. For each safety issue, comments and recommendations are made by the IAEA; the status of corresponding measures to improve safety implemented or planned at each site are presented in the

  16. Safety issues and their ranking for 'small series' WWER-1000 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    2000-09-01

    This report presents the safety issues in 'small series' WWER-1000 nuclear power plants (NPPs). Safety issues are deviations from current recognized safety practices in design and operation judged to be safety significant by their impact on the plants' defence in depth. This report is intended to serve as reference for the development of plant specific safety improvement programmes and for the evaluation of measures proposed and/or implemented. The identification of safety issues is based on safety studies conducted by the operators of 'small series' WWER-1000 units and by organizations dealing with these reactors, on findings of IAEA safety missions to 'small series' WWER-1000 plants in South Ukraine, at Novovoronezh and Kalinin, and on information obtained from specialists from various countries during an IAEA consultants meeting, 8-12 September 1997 in Vienna, within the framework of the Extra budgetary Programme on the Safety of WWER and RBMK NPPs. Safety issues are first presented according to their impact on the main safety functions and are then described individually. The safety issues are characterized by issue title and specified by issue clarification. Safety issues connected with plant design are followed by the ranking of the issue and ranking justification. Altogether 85 safety issues have been identified, 12 of which are in Category III (defence in depth is insufficient, immediate corrective action is necessary), 38 in Category 11 (defence in depth is degraded, action is needed to resolve the issue) and 22 in Category I (departure from international practices, to be addressed as part of actions to resolve higher priority issues). In the case of operational safety issues (13 safety issues) no ranking is provided as the available material was considered insufficient. For each safety issue, comments and recommendations are made by the IAEA; the status of corresponding measures to improve safety implemented or planned at each site are presented in the

  17. 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…

  18. 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

  19. A stepwise procedure for science communication in the field

    Science.gov (United States)

    Nisancioglu, Kerim; Paasche, Øyvind

    2017-04-01

    Communicating and disseminating earth science to laypersons, high-school students and their teachers are becoming increasingly important considering the overwhelming impact human civilization have on the planet. One of the main challenges with this type of dissemination arises from the cross-disciplinary nature of the Earth system as it encompasses anything from cloud physics to the geological evidence of ice ages being played out on millennial time scales. During the last four years we have tested and developed an approach referred to as «Turspor» which can be translated to 'Trail Tracks'. The ambition with "Turspor" is to inspire participants to seek in-depth knowledge relating to observations of features made in the field (glacial moraines, active permafrost, clouds, winds and so forth) as we have come to learn that observations made in the field enhances students capability to grasp the bare essentials related to the phenomena in question. By engaging master and PhD students in the process we create a platform where students can improve their teaching and communicative skills through a stepwise procedure. The initial concept was tested on 35 high school students during the summer of 2012 in the mountainous area of Snøheim on Dovre, Southern Norway. Before the arrival of the high school students, the university students prepared one page written summaries describing relevant geological or meteorological features and trained on how to best disseminate a basic scientific understanding of these. Specific examples were patterned ground caused by permafrost, glacier flour, katabatic winds, and equilibrium line altitude of glaciers. Based on the success of the program over the past 4 years with field trips together with local schools, we are in the process of developing the concept to be offered as a course at the master and PhD level, including a week of training in didactics applied to topics in the geosciences as well as practical training in the field. The

  20. 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)

  1. Stepwise multi-criteria optimization for robotic radiosurgery

    International Nuclear Information System (INIS)

    Schlaefer, A.; Schweikard, A.

    2008-01-01

    Achieving good conformality and a steep dose gradient around the target volume remains a key aspect of radiosurgery. Clearly, this involves a trade-off between target coverage, conformality of the dose distribution, and sparing of critical structures. Yet, image guidance and robotic beam placement have extended highly conformal dose delivery to extracranial and moving targets. Therefore, the multi-criteria nature of the optimization problem becomes even more apparent, as multiple conflicting clinical goals need to be considered coordinate to obtain an optimal treatment plan. Typically, planning for robotic radiosurgery is based on constrained optimization, namely linear programming. An extension of that approach is presented, such that each of the clinical goals can be addressed separately and in any sequential order. For a set of common clinical goals the mapping to a mathematical objective and a corresponding constraint is defined. The trade-off among the clinical goals is explored by modifying the constraints and optimizing a simple objective, while retaining feasibility of the solution. Moreover, it becomes immediately obvious whether a desired goal can be achieved and where a trade-off is possible. No importance factors or predefined prioritizations of clinical goals are necessary. The presented framework forms the basis for interactive and automated planning procedures. It is demonstrated for a sample case that the linear programming formulation is suitable to search for a clinically optimal treatment, and that the optimization steps can be performed quickly to establish that a Pareto-efficient solution has been found. Furthermore, it is demonstrated how the stepwise approach is preferable compared to modifying importance factors

  2. Traumatic eye ball luxation: A stepwise approach to globe salvage

    Directory of Open Access Journals (Sweden)

    Himika Gupta

    2017-10-01

    Full Text Available Craniofacial trauma is often associated with orbital and ocular injuries. We report a case of a 21-year-old male with motor vehicular accident, orbital roof blow-in fracture, cerebrospinal fluid (CSF leak, and left sided globe luxation with corneal abrasion and complete conjunctival denuding. The patient was managed by a multispeciality team and the eyeball was protected by amniotic membrane graft (AMG biological dressing with novel use of inverted sterile metallic bowl as mechanical protection till the patient stabilized. During surgery, eyeball was reposited and ocular surface was reconstructed using amniotic membrane and symblepharon ring. Surgical correction and plating of the facial fractures and dural repair with autologus tensor fascia lata was done. Post surgery ocular surface was intact, ocular motility was well preserved and the globe was prephthisical. Traumatic eyeball luxation is a rare, but dramatic presentation which may occur in a blow in fracture when the intra orbital volume reduces and expels the eye ball out of the socket. This may be associated with extra ocular muscle rupture or optic nerve avulsion. The visual prognosis is nil in majority cases. However, the management is targeted towards globe preservation in view of psychological benefit and ease of cosmetic or prosthetic rehabilitation. Knowing the mechanism of luxation helps to plan the management. A stepwise approach for globe salvage is recommended. Team efforts to take care of various morbidities with special steps to safeguard the eye help to optimize outcomes. Keywords: Traumatic eyeball luxation, Blow in orbital fractures, Amniotic membrane graft for ocular surface, Globe reposition

  3. TKS-2006. Nuclear waste management of the Olkiluoto and Loviisa power plants: Programme for research, development and technical design for 2007-2009

    International Nuclear Information System (INIS)

    2006-11-01

    The report at hand describes the status and near-term future plans of the research and technology development (RTD) for the nuclear waste management of the Olkiluoto and Loviisa nuclear power plants. Since the facilities for the management and disposal of low- and intermediate-level wastes have already been built and are in operation, and the decommissioning of the nuclear power plant will only take place far away in the future, the emphasis of this report is on the RTD related to the disposal of spent fuel. For the RTD programme on spent fuel disposal the report is also a part of the interim reporting proposed by the Finnish Radiation and Nuclear Safety Authority (STUK) in the early 2000's. Other reports related to the interim reporting include the updated facility description and the separate reports on the expected evolution of the spent fuel repository, the summary of the biosphere studies and the updated site description ('Site 2006'). Pursuant to the guidelines given by the Ministry of Trade and Industry (KTM) Posiva aims at submission of the application of the construction license for the disposal facility by the end of the year 2012. By the end of 2009 Posiva will present an outline of the whole documentation intended for the application. In practice this requires that the components of the disposal system are specified in sufficient detail for the actual implementation. Accordingly, the principal goals of the next three-year period 2007 - 2009 will be: to define the performance goals for the main components of the disposal system in a way that the system as a whole fulfils the safety requirements set for disposal, and to demonstrate that these requirements can be met by the technology available. The report reviews the present status of the performance goals for the main components. For most main components (release barriers) the principal performance goals have already been defined and their feasibility has been demonstrated. The encapsulation technology

  4. NPP financial and regulatory risks-Importance of a balanced and comprehensive nuclear law for a newcomer country considering nuclear power programme

    Science.gov (United States)

    Manan, J. A. N. Abd; Mostafa, N. A.; Salim, M. F.

    2015-04-01

    understanding of various requirements of public, regulators, investors, financial institutions, international community, operator and other important stakeholders. Ambiguities and uncertainties, especially with regards to certain conditions and requirements should be minimised by emulating good practices of experienced nuclear regulators. The imposition of various financial requirements such as funds for decommissioning, radioactive waste management, financial security, nuclear liabilities and licensing fees are necessary, but at the same time the quantum needs to be clearly defined. Concerns on absolute liability of the operators need to be addressed through a creation of necessary and proper nuclear insurance legislations to mitigate operator S nuclear liability obligations and other financial risks. Another major risk to investors is the possibility of public resistance which will not only can hinder the construction but can also stop operation of the nuclear power plant which will contribute to huge losses to investors and countries. This may require a provision in the legislation that provide proper compensation for these situations and at the same time to allow operators to engage in nuclear promotional activities, such as community benefit and public consultation as voluntary initiatives. Through proper planning, research, consultation and execution, the proposed nuclear law shall be able to promote good regulatory practices for public and investors' confidence and benefit. Early involvement of various stakeholders is essential as a platform for regular communications between regulators and interested parties. Stakeholders' participation in the NPP programme and law developments will also promote transparency of the projects while upholding the independency of the regulators.

  5. NPP financial and regulatory risks-Importance of a balanced and comprehensive nuclear law for a newcomer country considering nuclear power programme

    International Nuclear Information System (INIS)

    Manan, J. A. N. Abd; Mostafa, N. A.; Salim, M. F.

    2015-01-01

    understanding of various requirements of public, regulators, investors, financial institutions, international community, operator and other important stakeholders. Ambiguities and uncertainties, especially with regards to certain conditions and requirements should be minimised by emulating good practices of experienced nuclear regulators. The imposition of various financial requirements such as funds for decommissioning, radioactive waste management, financial security, nuclear liabilities and licensing fees are necessary, but at the same time the quantum needs to be clearly defined. Concerns on absolute liability of the operators need to be addressed through a creation of necessary and proper nuclear insurance legislations to mitigate operator S nuclear liability obligations and other financial risks. Another major risk to investors is the possibility of public resistance which will not only can hinder the construction but can also stop operation of the nuclear power plant which will contribute to huge losses to investors and countries. This may require a provision in the legislation that provide proper compensation for these situations and at the same time to allow operators to engage in nuclear promotional activities, such as community benefit and public consultation as voluntary initiatives. Through proper planning, research, consultation and execution, the proposed nuclear law shall be able to promote good regulatory practices for public and investors’ confidence and benefit. Early involvement of various stakeholders is essential as a platform for regular communications between regulators and interested parties. Stakeholders’ participation in the NPP programme and law developments will also promote transparency of the projects while upholding the independency of the regulators

  6. NPP financial and regulatory risks-Importance of a balanced and comprehensive nuclear law for a newcomer country considering nuclear power programme

    Energy Technology Data Exchange (ETDEWEB)

    Manan, J. A. N. Abd, E-mail: jamalan@tnb.com.my; Mostafa, N. A.; Salim, M. F. [Nuclear Energy Department, Planning Division, Tenaga Nasional Berhad Level 32, Dua Sentral, No. 8 Jalan Tun Sambanthan, 50470 Brickfields, Kuala Lumpur (Malaysia)

    2015-04-29

    understanding of various requirements of public, regulators, investors, financial institutions, international community, operator and other important stakeholders. Ambiguities and uncertainties, especially with regards to certain conditions and requirements should be minimised by emulating good practices of experienced nuclear regulators. The imposition of various financial requirements such as funds for decommissioning, radioactive waste management, financial security, nuclear liabilities and licensing fees are necessary, but at the same time the quantum needs to be clearly defined. Concerns on absolute liability of the operators need to be addressed through a creation of necessary and proper nuclear insurance legislations to mitigate operator S nuclear liability obligations and other financial risks. Another major risk to investors is the possibility of public resistance which will not only can hinder the construction but can also stop operation of the nuclear power plant which will contribute to huge losses to investors and countries. This may require a provision in the legislation that provide proper compensation for these situations and at the same time to allow operators to engage in nuclear promotional activities, such as community benefit and public consultation as voluntary initiatives. Through proper planning, research, consultation and execution, the proposed nuclear law shall be able to promote good regulatory practices for public and investors’ confidence and benefit. Early involvement of various stakeholders is essential as a platform for regular communications between regulators and interested parties. Stakeholders’ participation in the NPP programme and law developments will also promote transparency of the projects while upholding the independency of the regulators.

  7. 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

  8. 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)

  9. 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

  10. The safety of WWER and RBMK nuclear power plants. Progress report on the IAEA extrabudgetary programme on the safety of WWER and RBMK nuclear power plants, 1992-1994

    International Nuclear Information System (INIS)

    1994-11-01

    This report, prepared by the IAEA secretariat, provides an overview of the IAEA Extrabudgetary Programme activities and results from 1992 until June 1994. The report describes the scope, the current status of the implementation and major findings and recommendations of the Programme. Though this report concentrates on the results of the Extrabudgetary Programme, it also refers to the significant related activities carried out under IAEA Technical Co-operation projects, as well as other international activities relevant to the safety of WWER and RBMK reactors. 13 figs, 9 tabs

  11. Co-ordinated research programme on benchmark study for the seismic analysis and testing of WWER-type nuclear power plants. V. 3A. Kozloduy NPP units 5/6: 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. This volume of Working material contains reports related analyses and testing of Kozloduy nuclear power plant, units 5 and 6

  12. Co-ordinated research programme on benchmark study for the seismic analysis and testing of WWER-type nuclear power plants. V. 3B. Kozloduy NPP units 5/6: Analysis/testing. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    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. This volume of Working material contains reports related analyses and testing of Kozloduy nuclear power plant, units 5 and 6.

  13. Stepwise development of MAIT cells in mouse and human.

    Directory of Open Access Journals (Sweden)

    Emmanuel Martin

    2009-03-01

    Full Text Available Mucosal-associated invariant T (MAIT cells display two evolutionarily conserved features: an invariant T cell receptor (TCRalpha (iTCRalpha chain and restriction by the nonpolymorphic class Ib major histocompatibility complex (MHC molecule, MHC-related molecule 1 (MR1. MR1 expression on thymus epithelial cells is not necessary for MAIT cell development but their accumulation in the gut requires MR1 expressing B cells and commensal flora. MAIT cell development is poorly known, as these cells have not been found in the thymus so far. Herein, complementary human and mouse experiments using an anti-humanValpha7.2 antibody and MAIT cell-specific iTCRalpha and TCRbeta transgenic mice in different genetic backgrounds show that MAIT cell development is a stepwise process, with an intra-thymic selection followed by peripheral expansion. Mouse MAIT cells are selected in an MR1-dependent manner both in fetal thymic organ culture and in double iTCRalpha and TCRbeta transgenic RAG knockout mice. In the latter mice, MAIT cells do not expand in the periphery unless B cells are added back by adoptive transfer, showing that B cells are not required for the initial thymic selection step but for the peripheral accumulation. In humans, contrary to natural killer T (NKT cells, MAIT cells display a naïve phenotype in the thymus as well as in cord blood where they are in low numbers. After birth, MAIT cells acquire a memory phenotype and expand dramatically, up to 1%-4% of blood T cells. Finally, in contrast with NKT cells, human MAIT cell development is independent of the molecular adaptor SAP. Interestingly, mouse MAIT cells display a naïve phenotype and do not express the ZBTB16 transcription factor, which, in contrast, is expressed by NKT cells and the memory human MAIT cells found in the periphery after birth. In conclusion, MAIT cells are selected by MR1 in the thymus on a non-B non-T hematopoietic cell, and acquire a memory phenotype and expand in the

  14. 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

  15. Anticipated transients without scram for WWER reactors. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1999-12-01

    Anticipated transients without scram (ATWS) are anticipated operational occurrences followed by the failure of one reactor scram function. Current international practice requires that the capability of pressurized water reactors (PWRs) to cope with ATWS be demonstrated following a systematic evaluation of plants' defence in depth. Countries operating PWRs require design consideration of ATWS events on a deterministic basis. The regulatory requirements may concern either specific mitigating systems or acceptable plant performance during these events. The prevailing international practice for performing transient analysis of ATWS for licensing is the best estimate approach. Available transient analyses of ATWS events indicate that WWER reactors, like PWRs, have the tendency to shut themselves down if the inherent nuclear feedback is sufficiently negative. Various control and limitation functions of the WWER plants also provide a degree of defence against ATWS. However, for most WWER plants, complete and systematic ATWS analyses have yet to be submitted for rigorous review by the regulatory authorities and preventive or mitigative measures have not been established. In addition, it has also been recognized that plant behaviour in case of ATWS also relies on certain system functions (use of pressurizer safety valves for liquid discharge, availability of steam dump valve to both the condenser (BRU-K) and the atmosphere (BRU-A) for secondary side pressure control, and others) which have been identified as safety issues and need to be qualified for accident conditions. In all countries operating WWERs, the need for ATWS investigations is recognized and reflected in the safety improvement programmes. ATWS analysis for WWERs is not required for the licensing process in Bulgaria, the Czech Republic (with the exception of the Temelin nuclear power plant) and Russia. Design consideration of ATWS is required if expert assessments of probabilistic safety assessment (PSA) results

  16. 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

  17. ISOLDE PROGRAMME

    CERN Multimedia

    Fedosseev, V; Herfurth, F; Scheidenberger, C; Geppert, C; Gorges, C; Ratajczyk, T; Wiederhold, J C; Vogel, S; Munch, M K; Nieminen, P; Pakarinen, J J A; Lecesne, N; Bouzomita, H; Grinyer, J; Marques moreno, F M; Parlog, M; Blank, B A; Pedroza, J; Ghetta, V; Lozeva, R; Zacarias, S M; Guillemaud mueller, D S; Cottereau, E; Cheikh mhamed, M; Tusseau nenez, S; Tungate, G; Walker, P M; Smith, A G; Fitzpatrick, C; Dominik, W M; Karny, M; Ciemny, A A; Nyman, G H; Thies, R M A; Lindberg, S K G; Langouche, G F; Velten, P; Araujo escalona, V I; Boudreau, M; Domnanich, K A; Richter, D; Lutter, R J; Javaji, A; Engel, R Y; Wiehr, S; Nacher gonzalez, E; Jungclaus, A; Ribeiro jimenez, G; Marroquin alonso, I; Cal gonzalez, J; Paziy, V; Salsac, M; Murphy, C; Podolyak, Z F; Bajoga, A D; Butler, P; Pritchard, A; Colosimo, S J; Steer, A N; Fox, S P; Wadsworth, B A; Truesdale, V L; Al monthery, M; Bracco, A; Guttormsen, M S; Badea, M N; Calinescu, S; Ujeniuc, S; Cederkall, J A; Zemlyanoy, S; Donets, E D; Golovkov, M; Schweitzer, D K; Vranicar, A; Harrichunder, S; Ncube, M; Nannini, A; Strisovska, J; Wolf, E; Gerten, R F; Lehnert, J; Rainovski, G I; Pospisil, S; Datta pramanik, U; Benzoni, G; Fedorov, D; Maier, F M; Bonanni, A; Pfeiffer, B; Griesel, T; Wehner, L W; Mikkelsen, M; Recchia, F; Lenzi, S M; Smith, J F; Kelly, C M; Acosta sanchez, L A; Chavez lomeli, E R; De melo bandeira tavares, P M; Vieira, J M; Martins da silva, M A; Lima lopes, A M; Lopes leal, T J; Mader, J; Kessler, P; Laurent, B G; Schweikhard, L C; Marx, G H; Kulczycka, E; Komorowska, M; Da silva, M F; Goncalves marques, C P; Baptista peres, M A; Welander, J E; Reiter, P; Miller, C; Martin sanchez-cano, D; Wiens, A; Blazhev, A A; Braun, N; Cappellazzo, M V; Birkenbach, B; Gerst, R; Dannhoff, M F; Sithole, M J; Bilgier, B; Nardelli, S; Araujo mendes, C M; Agramunt ros, J; Valencia marin, E; Pantea, E; Hessberger, F P; Leduc, A J; Mitsuoka, S; Carbonari, A W; Buchegger, F J; Garzon camacho, A; Dapo, H; Papka, P; Stachura, M K; Stora, T; Marsh, B A; Thiboud, J A; Heylen, H; Antalic, S; Stahl, C; Bauer, C; Thurauf, M; Maass, B; Sturm, S; Boehm, C; Wolf, N R; Ways, M; Steinsberger, T P; Riisager, K; Ruotsalainen, P A; Bastin, B; Duval, F T; Penessot, G; Flechard, X D; Desrues, P; Giovinazzo, J; Kurtukian nieto, T; Ascher, P E L; Roccia, S; Matea, I; Croizet, H A G; Bonnin, C M; Morfouace, P; Smith, A J; Guin, R; Banerjee, D; Gunnlaugsson, H P; Ohtsubo, T; Zhukov, M V; Tengborn, E A; Welker, A; Giannopoulos, E; Dessagne, P; Juscamaita vivanco, Y; Da costa pereira, L M; Hustings, J; Yu, H; Kruecken, R; Nowak, A K; Jankowski, M; Cano ott, D; Galve lahoz, P; Murphy, A S J; Shand, C M; Jones, G D; Herzberg, R; Ikin, P; Revill, J P; Everett, C; Napoli, D R; Scarel, G; Larsen, A; Tornyi, T G; Pascu, S G; Stroe, L; Toma, S; Jansson, K; Dronjak fahlander, M; Krupko, S; Hurst, A M; Veskovic, M; Nikolov, J; Masenda, H; Sibanda, W N; Rocchini, M; Klimo, J; Deicher, M; Wichert, T; Kronenberg, J; Helmke, A; Meliani, Z; Ivanov, V S; Green, B L; Keatings, J M; Kuti, I; Halasz, Z; Henry, M O; Bras de sequeira amaral, V; Espirito santo, F; Da silva, D J; Rosendahl, S; Vianden, R J; Speidel, K; Agarwal, I; Faul, T; Kownacki, J M; Martins correia, J G; Lorenz, K; Costa miranda, S M; Granadeiro costa, A R; Zyabkin, D; Kotthaus, T; Pfeiffer, M; Gironi, L; Jensen, A; Romstedt, F; Constantino silva furtado, I; Heredia cardona, J A; Jordan martin, M D; Montaner piza, A; Zacate, M O; Plewinski, F; Mesli, A; Akakpo, E H; Pichard, A; Hergemoller, F; Neu, W; Fallis starhunter, J P; Voulot, D; Mrazek, J; Ugryumov, V; Savreux, R P; Kojouharov, I M; Kern, R O; Papst, O; Fitting, J; Lauer, M; Kirsebom, O S; Jensen, K L; Jokinen, A; Rahkila, P J; Hager, U D K; Konki, J P; Dubois, M; Orr, N A; Fabian, X; Huikari, J E; Goigoux, T; Magron, C; Zakari, A A; Maietta, M; Bachelet, C E M; Roussiere, B; Li, R; Canavan, R L; Lorfing, C; Foster, R M; Gislason, H P; Shayestehaminzadeh, S; Qi, B; Mukai, M; Watanabe, Y; Willmann, L; Kurcewicz, W; Wimmer, K; Meisel, Z P; Dorvaux, O; Nowacki, F; Koudriavtsev, I; Lievens, P; Delaure, B J P; Neyens, G; Ceruti, S; Bunka, M; Vermeulen, C; Umbricht, C A; De boer, J; Podadera aliseda, I; Alcorta moreno, M; Pesudo fortes, V; Zielinska, M; Korten, W; Wang, C H; Lotay, G J; Mason, P; Rice, S J; Regan, P H; Willenegger, L M; Andreev, A; Yavuzkanat, N; Hass, M; Kumar, V; Valiente dobon, J J; Crespo campo, L; Zamfir, N - V; Deleanu, D; Clisu, C; Jeppesen, H B; Wu, C; Pain, S D; Stracener, D W; Wuosmaa, A H; Szilner, S; Colovic, P; Matousek, V; Venhart, M; Birova, M; Li, X; Stuchbery, A E; Lellep, G M; Chakraborty, S; Leoni, S; Chupp, T; Yilmaz, C; Severin, G; Garcia ramos, J E; Newton, M E; Hadinia, B; Mc glynn, E; Monteiro de sena silvares de carvalho, I; Friedag, P; Figuera, P; Koos, V; Meot, V H; Pauwels, D B; Jancso, A; Srebrny, J; Alves, E J; David bosne, E; Bengtsson, L; Kalkuehler, M; Albers, M; Bharuth-ram, K; Akkus, B; Hemmingsen, L B S; Pedersen, J T; Dos santos redondo, L M; Rubio barroso, B; Algora, A; Kozlov, V; Mavela, D L; Mokhles gerami, A; Keeley, N; Bernardo da silva, E; Unzueta solozabal, I; Schell, J; Szybowicz, M; Yang, X; Plavec, J; Lassen, J; Johnston, K; Coquard, L; Bloch, T P; Bonig, E S; Stegmann, R; Ignatov, A; Paschalis, S; Fernandez martinez, G; Schilling, M; Habermann, T; Von hahn, R; Minaya ramirez, E E; Moore, I D; Wang, Y; Saastamoinen, A J; Grahn, T; Herzan, A; Stolze, S M; Clement, E; Dijon, A; Shornikov, A; Lienard, E; Gibelin, J D; Pain, C; Canchel, G; Simpson, G S; Latrasse, L P; Huang, W; Forest, D H; Billowes, J; Flanagan, K; Strashnov, I; Binnersley, C L; Sanchez poncela, M; Simpson, J; Morrall, P S; Grant, A F; Charisopoulos, S; Lagogiannis, A; Bhattacharya, C; Olafsson, S; Stepaniuk, M; Tornqvist, H T; Heinz, A M; White iv, E R; Courtin, S; Marechal, F; Da silva fenta, A E; De lemos lima, T A; Stryjczyk, M; Dockx, K; Haller, S; Rizzi, M; Reichert, S B; Bonn, J; Thirolf, P G; Garcia rios, A R; Gugliermina, V M; Cubero campos, M A; Sanchez tembleque, V; Benito garcia, J; Senoville, M; Mountford, D J; Gelletly, W; Alharbi, T S T; Wilson, E; Rigby, S V; Andreoiu, C; Paul, E S; Harkness, L J; Judson, D S; Wraith, C; Van esbroeck, K; Wadsworth, R; Cubiss, J G; Harding, R D; Vaintraub, S; Mandal, S K; Scarpa, D; Hoff, P; Syed naeemul, H; Borcea, R; Balabanski, D L; Marginean, R; Rotaru, F; Rudolph, D; Fahlander, C H; Chudoba, V; Kay, B P; Soic, N; Naidoo, D; Veselsky, M; Kliman, J; Raisanen, J A; Dietrich, M; Maung maung than, M M T; Reed, M W; Danchev, M T; Ray, J; Roy, M; Hammen, M; Capponi, L; Veghne csatlos, M M; Fryar, J; Mirzadeh vaghefi, S P; Trindade pereira, A M; De pinho oliveira, G N; Bakenecker, A; Tramm, C; Germic, V; Morel, P A; Kowalczyk, M; Matejska-minda, M; Wolinska-cichocka, M; Ringvall moberg, A; Mantovan, R; Fransen, C H; Radeck, F; Schneiders, D W; Steinbach, T; Vibenholt, J E; Magnussen, M J; Stevnhoved, H M; Comas lijachev, V; Dasenbrock-gammon, N M; Perkowski, J; O'neill, G G; Matveev, Y; Wegner, M; Liu, Z; Perez alvarez, T; Cerato, L; Radchenko, V; Molholt, T E; Tabares giraldo, J A; Srnka, D; Dlouhy, Z; Beck, D; Werner, V R; Homm, I; Eliseev, S; Blaum, K; Probst, M B; Kaiser, C J; Martin, J A; Refsgaard, J; Peura, P J; Greenlees, P T; Auranen, K; Delahaye, P; Traykov, E K; Perez loureiro, D; Mery, A A; Couratin, C; Tsekhanovich, I; Lunney, D; Gaulard, C V; Mottram, A D; Cullen, D M; Das, S K; Van de walle, J; Mazzocchi, C; Jonson, B N G; Woehr, A; Lesher, S R; Zuber, K T; Filippin, L; De witte, H J; Van den bergh, P A M; Raabe, R; Dirkx, D; Parnefjord gustafsson, F O A; Dunlop, R A; Tarasava, K; Gernhaeuser, R A; Weinzierl, W; Berger, C; Wendt, K; Achtzehn, T; Gottwald, T; Schug, M; Rossel, R E; Dominguez reyes, R R; Fraile prieto, L M; Briz monago, J A; Koester, U H; Bunce, M R; Bowry, M D; Nakhostin, M; Shearman, R; Cresswell, J R; Joss, D T; Gredley, A; Groombridge, D; Laird, A M; Aslanoglou, X; Siem, S; Weterings, J A; Renstrom, T; Szpak, B T; Luczkowski, M J; Ghita, D; Bezbakh, A; Soltz, R A; Bollmann, J; Bhattacharya, P; Roy, S; Rahaman, M A; Wlodarski, T; Carvalho soares, J; Barzakh, A; Schertz, F; Froemmgen, N E; Liberati, V; Foy, B E; Baptista barbosa, M; Weinheimer, C P; Zboril, M; Simon, R E; Popescu, L A; Czosnyka, T; Miranda jana, P A; Leimbach, D; Naskrecki, R; Plociennik, W A; Ruchowska, E E; Chiara, C J; Walters, W; Eberth, J H; Thomas, T; Thole, P; Queiser, M T; Lo bianco, G; D'amico, F; Muller, S; Sanchez alarcon, R M; Tain enriquez, J L; Orrigo, S E A; Orlandi, R; Masango, S; Plazaola muguruza, F C; Lepareur, N G; Fiebig, J M; Ceylan, N; Wildner, E; Kowalska, M; Malbrunot, S; Garcia ruiz, R F; Pallada, S; Slezak, M; Roeckl, E; Schrieder, G H; Ilieva, S K; Koenig, K L; Amoretti, M A; Lommen, J M; Fynbo, H O U; Weyer, G O P; Koldste, G T; Madsboll, K; Jensen, J H; Nieminen, A M; Reponen, M; Villari, A; Thomas, J; Saint-laurent, M; Sorlin, O H; Carniol, B; Pereira lopez, J; Grevy, S; Plaisir, C; Marie-jeanne, M J; Georgiev, G P; Etile, A M; Le blanc, F M; Verney, D; Stefan, G I; Assie, M; Suzuki, D; Guillot, J; Vazquez rodriguez, L; Campbell, P; Deacon, A N; Ware, T; Flueras, A; Xie, L; Banerjee, K; Piersa, M; Galaviz redondo, D; Johansson, H T; Schwarz, S; Toysa, A S; Aumont, J; Van duppen, P L E; Atanasov, D; Zadvornaya, A; Renaud, M A; Xu, Z; Garrett, P E; Rapisarda, E; Reber, J A; Mattolat, C F; Raeder, S; Habs, D; Vidal, M; Perez liva, M; Calvo portela, P; Ulla pedrera, F J; Wood, R T; Lalkovski, S; Page, R; Petri, M; Barton, C J; Nichols, A J; Vermeulen, M J; Bloor, D M; Henderson, J; Wilson, G L; De angelis, G; Buerger, A; Modamio hoybjor, V; Klintefjord, M L; Ingeberg, V W; Fornal, B A; Marginean, R; Sava, T; Kusoglu, A; Suvaila, R; Lica, R; Costache, C; Mihai, R; Ionescu, A; Baeck, T M; Hoffman, C R; Sedlak, M; Koskelo, O K; Kyaw myat, K M; Gladnishki, K A; Ganguly, B; Goncalves marques, J; Cardoso, S; Seliverstov, M; Niessen, B D; Gutt, L E; Chapman, R; Spagnoletti, P N; Lopes, C; De oliveira amorim, C; Batista lopes, C M; Araujo, J; Schielke, S J; Daugas, J R; Gaudefroy, L; Chevrier, R; Szunyogh, D M; Napiorkowski, P J; Wrzosek-lipska, K; Wahl, U; Catarino, N; Pereira carvalho alves de sequeira, M; Hess, H E; Holler, A; Bettermann, L; Geibel, K; Taprogge, J; Lewandowski, L T N; Manchado de sola, F; Cakirli mutlu, R B; Das gupta, S; Thulstrup, P W; Heinz, U; Nogwanya, T; Neidherr, D M; Morales lopez, A I; Gumenyuk, O; Peaker, A R; Wakabayashi, Y; Abrahams, K J; Martin montes, E J; Mach, H A; Souza ribeiro junior, I; He, J; Chalil, A; Xing, R; Dos santos augusto, R M; Giles, T J; Dorsival, A; Trujillo hernandez, J S; Kalaninova, Z; Andel, B; Venos, D; Kraemer, J; Saha, S; Neugart, R; Eronen, T O; Kreim, K D; Heck, M K; Goncharov, M; Karthein, J; Julin, R J; Eleon, C; Achouri, N L; Grinyer, G F; Fontbonne, C M; Alfaurt, P; Lynch, K M; Wilkins, S G; Brown, A R; Imai, N; Pomorski, M J; Janiak, L; Nilsson, T; Stroke, H H; Stanja, J; Dangelser, E; Heenen, P; Godefroid, M; Mallion, S N; Gins, W A M; Stegemann, S T; Koszorus, A; Mcnulty, J F; Lin, P; Ohlert, C M; Schwerdtfeger, W; Tengblad, O; Becerril reyes, A D; Perea martinez, A; Martinez perez, M C; Margerin, V; Rudigier, M; Alexander, T D; Patel, Z V; Hammond, N; Wearing, F; Patel, A; Jenkins, D G; Corradi, L; Galtarossa, F; Debernardi, A; Giacoppo, F; Tveten, G M; Malatji, K L; Krolas, W A; Stanoiu, M A; Rickert, E U; Ter-akopian, G; Cline, D; Riihimaeki, I A; Simon, K D; Wagner, F E; Turker, M; Neef, M H; Coombes, B J; Jakubek, J; Vagena, E; Bottoni, S; Nishimura, K; Correia, J; Rodrigues valdrez, C J; Molkanov, P; Adhikari, R; Ostrowski, A N; Hallmann, O; Scheck, M; Wady, P T; Lane, J; Krasznahorkay, A J; Kunne sohler, D; Meaney, A J; Hochschulz, F; Roig, O; Behan, C C; Kargoll, S; Kemnitz, S; Carvalho teixeira, R C; Redondo cubero, A; Tallarida, G; Kaczarowski, R; Finke, F; Linnemann, A; Altenkirch, R; Saed-samii, N; Ansari, S H; Dlamini, W B; Adoons, V N; Ronning, C R; Wiedeking, M; Herlert, A J; Mehl, C V; Judge, S M; Gaertner, D; Divinskyi, S; Karabasov, M O; Zagoraios, G; Boztosun, I; Van zyl, J J; Catherall, R; Lettry, J; Wenander, F J C; Zakoucky, D; Catchen, G L; Noertershaeuser, W; Kroell, T; Leske, J; Shubina, D; Murray, I M; Pancin, J; Delaunay, F; Poincheval, J J L; Audirac, L L; Gerbaux, M T; Aouadi, M; Sole, P G P; Fallot, M P; Onillon, A; Duchemin, C; Formento cavaier, R; Audi, G; Boukhari, A; Lau, C; Martin, J A; Barre, N H; Berry, T A; Procter, T J; Bladen, L K; Axiotis, M; Muto, S; Jeong, S C; Hirayama, Y; Korgul, A B; Minamisono, K; Bingham, C R; Aprahamian, A; Bucher, B M; Severijns, N; Huyse, M L; Ferrer garcia, R; Verlinde, M N S; Romano, N; Maugeri, E A; Klupp, S C; Dehn, M H; Heinke, R M; Naubereit, P; Maira vidal, A; Vedia fernandez, M V; Ibanez garcia, P B; Bruyneel, B J E; Materna, T; Hadynska-klek, K; Al-dahan, N; Alazemi, N; Carroll, R J; Babcock, C; Patronis, N; Eleme, Z; Dhal, A; Sahin, E; Goergen, A; Maj, A; Bednarczyk, P A; Borcea, C; Negoita, F; Suliman, G; Marginean, N M; Sotty, C O; Negret, A L; Nae, S A; Nita, C; Golubev, P I; Knyazev, A; Jost, C U; Petrik, K; Vaeyrynen, S A; Dracoulis, G D; Uher, J; Fernandez dominguez, B; Chakraborty, P; Avigo, R; Falahat, S; Lekovic, F; Dorrer, H J; Mengoni, D; Derkx, X; Angus, L J; Sandhu, K S; Gregor, E; Kelly, N A; Byrne, D J; Haas, H; Lourenco, A A; Sousa pereira, S M; Sousa, J B; De melo mendonca, T M; Tavares de sousa, C; Guerreiro dos santos oliveira custodio, L M; Da rocha rodrigues, P M; Yamaguchi, T; Thompson, P C; Rosenbusch, M; Wienholtz, F; Fischer, P; Iwanicki, J S; Rusek, K M; Hanstorp, D; Vetter, U; Wolak, J M; Park, S H; Warr, N V; Doornenbal, P C; Imig, A; Seidlitz, M; Moschner, K; Vogt, A; Kaya, L; Martel bravo, I; Orduz, A K; Serot, O; Majola, S N; Litvinov, Y; Bommert, M; Hensel, S; Markevich, V; Nishio, K; Ota, S; Matos, I; Zenkevich, A; Picado sandi, E; Forstner, O; Hu, B; Ntshangase, S S; Sanchez-segovia, J

    2002-01-01

    The experiments aim at a broad exploration of the properties of atomic nuclei far away from the region of beta stability. Furthermore, the unique radioactive beams of over 60~elements produced at the on-line isotope separators ISOLDE-2 and ISOLDE-3 are used in a wide programme of atomic, solid state and surface physics. Around 300 scientists are involved in the project, coming from about 70 laboratories. \\\\ \\\\ The electromagnetic isotope separators are connected on-line with their production targets in the extracted 600 MeV proton or 910~MeV Helium-3 beam of the Synchro-Cyclotron. Secondary beams of radioactive isotopes are available at the facility in intensities of 10$^1

  18. Power

    DEFF Research Database (Denmark)

    Elmholdt, Claus Westergård; Fogsgaard, Morten

    2016-01-01

    and creativity suggests that when managers give people the opportunity to gain power and explicate that there is reason to be more creative, people will show a boost in creative behaviour. Moreover, this process works best in unstable power hierarchies, which implies that power is treated as a negotiable....... It is thus a central point that power is not necessarily something that breaks down and represses. On the contrary, an explicit focus on the dynamics of power in relation to creativity can be productive for the organisation. Our main focus is to elaborate the implications of this for practice and theory...

  19. 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

  20. Multifaceted Modularity: A Key for Stepwise Building of Hierarchical Complexity in Actinide Metal–Organic Frameworks

    Energy Technology Data Exchange (ETDEWEB)

    Dolgopolova, Ekaterina A. [Department; Ejegbavwo, Otega A. [Department; Martin, Corey R. [Department; Smith, Mark D. [Department; Setyawan, Wahyu [Pacific Northwest National Laboratory, Richland, Washington 99352, United States; Karakalos, Stavros G. [College; Henager, Charles H. [Pacific Northwest National Laboratory, Richland, Washington 99352, United States; zur Loye, Hans-Conrad [Department; Shustova, Natalia B. [Department

    2017-11-07

    Growing necessity for efficient nuclear waste management is a driving force for development of alternative architectures towards fundamental understanding of mechanisms involved in actinide integration inside extended structures. In this manuscript, metal-organic frameworks (MOFs) were investigated as a model system for engineering radionuclide containing materials through utilization of unprecedented MOF modularity, which cannot be replicated in any other type of materials. Through the implementation of recent synthetic advances in the MOF field, hierarchical complexity of An-materials were built stepwise, which was only feasible due to preparation of the first examples of actinide-based frameworks with “unsaturated” metal nodes. The first successful attempts of solid-state metathesis and metal node extension in An-MOFs are reported, and the results of the former approach revealed drastic differences in chemical behavior of extended structures versus molecular species. Successful utilization of MOF modularity also allowed us to structurally characterize the first example of bimetallic An-An nodes. To the best of our knowledge, through combination of solid-state metathesis, guest incorporation, and capping linker installation, we were able to achieve the highest Th wt% in mono- and bi-actinide frameworks with minimal structural density. Overall, combination of a multistep synthetic approach with homogeneous actinide distribution and moderate solvothermal conditions could make MOFs an exceptionally powerful tool to address fundamental questions responsible for chemical behavior of An-based extended structures, and therefore, shed light on possible optimization of nuclear waste administration.

  1. Guidance for the application of the leak before break concept. Report of the IAEA extrabudgetary programme on the safety of WWER-440 model 230 nuclear power plants

    International Nuclear Information System (INIS)

    1994-11-01

    This document provides additional guidance on application of the LBB concept to WWER-440/230 NPPs and complements the IAEA-TECDOC-710. The objective of the report is to describe in detail the elements of the LBB concept, the necessary support as well as the condition to be fulfilled, and the verification programme. It should also provide a clear picture of all the activities and resources needed to implement the LBB successfully as a comprehensive concept

  2. 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)

  3. Stepwise mitigation of the Macesnik landslide, N Slovenia

    Directory of Open Access Journals (Sweden)

    M. Mikoš

    2005-01-01

    the landslide movement starting from the slide plane towards its surface. Due to the length of the landslide and its longitudinal geometry it will be divided into several sections, and the mitigation works will be executed consecutively in phases. Such an approach proved effective in the 800 m long uppermost section of the landslide, where 3 parallel deep drain trenches (250 m long, 8 to 12 m deep were executed in the autumn of 2003. The reduction of the movements in 2004 enabled the construction of two 5 m wide and 22 m deep reinforced concrete shafts, finished in early 2005. In Slovenia, this sort of support construction, known from road construction, was used for the first time for landslide mitigation. The monitoring results show that the landslide displacements have been drastically reduced to less than 1 cm/day. As a part of the stepwise mitigation of the Macesnik landslide, further reinforced concrete shafts are to be constructed in the middle section of the landslide to support the road crossing the landslide. At the landslide toe, a support construction is planned to prevent further landslide advancement, and its type is still to be defined during the procedure of adopting a detailed plan of national importance for the Macesnik landslide.

  4. Stepwise kinetic equilibrium models of quantitative polymerase chain reaction

    Directory of Open Access Journals (Sweden)

    Cobbs Gary

    2012-08-01

    Full Text Available Abstract Background Numerous models for use in interpreting quantitative PCR (qPCR data are present in recent literature. The most commonly used models assume the amplification in qPCR is exponential and fit an exponential model with a constant rate of increase to a select part of the curve. Kinetic theory may be used to model the annealing phase and does not assume constant efficiency of amplification. Mechanistic models describing the annealing phase with kinetic theory offer the most potential for accurate interpretation of qPCR data. Even so, they have not been thoroughly investigated and are rarely used for interpretation of qPCR data. New results for kinetic modeling of qPCR are presented. Results Two models are presented in which the efficiency of amplification is based on equilibrium solutions for the annealing phase of the qPCR process. Model 1 assumes annealing of complementary targets strands and annealing of target and primers are both reversible reactions and reach a dynamic equilibrium. Model 2 assumes all annealing reactions are nonreversible and equilibrium is static. Both models include the effect of primer concentration during the annealing phase. Analytic formulae are given for the equilibrium values of all single and double stranded molecules at the end of the annealing step. The equilibrium values are then used in a stepwise method to describe the whole qPCR process. Rate constants of kinetic models are the same for solutions that are identical except for possibly having different initial target concentrations. Analysis of qPCR curves from such solutions are thus analyzed by simultaneous non-linear curve fitting with the same rate constant values applying to all curves and each curve having a unique value for initial target concentration. The models were fit to two data sets for which the true initial target concentrations are known. Both models give better fit to observed qPCR data than other kinetic models present in the

  5. Stepwise kinetic equilibrium models of quantitative polymerase chain reaction.

    Science.gov (United States)

    Cobbs, Gary

    2012-08-16

    Numerous models for use in interpreting quantitative PCR (qPCR) data are present in recent literature. The most commonly used models assume the amplification in qPCR is exponential and fit an exponential model with a constant rate of increase to a select part of the curve. Kinetic theory may be used to model the annealing phase and does not assume constant efficiency of amplification. Mechanistic models describing the annealing phase with kinetic theory offer the most potential for accurate interpretation of qPCR data. Even so, they have not been thoroughly investigated and are rarely used for interpretation of qPCR data. New results for kinetic modeling of qPCR are presented. Two models are presented in which the efficiency of amplification is based on equilibrium solutions for the annealing phase of the qPCR process. Model 1 assumes annealing of complementary targets strands and annealing of target and primers are both reversible reactions and reach a dynamic equilibrium. Model 2 assumes all annealing reactions are nonreversible and equilibrium is static. Both models include the effect of primer concentration during the annealing phase. Analytic formulae are given for the equilibrium values of all single and double stranded molecules at the end of the annealing step. The equilibrium values are then used in a stepwise method to describe the whole qPCR process. Rate constants of kinetic models are the same for solutions that are identical except for possibly having different initial target concentrations. Analysis of qPCR curves from such solutions are thus analyzed by simultaneous non-linear curve fitting with the same rate constant values applying to all curves and each curve having a unique value for initial target concentration. The models were fit to two data sets for which the true initial target concentrations are known. Both models give better fit to observed qPCR data than other kinetic models present in the literature. They also give better estimates of

  6. 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

  7. 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.

  8. 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

  9. 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.

  10. 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)

  11. 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)

  12. System for step-wise accident protection of nuclear reactors

    International Nuclear Information System (INIS)

    Rubek, J.; Kuklik, B.; Bednarik, K.

    1991-01-01

    A system comprising electric switching circuits is proposed for the control of a WWER type reactor shutdown in case of turbine failure or another abnormal situation. The fastest reactor shutdown mode is only resorted to if the pressures in the primary and secondary circuits would otherwise increase above tolerable limits and safety valves would open. The temperature and pressure stress of the nuclear power plant components and fuel is reduced. In this manner, the losses emerging during turbine failures due to false alarms are minimized. The contacts of the system switch if the turbines are relieved to the power of the unit home consumption, if the first or second turbine fails by closing the quick-acting valves, if a signal for blocking the by-pass stations of the operated turbines appears, or if the electric supply of the control system and of the turbo-set protection fails. (M.D.). 1 fig

  13. Programmable Pacemaker

    Science.gov (United States)

    1996-01-01

    Released in 1995, the Trilogy cardiac pacemaker is the fourth generation of a unit developed in the 1970s by NASA, Johns Hopkins Applied Physics Laboratory and St. Jude Medical's Cardiac Rhythm Management Division (formerly known as Pacesetter Systems, Inc.). The new system incorporates the company's PDx diagnostic and programming software and a powerful microprocessor that allows more functions to be fully automatic and gives more detailed information on the patient's health and the performance of the pacing systems. The pacemaker incorporates bidirectional telemetry used for space communications for noninvasive communication with the implanted pacemaker, smaller implantable pulse generators from space microminiaturization, and longer-life batteries from technology for spacecraft electrical power systems.

  14. 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)

  15. Empowering Women for Development through Community-Driven Sustainable Programmes: A Response to Traditional Patriarchal Power in the Southern African Region

    Science.gov (United States)

    Braimoh, Dele; Lekoko, Rebecca; Alade, Eunice B.

    2004-01-01

    In the Southern Africa region, the act of prejudice against women mostly occurs where patriarchal power reigns. This type of power is felt in areas such as inheritance right, division of labour, access to political and economic resources and legal and social matters. Other areas of discrimination against women include access to educational and…

  16. Cycle for fuel elements. Uranium production, programs for nuclear power stations and capital expenditure involved; Cycles de combustibles. Production d'uranium, programme de centrales electriques et effort financier correspondant

    Energy Technology Data Exchange (ETDEWEB)

    Andriot, J; Gaussens, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    A number of different possible programs for nuclear power stations of various types are presented in this survey. These programs are established in relation to the use of uranium and thorium in amounts similar to those that shall probably be produced in France during the next fifteen years. As it is possible to draw plans for nuclear power stations in which several processes exist simultaneously, an unlimited number of variations being thinkable, this survey is limited to successive analysis of the results obtained by use of only one of each of the following three systems: - system natural uranium-graphite, - system natural uranium-heavy water, -system enriched uranium-pressurised light water. All schemes are considered as assemblages of these three simple systems. The effects of plutonium recycling are also considered for each system. The electric power installed and the capacity of stations situated up-stream and down-stream have been calculated by this method and an attempt has been made to establish the sum to be invested during the fifteen years necessary for the launching of the programs scheduled. A table of timing for the investments groups the results obtained. Considering the fact that French availabilities in capital shall not be unlimited during the coming years, this way of presenting the results seems to be interesting. (author)Fren. [French] L'etude presentee comporte l'examen d'un certain nombre d'hypotheses de programmes de centrales nucleaires de types differents. Ces programmes correspondent a l'utilisation de tonnages d'uranium et de thorium de l'ordre de grandeur de ceux qui seront probablement produits par la France dans les quinze prochaines annees. Comme il est possible de batir un programme de centrales nucleaires, comportant a la fois plusieurs filieres suivant des variantes en nombre infini, on s'est contente d'examiner successivement les resultats ous si on utilisait exclusivement l'une des trois filieres suivantes: - filiere uranium

  17. Cycle for fuel elements. Uranium production, programs for nuclear power stations and capital expenditure involved; Cycles de combustibles. Production d'uranium, programme de centrales electriques et effort financier correspondant

    Energy Technology Data Exchange (ETDEWEB)

    Andriot, J.; Gaussens, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    A number of different possible programs for nuclear power stations of various types are presented in this survey. These programs are established in relation to the use of uranium and thorium in amounts similar to those that shall probably be produced in France during the next fifteen years. As it is possible to draw plans for nuclear power stations in which several processes exist simultaneously, an unlimited number of variations being thinkable, this survey is limited to successive analysis of the results obtained by use of only one of each of the following three systems: - system natural uranium-graphite, - system natural uranium-heavy water, -system enriched uranium-pressurised light water. All schemes are considered as assemblages of these three simple systems. The effects of plutonium recycling are also considered for each system. The electric power installed and the capacity of stations situated up-stream and down-stream have been calculated by this method and an attempt has been made to establish the sum to be invested during the fifteen years necessary for the launching of the programs scheduled. A table of timing for the investments groups the results obtained. Considering the fact that French availabilities in capital shall not be unlimited during the coming years, this way of presenting the results seems to be interesting. (author)Fren. [French] L'etude presentee comporte l'examen d'un certain nombre d'hypotheses de programmes de centrales nucleaires de types differents. Ces programmes correspondent a l'utilisation de tonnages d'uranium et de thorium de l'ordre de grandeur de ceux qui seront probablement produits par la France dans les quinze prochaines annees. Comme il est possible de batir un programme de centrales nucleaires, comportant a la fois plusieurs filieres suivant des variantes en nombre infini, on s'est contente d'examiner successivement les resultats ous si on utilisait exclusivement l

  18. 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

  19. IGNITOR Programme

    International Nuclear Information System (INIS)

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

    2005-01-01

    While finalising the design of IGNITOR, considerable progress has been made in understanding the plasma physics regimes expected to be experimented on the machine. Even before reaching its main goals, IGNITOR will produce intermediate results and provide assessments for some of the most critical extrapolation involved in designing burning plasma experiments. Although significant tritium burning is a necessary step for any new, advanced fusion facility, it is important to note that even with hydrogen, helium and deuterium IGNITOR will provide results, which alone would justify the machine's construction. Another significant feature of IGNITOR - and probably the most important - is the high level of internal power density that will be available

  20. IGNITOR Programme

    Energy Technology Data Exchange (ETDEWEB)

    Batistoni, Paola; De Marco, Francesco; Pieroni, Leonardo (ed.)

    2005-07-01

    While finalising the design of IGNITOR, considerable progress has been made in understanding the plasma physics regimes expected to be experimented on the machine. Even before reaching its main goals, IGNITOR will produce intermediate results and provide assessments for some of the most critical extrapolation involved in designing burning plasma experiments. Although significant tritium burning is a necessary step for any new, advanced fusion facility, it is important to note that even with hydrogen, helium and deuterium IGNITOR will provide results, which alone would justify the machine's construction. Another significant feature of IGNITOR - and probably the most important - is the high level of internal power density that will be available.

  1. Pluri-annual planning of power generation investments. 2005-2015 era; Programmation pluriannuelle des investissements de production electrique. Periode 2005-2015

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The pluri-annual planning of power generation investments (PPI) is provided by article 6 of the law from February 10, 2000 relative to the modernization and development of the electric utility. The PPI is the concrete translation of the energy policy and aims to identify the necessary investments with respect to the security of power supplies and beyond the already known commitments. In the framework of market deregulation and respect of competition, the PPI is limited to the identification of such investments but not to their realization. This document, which corresponds to the 2005 exercise, is the second report to the Parliament. It stresses on the following points: the mastery of power demand and the demand scenarios, the level of accepted risk, the carrying out of the development of renewable energy sources (5 GW by 2010 and 12.5 GW by 2016 for wind power, and 6 TWh more for biomass by 2016), the start-up of an EPR reactor in 2012, the investment needs for classical thermal power plants (+2.6 GW of diesel fuel power plants and +500 MW of combustion turbines as decided by EdF), the development of production means in 2 regions with specific needs: Provence-Alpes-Cote d'Azur and Bretagne (Brittany), and also in insular areas (Corsica and overseas territories), and the reflexions to carry on in continuation of the PPI. (J.S.)

  2. National programme: Finland

    International Nuclear Information System (INIS)

    Forsten, J.

    1986-01-01

    Finland's programmes in the field of reactor pressure components are presented in this paper. The following information on each of these programmes is given: the brief description of the programme; the programme's schedule and duration; the name of the project manager

  3. Evaluation of measuring data of small photovoltaic power systems within the framework of the German Federal-State 1000 Roofs PV programme. Final report; 1000-Daecher Mess- und Auswerteprogramm. Auswertung der Messdaten von photovoltaischen Kleinanlagen im Rahmen des Bund-Laender-1000 Daecher-Photovoltaik-Programms. Wissenschaftlicher Endbericht

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmann, V U [comp.; Erge, T; Kiefer, K [Fraunhofer-Institut fuer Solare Energiesysteme (ISE), Freiburg im Breisgau (Germany); Becker, H [Technischer Ueberwachungs-Verein Rheinland e.V., Duesseldorf (Germany); Decker, B; Grochowski, J [Institut fuer Solarenergieforschung GmbH (ISFH), Hannover (Germany); Heilscher, G [Ist EnergieCom GmbH, Augsburg (Germany); Riess, H [WIP Energie und Umwelt, Muenchen (Germany); Rindelhardt, U [Forschungszentrum Rossendorf e.V. (FZR), Dresden (Germany)

    1998-10-16

    Within the framework of the German Federal-State 1000 Roofs Photovoltaic Programme monthly measuring data and verbal comments on the PV system operation (reports on failures and defects) have been collected, stored in a databank and evaluated for the period 1991 to 1997 for a differing number of PV systems. In addition to this came along data of initially 100, then 40 intensively measured systems. The results of the measuring data evaluation as well as the results of further accompanying research projects to the Federal-State 1000 Roofs Photovoltaic Programme (e.g. low energy yield analysis, on-site inspections and measuring of nominal powers) are summarised. Starting from the gained results, conclusions and recommendations are given for the design, installation and operation for future grid-connected PV-systems. Also it is pointed to the remaining need for optimisation and R and D. Additional part of the report are the Annual Journal (published in a large print run) and the comprehensive final reports of the involved institutions (listed in Appendix 2). (orig.)

  4. Report to the parliament. Pluri-annual planning of power production investments; Rapport au parlement. Programmation pluriannuelle des investissements de production electrique

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-01-01

    The article 6 of the law from February 10, 2000, relative to the modernization and development of the electric utility, schedules a pluri-annual planning of the production investments (PPI) which represents a concrete translation of the energy policy in the domain of electricity. The PPI will allow to reach the energy policy goals using a balanced development of the national production means in terms of primary energy sources, techniques of production and geographical distribution of investments. This document is the first PPI report to the parliament. It is based on the scheme of energy collective services and on a provisional status made by the manager of the transportation network (RTE). In 2010, renewable energies should cover 21% of the French electricity needs. This ratio will be reached mainly thanks to the development of wind power (7000 to 14000 MW of installed power, which represents 20 to 35 TWh of additional production). Hydro-power should be increased of 8 TWh max, depending on the public policies implemented, and biomass will have a significant contribution too. On the other hand, actions of mastery of the electricity demand will have to be implemented. From 2008 onward, the decommissioning of several power plants will impose to find new solutions to satisfy the peak power needs. The covering of consumption peaks requires a correlation study of the power peaks at the European scale. Finally, the situation of non-interconnected areas and of areas with fragile supply has been carefully considered. The creation of new power production means must be envisaged in most of these areas. (J.S.)

  5. Co-ordinated research programme on operator support systems in nuclear power plants. Working material. Report of a research co-ordinated meeting held in Rome, 10-14 October 1994

    International Nuclear Information System (INIS)

    1995-01-01

    In September 1991, the IAEA Committee for Contractual Scientific Services approved the Co-ordinated Research Programme (CRP) on ''Operator Support Systems (OPS) in Nuclear Power Plants'' 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, including the experience with man-machine interface and closely related issues such as instrumentation and control, the use of computers, and operator qualification. The third meeting of the CRP participants was held in Rome/Italy, from 10 to 14 October 1994 and was sponsored by the ANPA. The meeting reviewed the progress of the CRP tasks, considered the reports of national activities in the subject area and agreed on the time scheduled for the preparation of the final report. The present volume contains: materials prepared by the CRP meeting; list of the CRP participants; and reports presented by the national delegates. Refs, figs and tabs

  6. Co-ordinated research programme on operator support systems in nuclear power plants. Working material. Report of a research co-ordinated meeting held in Rome, 10-14 October 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    In September 1991, the IAEA Committee for Contractual Scientific Services approved the Co-ordinated Research Programme (CRP) on ``Operator Support Systems (OSS) in Nuclear Power Plants`` 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, including the experience with man-machine interface and closely related issues such as instrumentation and control, the use of computers, and operator qualification. The third meeting of the CRP participants was held in Rome/Italy, from 10 to 14 October 1994 and was sponsored by the ANPA. The meeting reviewed the progress of the CRP tasks, considered the reports of national activities in the subject area and agreed on the time scheduled for the preparation of the final report. The present volume contains: materials prepared by the CRP meeting; list of the CRP participants; and reports presented by the national delegates. Refs, figs and tabs.

  7. Scientific forum during the 46th regular session of the IAEA General Conference. Topical issues: Nuclear Power - Life Cycle Management; Managing Nuclear Knowledge; Nuclear Security. Programme and synopses

    International Nuclear Information System (INIS)

    2002-01-01

    In response to the recommendations of several Agency advisory committees, to address issues related to nuclear power life cycle management, knowledge management in the field of nuclear power, and security of radiation sources and other nuclear material the IAEA is organizing the scientific forum to be held during the General Conference. The purpose of the meeting is to sharpen awareness and understanding of the emerging concerns about the aging of nuclear power plants, maintenance and preservation of knowledge and expertise in nuclear science, technology and applications, to emphasise the significance of security and physical protection of radiation sources and other radioactive material, and to better comprehend the role of the Agency in these processes

  8. 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

  9. 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.)

  10. 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.

  11. Co-ordinated research programme on benchmark study for the seismic analysis and testing of WWER-type nuclear power plants. V. 4A. 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 data related to seismic analyses of structures of Paks and Kozloduy reactor buildings and WWER-440/213 primary coolant loops with different antiseismic devices

  12. Co-ordinated research programme on benchmark study for the seismic analysis and testing of WWER-type nuclear power plants. V. 3E. Kozloduy NPP units 5/6: Analysis/testing. Working material

    International Nuclear Information System (INIS)

    1996-01-01

    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 data related to floor response spectra of Kozloduy NPP; calculational-experimental examination and ensuring of equipment and pipelines seismic resistance at starting and operating WWER-type NPPs; analysis of design floor response spectra and testing of the electrical systems; experimental investigations and seismic analysis Kozloduy NPP; testing of components on the shaking table facilities and contribution to full scale dynamic testing of Kozloduy NPP; seismic evaluation of the main steam line, piping systems, containment pre-stressing and steel ventilation chimney of Kozloduy NPP

  13. Co-ordinated research programme on benchmark study for the seismic analysis and testing of WWER-type nuclear power plants. V. 2. Generic material: Codes, standards, criteria. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    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 related to generic material, namely codes, standards and criteria for benchmark analysis.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    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 data related to seismic analyses of structures of Paks and Kozloduy reactor buildings and WWER-440/213 primary coolant loops with different antiseismic devices.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-07-01

    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 involves comparative analysis of the seismic analysis results of the reactor building for soft soil conditions, derivation of design response spectra for components and systems; and upper range design response spectra for soft soil site conditions at Paks NPP.

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

    International Nuclear Information System (INIS)

    1996-01-01

    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 involves comparative analysis of the seismic analysis results of the reactor building for soft soil conditions, derivation of design response spectra for components and systems; and upper range design response spectra for soft soil site conditions at Paks NPP

  17. Co-ordinated research programme on benchmark study for the seismic analysis and testing of WWER-type nuclear power plants. V. 1. Data related to sites and plants: Paks NPP, Kozloduy NPP. 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 data related to sites and NPPs Paks and Kozloduy

  18. Co-ordinated research programme on benchmark study for the seismic analysis and testing of WWER-type nuclear power plants. V. 1. Data related to sites and plants: Paks NPP, Kozloduy NPP. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    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 data related to sites and NPPs Paks and Kozloduy.

  19. Co-ordinated research programme on benchmark study for the seismic analysis and testing of WWER-type nuclear power plants. V. 2. Generic material: Codes, standards, criteria. 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 related to generic material, namely codes, standards and criteria for benchmark analysis

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

    International Nuclear Information System (INIS)

    1996-01-01

    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 seismic margin assessment and earthquake experience based methods for WWER-440/213 type NPPs; structural analysis and site inspection for site requalification; structural response of Paks NPP reactor building; analysis and testing of model worm type tanks on shaking table; vibration test of a worm tank model; evaluation of potential hazard for operating WWER control rods under seismic excitation

  1. Regulatory Practices on Ageing Management and Long Term Operation of Nuclear Power Plants in the Ibero-American Region. Results of the FORO/IAEA Programme on Nuclear and Radiation Safety in Ibero-America

    International Nuclear Information System (INIS)

    2014-09-01

    Although the operating lifetime of a nuclear power plant was originally anticipated to be in the range of 30-40 years, 200 of the 434 currently in operation are over 30 years old. In this context, Member States have assigned high priority to continuing the operation of nuclear power plants beyond the lifetime initially planned - while also maintaining the highest safety conditions possible. It is thus essential to encourage international cooperative efforts in the development of safety regulatory practices on ageing management and long term operation. Established in 1997, the Ibero-American Forum of Radiological and Nuclear Regulatory Agencies (FORO) aims to strengthen its members' radiological and nuclear safety regulatory organizations. Through a regional network of radiological and nuclear safety regulators, States in the Ibero-American region have worked together to strengthen radiation protection for patients, to improve safety at radiation installations, to tightten controls on radioactive sources used in medicine, agriculture and industry, and to improve safety and security at nuclear power plants. Since FORO's creation, it has cooperated with the IAEA in areas of mututal interest, and a technical programme administered by the IAEA was established in 2003 and formalized in Practical Arrangements signed in 2010. This publication presents the results of the 2009-2010 FORO/IAEA project on regulatory practices on ageing management and safety considerations for extending the operating lifetime of nuclear power plants. The purpose of the project was to provide nuclear regulators in the region with guidance on regulatory criteria, assessment, regulatory inspection and periodic safety reviews relating to ageing management and long term operation of nuclear power plants. The results are presented in a set of four reports, with guidelines for FORO members and a summary report of the project. These reports contain valuable information for the development of future

  2. The CEA-FRAGEMA ramp test programme for the study of the effect of power cycling on PCI at high burn-up

    International Nuclear Information System (INIS)

    Joseph, J.; Atabek, R.; Trotabas, M.

    1983-01-01

    The ramp test programme developed jointly by FRAGEMA and CEA is presented. Today, more than thirty PWR fuel rods have been ramp-tested in experimental reactors SILOE and OSIRIS. Nineteen fuel rods, named 'PRISCA', were base irradiated in BR3 and twelve fuel rods have been refabricated in hot cell by the FABRICE technique. The average fuel burn-up lies between 11 GWd.tU -1 and 46 GWd.tU -1 . In the major cases, the flux profile, during ramp-test, was decentred with respect to the base irradiated flux, and allows to obtain much more information than with a centred flux profile. The failure threshold was established under a set of more than thirty fuel rods of various designs. In particular, the post irradiation examinations allow to locate all rupture locations and thus to define precisely the threshold condition for failure of fuel rods. As an example, the results obtained in the PRISCA 109 experiments are presented. The refabricated fuel rods FABRICE behave identically, with regard to PCI, rather than PRISCA rods. An example of load follow transient in a PWR reactor is presented, and indicates any risk of failure due to PCI. (author)

  3. 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

  4. 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

  5. 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.

  6. 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.

  7. National Environmental Radiation Warning And Monitoring Network And Proposed Radiation Monitoring Programme For The 1st Nuclear Power Plant Ninth Thuan

    International Nuclear Information System (INIS)

    Vuong Thu Bac

    2011-01-01

    National Environmental Radiation Warning and Monitoring Network has been gradually setting up based on some of legislative documents which have been issued in recent years. Studies and surveys to build an environmental radiation monitoring program for nuclear power plant (NPP) have also been implemented. This paper aims to introduce National Environmental Radiation Warning and Monitoring Network in Vietnam which has been approved by the government, the draft program for environmental radiation monitoring Ninh Thuan NPP and some initial results of research about environmental radiation in the planning area for building first NPP in Vietnam. (author)

  8. WWER-440/230 reactor pressure vessel integrity. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-08-01

    This report was prepared with the objective of integrating all aspects involved and to provide plant specific information on the issue of reactor pressure vessel integrity including pressurized thermal shock assessment. Areas of the thermal hydraulic analysis including selection of transients, of the structural analysis including fracture mechanics assessment and of the material properties including embrittlement, annealing and re-embrittlement behaviour are addressed. The report also provides related recommendations and conclusions as well as detailed information on the plant specific status for operating WWER-440/230 nuclear power plants. 10 refs, 9 figs, 9 tabs

  9. Efficient red organic electroluminescent devices based on trivalent europium complex obtained by designing the device structure with stepwise energy levels

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-02-15

    In this study, we aim to further enhance the electroluminescence (EL) performances of trivalent europium complex Eu(TTA){sub 3}phen (TTA=thenoyltrifluoroacetone and phen=1,10-phenanthroline) by designing the device structure with stepwise energy levels. The widely used bipolar material 2,6-bis(3-(9H-carbazol-9-yl)phenyl)pyridine (26DCzPPy) was chosen as host material, while the doping concentration of Eu(TTA){sub 3}phen was optimized to be 4%. To facilitate the injection and transport of holes, MoO{sub 3} anode modification layer and 4,4′,4′′-Tris(carbazole-9-yl)triphenylamine (TcTa) hole transport layer were inserted in sequence. Efficient pure red emission with suppressed efficiency roll-off was obtained attributed to the reduction of accumulation holes, the broadening of recombination zone, and the improved balance of holes and electrons on Eu(TTA){sub 3}phen molecules. Finally, the device with 3 nm MoO{sub 3} and 5 nm TcTa obtained the highest brightness of 3278 cd/m{sup 2}, current efficiency of 12.45 cd/A, power efficiency of 11.50 lm/W, and external quantum efficiency of 6.60%. Such a device design strategy helps to improve the EL performances of emitters with low-lying energy levels and provides a chance to simplify device fabrication processes. - Highlights: • Electroluminescent performances of europium complex were further improved. • Device structure with stepwise energy levels was designed. • Better carriers' balance was realized by improving the injection and transport of holes. • The selection of bipolar host caused the broadening of recombination zone.

  10. Ghana's nuclear programme

    International Nuclear Information System (INIS)

    Ahafia, Albert K.

    1988-01-01

    The Paper gives the purpose of Ghana's Nuclear Programme and describes some specific research activities and peaceful applications of atomic energy in agriculture, medicine and industry. A discussion of some of the problem facing the programme concludes the Paper. (author)

  11. 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 ...

  12. 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…

  13. Stepwise extraction of Lepidium sativum seed gum: Physicochemical characterization and functional properties

    DEFF Research Database (Denmark)

    Razmkhah, Somayeh; Razavi, Seyed Mohammad Ali; Mohammadifar, Mohammad Amin

    2016-01-01

    Cress seed gum (CSG) was fractionated using stepwise extraction with water, yielding three fractions (F1, F2, F3) whose average molecular weights ranged from 863 to 1080 kDa. The chemical composition (monosaccharide, ash, moisture, CHN and uronic acid contents) and molecular weight of the fractio...

  14. 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...

  15. 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...

  16. 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

  17. Stepwise or concerted? DFT study on the mechanism of ionic Diels-Alder reaction of chromanes

    Directory of Open Access Journals (Sweden)

    Haghdadi Mina

    2016-01-01

    Full Text Available The stepwise and concerted Ionic Diels-Alder reaction between phenyl (pyridin-2-ylmethylene oxonium and styrene derivatives are explored using theoretical method. The results support using computational method via persistent intermediates. The DFT method was essential to reproduce a reasonable potential energy surface for these challenging systems.

  18. Stepwise radical endoscopic resection for Barrett's esophagus with early neoplasia: report on a Brussels' cohort

    NARCIS (Netherlands)

    Pouw, R. E.; Peters, F. P.; Sempoux, C.; Piessevaux, H.; Deprez, P. H.

    2008-01-01

    Background and study aims: The aim of this retrospective study was to assess safety and efficacy of stepwise radical endoscopic resection (SRER) in patients with Barrett's esophagus with high-grade intraepithelial neoplasia (HGIN) or early cancer. Patients and methods: Patients undergoing SRER

  19. 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.

  20. 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...

  1. 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...

  2. 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

  3. The 'Alte Ziegelei' small hydro-power installation in Derendingen, Switzerland; Kleinwasserkraftwerk alte Ziegelei in Derendingen. Programm Kleinwasserkraftwerke. Erfahrungs- und Schlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Koehli, T.

    2006-07-01

    This final report for the Swiss Federal Office of Energy (SFOE) discusses the experience gained with a small hydro-power installation in Derendingen, Switzerland. This unique 'micro' installation uses an archimedian screw to produce 6.8 kW of power from a head of 1.15 m and a through-flow of 800 - 1000 litres per second. Optimisation of the project is discussed as are the effects of changing water levels above and below the screw. Winter operation is described and the mounting of gratings necessary to avoid the intake of debris is discussed. Fish-passes are looked at and the effort required for maintenance is compared with that for other types of installations. An accident that occurred is analysed and the results of energy-efficiency measurements made on the installation are presented. The report is rounded off with an evaluation of the plant's performance and a review of future work to be done.

  4. 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)

  5. The Winfrith DSN programme

    International Nuclear Information System (INIS)

    Francescon, S.

    1963-05-01

    The programme, which is written in the Fortran language, solves the Carlson discrete S n approximation to the Boltzmann transport equation in cylindrical geometry. This report describes the input and output facilities of the WINFRITH DSN programme and the associated editing programme WED. (author)

  6. The Winfrith DSN programme

    Energy Technology Data Exchange (ETDEWEB)

    Francescon, S [General Reactor Physics Division, Atomic Energy Establishment, Winfrith, Dorchester, Dorset (United Kingdom)

    1963-05-15

    The programme, which is written in the Fortran language, solves the Carlson discrete S{sub n} approximation to the Boltzmann transport equation in cylindrical geometry. This report describes the input and output facilities of the WINFRITH DSN programme and the associated editing programme WED. (author)

  7. UNESCO's Ethics Education Programme.

    NARCIS (Netherlands)

    Have, H.A.M.J. ten

    2008-01-01

    Unesco initiated the Ethics Education Programme in 2004 at the request of member states to reinforce and increase the capacities in the area of ethics teaching. The programme is focused on providing detailed information about existing teaching programmes. It also develops and promotes teaching

  8. 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

  9. The Swedish energy programme

    International Nuclear Information System (INIS)

    Setterwall, M.

    1985-01-01

    The article discusses factors affecting the present and future supply of energy in Sweden. Before 1973 Sweden had the highest per capita oil importation in the world; it has no indigenous oil, gas or coal but is well off for water power, about three quarters of which is at present exploited, the remaining quarter being nearly all sterilised for the time being on conservationist grounds. By 1985 twelve nuclear generators should be in action, but further nuclear development has been stopped by political decisions. Official policy is to reduce dependence upon imported oil by the present use of nuclear energy and without increased importation of coal, but by AD2010 completely to replace nuclear energy by energy saving, using indigenous wood and peat, and developing the alternative sources of sun and wind. Heavy subsidy of the last however has produced little result so far. The author views this programme with great scepticism and opines that the present political blocking of increased generation by oil, coal, water power and nuclear energy will have to be broken, and that nuclear energy will play a major role for a long time to come. (C.J.O.G.)

  10. Safety issues and their ranking for WWER-440 model 213 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-04-01

    The objective of this report is to present a consolidated list of generic safety concerns, called safety issues, ranked according to their safety significance and the corrective measures to improve safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. Section 2 provides and overview of the impact of all relevant issues on the main safety functions and other aspects important to overall plant safety. Section 3 presents safety issues identified in design according to the structure described below. Section 4 presents the safety issues in the area of operation, according to the same structure except that no ranking is given. At the end of Section 2, Tables 1 and 2 present a summary of all safety issues in a tabular form. 138 refs, tabs

  11. NDA National Graduate Programme 'nucleargraduates'

    International Nuclear Information System (INIS)

    Dawson, Carl

    2010-01-01

    leading technical proficiency mixed with indications of 'high performer' potential. Professional - Throughout the programme the graduates will be working towards achieving professional qualifications though the relevant 'Institute' for their discipline, such as the IMECHE. The training and experience gained from the scheme is programmed around a syllabus of work and courses, which will be accredited retrospectively by the 'Institutes'. The two year 'initial professional development' programme whilst the graduate is with the NDA is then fitted into a further two years with stakeholders for their first 'substantive role'. Whilst there is no monetary contribution from the stakeholders there is a significant resource support from the programme stakeholders. They will provide a sophisticated matrix of support in attraction and assessment support, professional development, mentoring, training and scheme evaluation. The programme will be using cutting edge marketing, assessment, recruitment and training tools. It will also deliver a pioneering socio economic programme that will combine professional training with cultural and behavioural insight work. The aims of the programme are aligned with the NDA succession plan and Skills Strategy Document. The graduate profile by the end of the two year programme is 'mobile, professional, aware and ambitious.' The Programme is driven by a group comprising of companies across the industry including the NDA, SLC's, defence operators, operational power station organisations, regulators and the supply chain. Uniquely, the programme offers no 'specific job' with the NDA after the two year programme is completed. The programme will be integrated into the existing partners' schemes to ensure smooth progression. The Graduate's progress after 2 years will be facilitated by a careers service and formal rules governing the behaviour of partners. The first cohort targeted graduates from the following disciplines areas: Civil and Mechanical Engineering

  12. 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)

  13. 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.)

  14. 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.)

  15. 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.)

  16. 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.).

  17. 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

    The control of occupational exposure received at commercial nuclear generating plants in the United Kingdom has been subject to regulatory requirements embodied in site licence conditions since 1959, and at commercial fuel production and reprocessing plants since 1971. The paper indicates the main radiological control objectives which have applied, reviews the statutory measures introduced for their achievement and indicates some of the administrative arrangements made by site operators in order to comply. The principal sources of occupational exposure associated with each stage of the fuel cycle are identified and exposure data since licensed operations commenced are reviewed. The effectiveness of the United Kingdom site licensing procedure in ensuring adequate radiological control procedures, including the minimisation of occupational exposure, is examined in relation to the relevant ICRP recommendations and against the background of the first 20 years of commercial nuclear power production. The impact on these procedures of more recently introduced legislation relating to health and safety at all places of employment in the United Kingdom is discussed. The paper considers the changes in current regulatory procedures that may result from the introduction of ICRP-26 and the recommendations of ICRP Committee 2, and concludes with a review of the more important problems facing the licensee and the Nuclear Inspectorate with regard to the implementation of future radiological control procedures. (H.K.)

  18. Safety issues and their ranking for WWER-1000 model 320 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-03-01

    The objective of this report is to present a consolidated list of safety deficiencies, called safety issues, ranked according to their safety significance and the corrective measures to improve overall safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. To the extent that information was made available to the IAEA, the country/plant specific status with respect to each safety issue is described. Section 2 provides an overview of the impact of the relevant issues on the main safety functions in different operational conditions and other aspects important to overall plant safety. A summary of the safety issues and their respective ranking is given in Tables 1 and 2 at the end of Section 2. Section 3 deals with individual safety issues identified in the design which are presented according to the structure below. Section 4 presents the safety issues related to operational safety according to a similar structure but without the ranking. 73 refs, 3 tabs

  19. Safety issues and their ranking for WWER-1000 model 320 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1997-04-01

    The objective of this report is to present a consolidated list of safety deficiencies, called safety issues, ranked according to their safety significance and the corrective measures to improve overall safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. To the extent that information was made available to the IAEA, the country/plant specific status with respect to each safety issue is described. Section 2 provides an overview of the impact of the relevant issues on the main safety functions in different operational conditions and other aspects important to overall plant safety. A summary of the safety issues and their respective ranking is given in Tables 1 and 2 at the end of Section 2. Section 3 deals with individual safety issues identified in the design which are presented according to the structure below. Section 4 presents the safety issues related to operational safety according to a similar structure but without the ranking

  20. Implementation of the World Health Organization Regional Office for Africa Stepwise Laboratory Quality Improvement Process Towards Accreditation.

    Science.gov (United States)

    Ndihokubwayo, Jean-Bosco; Maruta, Talkmore; Ndlovu, Nqobile; Moyo, Sikhulile; Yahaya, Ali Ahmed; Coulibaly, Sheick Oumar; Kasolo, Francis; Turgeon, David; Abrol, Angelii P

    2016-01-01

    The increase in disease burden has continued to weigh upon health systems in Africa. The role of the laboratory has become increasingly critical in the improvement of health for diagnosis, management and treatment of diseases. In response, the World Health Organization Regional Office for Africa (WHO AFRO) and its partners created the WHO AFRO Stepwise Laboratory (Quality) Improvement Process Towards Accreditation (SLIPTA) program. WHO AFRO defined a governance structure with roles and responsibilities for six main stakeholders. Laboratories were evaluated by auditors trained and certified by the African Society for Laboratory Medicine. Laboratory performance was measured using the WHO AFRO SLIPTA scoring checklist and recognition certificates rated with 1-5 stars were issued. By March 2015, 27 of the 47 (57%) WHO AFRO member states had appointed a SLIPTA focal point and 14 Ministers of Health had endorsed SLIPTA as the desired programme for continuous quality improvement. Ninety-eight auditors from 17 African countries, competent in the Portuguese (3), French (12) and English (83) languages, were trained and certified. The mean score for the 159 laboratories audited between May 2013 and March 2015 was 69% (median 70%; SD 11.5; interquartile range 62-77). Of these audited laboratories, 70% achieved 55% compliance or higher (2 or more stars) and 1% scored at least 95% (5 stars). The lowest scoring sections of the WHO AFRO SLIPTA checklist were sections 6 (Internal Audit) and 10 (Corrective Action), which both had mean scores below 50%. The WHO AFRO SLIPTA is a process that countries with limited resources can adopt for effective implementation of quality management systems. Political commitment, ownership and investment in continuous quality improvement are integral components of the process.

  1. Comparison of different stepwise screening strategies for type 2 diabetes: Finding from Danish general practice, Addition-DK.

    Science.gov (United States)

    Dalsgaard, Else-Marie; Christensen, Jesper O; Skriver, Mette Vinter; Borch-Johnsen, Knut; Lauritzen, Torsten; Sandbaek, Annelli

    2010-12-01

    To examine attendance, number of people with T2DM and costs of three different stepwise screening strategies for T2DM in general practice (GP). Diabetes risk questionnaires were mailed to individuals aged 40-69 years from 45 general practices in 2001-2002 and individuals at high risk for T2DM, were asked to contact their GP to arrange a screening test. In 2005-2006, 26 general practices were randomised into two different opportunistic screening programmes (OP-direct and OP-subsequent) and risk questionnaires were distributed to individuals aged 40-69 years during GP consultations. In the OP-direct approach, high-risk individuals were offered to start the screening during the actual consultation while high-risk individuals in the OP-subsequent approach, were invited to a screening test at a later date. We report attendance, number of people with T2DM and costs of each screening approach. The mail-distributed approach identified 0.8% of the target population with T2DM, the OP-direct approach and the OP-subsequent approach, 0.9% and 0.5% respectively. Cost per person with T2DM was in the mail-distributed approach: € 1058, OP-direct approach: € 707 and the OP-subsequent approach: € 727. This study indicates that opportunistic screening identifies the same level of unknown diabetes as a mail-distributed approach but with lower costs. Copyright © 2010 Primary Care Diabetes Europe. Published by Elsevier Ltd. All rights reserved.

  2. 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.

  3. 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.

  4. 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.

  5. Impact of Antibiotic Shortage on H. Pylori Treatment: A Step-Wise Approach for Pharmacist Management

    Directory of Open Access Journals (Sweden)

    Michelle M. Lamb

    2013-01-01

    Full Text Available The current drug shortage crisis involving multiple oral antibiotics has significantly impacted preferred therapeutic options for treatment of H.pylori infection. Pharmacists may help alleviate the impact of this shortage through a proposed step-wise approach which includes proper inventory management, verification of indication, evaluation of regimen, therapeutic monitoring, and communication with patients and providers regarding alternative therapy or symptomatic relief.   Type: Original Research

  6. 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.

  7. 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.

  8. 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....

  9. Stepwise synthesis and characterization of germa[4], [5], [8], and [10]pericyclynes.

    Science.gov (United States)

    Tanimoto, Hiroki; Nagao, Tomohiko; Fujiwara, Taro; Nishiyama, Yasuhiro; Morimoto, Tsumoru; Suzuka, Toshimasa; Tsutsumi, Ken; Kakiuchi, Kiyomi

    2015-07-14

    The stepwise syntheses of germa[N]pericyclynes, including [5]pericyclynes, and their characterization are described. The yields of germa[4] and [8]pericyclynes were improved significantly compared to those obtained in previous studies. The routes reported herein afforded the novel germa[5] and [10]pericyclynes, which were characterized by X-ray crystallography, UV-Vis spectroscopy, and fluorescence emission spectroscopy. A unique fluorescence emission was observed for the large germa[10]pericyclyne ring.

  10. Impact of Antibiotic Shortage on H. Pylori Treatment: A Step-Wise Approach for Pharmacist Management

    Directory of Open Access Journals (Sweden)

    Ann Lloyd, Pharm.D., BCPS

    2013-01-01

    Full Text Available The current drug shortage crisis involving multiple oral antibiotics has significantly impacted preferred therapeutic options for treatment of H.pylori infection. Pharmacists may help alleviate the impact of this shortage through a proposed step-wise approach which includes proper inventory management, verification of indication, evaluation of regimen, therapeutic monitoring, and communication with patients and providers regarding alternative therapy or symptomatic relief.

  11. The Intramolecular Diels–Alder Reaction of Tryptamine-Derived Zincke Aldehydes Is a Stepwise Process

    OpenAIRE

    Pham, Hung V.; Martin, David B. C.; Vanderwal, Christopher D.; Houk, K. N.

    2012-01-01

    Computational studies show that the base-mediated intramolecular Diels–Alder of tryptamine-derived Zincke aldehydes, used as a key step in the synthesis of the Strychnos alkaloids norfluorocurarine and strychnine, proceeds via a stepwise pathway. The experimentally determined importance of a potassium counterion in the base is explained by its ability to preorganize the Zincke aldehyde diene in an s-cis conformation suitable to bicyclization. Computation also supports the thermodynamic import...

  12. 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.

  13. 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.

  14. 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).

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. 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.

  20. 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.

  1. 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.)

  2. FPGAs for software programmers

    CERN Document Server

    Hannig, Frank; Ziener, Daniel

    2016-01-01

    This book makes powerful Field Programmable Gate Array (FPGA) and reconfigurable technology accessible to software engineers by covering different state-of-the-art high-level synthesis approaches (e.g., OpenCL and several C-to-gates compilers). It introduces FPGA technology, its programming model, and how various applications can be implemented on FPGAs without going through low-level hardware design phases. Readers will get a realistic sense for problems that are suited for FPGAs and how to implement them from a software designer’s point of view. The authors demonstrate that FPGAs and their programming model reflect the needs of stream processing problems much better than traditional CPU or GPU architectures, making them well-suited for a wide variety of systems, from embedded systems performing sensor processing to large setups for Big Data number crunching. This book serves as an invaluable tool for software designers and FPGA design engineers who are interested in high design productivity through behavi...

  3. 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)

  4. Finnish bioenergy research programme

    Energy Technology Data Exchange (ETDEWEB)

    Asplund, D. [VTT Energy, Jyvaeskylae (Finland)

    1996-12-31

    Finland is a leading country in the use of biofuels and has excellent opportunities to increase the use of biofuels by up to 25-30 %. The Finnish Government has set an objective for the promotion of bioenergy. The aim is to increase the use of bioenergy by about 25 % from the present level by 2005, and the increment corresponds to 1.5 million tonnes of oil equivalent (toe) per year. The R and D work has been considered as an important factor to achieve this ambitious goal. Energy research was organised into a series of research programmes in 1988 in accordance with the proposal of Finnish Energy Research Committee. The object of the research programmes is to enhance research activities and to bundle individual projects together into larger research packages. The common target of the Finnish energy research programmes is to proceed from basic and applied research to product development and pilot operation, and after that to the first commercial applications, e.g. demonstrations. As the organisation of energy research to programmes has led to good results, the Finnish Ministry of Trade and Industry decided to go on with this practice by launching new six-year programmes in 1993-1998. One of these programmes is the Bioenergy Research Programme and the co-ordination of this programme is carried out by VTT Energy. Besides VTT Energy the Finnish Forest Research Institute, Work Efficiency Institute, Metsaeteho and University of Joensuu are participating in the programme 7 refs.

  5. Finnish bioenergy research programme

    Energy Technology Data Exchange (ETDEWEB)

    Asplund, D [VTT Energy, Jyvaeskylae (Finland)

    1997-12-31

    Finland is a leading country in the use of biofuels and has excellent opportunities to increase the use of biofuels by up to 25-30 %. The Finnish Government has set an objective for the promotion of bioenergy. The aim is to increase the use of bioenergy by about 25 % from the present level by 2005, and the increment corresponds to 1.5 million tonnes of oil equivalent (toe) per year. The R and D work has been considered as an important factor to achieve this ambitious goal. Energy research was organised into a series of research programmes in 1988 in accordance with the proposal of Finnish Energy Research Committee. The object of the research programmes is to enhance research activities and to bundle individual projects together into larger research packages. The common target of the Finnish energy research programmes is to proceed from basic and applied research to product development and pilot operation, and after that to the first commercial applications, e.g. demonstrations. As the organisation of energy research to programmes has led to good results, the Finnish Ministry of Trade and Industry decided to go on with this practice by launching new six-year programmes in 1993-1998. One of these programmes is the Bioenergy Research Programme and the co-ordination of this programme is carried out by VTT Energy. Besides VTT Energy the Finnish Forest Research Institute, Work Efficiency Institute, Metsaeteho and University of Joensuu are participating in the programme 7 refs.

  6. 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

  7. 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

  8. 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

  9. Methodology for qualification of in-service inspection systems for WWER nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1998-03-01

    Program was initiated by IAEA in 1990 with the aim to assist the countries of Central and Eastern Europe and former Soviet Union in evaluating the safety of their first generation WWER-440/230 nuclear power plants. The main objectives were: to identify major design and operational safety issues; to establish international consensus on priorities for safety improvements; and to provide assistance in the review of the competence and and adequacy of safety improvement programs. The scope was extended in 1992 to include RBMK, WWER-440/312 and WWER-1000 plants in operation and under construction. Integrity of primary circuit is fundamental for the safe operation of any nuclear power plant. In-service inspection (ISI) in general terms and in particular, non-destructive tests (NDT) play a key role in maintaining primary circuit integrity. This report provides a methodology for qualification of ISI systems which might be used by WWER operating countries as a commonly accepted basis for further development of the necessary qualification related infrastructures. It also provides several qualification principles defining the administrative framework needed for the practical implementation of the methodology, a description of the process of qualification of an inspection system, specifying its minimum technical and documentation related requirements, as well as specific requirements with regard to the NDT procedures, equipment and personnel to be qualified and the test specimen to be used in practical trials. Finally, the report suggests an appropriate distribution of responsibilities among all the parties involved in a qualification process, based on international practice

  10. 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

  11. 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, 11th and 12th executive committee meetings); 1998 nendo taiyoko hatsuden system jitsuyoka gijutsu kaihatsu kokusai kyoryoku jigyo. IEA taiyoko hatsuden system kenkyu kyoryoku program jisshi kyotei dai 12 kai dai 11 kai shikko 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 11th and 12th 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. Presented to the 11th executive committee meeting are progresses in each task, review of the PVPS programme by an independent reviewer, strategy for the next term of the PVPS agreement, and marketing of PV in the IEA member countries. The meeting also has confirmed the action plans and partial responsibilities. In the 12th executive committee meeting, the progresses of the tasks, e.g., objects, activities and problems, are reported, and reviewed by the participants. Discussed in the task 1, information exchange, are new communication methods, publication frequency and contents of Internal Survey Report, and opening of the internet home page, among others. (NEDO)

  12. 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

  13. 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

  14. Fusion technology programme

    International Nuclear Information System (INIS)

    Finken, D.

    1984-04-01

    KfK participates to the Fusion Technology Programme of the European Community. Most of the work in progress addresses the Next European Torus (NET) and the long term technology aspects as defined in the 82/86 programme. A minor part serves to preparation of future contributions and to design studies on fusion concepts in a wider perspective. The Fusion Technology Programme of Euratom covers mainly aspects of nuclear engineering. Plasma engineering, heating, refueling and vacuum technology are at present part of the Physics Programme. In view of NET, integration of the different areas of work will be mandatory. KfK is therefore prepared to address technical aspects beyond the actual scope of the physics experiments. The technology tasks are reported project wise under title and code of the Euratom programme. Most of the projects described here are shared with other European fusion laboratories as indicated in the table annexed to this report. (orig./GG)

  15. Technicians for the Brazilian nuclear power programme

    International Nuclear Information System (INIS)

    Martins Pinto, C.S.; Spitalnik, J.; Meakins, E.J.; Hurley, I.

    1980-01-01

    The technician has a responsible role to fulfil in nuclear industry, acting as a bridge between the engineer and the skilled worker. Technicians must have sufficient theoretical knowledge to communicate with engineers, and a thorough understanding of technological practice; the nuclear industry demands both theory and practice of a high standard. In Brazil the essential role of the technician in industry is in general recognized. However, the lack of a nationally recognized Nuclear Technician and Nuclear Technologist qualification, as well as a desire of the best technicians to quality as engineers and, in some areas, inadequate salaries has resulted in a shortage of well-trained technicians. A first step to ensure availability of these technicians is to improve their career prospects and status through definition of appropriate career standards and salaries. Practical training by the industry can only be given in factories, plants and construction sites where nuclear work is done. It is proposed to extend apprentice training centres at three sites, to give the most promising students after two years of apprentice training two further years of instruction and practice to qualify as Nuclear Technicians. The training centres are chosen to cover the three sectors of nuclear industry where special training of technicians is important: manufacture and construction; operation and maintenance; and testing and analysis for process control and safety. (author)

  16. 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.

  17. 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...

  18. Technical basis for instrumentation and control design improvements in WWER-440/230 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-01-01

    Instrumentation and control (I and C) has been recognized as an area which requires substantial improvements in WWER NNPs, particularly for model 230 plants. Under contract with the IAEA the Spanish company Empresarios Agrupados (EA) developed a basic document proposing a technical basis for improvements related to the following most significant aspects of I and C: criteria for safety classification; remote shutdown panel; I and C support to operation and control room design; instrumentation set point margins; accident monitoring instrumentation. This publication is derived from the original report of EA which was circulated by the IAEA for review by staff members and experts from various Member States. It was finally agreed upon at a Consultants' meeting convened by the IAEA in Vienna in May 1994 with the participation of experts from France, Germany and Spain. The guidance expressed in this report is based on the IAEA/NUSS standards, safety guides and practices, and on regulations in use in various Member States. It is proposed as a way of carrying out the necessary studies to improve safety by upgrading the vital part of instrumentation an control in WWER-440 model 230 nuclear power plants. 28 refs, 3 figs

  19. Optimization of fuel recovery through the stepwise co-pyrolysis of palm shell and scrap tire

    International Nuclear Information System (INIS)

    Abnisa, Faisal; Wan Daud, Wan Mohd Ashri

    2015-01-01

    Highlights: • The co-pyrolysis of palm shell and scrap tire was studied. • The effect of stepwise co-pyrolysis temperature was investigated. • Co-pyrolysis successfully improved the quantity and quality of product yields. • Stepwise co-pyrolysis slightly increased oil and gas, and decreased char. • The co-pyrolysis of 50% biomass and 50% scrap tire is recommended. - Abstract: This study optimized the use of biomass waste to generate fuel through co-pyrolysis. In this paper, the effects of stepwise co-pyrolysis temperature and different ratios between palm shells and scrap tires in feedstock were studied to observe any improvements in the quantity and quality of the liquid yield and its byproduct. The ratio of palm shells and scrap tires varied at 100:0, 75:25, 50:50, 25:75, and 0:100. The experiment was conducted in a fixed-bed reactor. The study was divided into two scenarios. The first scenario was performed at the optimum temperature of 500 °C with a reaction time of 60 min. In the second scenario, the temperature was set at 500 °C for 60 min before the temperature was increased to 800 °C with a high heating rate. After the temperature reached 800 °C, the condition was maintained for approximately 45 min. Results showed that an increase in the liquid and gas yields was achieved when the temperature increased after optimum conditions. Increased yield was also obtained when the proportion of scrap tire was increased in the feedstock. Several other important findings are discussed in this paper, including the phases of pyrolysis oil, features of the liquid product, and characteristics of the byproducts. All products from both scenarios were analyzed by various methods to understand their fuel characteristics

  20. Dissipated energy and entropy production for an unconventional heat engine: the stepwise `circular cycle'

    Science.gov (United States)

    di Liberto, Francesco; Pastore, Raffaele; Peruggi, Fulvio

    2011-05-01

    When some entropy is transferred, by means of a reversible engine, from a hot heat source to a colder one, the maximum efficiency occurs, i.e. the maximum available work is obtained. Similarly, a reversible heat pumps transfer entropy from a cold heat source to a hotter one with the minimum expense of energy. In contrast, if we are faced with non-reversible devices, there is some lost work for heat engines, and some extra work for heat pumps. These quantities are both related to entropy production. The lost work, i.e. ? , is also called 'degraded energy' or 'energy unavailable to do work'. The extra work, i.e. ? , is the excess of work performed on the system in the irreversible process with respect to the reversible one (or the excess of heat given to the hotter source in the irreversible process). Both quantities are analysed in detail and are evaluated for a complex process, i.e. the stepwise circular cycle, which is similar to the stepwise Carnot cycle. The stepwise circular cycle is a cycle performed by means of N small weights, dw, which are first added and then removed from the piston of the vessel containing the gas or vice versa. The work performed by the gas can be found as the increase of the potential energy of the dw's. Each single dw is identified and its increase, i.e. its increase in potential energy, evaluated. In such a way it is found how the energy output of the cycle is distributed among the dw's. The size of the dw's affects entropy production and therefore the lost and extra work. The distribution of increases depends on the chosen removal process.