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Sample records for candu nuclear power

  1. CANDU nuclear power system

    International Nuclear Information System (INIS)

    This report provides a summary of the components that make up a CANDU reactor. Major emphasis is placed on the CANDU 600 MW(e) design. The reasons for CANDU's performance and the inherent safety of the system are also discussed

  2. Development situation about the Canadian CANDU Nuclear Power Generating Stations

    International Nuclear Information System (INIS)

    The CANDU reactor is the most versatile commercial power reactor in the world. The acronym 'CANDU', a registered trademark of Atomic Energy of Canada Limited, stands for 'CANada Deuterium Uranium'. CANDU uses heavy water as moderator and uranium (originally, natural uranium) as fuel. All current power reactors in Canada are of the CANDU type. Canada exports CANDU type reactor in abroad. CANDU type is used as the nuclear power plants to produce electrical. Today, there are 41 CANDU reactors in use around the world, and the design has continuously evolved to maintain into unique technology and performance. The CANDU-6 power reactor offers a combination of proven, superior and state-of-the-art technology. CANDU-6 was designed specifically for electricity production, unlike other major reactor types. One of its characteristics is a very high operating and fuel efficiency. Canada Nuclear Power Generating Stations were succeeded in a commercial reactor of which the successful application of heavy water reactor, natural uranium method and that on-power fuelling could be achieved. It was achieved through the joint development of a major project by strong support of the federal government, public utilities and private enterprises. The potential for customization to any country's needs, with competitive development and within any level of domestic industrial infrastructure, gives CANDU technology strategic importance in the 21st century

  3. Periodic inspection of CANDU nuclear power plant containment components

    International Nuclear Information System (INIS)

    This Standard is one in a series intended to provide uniform requirements for CANDU nuclear power plants. It provides requirements for the periodic inspection of containment components including the containment pressure suppression systems

  4. A short history of the CANDU nuclear power system

    International Nuclear Information System (INIS)

    This paper provides a short historical summary of the evolution of the CANDU nuclear power system with emphasis on the roles played by Ontario Hydro and private sector companies in Ontario in collaboration with Atomic Energy of Canada Limited (AECL). (author). 1 fig., 61 refs

  5. Safety of CANDU nuclear power stations

    International Nuclear Information System (INIS)

    A nuclear plant contains a large amount of radioactive material which could be a potential threat to public health. The plant is therefore designed, built and operated so that the risk to the public is low. Careful design of the normal reactor systems is the first line of defense. These systems are highly resistant to an accident happening in the first place, and can also be effective in stopping it if it does happen. Independent and redundant safety sytems minimize the effects of an accident, or stop it completely. They include shutdown systems, emergency core cooling systems, and containment systems. Massive impairment of any one safety system together with an accident can be tolerated. This 'defence in depth' approach recognizes that men and machines are imperfect and that the unexpected happens. The nuclear power plant need not be perfect to be safe. To allow meaningful judgements we must know how safe the plant is. The Atomic Energy Control Board guidelines give one such measure, but they may overestimate the true risk. We interpret these guidelines as an upper limit to the total risk, and trace their evolution. (author)

  6. Future CANDU nuclear power plant design requirements document executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young [Korea Atomic Energy Research Institute, Daeduk (Korea, Republic of); Usmani, S.A. [Atomic Energy of Canada Ltd., Toronto (Canada)

    1996-03-01

    The future CANDU Requirements Document (FCRED) describes a clear and complete statement of utility requirements for the next generation of CANDU nuclear power plants including those in Korea. The requirements are based on proven technology of PHWR experience and are intended to be consistent with those specified in the current international requirement documents. Furthermore, these integrated set of design requirements, incorporate utility input to the extent currently available and assure a simple, robust and more forgiving design that enhances the performance and safety. The FCRED addresses the entire plant, including the nuclear steam supply system and the balance of the plant, up to the interface with the utility grid at the distribution side of the circuit breakers which connect the switchyard to the transmission lines. Requirements for processing of low level radioactive waste at the plant site and spent fuel storage requirements are included in the FCRED. Off-site waste disposal is beyond the scope of the FCRED. 2 tabs., 1 fig. (Author) .new.

  7. Advancement of safeguards inspection technology for CANDU nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jae Sung; Park, W. S.; Cha, H. R.; Ham, Y. S.; Lee, Y. G.; Kim, K. P.; Hong, Y. D

    1999-04-01

    The objectives of this project are to develop both inspection technology and safeguards instruments, related to CANDU safeguards inspection, through international cooperation, so that those outcomes are to be applied in field inspections of national safeguards. Furthermore, those could contribute to the improvement of verification correctness of IAEA inspections. Considering the level of national inspection technology, it looked not possible to perform national inspections without the joint use of containment and surveillance equipment conjunction with the IAEA. In this connection, basic studies for the successful implementation of national inspections was performed, optimal structure of safeguards inspection was attained, and advancement of safeguards inspection technology was forwarded. The successful implementation of this project contributed to both the improvement of inspection technology on CANDU reactors and the implementation of national inspection to be performed according to the legal framework. In addition, it would be an opportunity to improve the ability of negotiating in equal shares in relation to the IAEA on the occasion of discussing or negotiating the safeguards issues concerned. Now that the national safeguards technology for CANDU reactors was developed, the safeguards criteria, procedure and instruments as to the other item facilities and fabrication facilities should be developed for the perfection of national inspections. It would be desirable that the recommendations proposed and concreted in this study, so as to both cope with the strengthened international safeguards and detect the undeclared nuclear activities, could be applied to national safeguards scheme. (author)

  8. Advancement of safeguards inspection technology for CANDU nuclear power plants

    International Nuclear Information System (INIS)

    The objectives of this project are to develop both inspection technology and safeguards instruments, related to CANDU safeguards inspection, through international cooperation, so that those outcomes are to be applied in field inspections of national safeguards. Furthermore, those could contribute to the improvement of verification correctness of IAEA inspections. Considering the level of national inspection technology, it looked not possible to perform national inspections without the joint use of containment and surveillance equipment conjunction with the IAEA. In this connection, basic studies for the successful implementation of national inspections was performed, optimal structure of safeguards inspection was attained, and advancement of safeguards inspection technology was forwarded. The successful implementation of this project contributed to both the improvement of inspection technology on CANDU reactors and the implementation of national inspection to be performed according to the legal framework. In addition, it would be an opportunity to improve the ability of negotiating in equal shares in relation to the IAEA on the occasion of discussing or negotiating the safeguards issues concerned. Now that the national safeguards technology for CANDU reactors was developed, the safeguards criteria, procedure and instruments as to the other item facilities and fabrication facilities should be developed for the perfection of national inspections. It would be desirable that the recommendations proposed and concreted in this study, so as to both cope with the strengthened international safeguards and detect the undeclared nuclear activities, could be applied to national safeguards scheme. (author)

  9. Licensing evaluation of CANDU-PHW nuclear power plants relative to U.S. regulatory requirements

    International Nuclear Information System (INIS)

    Differences between the U.S. and Canadian approach to safety and licensing are discussed. U.S. regulatory requirements are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to current Regulatory Requirements and Guides. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S. These modifications are proposed solely for the purpose of maintaining consistency within the current U.S. regulatory system and not out of a need to improve the safety of current-design CANDU-PHW nuclear power plants. A number of issues are identified which still require resolution. Most of these issues are concerned with design areas not (yet) covered by the ASME code. (author)

  10. Requirements for the support power systems of CANDU nuclear power plants

    International Nuclear Information System (INIS)

    This Standard covers principal criteria and requirements for design, fabrication, installation, qualification, inspection, and documentation for assurance that support power will be available as required. The minimum requirements for support power are determined by the special safety systems and other safety-related systems that must function to ensure that the public health risk is acceptably low. Support power systems of a CANDU nuclear power plant include those parts of the electrical systems and instrument air systems that are necessary for the operation of safety-related systems

  11. Implementation of an on-line monitoring system for transmitters in a CANDU nuclear power plant

    Science.gov (United States)

    Labbe, A.; Abdul-Nour, G.; Vaillancourt, R.; Komljenovic, D.

    2012-05-01

    Many transmitters (pressure, level and flow) are used in a nuclear power plant. It is necessary to calibrate them periodically to ensure that their measurements are accurate. These calibration tasks are time consuming and often contribute to worker radiation exposure. Human errors can also sometimes degrade their performance since the calibration involves intrusive techniques. More importantly, experience has shown that the majority of current calibration efforts are not necessary. These facts motivated the nuclear industry to develop new technologies for identifying drifting instruments. These technologies, well known as on-line monitoring (OLM) techniques, are non-intrusive and allow focusing the maintenance efforts on the instruments that really need a calibration. Although few OLM systems have been implemented in some PWR and BWR plants, these technologies are not commonly used and have not been permanently implemented in a CANDU plant. This paper presents the results of a research project that has been performed in a CANDU plant in order to validate the implementation of an OLM system. An application project, based on the ICMP algorithm developed by EPRI, has been carried out in order to evaluate the performance of an OLM system. The results demonstrated that the OLM system was able to detect the drift of an instrument in the majority of the studied cases. A feasibility study has also been completed and has demonstrated that the implementation of an OLM system at a CANDU nuclear power plant could be advantageous under certain conditions.

  12. Preliminary evaluation of licensing issues associated with U. S. -sited CANDU-PHW nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    van Erp, J B

    1977-12-01

    The principal safety-related characteristics of current CANDU-PHW power plants are described, and a distinction between those characteristics which are intrinsic to the CANDU-PHW system and those that are not is presented. An outline is given of the main features of the Canadian safety and licensing approach. Differences between the U.S. and Canadian approach to safety and licensing are discussed. Some of the main results of the safety analyses, routinely performed for CANDU-PHW reactors, are presented. U.S.-NRC General Design Criteria are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to its conformance to the U.S.-NRC General Design Criteria. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S.

  13. CAE advanced reactor demonstrators for CANDU, PWR and BWR nuclear power plants

    International Nuclear Information System (INIS)

    CAE, a private Canadian company specializing in full scope flight, industrial, and nuclear plant simulators, will provide a license to IAEA for a suite of nuclear power plant demonstrators. This suite will consist of CANDU, PWR and BWR demonstrators, and will operate on a 486 or higher level PC. The suite of demonstrators will be provided to IAEA at no cost to IAEA. The IAEA has agreed to make the CAE suite of nuclear power plant demonstrators available to all member states at no charge under a sub-license agreement, and to sponsor training courses that will provide basic training on the reactor types covered, and on the operation of the demonstrator suite, to all those who obtain the demonstrator suite. The suite of demonstrators will be available to the IAEA by March 1997. (author)

  14. The development of emergency core cooling systems in the PWR, BWR, and HWR Candu type of nuclear power plants

    International Nuclear Information System (INIS)

    Emergency core cooling systems in the PWR, BWR, and HWR-Candu type of nuclear power plant are reviewed. In PWR and BWR the emergency cooling can be catagorized as active high pressure, active low pressure, and a passive one. The PWR uses components of the shutdown cooling system: whereas the BWR uses components of pressure suppression contaiment. HWR Candu also uses the shutdown cooling system similar to the PWR except some details coming out from moderator coolant separation and expensive cost of heavy water. (author)

  15. Control and instrumentation systems for the 600 MWe CANDU PHW nuclear power plants

    International Nuclear Information System (INIS)

    The control and instrumentation systems for CANDU power plants are designed for high reliability and availabilty to meet stringent safety and operational requirements. To achieve these goals a 'defence-in-depth' design philosophy is employed. The diversely functioning systems designed to satisfy these requirements are described, along with the extensive use of computers for important plant control and man-machine functions

  16. Preliminary evaluation of licensing issues associated with U.S.-sited CANDU-PHW nuclear power plants

    International Nuclear Information System (INIS)

    The principal safety-related characteristics of current CANDU-PHW power plants are described, and a distinction between those characteristics which are intrinsic to the CANDU-PHW system and those that are not is presented. An outline is given of the main features of the Canadian safety and licensing approach. Differences between the U.S. and Canadian approach to safety and licensing are discussed. Some of the main results of the safety analyses, routinely performed for CANDU-PHW reactors, are presented. U.S.-NRC General Design Criteria are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to its conformance to the U.S.-NRC General Design Criteria. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S

  17. Experience teaching CD-ROM-based course on CANDU nuclear-power-plant systems and operation

    International Nuclear Information System (INIS)

    This paper presents personal experience garnered from teaching a CD-ROM-based course on CANDU Power-Plant Systems and Operation. This course was originally developed by Prof. G.T. Bereznai as research in distance-learning techniques when he was directing the Thai-Canadian Human Resources Development Project at Chulalongkorn University in Bangkok. The course has been offered in a number of universities, including McMaster University and the University of Ontario Institute of Technology. All the course material, including lectures, assignments, and a simulator, is provided on a CD-ROM. Lectures include a spoken soundtrack covering the material. The class often includes both undergraduate and graduate students. I found that most students appreciate having the material on electronic format, which they can view and review at will and on their own time. Students find this course quite intensive - it covers all major systems in the CANDU reactor and power plant in detail. A very important component of the course is the simulator, which teaches students how systems operate in normal operation, in power manoeuvres, and during process-system malfunctions. Effort in absorbing the material and performing assignments can often exceed 10 hours per week. Some of the simulator assignments involve tricky manoeuvres, requiring several tries to achieve the expected result. Some assignments may take several hours, especially if the manoeuvres requiring repetition take 30 minutes or more in real time. I found that some instruction in the basic theory of reactor physics and systems is appreciated by students. A few possible enhancements to the simulator model were identified. Graduate students taking the course are required to do an additional project; I assigned an investigation of the effects of xenon-concentration changes during 1 week of load cycling. In summary, this course provides to students the opportunity to learn a great deal about the workings of CANDU-plant systems. (author)

  18. A foundation for allocating control functions to humans and machines in future CANDU nuclear power plants

    International Nuclear Information System (INIS)

    Since the control room for the Atomic Energy of Canada Limited CANDU 6 plant was designed in the 1970s, requirements for control rooms have changed dramatically as a result of new licensing requirements, evolution of major new standards for control centre design and technological advances. The role of the human operator has become prominent in the design and operation of industrial and, in particular, nuclear plants. Major industrial accidents in the last decade have highlighted the need for paying significantly more attention to the requirements of the human as an integral part of the plant control system. A Functional Design Methodology has been defined that addresses the issues related to maximizing the strengths of the human and the machine in the next generation of CANDU plants. This method is based, in part, on the recently issued international standard IEC 964. The application of this method will lead to the definition of the requirements for detailed design of the control room, including man-machine interfaces, preliminary operating procedures, staffing and training. Further, it provides a basis for the verification and validation of the allocation of functions to the operator and the machine

  19. Conceptual Study on Dismantling of CANDU Nuclear Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Woo-Tae; Lee, Sang-Guk [KHNP-CRI, Daejeon (Korea, Republic of)

    2014-10-15

    In this paper, we reviewed 3D design model of the CANDU type reactor and suggested feasible cutting scheme. The structure of CANDU nuclear reactor, the calandria assembly was reviewed using 3-D CAD model for future decommissioning. Through the schematic diagram of CANDU nuclear power plant, we identified the differences between PWR and CANDU reactor assembly. Method of dismantling the fuel channels from the calandria assembly was suggested. Custom made cutter is recommended to cut all the fuel channels. The calandria vessel is recommended to be cut by band saw or plasma torch. After removal of the fuel channels, it was assumed that radiation level near the calandria vessel is not very high. For cutting of the end shields, various methods such as band saw, plasma torch, CAMC could be used. The choice of a specific method is largely dependent on radiological environment. Finally, method of cutting the embedment rings is considered. As we assume that operators could cut the rings without much radiation exposure, various industrial cutting methods are suggested to be applied. From the above reviews, we could conclude that decommissioning of CANDU reactor is relatively easy compared to that of PWR reactor. Technologies developed from PWR reactor decommissioning could be applied to CANDU reactor dismantling.

  20. Exporting apocalypse: CANDU reactors and nuclear proliferation

    International Nuclear Information System (INIS)

    The author believes that the peaceful use of nuclear technology leads inevitably to the production of nuclear weapons, and that CANDU reactors are being bought by countries that are likely to build bombs. He states that exports of reactors and nuclear materials cannot be defended and must be stopped

  1. CANDU nuclear plant configured for multiple oil sands and power applications

    International Nuclear Information System (INIS)

    There is a need to meet expanding demand in Alberta for electricity for an expanding economy, high-pressure steam for oil sands recovery, and hydrogen for bitumen upgrading. This demand must be satisfied in a sustainable, environmentally acceptable and economic manner. Nuclear technology, and in particular AECL's new ACR-1000 reactor, is emerging as the best way to meet these multiple demands. The ACR-1000 can be configured to supply both high-pressure steam and electricity with the steam / electricity ratio optimized to standard turbine-generator sizing and oil sands requirements - thereby affording more options for nuclear plant siting and deployment. Energy for oil sands applications can be supplied in several ways by a centralized nuclear plant with a uniquely configured Balance of Plant (BOP). Steam could be piped to one or several in-situ oil Steam Assisted Gravity Drainage (SAGD) operations within 15 km of the plant boundary. Electricity could be transmitted to more remote facilities including an electrolytic hydrogen plant for bitumen upgraders, resistance-heating devices used for extraction of oil from shale, and electric boilers that generate steam for small in-situ oil sands recovery facilities. The various product streams from the 1200 MWe Class ACR-1000 could be sold by the plant owner through a combination of long-term power purchase agreements and flexible contracts that respond to variable grid prices and demand. In addition the electrolytic hydrogen plant to also serve as an energy storage facility at times of low power demand. These flexible nuclear power plant configurations increase the potential to use clean nuclear energy for more environmentally benign oil sands recovery while still meeting future energy demands economic constraints. (author)

  2. Design requirements, criteria and methods for seismic qualification of CANDU power plants

    International Nuclear Information System (INIS)

    This report describes the requirements and criteria for the seismic design and qualification of systems and equipment in CANDU nuclear power plants. Acceptable methods and techniques for seismic qualification of CANDU nuclear power plants to mitigate the effects or the consequences of earthquakes are also described. (auth)

  3. Thermal stability of chloroform in the steam condensate cycle of CANDU-PHW nuclear power plant

    International Nuclear Information System (INIS)

    Analysis of samples taken at the Gentilly 2 (Quebec) CANDU-PHW (CANadian Deuterium Uranium - Pressurized Heavy Water) plant after chlorination and demineralization revealed the presence of all four trihalomethanes (THMs) (CHCl3, CHBrCl2, CHBr2Cl and CHBr3) and other unidentified halogenated volatile compounds. Among the THMs, chloroform was the major contaminant. A study of its thermal stability in water at different temperatures confirmed the degradation of the CHCl3 molecule according to the equation CHCl3 + H2O → CO + 3 HCl. The reaction follows first order kinetics and has an activation energy of 100 kJ/mol. The estimated half-life is six seconds at 260 deg C, the maximum temperature of the steam condensate cycle

  4. Methodology for identifying boundaries of systems important to safety in CANDU nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Therrien, S.; Komljenovic, D.; Therrien, P.; Ruest, C.; Prevost, P.; Vaillancourt, R. [Hydro-Quebec, Nuclear Generating Station Gentilly-2, Becancour, Quebec (Canada)

    2007-07-01

    This paper presents a methodology developed to identify the boundaries of the systems important to safety (SIS) at the Gentilly-2 Nuclear Power Plant (NPP), Hydro-Quebec. The SIS boundaries identification considers nuclear safety only. Components that are not identified as important to safety are systematically identified as related to safety. A global assessment process such as WANO/INPO AP-913 'Equipment Reliability Process' will be needed to implement adequate changes in the management rules of those components. The paper depicts results in applying the methodology to the Shutdown Systems 1 and 2 (SDS 1, 2), and to the Emergency Core Cooling System (ECCS). This validation process enabled fine tuning the methodology, performing a better estimate of the effort required to evaluate a system, and identifying components important to safety of these systems. (author)

  5. Assessment of LOCA with loss of class IV power for CANDU-6 reactors using RELAP-CANDU/SCAN coupled code system

    International Nuclear Information System (INIS)

    Recently, there is an effort to improve the accuracy and reality in the transient simulation of nuclear power plants. In the prediction of the system transient, the system code simulates the system transient using the power transient curve predicted from the reactor core physics code. However, the pre-calculated power curve could not adequately predict the behavior of power distribution during transient since the coolant density change has influence on the power shape due to the change of the void reactivity. Therefore, the consolidation between the reactor core physics code and the system thermal-hydraulic code takes into consideration to predict more accurate and realistic for the transient simulation. In this regard, there are two codes are developed to assess the safety of CANDU reactor. RELAP-CANDU is a thermal-hydraulic system code for CANDU reactors developed on the basis of RELAP5/MOD3 in such a way to modify inside model for simulating the thermal-hydraulic characteristics of horizontal type reactors. SCAN (SNU CANDU-PHWR Neutronics) is a three dimensional neutronics nodal code to simulate the core physics characteristics for CANDU reactors. To couple SCAN code with RELAP-CANDU code, SCAN code was improved as a spatial kinetics calculation module in such a way to generate a SCAN DLL (dynamic linked library version of SCAN). The coupled code system, RELAP-CANDU/SCAN, enables real-time feedback calculations between thermal-hydraulic variables of RELAP-CANDU and reactor powers of SCAN. To verify the reliability of RELAP-CANDU/SCAN coupled code system, an assessment of 40% reactor inlet header (RIH) break loss of coolant accident (LOCA) with loss of Class IV power (LOP) for Wolsong Unit 2 conducted using RELAP/CANDU-SCAN coupled system. The LOCA with LOP is one of GAI (Generic Action Items) for CANDU reactors issued by CNSC (Canadian Nuclear Safety Commission) and IAEA (International Atomic Energy Agency)

  6. Utilization of spent PWR fuel-advanced nuclear fuel cycle of PWR/CANDU synergism

    Institute of Scientific and Technical Information of China (English)

    HUO Xiao-Dong; XIE Zhong-Sheng

    2004-01-01

    High neutron economy, on line refueling and channel design result in the unsurpassed fuel cycle flexibility and variety for CANDU reactors. According to the Chinese national conditions that China has both PWR and CANDU reactors and the closed cycle policy of reprocessing the spent PWR fuel is adopted, one of the advanced nuclear fuel cycles of PWR/CANDU synergism using the reprocessed uranium of spent PWR fuel in CANDU reactor is proposed, which will save the uranium resource (~22.5%), increase the energy output (~41%), decrease the quantity of spent fuels to be disposed (~2/3) and lower the cost of nuclear power. Because of the inherent flexibility of nuclear fuel cycle in CANDU reactor, and the low radiation level of recycled uranium(RU), which is acceptable for CANDU reactor fuel fabrication, the transition from the natural uranium to the RU can be completed without major modification of the reactor core structure and operation mode. It can be implemented in Qinshan Phase Ⅲ CANDU reactors with little or no requirement of big investment in new design. It can be expected that the reuse of recycled uranium of spent PWR fuel in CANDU reactor is a feasible and desirable strategy in China.

  7. Requirements for class 1C, 2C, and 3C pressure-retaining components and supports in CANDU nuclear power plants

    International Nuclear Information System (INIS)

    This Standard applies to pressure-retaining components of CANDU nuclear power plants that have a code classification of Class 1C, 2C or 3C. These are pressure-retaining components where, because of the design concept, the rules of the ASME Boiler and Pressure Vessel Code do not exist, are not applicable, or are not sufficient. The Standard provides rules for the design, fabrication, installation, examination and inspection of these components and supports. It provides rules intended to ensure the pressure-retaining integrity of components, not the operability. It also provides rules for the support of fueling machines. The Standard applies only to new construction prior to the plant being declared in service

  8. Machine learning techniques for the verification of refueling activities in CANDU-type nuclear power plants (NPPs) with direct applications in nuclear safeguards

    International Nuclear Information System (INIS)

    This dissertation deals with the problem of automated classification of the signals obtained from certain radiation monitoring systems, specifically from the Core Discharge Monitor (CDM) systems, that are successfully operated by the International Atomic Energy Agency (IAEA) at various CANDU-type nuclear power plants around the world. In order to significantly reduce the costly and error-prone manual evaluation of the large amounts of the collected CDM signals, a reliable and efficient algorithm for the automated data evaluation is necessary, which might ensure real-time performance with maximum of 0.01 % misclassification ratio. This thesis describes the research behind finding a successful prototype implementation of such automated analysis software. The finally adopted methodology assumes a nonstationary data-generating process that has a finite number of states or basic fueling activities, each of which can emit observable data patterns having particular stationary characteristics. To find out the underlying state sequences, a unified probabilistic approach known as the hidden Markov model (HMM) is used. Each possible fueling sequence is modeled by a distinct HMM having a left-right profile topology with explicit insert and delete states. Given an unknown fueling sequence, a dynamic programming algorithm akin to the Viterbi search is used to find the maximum likelihood state path through each model and eventually the overall best-scoring path is picked up as the recognition hypothesis. Machine learning techniques are applied to estimate the observation densities of the states, because the densities are not simply parameterizable. Unlike most present applications of continuous monitoring systems that rely on heuristic approaches to the recognition of possibly risky events, this research focuses on finding techniques that make optimal use of prior knowledge and computer simulation in the recognition task. Thus, a suitably modified, approximate n-best variant of

  9. Pressure tube life management in CANDU-6 nuclear plant

    International Nuclear Information System (INIS)

    Operating parameters of pressure tube in CANDU-6 reactor, the relation between pressure tube life and plant life improvement of pressure tube by AECL in past years were summarized, and the factors affecting pressure tube life, idea and main measures of pressure tube life management in QINSHAN CANDU-6 power plant introduced

  10. Generic validation of computer codes used in safety analyses of CANDU power plants

    International Nuclear Information System (INIS)

    Since the 1960s, the CANDU industry has been developing and using scientific computer codes, validated according to the quality-assurance practices of the day, for designing and analyzing CANDU power plants. To provide a systematic framework for the validation work done to date and planned for the future, the industry has decided to adopt the methodology of validation matrices, similar to that developed by the Nuclear Energy Agency of the Organization for Economic Co-operation and Development for Light Water Reactors (LWR). Specialists in six scientific disciplines are developing the matrices for CANDU plants, and their progress to date is presented. (author)

  11. Nuclear power in Canada

    International Nuclear Information System (INIS)

    The Canadian Nuclear Association believes that the CANDU nuclear power generation system can play a major role in achieving energy self-sufficiency in Canada. The benefits of nuclear power, factors affecting projections of electric power demand, risks and benefits relative to other conventional and non-conventional energy sources, power economics, and uranium supply are discussed from a Canadian perspective. (LL)

  12. Role of accident analysis in development of severe accident management guidance for multi-unit CANDU nuclear power plants

    International Nuclear Information System (INIS)

    This paper discusses the role of accident analysis in support of the development of Severe Accident Management Guidance for domestic CANDU reactors. In general, analysis can identify what types of challenges can be expected during accident progression but it cannot specify when and to what degree accident phenomena will occur. SAMG overcomes these limitations by monitoring the actual values of key plant indicators that can be used directly or indirectly to infer the condition of the plant and by establishing setpoints beyond which corrective action is required. Analysis can provide a means to correlate observed post-accident plant behavior against predicted behaviour to improve the confidence in and quality of accident mitigation decisions. (author)

  13. Plant condition assessments as a requirement before major investment in life extension for a CANDU nuclear power plant

    International Nuclear Information System (INIS)

    Full text: Since, to extend the life of a CANDU-6 reactor beyond its original design life requires the replacement of reactor components (380 pressure and calandria tubes), a major investment will have to be done. After a preliminary technical and economical feasibility study, Hydro- Quebec, owner of the Gentilly-2 NPP, has decided to perform a more detailed assessment to: 1. Get assurance that it is technically and economically viable to extend Gentilly-2 for another 20 years beyond the original design life; 2. Identify the detailed work to be done during the refurbishment period planned in 2008-2009; 3. Define the overall cost and the general schedule of the refurbishment phase; 4. Ensure an adequate licensing strategy to restart after refurbishment; 5. Complete all the Environmental Impact Studies required to obtain the government authorizations. The business case to support the refurbishment of Gentilly-2 has to take in consideration the reactor core components, which will be the major work to be completed during refurbishment. In summary the following main component will have to be changed or refreshed: The pressure and calandria tubes and the feeders (partial replacement only) (ageing mechanisms); The control computers (obsolescence); The condenser tubes (tubes plugging); The turbine control and electric-governor (obsolescence). An extensive campaign is under way to assess the 'health' of the station systems, structures and components (SSC). Two processes have been used for this assessment: Plant Life Management Studies (PLIM) for approximately 10 critical SSC or families of SSC (PLIM Studies); Condition Assessment Studies for other SSC with a lower impact on the Plant production or safety). The PLIM Studies are done on SSC's, which were judged critical because they are not replaceable (Reactor Building, Calandria), or that their failure could have a significant impact on safety or production (electrical motors, majors pumps, heat exchangers and pressure

  14. Cobalt-60 production in CANDU power reactors

    International Nuclear Information System (INIS)

    The technology for cobalt-60 production in CANDU reactors, designed and developed by MDS Nordion and AECL, has been safely,economically and successfully employed in CANDU reactors with over 195 reactor years of production. Today over forty percent of the world's disposable medical supplies are made safer through sterilization using cobalt-60 sources from MDS Nordion. Over the past 40 years, MDS Nordion with its CANDU reactor owner partners, has safely and reliably shipped more than 500 million curies of cobalt-60 sources to customers around the world

  15. The Candu system - The way for nuclear autonomy

    International Nuclear Information System (INIS)

    The experience acquired by Canada during the development of Candu System is presented. Some basic foundations of technology transfer are defined and, the conditions of canadian nuclear industry to provide developing countries, technical assistence for acquisition of nuclear energy autonomy, are analysed. (M.C.K.)

  16. Integrated control centre concepts for CANDU power plants

    International Nuclear Information System (INIS)

    The size and complexity of nuclear power plants has increased significantly in the last 20 years. There is general agreement that plant safety and power production can be enhanced if more operational support systems that are significantly different from the ones based on the more conventional technologies used in plant control rooms. In particular, artificial intelligence and related technologies will play a major role in the development of innovative methods for information processing and presentation. These technologies must be integrated into the overall management and control philosophy of the plant and not be treated as vehicles to implement point solutions. The underlying philosophy behind our approach is discussed in this paper. Operator support systems will integrate into the overall control philosophy by complementing the operator. Four support systems are described; each is a prototype of a system being considered for the CANDU 3 control centre

  17. Economics of CANDU

    International Nuclear Information System (INIS)

    The cost of producing electricity from CANDU reactors is discussed. The total unit energy cost of base-load electricity from CANDU reactors is compared with that of coal-fired plants in Ontario. In 1980 nuclear power was 8.41 m$/kW.h less costly for plants of similar size and vintage. Comparison of CANDU with pressurized water reactors indicated that the latter would be about 26 percent more costly in Ontario

  18. Inspection of Candu Nuclear Reactor Fuel Channels

    International Nuclear Information System (INIS)

    The Channel Inspection and Gauging Apparatus of Reactors (CIGAR) is a fully atomated, remotely operated inspection system designed to perform multi-channel, multi-task inspection of CANDU reactor fuel channels. Ultrasonic techniques are used for flaw detection, (with a sensitivity capable of detecting a 0.075 mm deep notch with a signal to noise ratio of 10 dB) and pressure tube wall thickness and diameter measurements. Eddy currrent systems are used to detect the presence of spacers between the coaxial pressure tube and calandria tube, as well as to measure their relative spacing. A servo-accelerometer is used to estimate the sag of the fuel channels. This advanced inspection system was commissioned and declared in service in September 1985. The paper describes the inspection systems themselves and discussed the results achieved to-date. (author)

  19. Public health risks associated with the CANDU nuclear fuel cycle

    International Nuclear Information System (INIS)

    This report analyzes in a preliminary way the risks to the public posed by the CANDU nuclear fuel cycle. Part 1 considers radiological risks, while part 2 (published as INFO-0141-2) evaluates non-radiological risks. The report concludes that, for radiological risks, maximum individual risks to members of the public are less than 10-5 per year for postulated accidents, are less than 1 percent of regulatory limits for normal operation and that collective doses are small, less than 3 person-sieverts. It is also concluded that radiological risks are much smaller than the non-radiological risks posed by activities of the nuclear fuel cycle

  20. The Impact of Power Coefficient of Reactivity on CANDU 6 Reactors

    International Nuclear Information System (INIS)

    The combined effects of reactivity coefficients, along with other core nuclear characteristics, determine reactor core behavior in normal operation and accident conditions. The Power Coefficient of Reactivity (PCR) is an aggregate indicator representing the change in reactor core reactivity per unit change in reactor power. It is an integral quantity which captures the contributions of the fuel temperature, coolant void, and coolant temperature reactivity feedbacks. All nuclear reactor designs provide a balance between their inherent nuclear characteristics and the engineered reactivity control features, to ensure that changes in reactivity under all operating conditions are maintained within a safe range. The CANDU reactor design takes advantage of its inherent nuclear characteristics, namely a small magnitude of reactivity coefficients, minimal excess reactivity, and very long prompt neutron lifetime, to mitigate the demand on the engineered systems for controlling reactivity and responding to accidents. In particular, CANDU reactors have always taken advantage of the small value of the PCR associated with their design characteristics, such that the overall design and safety characteristics of the reactor are not sensitive to the value of the PCR. For other reactor design concepts a PCR which is both large and negative is an important aspect in the design of their engineered systems for controlling reactivity. It will be demonstrated that during Loss of Regulation Control (LORC) and Large Break Loss of Coolant Accident (LBLOCA) events, the impact of variations in power coefficient, including a hypothesized larger than estimated PCR, has no safety-significance for CANDU reactor design. Since the CANDU 6 PCR is small, variations in the range of values for PCR on the performance or safety of the reactor are not significant

  1. CANDU 9 design

    International Nuclear Information System (INIS)

    AECL has made significant design improvements in the latest CANDU nuclear power plant (NPP) - the CANDU 9. The CANDU 9 operates with the energy efficient heavy water moderated reactor and natural uranium fuel and utilizes proven technology. The CANDU 9 NPP design is similar to the world leading CANDU 6 but is based upon the single unit adaptation of the 900 MWe class reactors currently operating in Canada as in integrated four-unit configurations. The evolution of the CANDU family of heavy water reactors (HAIR) is based on a continuous product improvement approach. Proven equipment and systems from operating stations are standardized and used in new products. As a result of the flexibility of the technology, evolution of the current design will ensure that any new requirements can be met, and there is no need to change the basic concept. This paper will provide an overview for some of the key features of the CANDU 9 NPP such as nuclear systems and equipment, advanced control and computer systems, safety design and protection features, and plant layout. The safety enhancements and operability improvements implemented in this design are described and some of the advantages that can be expected by the operating utility are highlighted. (author)

  2. Validation of computer codes used in safety analyses of CANDU power plants

    International Nuclear Information System (INIS)

    Since the 1960s, the CANDU industry has been developing and using scientific computer codes for designing and analysing CANDU power plants. In this endeavour, the industry has been following nuclear quality-assurance practices of the day, including verification and validation of design and analysis methodologies. These practices have resulted in a large body of experience and expertise in the development and application of computer codes and their associated documentation. Major computer codes used in safety analyses of operating plants and those under development have been, and continue to be subjected to rigorous processes of development and application. To provide a systematic framework for the validation work done to date and planned for the future, the industry has decided to adopt the methodology of validation matrices for computer-code validation, similar to that developed by the Nuclear Energy Agency of the Organization for Economic Co-operation and Development and focused on thermalhydraulic phenomena in Light Water Reactors (LWR). To manage the development of validation matrices for CANDU power plants and to engage experts who can work in parallel on several topics, the CANDU task has been divided into six scientific disciplines. Teams of specialists in each discipline are developing the matrices. A review of each matrix will show if there are gaps or insufficient data for validation purposes and will thus help to focus future research and development, if needed. Also, the industry is examining its suite of computer codes, and their specific, additional validation needs, if any, will follow from the work on the validation matrices. The team in System Thermalhydraulics is the furthest advanced, since it had the earliest start and the international precedent on LWRs, and has developed its validation matrix. The other teams are at various stages in this multiphase, multi-year program, and their progress to date is presented. (author)

  3. Explosive and corrosive concentration analysis of gases produced in a CANDU type (N2, D2, O2, H2) nuclear power plant

    International Nuclear Information System (INIS)

    The primary loop gas of an automatic control system of a nuclear power plant is of great importance as regards conservation and safety of the plant. These gases are produced by dissociation due to radiation effects on heavy water. The system is based on a sample capture equipment, a chromatographic analyzer with its associated electronics, a sample separator and conditioner, a temperature and pressure control system of the transport gas, all included in the reactor building, apart from other supporting instrumentation. (Author)

  4. Proceedings of the Canadian Nuclear Society CANDU maintenance conference

    International Nuclear Information System (INIS)

    The conference proceedings comprise 51 papers on the following aspects of maintenance of CANDU reactors: Major maintenance projects, maintenance planning and preparation, maintenance effectiveness, future maintenance issues, safety and radiation protection. The individual papers have been abstracted separately

  5. The Study of Nuclear Fuel Cycle Options Based On PWR and CANDU Reactors

    International Nuclear Information System (INIS)

    The study of nuclear fuel cycle options based on PWR and CANDU type reactors have been carried out. There are 5 cycle options based on PWR and CANDU reactors, i.e.: PWR-OT, PWR-OT, PWR-MOX, CANDU-OT, DUPIC, and PWR-CANDU-OT options. While parameters which assessed in this study are fuel requirement, generating waste and plutonium from each cycle options. From the study found that the amount of fuel in the DUPIC option needs relatively small compared the other options. From the view of total radioactive waste generated from the cycles, PWR-MOX generate the smallest amount of waste, but produce twice of high level waste than DUPIC option. For total plutonium generated from the cycle, PWR-MOX option generates smallest quantity, but for fissile plutonium, DUPIC options produce the smallest one. It means that the DUPIC option has some benefits in plutonium consumption aspects. (author)

  6. Report of the COG/IAEA international workshop on managing nuclear safety at CANDU (PHWR) plants. Working material

    International Nuclear Information System (INIS)

    The workshop, hosted by COG and co-sponsored by the International Atomic Energy Agency (IAEA, Vienna) was held in Toronto, April 28 - May 1st, 1997. The 40 participants included senior managers from IAEA member countries operating or constructing CANDU (PHWR) stations. All the offshore utilities with PHWR stations in Korea, Romania, India, Argentina, Pakistan, and China were present with their domestic counterparts from Ontario Hydro Nuclear, Hydro Quebec, New Brunswick Power, and AECL. The objectives of the workshop were to: provide a forum for exchange of ideas among nuclear safety managers operating CANDU (PHWR) stations and to learn from each other's experiences; to foster sharing of information on different operating approaches to managing safety and, in particular, to highlight the strategies for controlling the overall plant risk to a low level; to identify and discuss issues of mutual interest pertinent to PHWR stations and to define future follow-up activities. Refs, figs

  7. A CANDU-type small/medium power reactor

    International Nuclear Information System (INIS)

    The assembly known as a CANDU power reactor consists of a number of standardized fuel channels or 'power modules'. Each of these channels produces about 5 thermal megawatts on average. Within practical limitations on fuel enrichment and ultimately on economics, the number of these channels is variable between about 50 and approximately 700. Small reactors suffer from inevitable disadvantages in terms of specific cost of design/construction as well as operating cost. Their natural 'niche' for application is in remote off-grid locations. At the same time this niche application imposes new and strict requirements for staff complement, power system reliability, and so on. The distinct advantage of small reactors arises if the market requires installation of several units in a coordinated installation program - a feature well suited to power requirements in Canada's far North. This paper examines several of the performance requirements and constraints for installation of these plants and presents means for designers to overcome the consequent negative feasibility factors.

  8. CANDU operating experience

    International Nuclear Information System (INIS)

    The CANDU Pressurized Heavy Water (CANDU-PHW) type of nuclear electric generating station has been developed jointly by Atomic Energy of Canada Limited and Ontario Hydro. This paper highlights Ontario Hydro's operating experience using the CANDU-PHW system, with a focus on the operating performance and costs, reliability of system components and nuclear safety considerations both to the workers and the public

  9. Economics of CANDU-PHW

    International Nuclear Information System (INIS)

    The CANDU-Pressurized Heavy Water (CANDU-PHW) type of nuclear-electric generating station has been developed jointly by Atomic Energy of Canada Limited and Ontario Hydro. This paper discusses the cost of producing electricity from CANDU, presents actual cost experience of CANDU and coal in Ontario, presents projected CANDU and coal costs in Ontario and compares CANDU and Light Water Reactor cost estimates in Ontario

  10. CANDU-OCR power station options and costs

    International Nuclear Information System (INIS)

    This report updates and in some cases expands the technical and economic parameters presented originally in AECL-4441. 'Summary report on the design of a prototypical 500 MWe CANDU-OCR power station.' Updating is desirable owing to the increasing number of inquiries that have been received by Atomic Energy of Canada Ltd. from government agencies and the private sector. Each is exploring the available options in their continuing endeavour to provide sufficient and economical energy. The organic-cooled reactor (OCR) concept is particularly interesting to the oil industry because the high steam pressures it can develop allow it to be used for heavy oil extraction can also be used economically for other large thermal and electrical energy production requirements such as those encountered in district heating schemes, heavy water production and electricity production. The report describes a reference OCR-500 MWe reactor. It includes an overview of organic reactor experience and areas for further development based on 14 years of operating experience with the WR-1 reactor. A discussion of several variations on the reference design is given including estimates of costs for various reactor sizes, enrichments and operating functions. Costs are presented in a form which allow easy comparison with those of competing energy options. (auth)

  11. A journalist's guide to nuclear power

    International Nuclear Information System (INIS)

    This guidebook is meant to assist journalists in communicating information about nuclear power. It provides basic information about the CANDU reactor and its use by Ontario Hydro, radiation, and fission, as well as background and statistics on the use of nuclear power in Canada and around the world

  12. Modelling nuclear fuel vibrations in horizontal CANDU reactors

    International Nuclear Information System (INIS)

    Flow-induced fuel vibrations in the pressure tubes of CANDU reactors are of vital interest to designers because fretting damage may result. Computer simulation is being used to study how bundles vibrate and to identify bundle design features which will reduce vibration and hence fretting. (author)

  13. An investigation into the relationship between local and global power excursions in CANDU

    International Nuclear Information System (INIS)

    If a reactor exhibits large neutronic decoupling of one core region from another, it may be able to sustain localized power excursions. If such an excursion is too localized, there may be no in-core detector close enough to detect it promptly. To confirm that CANDU reactors are unlikely to support local power excursions, we selected a credible local reactivity-insertion mechanism in the CANDU 600 and calculated the resulting neutron flux transient with a three-dimensional model. A coupled neutronics-thermohydraulics simulation of the transient was performed. The transient was subdivided into appropriate time steps, and iteration between the neutronics and thermohydraulics calculations was carried out at each step, so that the proper distribution of thermohydraulic feedback reactivity was obtained. The calculation shows that, with credible reactivity insertions, the neutronic characteristics of CANDU reactors do not allow local power excursions to occur without a comparable global power increase. The latter would not escape detection by the protective systems

  14. Experimental validation of Pu-Sm evolution model for CANDU-6 power transients

    International Nuclear Information System (INIS)

    Development of a methodology to evaluate the reactivity produced by Pu-Sm transient, effect displayed after power transients. This methodology allows to predict the behavior of liquid zones with which the fine control of CANDU reactor power is made. With this information, it is easier to foresee the refueling demand after power movements. The comparison with experimental results showed good agreement. (author)

  15. Development of nuclear fuel. Development of CANDU advanced fuel bundle

    International Nuclear Information System (INIS)

    In order to develop CANDU advanced fuel, the agreement of the joint research between KAERI and AECL was made on February 19, 1991. AECL conceptual design of CANFLEX bundle for Bruce reactors was analyzed and then the reference design and design drawing of the advanced fuel bundle with natural uranium fuel for CANDU-6 reactor were completed. The CANFLEX fuel cladding was preliminarily investigated. The fabricability of the advanced fuel bundle was investigated. The design and purchase of the machinery tools for the bundle fabrication for hydraulic scoping tests were performed. As a result of CANFLEX tube examination, the tubes were found to be meet the criteria proposed in the technical specification. The dummy bundles for hydraulic scoping tests have been fabricated by using the process and tools, where the process parameters and tools have been newly established. (Author)

  16. Joint submission of the Canadian Nuclear Association and the Organization of CANDU Industries to the Ontario Nuclear Safety Review

    International Nuclear Information System (INIS)

    The manufacturing company members of the Canadian Nuclear Association and the Organization of CANDU Industries are proud to have played their part in the development of the peaceful application of nuclear technology in Ontario, and the achievement of the very real benefits discussed in this paper, which greatly outweigh the hypothetical risks

  17. Exporting technology for CANDU fuel manufacturing to the People's Republic of China - a stimulating experience for the Romanian nuclear fuel plant

    International Nuclear Information System (INIS)

    Adopting CANDU type reactors to produce nuclear-generated electricity, Romania has also developed his capability to produce nuclear fuel. Since 1995, FCN Pitesti is the unique nuclear fuel supplier for Cernavoda CANDU Power Station. Fuel plant upgrading and qualification was achieved in co-operation with AECL and Zircatec Precision Industries Inc. The fuel bundles manufactured at FCN Pitesti proved to be of excellent quality, operating with a very low defect rate, all defected fuel being reported in the first period of the reactor operation. It is a fact now that FCN has the capability to solve a wide variety of aspects one of the most significant being the development of new equipment and the increase of the capacity in order to cover the future nuclear fuel needs. On this basis FCN was invited to contribute with his potential to a supplying contract with China National Nuclear Corporation - 202 Plant, for CANDU nuclear fuel technology. Following an offer including several categories of equipment and technology, the option was for beryllium coaters and coating technology and training for end cap manufacturing. The arrangements consider Romanian company as a sub-supplier, this option ensuring the consistence with the largest part of the supply for CANDU fuel technology, offered by Zircatec. Two pieces of beryllium coaters have been produced and tested in Romania and the operating demonstration was made in the presence of Zircatec staff and Chinese delegates. The Chinese delegated were trained for complete operating modes and their ability to handle the equipment was certified accordingly. They also have been trained in the end cap technology and related quality inspection. The paper includes a short presentation of the equipment and associated work to fit the specified needs. The involvement of the Romanian fuel plant in this contract could be considered as an extension of the previous co-operation with the Canadian partners on CANDU nuclear fuel and finally

  18. A proposed structural, risk-informed approach to the periodicity of CANDU-6 nuclear containment integrated leak rate testing

    Energy Technology Data Exchange (ETDEWEB)

    Saliba, N. [McGill Univ., Dept. of Civil Engineering and Applied Mechanics, Montreal, Quebec (Canada); Komljenovic, D. [Hydro-Quebec, Gentilly-2 Nuclear Power Plant, Becancour, Quebec (Canada); Chouinard, L. [McGill Univ., Dept. of Civil Engineering and Applied Mechanics, Montreal, Quebec (Canada); Vaillancourt, R.; Chretien, G. [Hydro-Quebec, Gentilly-2 Nuclear Power Plant, Becancour, Quebec (Canada); Gocevski, V. [Hydro-Quebec Equipements, Montreal, Quebec (Canada)

    2010-07-01

    As ultimate lines of defense against leakage of large amounts of radioactive material to the environment in case of major reactor accidents, containments have been monitored through well designed periodic tests to ensure their proper performance. Regulatory organizations have imposed types and frequencies of containment tests based on highly-conservative deterministic approaches, and judgments of knowledgeable experts. Recent developments in the perception and methods of risk evaluation have been applied to rationalize the leakage-rate testing frequencies while maintaining risks within acceptable levels, preserving the integrity of containments, and respecting the defense-in-depth philosophy. The objective of this paper is to introduce a proposed risk-informed decision making framework on the periodicity of nuclear containment ILRTs for CANDU-6 nuclear power plants based on five main decision criteria, namely: 1) the containment structural integrity; 2) inputs from PSA Level-2; 3) the requirements of deterministic safety analyses and defense-in-depth concepts; 4- the obligations under regulatory and standard requirements; and 5) the return of experience from nuclear containments historic performance. The concepts of dormant reliability and structural fragility will guide the assessment of the containment structural integrity, within the general context of a global containment life cycle management program. This study is oriented towards the requirements of CANDU-6 reactors, in general, and Hydro-Quebec's Gentilly-2 nuclear power plant, in particular. The present article is the first part in a series of papers that will comprehensively detail the proposed research. (author)

  19. CANDU safety under severe accidents

    International Nuclear Information System (INIS)

    The characteristics of the CANDU reactor relevant to severe accidents are set first by the inherent properties of the design, and second by the Canadian safety/licensing approach. Probabilistic safety assessment studies have been performed on operating CANDU plants, and on the 4 x 880 MW(e) Darlington station now under construction; furthermore a scoping risk assessment has been done for a CANDU 600 plant. They indicate that the summed severe core damage frequency is of the order of 5 x 10-6/year. CANDU nuclear plant designers and owner/operators share information and operational experience nationally and internationally through the CANDU Owners' Group (COG). The research program generally emphasizes the unique aspects of the CANDU concept, such as heat removal through the moderator, but it has also contributed significantly to areas generic to most power reactors such as hydrogen combustion, containment failure modes, fission product chemistry, and high temperature fuel behaviour. Abnormal plant operating procedures are aimed at first using event-specific emergency operating procedures, in cases where the event can be diagnosed. If this is not possible, generic procedures are followed to control Critical Safety Parameters and manage the accident. Similarly, the on-site contingency plans include a generic plan covering overall plant response strategy, and a specific plan covering each category of contingency

  20. Nuclear power

    International Nuclear Information System (INIS)

    The subject is covered in chapters entitled: nuclear power certainties and doubts; nuclear power in the Western World to 2000; the frequency of core meltdown accidents; hidden costs of the accident at Three Mile Island; costs of nuclear accidents - implications for reactor choice; defining the risks of nuclear power; the uncertain economics of a nuclear power program; the economics of enabling decisions (Sizewell B as an enabling decision); trade in nuclear electricity; some pointers to the future. (U.K.)

  1. Enhancing the seismic capability of the on-power refueling system of the CANDU reactor

    International Nuclear Information System (INIS)

    The CANDU reactor assembly includes several hundred horizontal fuel channels, each containing twelve fuel bundles, arranged in a square lattice, and supported by the reactor structures. CANDU operates on natural uranium or other low fissile content fuel, and is refueled on-power, with either four or eight fuel bundles in a channel being replaced during each refueling operation. The fueling machines clamp onto the opposite ends of the fuel channel to be refueled. The seismic capacity of this refueling system is evaluated in terms of its dynamic response during an earthquake. This paper describes the approach adopted to enhance the seismic capability of the fueling machine and calandria assembly for earthquakes of O.3g ground acceleration covering a broad range of soil conditions ranging from soft to hard. A detailed, 3-D finite element seismic model of the fueling machine and calandria assembly system is developed to calculate the seismic responses of the structure. Some relatively simple hardware design changes have been considered to increase the seismic capacity of the CANDU 6 reactor. These changes in the fueling machine and calandria assembly of the CANDU 6 reactor are briefly described. They have been incorporated into the finite element seismic model of the system. Most of these design changes have already been considered and implemented in other CANDU reactor projects. The current CANDU 6 reactor design fully meets the requirements of seismic qualification for sites with potential for O.2g ground acceleration where the seismic loads need to be combined with the other design loads for the support and pressure boundary components to demonstrate compliance with the applicable Code requirements. In the present study it is demonstrated that, with relatively simple hardware changes, the fueling machine and calandria assembly of the CANDU 6 reactor can withstand earthquakes of O.3g ground acceleration. Based on the current study and some preliminary analysis of the

  2. Investigation of techniques for the application of safeguards to the CANDU 600 MW(e) nuclear generating station

    International Nuclear Information System (INIS)

    A cooperative program with the Canadian Atomic Energy Control Board, Atomic Energy of Canada Limited and the IAEA was established in 1975: to determine the diversion possibilities at the CANDU type reactors using a diversion path analysis; to detect the diversion of nuclear materials using material accountancy and surveillance/containment. Specific techniques and instrumentation, some of which are unique to the CANDU reactor, were developed. 10 appendices bring together the relevant reports and memoranda of results for the Douglas Point Program

  3. Operations quality assurance for nuclear power plants

    International Nuclear Information System (INIS)

    This standard covers the quality assurance of all activities concerned with the operation and maintenance of plant equipment and systems in CANDU-based nuclear power plants during the operations phase, the period between the completion of commissioning and the start of decommissioning

  4. Ontario Hydro CANDU operating experience

    International Nuclear Information System (INIS)

    The CANDU Pressurized Heavy Water (CANDU-PHW) type of nuclear-electric generating station has been developed jointly by Atomic Energy of Canada Limited and Ontario Hydro. This report highlights Ontario Hydro's operating experience using the CANDU-PHW system, with a focus on the operating performance and costs, reliability of system components and nuclear safety considerations for the workers and the public

  5. Nuclear power

    OpenAIRE

    Waller, David; McDonald, Alan; Greenwald, Judith; Mobbs, Paul

    2005-01-01

    David Waller and Alan McDonald ask whether a nuclear renaissance can be predicted; Judith M. Greenwald discusses keeping the nuclear power option open; Paul Mobbs considers the availability of uranium and the future of nuclear energy.

  6. Recent experience related to neutronic transients in Ontario Hydro CANDU nuclear generating stations

    International Nuclear Information System (INIS)

    Ontario Hydro presently operates 18 CANDU reactors in the province of Ontario, Canada. All of these reactors are of the CANDU Pressurized Heavy Water design, although their design features differ somewhat reflecting the evolution that has taken place from 1971 when the first Pickering unit started operation to the present as the Darlington units are being placed in service. Over the last three years, two significant neutronic transients took place at the Pickering Nuclear Generating Station 'A' (NGS A) one of which resulted in a number of fuel failures. Both events provided valuable lessons in the areas of operational safety, fuel performance And accident analysis. The events and the lessons learned are discussed in this paper

  7. Korea signs for 2nd CANDU at Wolsong

    International Nuclear Information System (INIS)

    The sale of a second CANDU 6 reactor to Korea for the Wolsong site is discussed in relation to nuclear power in Korea, the Korean economy generally, Canadian trade with Korea, and cooperation between AECL and KAERI

  8. Simulation-based reactor control design methodology for CANDU 9

    Energy Technology Data Exchange (ETDEWEB)

    Kattan, M.K.; MacBeth, M.J. [Atomic Energy of Canada Limited, Saskatoon, Saskatchewan (Canada); Chan, W.F.; Lam, K.Y. [Cassiopeia Technologies Inc., Toronto, Ontario (Canada)

    1996-07-01

    The next generation of CANDU nuclear power plant being designed by AECL is the 900 MWe CANDU 9 station. This design is based upon the Darlington CANDU nuclear power plant located in Ontario which is among the world leading nuclear power stations for highest capacity factor with the lowest operation, maintenance and administration costs in North America. Canadian-designed CANDU pressurized heavy water nuclear reactors have traditionally been world leaders in electrical power generation capacity performance. This paper introduces the CANDU 9 design initiative to use plant simulation during the design stage of the plant distributed control system (DCS), plant display system (PDS) and the control centre panels. This paper also introduces some details of the CANDU 9 DCS reactor regulating system (RRS) control application, a typical DCS partition configuration, and the interfacing of some of the software design processes that are being followed from conceptual design to final integrated design validation. A description is given of the reactor model developed specifically for use in the simulator. The CANDU 9 reactor model is a synthesis of 14 micro point-kinetic reactor models to facilitate 14 liquid zone controllers for bulk power error control, as well as zone flux tilt control. (author)

  9. Power distribution control of CANDU reactors based on modal representation of reactor kinetics

    Energy Technology Data Exchange (ETDEWEB)

    Xia, Lingzhi, E-mail: lxia4@uwo.ca [Department of Electrical and Computer Engineering, The University of Western Ontario, London, Ontario N6A 5B9 (Canada); Jiang, Jin, E-mail: jjiang@eng.uwo.ca [Department of Electrical and Computer Engineering, The University of Western Ontario, London, Ontario N6A 5B9 (Canada); Luxat, John C., E-mail: luxatj@mcmaster.ca [Department of Engineering Physics, McMaster University, Hamilton, Ontario L8S 4L7 (Canada)

    2014-10-15

    Highlights: • Linearization of the modal synthesis model of neutronic kinetic equations for CANDU reactors. • Validation of the linearized dynamic model through closed-loop simulations by using the reactor regulating system. • Design of a LQR state feedback controller for CANDU core power distribution control. • Comparison of the results of this new controller against those of the conventional reactor regulation system. - Abstract: Modal synthesis representation of a neutronic kinetic model for a CANDU reactor core has been utilized in the analysis and synthesis for reactor control systems. Among all the mode shapes, the fundamental mode of the power distribution, which also coincides with the desired reactor power distribution during operation, is used in the control system design. The nonlinear modal models are linearized around desired operating points. Based on the linearized model, linear quadratic regulator (LQR) control approach is used to synthesize a state feedback controller. The performance of this controller has been evaluated by using the original nonlinear models under load-following conditions. It has been demonstrated that the proposed reactor control system can produce more uniform power distribution than the traditional reactor regulation systems (RRS); in particular, it is more effective in compensating the Xenon induced transients.

  10. Validation of the COBRA code for dry out power calculation in CANDU type advanced fuels

    International Nuclear Information System (INIS)

    Stern Laboratories perform a full scale CHF testing of the CANFLEX bundle under AECL request. This experiment is modeled with the COBRA IV HW code to verify it's capacity for the dry out power calculation . Good results were obtained: errors below 10 % with respect to all data measured and 1 % for standard operating conditions in CANDU reactors range . This calculations were repeated for the CNEA advanced fuel CARA obtaining the same performance as the CANFLEX fuel. (author)

  11. Nuclear power

    International Nuclear Information System (INIS)

    This chapter of the final report of the Royal Commission on Electric Power Planning in Ontario updates its interim report on nuclear power in Ontario (1978) in the light of the Three Mile Island accident and presents the commission's general conclusions and recommendations relating to nuclear power. The risks of nuclear power, reactor safety with special reference to Three Mile Island and incidents at the Bruce generating station, the environmental effects of uranium mining and milling, waste management, nuclear power economics, uranium supplies, socio-political issues, and the regulation of nuclear power are discussed. Specific recommendations are made concerning the organization and public control of Ontario Hydro, but the commission concluded that nuclear power is acceptable in Ontario as long as satisfactory progress is made in the disposal of uranium mill tailings and spent fuel wastes. (LL)

  12. Ontario Hydro CANDU operating experience

    International Nuclear Information System (INIS)

    The CANDU Pressurized Heavy Water (CANDU-PHW) type of nuclear-electric generating station has been developed jointly by Atomic Energy of Canada Limited and Ontario Hydro. This report highlights Ontario Hydro's operating experience using the CANDU-PHW system, with a focus on worker and public safety, operating performance and costs, and reliability of system components

  13. Nuclear power - a reliable future

    International Nuclear Information System (INIS)

    The Ministry of Education and Research - Department of Research has implemented a national Research and Development program taking into consideration the following: - the requirements of the European Union on research as a factor of development of the knowledge-based society; - the commitments to the assimilation and enforcement of the recommendations of the European Union on nuclear power prompted by the negotiations of the sections 'Science and Research' and ' Energy' of the aquis communautaire; - the major lines of interest in Romania in the nuclear power field established by National Framework Program of Cooperation with IAEA, signed on April 2001; - the short and medium term nuclear options of the Romanian Government; - the objectives of the National Nuclear Plan. The major elements of the nuclear research and development program MENER (Environment, Energy, Resources) supported by the Department of Research of the Ministry of Education and Research are the following: - reactor physics and nuclear fuel management; - operation safety of the Power Unit 1 of Cernavoda Nuclear Electric Power Station; - improved nuclear technological solutions at the Cernavoda NPP; - development of technologies for nuclear fuel cycle; - operation safety of the other nuclear plants in Romania; - assessment of nuclear risks and estimation of the radiological impact on the environment; - behavior of materials under the reactor service conditions and environmental conditions; - design of nuclear systems and equipment for the nuclear power stations and nuclear facilities; - radiological safety; - application of nuclear techniques and technologies in industry, agriculture, medicine and other fields of social life. Research to develop high performance methods and equipment for monitoring nuclear impact on environment are conducted to endorse the measures for radiation protection. Also mentioned are the research on implementing a new type of nuclear fuel cycle in CANDU reactors as well as

  14. Nuclear power as a regional energy supply

    International Nuclear Information System (INIS)

    The author describes the Point Lepreau nuclear power plant and its impact on the electric power grid and the economy of the small province of New Brunswick. The 600 MW CANDU reactor is considered suitable for small operations and has an excellent world record. Although nuclear energy has high capital costs, its fuel costs are low, thus rendering it comparatively inflation free. Its fuel costs of 3 to 4 mills are contrasted with 40 mills for oil-fuelled units. The cost advantage of uranium over coal and oil permits New Brunswick to put aside funds for waste management and decommissioning. Regulatory streamlining is needed to reduce both expense and time of construction. The CANDU system is ideally suited to providing base load, with coal as an intermediate load supply and hydro for peaking. There is room for tidal power as a future part of the mix

  15. Some aspects on security and safety in a potential transport of a CANDU spent nuclear fuel bundle, in Romania

    International Nuclear Information System (INIS)

    Each Member States (MS) is responsible for the security and safety of radioactive material during transport, since radioactive material is most vulnerable during transport. The paper presents some aspects on security and safety related to the potential transport of a CANDU Spent Nuclear Fuel (SNF) bundle from NPP CANDU Cernavoda to INR Pitesti. The possible environmental impact and radiological consequences following a potential event during transportation is analyzed, since the protection of the people and the environment is the essential goal to be achieved. Some testing for the package to be used for transportation will be also given. (author)

  16. Multi-step approach to Code-coupling for progression induced severe accidents in CANDU NPPs (MACPISA-CANDU)

    Energy Technology Data Exchange (ETDEWEB)

    Pohl, D.J.; Luxat, J.C. [McMaster Univ., Dept. of Engineering Physics, Hamilton, Ontario (Canada); Giannotti, W.; D' Auria, F. [Univ. of Pisa, Dept. of Mechanical, Nuclear and Production Engineering, Pisa (Italy)

    2009-07-01

    This paper reviews the progression of severe accidents, describes computer codes currently employed for analysis of severe accidents and outlines a new methodology to modelling the progression of severe accidents in CANDU nuclear power plants (NPPs) called the Multi-step Approach to Code-coupling for Progression Induced Severe Accidents in CANDU NPPs (MACPISA-CANDU). The MACPISA-CANDU methodology was used to couple the U.S. NRC codes SCDAP/RELAP5 (RELAP/SCDAPSIM Mod 3.4) and MELCOR (1.8.5) in order to model a small break loss of coolant accident with loss of emergency coolant injection (SBLOCA-LOECI) under natural circulation in a CANDU 6 NPP. Using this model it was shown that the sheath temperature did not exceed the zirconium melting temperature of 2098 K and hence the progression of the severe accident was terminated as expected. (author)

  17. The evolution of the CANDU energy system - ready for Europe's energy future

    International Nuclear Information System (INIS)

    As air quality and climate change issues receive increasing attention, the opportunity for nuclear to play a larger role in the coming decades also increases. The good performance of the current fleet of nuclear plants is crucial evidence of nuclear's potential. The excellent record of Cernavoda-1 is an important part of this, and demonstrates the maturity of the Romanian program and of the CANDU design approach. However, the emerging energy market also presents a stringent economic challenge. Current NPP designs, while established as reliable electricity producers, are seen as limited by high capital costs. In some cases, the response to the economic challenge is to consider radical changes to new design concepts, with attendant development risks from lack of provenness. Because of the flexibility of the CANDU system, it is possible to significantly extend the mid-size CANDU design, creating a Next Generation product, without sacrificing the extensive design, delivery and operations information base for CANDU. This enables a design with superior safety characteristics while at the same time meeting the economic challenge of emerging markets. The Romanian nuclear program has progressed successfully forward, leading to the successful operation of Cernavoda-1, and the project to bring Cernavoda-2 to commercial operation. The Romanian nuclear industry has become a full-fledged member of the CANDU community, with all areas of nuclear technology well established and benefiting from international cooperation with other CANDU organizations. AECL is an active partner with Romanian nuclear organizations, both through cooperative development programs, commercial contracts, and also through the activities of the CANDU owners' Group (COG). The Cernavoda project is part of the CANDU 6 family of nuclear power plants developed by AECL. The modular fuel channel reactor concept can be modified extensively, through a series of incremental changes, to improve economics, safety

  18. General overview of CANDU advanced fuel cycles program

    International Nuclear Information System (INIS)

    The R and D program for CANDU advanced fuel cycles may be roughly divided into two components which have a near-and long-term focus, respectively. The near-term focus is on the technology to implement improved once-through cycles and mixed oxide (plutonium-uranium oxides) recycle in CANDU and on technologies to separate zirconium isotopes. Included is work on those technologies which would allow a CANDU-LWR strategy to be developed in a growing nuclear power system. For the longer-term, activities are focused on those technologies and fuel cycles which would be appropriate in a period when nuclear fuel demand significantly exceeds mined uranium supplies. Fuel cycles and systems under study are thorium recycle, CANDU fast breeder systems and electro-nuclear fissile breeders. The paper will discuss the rationale underlying these activities, together with a brief description of activities currently under way in each of the fuel cycle technology areas

  19. CANDU safety and licensing framework and process

    International Nuclear Information System (INIS)

    Nuclear Safety is a shared responsibility of the Industry, public and the Government. The International Atomic Energy Agency's (IAEA) safety fundamentals, basic objectives and safety guides lay down the principles from which requirements, recommendations and methodologies for safety design of Nuclear Power Plants (NPP) are derived. Within the framework of the international regulations and those of the Canadian Nuclear Safety Commission (CNSC), this paper will discuss the overall safety objectives, the defence in depth philosophy guiding CANDU safety, as well as the licensing process defined to meet all applicable CNSC regulations. The application of such philosophy to the ACR design and safety approach will also be discussed along with aspects of its implementation. The role of deterministic analysis, and Probabilistic Safety Analysis (PSA) in the design and licensing process of the Advanced CANDU Reactor will be discussed. Postulated initiating events and their combinations, acceptance criteria, CANDU margins and limits, supporting methodologies and computer codes used in safety analysis will be reviewed. The paper will also note intrinsic safety characteristics of CANDU, some of the ACR passive safety features built-in by design, CANDU distinctive features with respect to severe core damage, mechanisms of heat rejection in those extreme conditions, emergency coolant injection system features and other post accident mitigating systems. Update on the ACR Canadian and US licensing progress will also be provided. (authors)

  20. Power pulse tests on CANDU type fuel elements in TRIGA reactor of INR Pitesti

    International Nuclear Information System (INIS)

    Pulse irradiation tests on short fuel elements have been carried out in TRIGA Annular Core Pulse Reactor (TRIGA ACPR) of INR Pitesti to investigate aspects related to the thermal and mechanical behavior of CANDU type fuel elements under short duration and large amplitude power pulse conditions. Short test fuel elements were instrumented with thermocouples for cladding surface temperature measurements and pressure sensor for element internal pressure measurement. Transient histories of reactor power, cooling water pressure, fuel element internal pressure and cladding temperature were recorded during tests. The fuel elements were subjected to total energy deposition from 70 to 280cal g-1 UO2. Rapid fuel pellet expansion due to a power excursion caused radial and longitudinal deformation of the cladding. Cladding failure mechanism and the failure threshold have been established. This paper presents some recent results obtained from these power pulse tests performed in TRIGA ACPR of INR Pitesti. (author)

  1. Behavior of CANDU fuel under power pulse conditions at the TRIGA reactor of INR Pitesti

    International Nuclear Information System (INIS)

    Pulse irradiation tests on short fuel elements have been carried out in TRIGA Annular Core Pulse Reactor (TRIGA ACPR) of INR Pitesti to investigate aspects related to the thermal and mechanical behavior of CANDU type fuel elements under short duration and large amplitude power pulse conditions. Short test fuel elements were instrumented with thermocouples for cladding surface temperature measurements and pressure sensors for element internal pressure measurement. Transient histories of reactor power, cooling water pressure, fuel element internal pressure and cladding temperature were recorded during tests. The fuel elements were subjected to total energy deposition from 70 to 280 cal g-1 UO2. Rapid fuel pellet expansion due to a power excursion caused radial and longitudinal deformation of the cladding. Cladding failure mechanism and the failure threshold have been established. This paper presents some recent results obtained from these power pulse tests performed in TRIGA ACPR of INR Pitesti. (orig.)

  2. A study to develop the domestic functional requirements of the specific safety systems of CANDU

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Man Woong; Lee, Jae Young; Bang, Kwang Hyun [Handong Global Univ., Pohang (Korea, Republic of)] (and others)

    2001-03-15

    The present research has been made to develop and review critically the functional requirements of the specific safety systems of CANDU such as SOS-1, SOS-2, ECCS and containment. Based on R documents for this, a systematic study was made to develop the domestic regulation statements. Also, the conventional laws are carefully reviewed to see the compatibility to CANDU. Also, the safety assessment method for CANDU was studied by reviewing C documents and recommendation of IAEA. Through the present works, the vague policy in the CANDU safety regulation is cleaning up in a systematic form and a new frame to measure the objective risk of nuclear power plants was developed.

  3. A study to develop the domestic functional requirements of the specific safety systems of CANDU

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Man Woong [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Lee, Jae Young; Park, Kun Chul [Handong Global Univ., Pohang (Korea, Republic of)] (and others)

    2003-03-15

    The present research has been made to develop and review critically the functional requirements of the specific safety systems of CANDU such as SDS-1, SDS2, ECCS, and containment. Based on R documents for this, a systematic study was made to develop the domestic regulation statements. Also, the conventional laws are carefully reviewed to see the compatibility to CANDU. Also, the safety assessment method for CANDU was studied by reviewing C documents and recommendation of IAEA. Through the present works, the vague policy in the CANDU safety regulation is cleaning up in a systematic form and a new frame to measure the objective risk of nuclear power plants was developed.

  4. Sensitivity of Candu-Scwr Reactor Physics Calculations to Nuclear Data Files

    Science.gov (United States)

    Kozier, K. S.; Dyck, G. R.

    2006-04-01

    A simplified MCNP model of a CANDU-SCWR lattice was used to test the sensitivity of the calculated reactivity to various nuclear data files involving issues of current interest. These tests were performed for cooled and voided conditions, with and without axial neutron leakage, for a uniform lattice of mid-life fuel and a mixed lattice with high-burnup and low-burnup fuel in alternate channels. Results were compared using different room-temperature data files for deuterium, various thermal-scattering-law data files for hydrogen bound in light water and deuterium bound in heavy water, and for pre-ENDF/B-VII and ENDF/B-VI.8 data for uranium. The reactivity differences observed were small (typically <1 mk) and increased with axial neutron leakage.

  5. ACR-1000TM - advanced Candu reactor design

    International Nuclear Information System (INIS)

    Atomic Energy of Canada Limited (AECL) has developed the Advanced CANDU ReactorTM- 1000 (ACR-1000TM) as an evolutionary advancement of the current CANDU 6TM reactor. This evolutionary advancement is based on AECL's in-depth knowledge of CANDU structures, systems, components and materials, gained during 50 years of continuous construction, engineering and commissioning, as well as on the experience and feedback received from operators of CANDU plants. The ACR design retains the proven strengths and features of CANDU reactors, while incorporating innovations and state-of-the-art technology. These innovations improve economics, inherent safety characteristics, and performance, while retaining the proven benefits of the CANDU family of nuclear power plants. The Canadian nuclear reactor design evolution that has reached today's stage represented by the ACR-1000, has a long history dating back to the early 1950's. In this regard, Canada is in a unique situation, shared only by a very few other countries, where original nuclear power technology has been invented and further developed. The ACR design has been reviewed by domestic and international regulatory bodies, and has been given a positive regulatory opinion about its licensability. The Canadian regulator, the Canadian Nuclear Safety Commission (CNSC) completed the Phase 1 and Phase 2 pre-project design reviews in December 2008 and August 2009, respectively, and concluded that there are no fundamental barriers to licensing the ACR-1000 design in Canada. The final stage of the ACR-1000 design is currently underway and will be completed by fall of 2011, along with the final elements of the safety analyses and probabilistic safety analyses supporting the finalized design. The generic Preliminary Safety Analysis Report (PSAR) for the ACR-1000 was completed in September 2009. The PSAR demonstrates ACR-1000 safety case and compliance with Canadian and international regulatory requirements and expectations. (authors)

  6. Optimization of the self-sufficient thorium fuel cycle for CANDU power reactors

    Directory of Open Access Journals (Sweden)

    Bergelson Boris R.

    2008-01-01

    Full Text Available The results of optimization calculations for CANDU reactors operating in the thorium cycle are presented in this paper. Calculations were performed to validate the feasibility of operating a heavy-water thermal neutron power reactor in a self-sufficient thorium cycle. Two modes of operation were considered in the paper: the mode of preliminary accumulation of 233U in the reactor itself and the mode of operation in a self-sufficient cycle. For the mode of accumulation of 233U, it was assumed that enriched uranium or plutonium was used as additional fissile material to provide neutrons for 233U production. In the self-sufficient mode of operation, the mass and isotopic composition of heavy nuclei unloaded from the reactor should provide (after the removal of fission products the value of the multiplication factor of the cell in the following cycle K>1. Additionally, the task was to determine the geometry and composition of the cell for an acceptable burn up of 233U. The results obtained demonstrate that the realization of a self-sufficient thorium mode for a CANDU reactor is possible without using new technologies. The main features of the reactor ensuring a self-sufficient mode of operation are a good neutron balance and moving of fuel through the active core.

  7. Marketing CANDU internationally

    International Nuclear Information System (INIS)

    The market for CANDU reactor sales, both international and domestic, is reviewed. It is reasonable to expect that between five and ten reactors can be sold outside Canada before the end of the centry, and new domestic orders should be forthcoming as well. AECL International has been created to market CANDU, and is working together with the Canadian nuclear industry to promote the reactor and to assemble an attractive package that can be offered abroad. (L.L.)

  8. The CANDU contribution to environmentally friendly energy production

    International Nuclear Information System (INIS)

    National prosperity is based on the availability of affordable, energy supply. However, this need is tempered by a complementary desire that the energy production and utilization will not have a major impact on the environment. The CANDU energy system, including a next generation of CANDU designs, is a major primary energy supply option that can be an important part of an energy mix to meet Canadian needs. CANDU nuclear power plants produce energy in the form of medium pressure steam. The advanced version of the CANDU design can be delivered in unit modules ranging from 400 to 1200 MWe. This Next Generation of CANDU designs features lower cost, coupled with robust safety margins. Normally this steam is used to drive a turbine and produce electricity. However, a fraction of this steam (large or small) may alternatively be used as process steam for industrial consumption. Options for such steam utilization include seawater desalination, oil sands extraction and heating. The electricity may be delivered to an electrical grid or alternatively used to produce quantities of hydrogen. Hydrogen is an ideal clean transportation fuel because its use only produces water. Thus, a combination of CANDU generated electricity and hydrogen distribution for vehicles is an available, cost-effective route to dramatically reduce emissions from the transportation sector. The CANDU energy system contributes to environmental protection and the prevention of climate change because of its very low emission. The CANDU energy system does not produce any NOx, SOx or greenhouse gas (notably CO2) emissions during operation. In addition, the CANDU system operates on a fully closed cycle with all wastes and emissions fully monitored, controlled and managed throughout the entire life cycle of the plant. The CANDU energy system is an environmentally friendly and flexible energy source. It can be an effective component of a total energy supply package, consistent with Canadian and global climate

  9. Nuclear power and durable development

    International Nuclear Information System (INIS)

    This paper highlights the role that the nuclear power can play in a durable development of society. From a comparative analysis of different energy sources capable to fulfil the national energy demand it turns out that for Romania the optimal alternative is nuclear power. The nuclear power proved its attributes and characteristics in ensuring durable development by: 1. the technological maturation of the CANDU system as demonstrated by the good functioning of Cernavoda NPP Unit 1; 2. optimal utilization of the uranium national resources as well as the mining industry; 3. uranium processing and nuclear fuel and heavy water manufacturing as entailed by an educational infrastructure, research and industrial development; 4. low environmental impact; 5. high professional skill of the nuclear personnel. In addition, the low cost of the energy produced by the nuclear sector, as well as the social effects, namely, a 100% utilization of industrial infrastructure and national research capacity, urges the decision makers to develop the Cernavoda NPP, to increase the weight of nuclear energy in the energy production of the country

  10. LOCA power pulse analysis for CANDU-6 CANFLEX-RU core

    International Nuclear Information System (INIS)

    The power pulses following a large LOCA are analyzed for CANDU-6 reactor core fuelled with CANFLEX-RU fuel. The coupled simulations for reactor physics and channel thermal-hydraulic phenomena are done using RFSP and CATHENA codes. The 55% pump suction, 35% reactor inlet header and 100% reactor outlet header breaks are selected. The highest power pulse is predicted for 100% reactor outlet header break and it is higher than that for the standard 37-element natural fuel. However, the summation of initial stored energy and transient pulse energy of hottest pin has the minimum 17% margin to the fuel break up. Therefore, it is expected that there is no fuel breakup during the LOCA for CANFLEX-RU core

  11. CANDU steam generator life management

    International Nuclear Information System (INIS)

    Steam generators are a critical component of a nuclear power reactor, and can contribute significantly to station unavailability, as has been amply demonstrated in Pressurized Water Reactors (PWRs). CANDU steam generators are not immune to steam generator degradation, and the variety of CANDU steam generator designs and tube materials has led to some unexpected challenges. However, aggressive remedial actions, and careful proactive maintenance activities, have led to a decrease in steam generator-related station unavailability of Canadian CANDUs. AECL and the CANDU utilities have defined programs that will enable existing or new steam generators to operate effectively for 40 years. Research and development work covers corrosion and mechanical degradation of tube bundles and internals, chemistry, thermalhydraulics, fouling, inspection and cleaning, as well as provision for specially tool development for specific problem solving. A major driving force is development of CANDU-specific fitness-for-service guidelines, including appropriate inspection and monitoring technology to measure steam generator condition. Longer-range work focuses on development of intelligent on-line monitoring for the feedwater system and steam generator. New designs have reduced risk of corrosion and fouling, are more easily inspected and cleaned, and are less susceptible to mechanical damage. The Canadian CANDU utilities have developed programs for remedial actions to combat degradation of performance (Gentilly-2, Point Lepreau, Bruce A/B, Pickering A/B), and have developed strategic plans to ensure that good future operation is ensured. The research and development program, as well as operating experience, has identified where improvements in operating practices and/or designs can be made in order to ensure steam generator design life at an acceptable capacity factory. (author)

  12. An analysis to determine industry's preferred option for an initial generic reliability database for CANDU

    Energy Technology Data Exchange (ETDEWEB)

    Komljenovic, D. [Hydro Quebec, Montreal, Quebec (Canada)], E-mail: komljenovic.dragan@hydro.qc.ca; Chan, E. [Bruce Power, Tiverton, Ontario (Canada); Ganguli, S. [Ontario Power Generation, Ontario (Canada); Wu, J. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Parmar, R. [Nuclear Safety Solutions Ltd., Toronto, Ontario (Canada)

    2008-07-01

    The paper presents a multi-attribute analysis approach that was used to choose the industry's preferred option in developing a generic reliability database for CANDU. The Risk and Reliability Working Group (sponsored by CANDU Owners Group - Nuclear Safety Committee - COG NSC) was faced with the decision to assess in depth the following four options: a) Use External Data Base Only; b) Full CANDU generic database (All Utilities); c) CANDU Specific plus External Generic Databases; d) Ontario Power Generation (OPG)/ Bruce Power (BP) Experience Only. Nine decision criteria were utilized to rank the proposed options (alternatives). The Analytic Hierarchy Process (AHP) was used in carrying out the ranking process. (author)

  13. Project planning and scheduling techniques for the CANDU programme - an overview

    International Nuclear Information System (INIS)

    The energy crisis and higher costs have imposed the need for tighter control of completion time for the construction of CANDU nuclear power plants. System procedures and techniques to meet this challenge are described

  14. Nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Hodgson, P.

    1985-01-01

    The question 'Do we really need nuclear power' is tackled within the context of Christian beliefs. First, an estimate is made of the energy requirements in the future and whether it can be got in conventional ways. The dangers of all the ways of supplying energy (eg coal mining, oil and gas production) are considered scientifically. Also the cost of each source and its environmental effects are debated. The consequences of developing a new energy source, as well as the consequences of not developing it, are considered. Decisions must also take into account a belief about the ultimate purpose of life, the relation of men to each other and to nature. Each issue is raised and questions for discussion are posed. On the whole the book comes down in favour of nuclear power.

  15. CANDU 9 safety enhancements and licensability

    International Nuclear Information System (INIS)

    The CANDU 9 design has followed the evolutionary product development approach that has characterized the CANDU family of nuclear power plants. In addition to utilizing proven equipment and systems from operating stations, the CANDU 9 design has looked ahead to incorporate design and safety enhancements necessary to meet evolving utility and regulatory requirements both in Canada and overseas. To demonstrate licensability in Canada, and to assure overseas customers that the design had independent regulatory review in the country of origin, the pre-project Basic Engineering Program included an extensive two year formal review by the Canadian regulatory authority, the Atomic Energy Control Board (AECB). Documentation submitted for this licensing review included the licensing basis, safety requirements and safety analysis necessary to demonstrate compliance with regulations as well as to assess system design and performance. The licensing review was successfully completed in 1997 January. In addition, to facilitate licensability in Korea, CANDU 9 incorporates feedback from the application of Korean licensing requirements to the CANDU 6 reactors at Wolsong site. (author)

  16. Nuclear power data 2016

    International Nuclear Information System (INIS)

    The brochure on nuclear power data 2016 covers the following topics: (I) nuclear power in Germany: nuclear power plants in Germany; shut-down and decommissioned nuclear power plants, gross electricity generation, primary energy consumption; (II) nuclear power worldwide: nuclear electricity production, nuclear power plants.

  17. New nuclear power plants for Ontario

    International Nuclear Information System (INIS)

    Towards the end of this year the Ontario government will select the technology for its future nuclear power plants. To clarify the differences between the contending reactors I have put together the following quick overview. Ontario's requirement is for a stand-alone two-unit nuclear power plant to provide around 2,000 to 3,500 MWe of baseload generating capacity at a site to he specified with an option for one or two additional units. It is likely that the first units will be located at either the Darlington site near Bowmanville or the Bruce site near Kincardine. However the output from the Bruce site is presently transmission constrained. All nuclear-electric generation in Ontario comes from Atomic Energy of Canada Limited's (AECL) CANDU reactors at Pickering, Darlington and Bruce. The contenders are, AECL's 1085 MWe (net) ACR-1000 (Advanced CANDU Reactor), Westinghouse Electric Company's 1117 MWe (net) AP1000 (Advanced Passive), AREVA NP's 1600 MWe (net) U.S. EPR (United States Evolutionary Pressurized Reactor) and the 1550 MWe (net) GE Hitachi Nuclear Energy's ESBWR (Economic and Simplified Boiling Water Reactor). Westinghouse has Toshiba as a majority shareholder, AREVA has the government of France as a majority shareholder and GE-Hitachi has GE as the major shareholder. AECL is a federal crown corporation and is part of Team CANDU consisting of Babcock and Wilcox Canada, GE-Hitachi Nuclear Energy Canada Inc., Hitachi Canada Limited and SNC-Lavalin Nuclear Inc. Generally the engineering split in Team CANDU would be, AECL, Mississauga, Ontario, responsible for the design of the nuclear steam plant including reactor and safety systems; Babcock and Wilcox Canada, Cambridge, Ontario, responsible for supply of the steam generators and other pressure retaining components; GE-Hitachi Nuclear Energy Canada Inc., Peterborough, Ontario for the fuel handling equipment; Hitachi Canada Limited, Mississauga, for the balance of plant steam to electricity conversion

  18. Incentives for improvement of CANDU

    International Nuclear Information System (INIS)

    CANDU is a relatively young technology which has demonstrated many achievements as an electrical power generation system. These achievements include an unsurpassed safety record, high annual and lifetime capacity factors, low electricity cost and a broad range of other performance strengths which together indicate that the CANDU technology is fundamentally sound. Known capabilities not yet fully exploited, such as advanced fuel cycle options, indicate that CANDU technology will continue to pay strong dividends on research, development and design investment. This provides a strong incentive for the improvement of CANDU on a continuing basis

  19. Nuclear power and nuclear weapons

    International Nuclear Information System (INIS)

    The proliferation of nuclear weapons and the expanded use of nuclear energy for the production of electricity and other peaceful uses are compared. The difference in technologies associated with nuclear weapons and nuclear power plants are described

  20. Nuclear Theory - Nuclear Power

    Science.gov (United States)

    Svenne, J. P.; Canton, L.; Kozier, K. S.

    2008-01-01

    The results from modern nuclear theory are accurate and reliable enough to be used for practical applications, in particular for scattering that involves few-nucleon systems of importance to nuclear power. Using well-established nucleon-nucleon (NN) interactions that fit well the NN scattering data, and the AGS form of the three-body theory, we have performed precise calculations of low-energy neutron-deuteron (n+d) scattering. We show that three-nucleon force effects that have impact on the low-energy vector analyzing powers have no practical effects on the angular distribution of the n+d cross-section. There appear to be problems for this scattering in the evaluated nuclear data file (ENDF) libraries, at the incident neutron energies less than 3.2 MeV. Supporting experimental data in this energy region are rather old (>25 years), sparse and often inconsistent. Our three-body results at low energies, 50 keV to 10.0 MeV, are compared to the ENDF/B-VII.0 and JENDL (Japanese Evaluated Nuclear Data Library) -3.3 evaluated angular distributions. The impact of these results on the calculated reactivity for various critical systems involving heavy water is shown.

  1. Overview of methods to increase dryout power in CANDU fuel bundles

    Energy Technology Data Exchange (ETDEWEB)

    Groeneveld, D.C., E-mail: degroeneveld@gmail.com [Chalk River Laboratories, AECL, Chalk River (Canada); University of Ottawa, Department of Mechanical Engineering, Ottawa (Canada); Leung, L.K.H. [Chalk River Laboratories, AECL, Chalk River (Canada); Park, J.H. [Korean Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-06-15

    Highlights: • Small changes in bundle geometry can have noticeable effects on the bundle CHF. • Rod spacing devices can results in increases of over 200% in CHF. • CHF enhancement decays exponentially downstream from spacers. • CHF-enhancing bundle appendages also increase the post-CHF heat transfer. - Abstract: In CANDU reactors some degradation in the CCP (critical channel power, or power corresponding to the first occurrence of CHF in any fuel channel) will occur with time because of ageing effects such as pressure-tube diametral creep, increase in reactor inlet-header temperature, increased hydraulic resistance of feeders. To compensate for the ageing effects, various options for recovering the loss in CCP are described in this paper. They include: (i) increasing the bundle heated perimeter, (ii) optimizing the bundle configuration, (iii) optimizing core flow and flux distribution, (iv) reducing the bundle hydraulic resistance, (v) use of CHF-enhancing bundle appendages, (vi) more precise experimentation, and (vii) redefining CHF. The increase in CHF power has been quantified based on experiments on full-scale bundles and subchannel code predictions. The application of several of these CHF enhancement principles has been used in the development of the 43-rod CANFLEX bundle.

  2. Development of Off-take Model, Subcooled Boiling Model, and Radiation Heat Transfer Input Model into the MARS Code for a Regulatory Auditing of CANDU Reactors

    International Nuclear Information System (INIS)

    Korea currently has four operating units of the CANDU-6 type reactor in Wolsong. However, the safety assessment system for CANDU reactors has not been fully established due to a lack of self-reliance technology. Although the CATHENA code had been introduced from AECL, it is undesirable to use a vendor's code for a regulatory auditing analysis. In Korea, the MARS code has been developed for decades and is being considered by KINS as a thermal hydraulic regulatory auditing tool for nuclear power plants. Before this decision, KINS (Korea Institute of Nuclear Safety) had developed the RELAP5/MOD3/CANDU code for CANDU safety analyses by modifying the model of the existing PWR auditing tool, RELAP5/MOD3. The main purpose of this study is to transplant the CANDU models of the RELAP5/MOD3/CANDU code to the MARS code including a quality assurance of the developed models

  3. Development of Off-take Model, Subcooled Boiling Model, and Radiation Heat Transfer Input Model into the MARS Code for a Regulatory Auditing of CANDU Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, C.; Rhee, B. W.; Chung, B. D. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Ahn, S. H.; Kim, M. W. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2009-05-15

    Korea currently has four operating units of the CANDU-6 type reactor in Wolsong. However, the safety assessment system for CANDU reactors has not been fully established due to a lack of self-reliance technology. Although the CATHENA code had been introduced from AECL, it is undesirable to use a vendor's code for a regulatory auditing analysis. In Korea, the MARS code has been developed for decades and is being considered by KINS as a thermal hydraulic regulatory auditing tool for nuclear power plants. Before this decision, KINS (Korea Institute of Nuclear Safety) had developed the RELAP5/MOD3/CANDU code for CANDU safety analyses by modifying the model of the existing PWR auditing tool, RELAP5/MOD3. The main purpose of this study is to transplant the CANDU models of the RELAP5/MOD3/CANDU code to the MARS code including a quality assurance of the developed models.

  4. Operation of CANDU power reactor in thorium self-sufficient fuel cycle

    Indian Academy of Sciences (India)

    B R Bergelson; A S Gerasimov; G V Tikhomirov

    2007-02-01

    This paper presents the results of calculations for CANDU reactor operation in thorium fuel cycle. Calculations are performed to estimate the feasibility of operation of heavy-water thermal neutron power reactor in self-sufficient thorium cycle. Parameters of active core and scheme of fuel reloading were considered to be the same as for standard operation in uranium cycle. Two modes of operations are discussed in the paper: mode of preliminary accumulation of 233U and mode of operation in self-sufficient cycle. For the mode of accumulation of 233U it was assumed for calculations that plutonium can be used as additional fissile material to provide neutrons for 233U production. Plutonium was placed in fuel channels, while 232Th was located in target channels. Maximum content of 233U in target channels was estimated to be ∼ 13 kg/t of ThO2. This was achieved by irradiation for six years. The start of the reactor operation in the self-sufficient mode requires 233U content to be not less than 12 kg/t. For the mode of operation in self-sufficient cycle, it was assumed that all channels were loaded with identical fuel assemblies containing ThO2 and certain amount of 233U. It is shown that nonuniform distribution of 233U in fuel assembly is preferable.

  5. The mode of operation of CANDU power reactor in thorium self-sufficient fuel cycle

    Directory of Open Access Journals (Sweden)

    Bergelson Boris R.

    2008-01-01

    Full Text Available This paper presents the results of calculations for CANDU reactor operation in the thorium fuel cycle. The calculations were performed to estimate feasibility of operation of a heavy-water thermal neutron power reactor in the self-sufficient thorium cycle. The parameters of the active core and the scheme of fuel reloading were considered to be the same as for the standard operation in the uranium cycle. Two modes of operation are discussed in the paper: the mode of preliminary accumulation of 233U and the mode of operation in the self-sufficient cycle. For calculations for the mode of accumulation of 233U, it was assumed that plutonium was used as the additional fissile material to provide neutrons for 233U production. Plutonium was placed in fuel channels, while 232Th was located in target channels. The maximum content of 233U in the target channels was about 13 kg/t of ThO2. This was achieved by six year irradiation. The start of reactor operation in the self-sufficient mode requires content of 233U not less than 12 kg/t. For the mode of operation in the self-sufficient cycle, it was assumed that all the channels were loaded with the identical fuel assemblies containing ThO2 and a certain amount of 233U. It was shown that the non-uniform distribution of 233U in a fuel assembly is preferable.

  6. Applicability of a track-based multiprocess portable robot to some maintenance tasks in CANDU nuclear plants

    International Nuclear Information System (INIS)

    Hydro-Quebec has developed a six-axis, track-based, multiprocess robot. This lightweight (30 kg) compact robot travels on a bent track with a radius of curvature ranging from 1 m to infinity (straight track). Standard and tandem wires GMAW, FCAW and Narrow gap TIG welding as well as plasma gouging and cutting, electrical and pneumatic rough and precision grinding, and profile measurement functionalities have been incorporated. A description of this technology an its newly developed functionalities is given in this paper. Since 1995, a number of industrial and R and D projects have been performed using this technology now called the Scompi technology. The main field of application is the in situ repair of hydraulic turbine runners. However some applications have been developed in the nuclear field. One particular development was funded by the International Thermonuclear Experimental Reactor (ITER) project. Scompi was selected by the ITER US Home Team for a demonstration of remote techniques for welding, cutting and rewelding the 30 m diameter, 17 m high, vacuum vessel. The demonstration involved all position robotic plasma cutting and NG-TIG welding of a 316L, 40 mm thick, double wall. In 1998, two Scompi robots working in tandem performed in York, Pa, the joint welding and cutting of a full scale portion of the vacuum vessel. In 1995, the applicability of the Scompi technology to the repair of the divider plates in the four steam generators at Gentilly-2 was evaluated based on a joint proposal by Ontario Hydro Technologies (now Ontario Power Technologies-OPT) and Hydro-Quebec. A MIG welding procedure was proposed for the horizontal and vertical divider plates welds. A complete simulation of the robot and primary head demonstrated the feasibility of the concept. However, based on cost and scheduling, it was decided to proceed with a manual repair. Nevertheless it is anticipated that this technology will find its niche in the maintenance of Candu reactors. (author)

  7. Applicability of a track-based multiprocess portable robot to some maintenance tasks in CANDU nuclear plants

    Energy Technology Data Exchange (ETDEWEB)

    Hazel, B.; Fihey, J.-L.; Laroche, Y. [Hydro-Quebec, Varennes, Quebec (Canada)

    2000-07-01

    Hydro-Quebec has developed a six-axis, track-based, multiprocess robot. This lightweight (30 kg) compact robot travels on a bent track with a radius of curvature ranging from 1 m to infinity (straight track). Standard and tandem wires GMAW, FCAW and Narrow gap TIG welding as well as plasma gouging and cutting, electrical and pneumatic rough and precision grinding, and profile measurement functionalities have been incorporated. A description of this technology an its newly developed functionalities is given in this paper. Since 1995, a number of industrial and R and D projects have been performed using this technology now called the Scompi technology. The main field of application is the in situ repair of hydraulic turbine runners. However some applications have been developed in the nuclear field. One particular development was funded by the International Thermonuclear Experimental Reactor (ITER) project. Scompi was selected by the ITER US Home Team for a demonstration of remote techniques for welding, cutting and rewelding the 30 m diameter, 17 m high, vacuum vessel. The demonstration involved all position robotic plasma cutting and NG-TIG welding of a 316L, 40 mm thick, double wall. In 1998, two Scompi robots working in tandem performed in York, Pa, the joint welding and cutting of a full scale portion of the vacuum vessel. In 1995, the applicability of the Scompi technology to the repair of the divider plates in the four steam generators at Gentilly-2 was evaluated based on a joint proposal by Ontario Hydro Technologies (now Ontario Power Technologies-OPT) and Hydro-Quebec. A MIG welding procedure was proposed for the horizontal and vertical divider plates welds. A complete simulation of the robot and primary head demonstrated the feasibility of the concept. However, based on cost and scheduling, it was decided to proceed with a manual repair. Nevertheless it is anticipated that this technology will find its niche in the maintenance of Candu reactors. (author)

  8. Joint studies on large CANDU

    International Nuclear Information System (INIS)

    CANDU PHWRs have demonstrated generic benefits which will be continued in future designs. These include economic benefits due to low operating costs, business potential, strategic benefits due to fuel cycle flexibility and operational benefits. These benefits have been realized in Korea through the operation of Wolsong 1, resulting in further construction of PHWRs at the same site. The principal benefit, low electricity cost, is due to the high capacity factor and the low fuel cost for CANDU. The CANDU plant at Wolsong has proven to be a safe, reliable and economical electricity producer. The ability of PHWR to burn natural uranium ensures security of fuel supply. Following successful Technology Transfer via the Wolsong 2,3 and 4 project, future opportunity exists between Korea and Canada for continuing co-operation in research and development to improve the technology base, for product development partnerships, and business opportunities in marketing and building PHWR plants in third countries. High reliability, through excellent design, well-controlled operation, efficient maintenance and low operating costs is critical to the economic viability of nuclear plants. CANDU plants have an excellent performance record. The four operating CANDU 6 plants, operated by four utilities in three countries, are world performance leaders. The CANDU 9 design, with higher output capacity, will help to achieve better site utilization and lower electricity costs. Being an evolutionary design, CANDU 9 assures high performance by utilizing proven systems, and component designs adapted from operating CANDU plants (Bruce B, Darlington and CANDU 6). All system and operating parameters are within the operating proven range of current plants. KAERI and AECL have an agreement to perform joint studies on future PHWR development. The objective of the joint studies is to establish the requirements for the design of future advanced CANDU PHWR including the utility need for design improvements

  9. CANDU, building the future

    Energy Technology Data Exchange (ETDEWEB)

    Stern, F. [Stern Laboratories (Canada)

    1997-07-01

    The CEO of Stern Laboratories delivered a speech on the problems and challenges facing the nuclear industry. The CANDU system is looked at as the practical choice for the future of our energy source. The people of the industry must be utilized and respected to deliver to the best of their ability.

  10. CANDU market prospects

    International Nuclear Information System (INIS)

    This 1994 survey of prospective markets for CANDU reactors discusses prospects in Turkey, Thailand, the Philippines, Korea, Indonesia, China and Egypt, and other opportunities, such as in fuel cycles and nuclear safety. It was concluded that foreign partners would be needed to help with financing

  11. The future of nuclear power

    International Nuclear Information System (INIS)

    When it was announced in June that France had beaten Japan in the race to host the world's next big fusion lab, the news made headlines around the world. The media reported in generally positive tones how the 10 bn Euro International Thermonuclear Experimental Reactor (ITER) will be the next step on the path to a commercially viable nuclear fusion reactor (Physics World August p5). The coverage was a clear sign of the growing debate surrounding the future of nuclear power. Nuclear Renaissance is a welcome contribution to that debate. The book bills itself as a 'semi-technical overview of modern technologies', which perhaps underplays what the author has achieved. It reviews past, current and prospective nuclear technologies, but links them clearly to the wider topics of energy policy, climate change and energy supply. Apart from being 'semi-technical', the book is also 'semi-British'. Although those sections on technology have a global scope, the lengthy first part - devoted to the 'policy landscape' - is firmly UK in its perspective. It provides a basic description of nuclear power, the economics of nuclear generation, and how nuclear energy could combat climate change. The contribution of nuclear power to a balanced energy supply and its links with weapons proliferation are also discussed. This opening part ends with a chapter on waste management. While the first part of the book could be a stand-alone introduction to nuclear power for layreaders, the second and third parts - on nuclear fission and nuclear fusion - seem to be aimed at a different readership altogether. In particular, they will help students who have some scientific training to understand in more detail how specific types of nuclear technology work. If you want to know how a Westinghouse Advanced Passive Reactor differs from a European Pressurised Water Reactor - or learn the specifics of the Canadian CANDU reactor or the South African pebble-bed modular reactor - then this is for you. Nuttall

  12. An elasto-plastic model for mechanical contact between the pellets and sheath in CANDU nuclear fuel elements

    International Nuclear Information System (INIS)

    During high-temperature transients, increased mechanical contact can occur between the fuel stack and the sheath in the axial and/or radial direction. As well, there is an axial linear power gradient and an axial gradient in mechanical properties of the sheath specific to a CANDU-type fuel element. This requires a code with the capability to treat multiple axial segments. This paper describes a contact model that allows the elasto-plastic mechanical contact in radial/axial direction for multiple axial segments. (14 figs., 5 refs.)

  13. Nuclear power economic database

    International Nuclear Information System (INIS)

    Nuclear power economic database (NPEDB), based on ORACLE V6.0, consists of three parts, i.e., economic data base of nuclear power station, economic data base of nuclear fuel cycle and economic database of nuclear power planning and nuclear environment. Economic database of nuclear power station includes data of general economics, technique, capital cost and benefit, etc. Economic database of nuclear fuel cycle includes data of technique and nuclear fuel price. Economic database of nuclear power planning and nuclear environment includes data of energy history, forecast, energy balance, electric power and energy facilities

  14. Assessment of System Behavior and Actions Under Loss of Electric Power For CANDU

    Energy Technology Data Exchange (ETDEWEB)

    Kang, San Ha; Moon, Bok Ja; Kim, Seoung Rae [Nuclear Engineering Service and Solution Co., Ltd., Daejeon (Korea, Republic of)

    2014-05-15

    For the analysis, the CANDU-6 plant in Korea is considered and only the passive components are operable. The other systems are assumed to be at failed condition due to the loss of electric power. At this accident, only the inventories remained in the primary heat transport system (PHTS) and steam generator can be used for the decay heat removal. Due to the transfer of decay heat, the inventory of steam generator secondary side is discharged to the air through passive operation of main steam safety valves (MSSVs). After the steam generators are dried, the PHTS is over-pressurized and the coolant is discharged to fuelling machine vault through passive operation of degasser condenser tank relief valves (DCRVs). Under this situation, the maintenance of the integrity of PHTS is important for the protection of radionuclides release to the environment. Thus, deterministic analysis using CATHENA code is carried out for the simulation of the accident and the appropriate operator action is considered. The loss of electric power results in the depletion of steam generator inventory which is necessary for the decay heat removal. If only the passive system is credited, the PT can be failed after the steam generator is depleted. For the prevention of the PT failure, the feedwater should be supplied to the steam generator before 4,800s after the accident. The feedwater can be supplied using water in dousing tank if the steam generators are depressurized. The decay heat from the core is removed through natural circulation if the feedwater can be supplied continuously.

  15. Development of risk monitor RiskAngel for risk-informed applications in nuclear power plants

    International Nuclear Information System (INIS)

    This paper presents the development of risk monitor software RiskAngel at FDS Team and its applications as a plant specific risk monitor, which supports risk-informed configuration risk management for the two CANDU 6 units at the Third Qinshan Nuclear Power Plant in China. It also describes the regulatory prospective on risk-informed PSA applications and the use of risk monitor at operating nuclear power plants, high level technical and functional requirements for the development of CANDU specific risk monitor software, and future development trends. (author)

  16. Thermochemical modelling of advanced CANDU reactor fuel

    Science.gov (United States)

    Corcoran, Emily Catherine

    2009-04-01

    With an aging fleet of nuclear generating facilities, the imperative to limit the use of non-renewal fossil fuels and the inevitable need for additional electricity to power Canada's economy, a renaissance in the use of nuclear technology in Canada is at hand. The experience and knowledge of over 40 years of CANDU research, development and operation in Ontario and elsewhere has been applied to a new generation of CANDU, the Advanced CANDU Reactor (ACR). Improved fuel design allows for an extended burnup, which is a significant improvement, enhancing the safety and the economies of the ACR. The use of a Burnable Neutron Absorber (BNA) material and Low Enriched Uranium (LEU) fuel has created a need to understand better these novel materials and fuel types. This thesis documents a work to advance the scientific and technological knowledge of the ACR fuel design with respect to thermodynamic phase stability and fuel oxidation modelling. For the BNA material, a new (BNA) model is created based on the fundamental first principles of Gibbs energy minimization applied to material phase stability. For LEU fuel, the methodology used for the BNA model is applied to the oxidation of irradiated fuel. The pertinent knowledge base for uranium, oxygen and the major fission products is reviewed, updated and integrated to create a model that is applicable to current and future CANDU fuel designs. As part of this thesis, X-Ray Diffraction (XRD) and Coulombic Titration (CT) experiments are compared to the BNA and LEU models, respectively. From the analysis of the CT results, a number of improvements are proposed to enhance the LEU model and provide confidence in its application to ACR fuel. A number of applications for the potential use of these models are proposed and discussed. Keywords: CANDU Fuel, Gibbs Energy Mimimization, Low Enriched Uranium (LEU) Fuel, Burnable Neutron Absorber (BNA) Material, Coulometric Titration, X-Ray Diffraction

  17. Ninth international conference on CANDU fuel, 'fuelling a clean future'

    International Nuclear Information System (INIS)

    The Canadian Nuclear Society's 9th International Conference on CANDU fuel took place in Belleville, Ontario on September 18-21, 2005. The theme for this year's conference was 'Fuelling a Clean Future' bringing together over 80 delegates ranging from: designers, engineers, manufacturers, researchers, modellers, safety specialists and managers to share the wealth of their knowledge and experience. This international event took place at an important turning point of the CANDU technology when new fuel design is being developed for commercial application, the Advanced CANDU Reactor is being considered for projects and nuclear power is enjoying a renaissance as the source energy for our future. Most of the conference was devoted to the presentation of technical papers in four parallel sessions. The topics of these sessions were: Design and Development; Fuel Safety; Fuel Modelling; Fuel Performance; Fuel Manufacturing; Fuel Management; Thermalhydraulics; and, Spent Fuel Management and Criticalty

  18. Candu reactors with thorium fuel cycles

    International Nuclear Information System (INIS)

    Over the last decade and a half AECL has established a strong record of delivering CANDU 6 nuclear power plants on time and at budget. Inherently flexible features of the CANDU type reactors, such as on-power fuelling, high neutron economy, fuel channel based heat transport system, simple fuel bundle configuration, two independent shut down systems, a cool moderator and a defence-in-depth based safety philosophy provides an evolutionary path to further improvements in design. The immediate milestone on this path is the Advanced CANDU ReactorTM** (ACRTM**), in the form of the ACR-1000TM**. This effort is being followed by the Super Critical Water Reactor (SCWR) design that will allow water-cooled reactors to attain high efficiencies by increasing the coolant temperature above 5500C. Adaptability of the CANDU design to different fuel cycles is another technology advantage that offers an additional avenue for design evolution. Thorium is one of the potential fuels for future reactors due to relative abundance, neutronics advantage as a fertile material in thermal reactors and proliferation resistance. The Thorium fuel cycle is also of interest to China, India, and Turkey due to local abundance that can ensure sustainable energy independence over the long term. AECL has performed an assessment of both CANDU 6 and ACR-1000 designs to identify systems, components, safety features and operational processes that may need to be modified to replace the NU or SEU fuel cycles with one based on Thorium. The paper reviews some of these requirements and the associated practical design solutions. These modifications can either be incorporated into the design prior to construction or, for currently operational reactors, during a refurbishment outage. In parallel with reactor modifications, various Thorium fuel cycles, either based on mixed bundles (homogeneous) or mixed channels (heterogeneous) have been assessed for technical and economic viability. Potential applications of a

  19. Thermalhydraulic characteristics for fuel channels using burnable poison in the CANDU reactor

    International Nuclear Information System (INIS)

    The power coefficient is one of the most important physics parameters governing nuclear reactor safety and operational stability, and its sign and magnitude have a significant effect on the safety and control characteristics of the power reactor. Recently, for an equilibrium CANDU core, the power coefficient was reported to be slightly positive when newly developed Industry Standard Tool set reactor physics codes were used. Therefore, it is required to find a new way to effectively decrease the positive power coefficient of CANDU reactor without seriously compromising the economy. In order to make the power coefficient of the CANDU reactor negative at the operating power, Roh et al. have evaluated the various burnable poison (BP) materials and its loading scheme in terms of the fuel performance and reactor safety characteristics. It was shown that reactor safety characteristics can be greatly improved by the use of the BP in the CANDU reactor. However, the previous study has mainly focused on the safety characteristics by evaluating the power coefficient for the fuel channel using BP in the CANDU reactor. Together with the safety characteristics, the economic performance is also important in order to apply the newly designed fuel channel to the power plant. In this study, the economic performance has been evaluated by analyzing the thermal hydraulic characteristics for the fuel channel using BP in the CANDU reactor

  20. Requirements for containment system components in CANDU nuclear power plants

    International Nuclear Information System (INIS)

    This Standard specifies the requirements and establishes the rules for design, fabrication, and installation of pressure-retaining containment system components. In this Standard the term 'components' includes non registered items

  1. Integrated evolution of the medium power CANDU{sup MD} reactors; Evolution integree des reacteurs CANDU{sup MD} de moyenne puissance

    Energy Technology Data Exchange (ETDEWEB)

    Nuzzo, F. [AECL Accelerators, Kanata, ON (Canada)

    2002-07-01

    The aim of this document is the main improvements of the CANDU reactors in the economic, safety and performance domains. The presentation proposes also other applications as the hydrogen production, the freshening of water sea and the bituminous sands exploitation. (A.L.B.)

  2. The Canadian approach to nuclear codes and standards. A CSA forum for development of standards for CANDU: radioactive waste management and decommissioning

    International Nuclear Information System (INIS)

    Together with the Canadian Standards Association (CSA), industry stakeholders, governments, and the public have developed a suite of standards for CANDU nuclear power plants that generate electricity in Canada and abroad. In this paper, we will describe: CSA's role in national and international nuclear standards development; the key issues and priority projects that the nuclear standards program has addressed; the new CSA nuclear committees and projects being established, particularly those related to waste management and decommissioning; the hierarchy of nuclear regulations, nuclear, and other standards in Canada, and how they are applied by AECL; the standards management activities; and the future trends and challenges for CSA and the nuclear community. CSA is an accredited Standards Development Organization (SDO) and part of the international standards system. CSA's Nuclear Strategic Steering Committee (NSSC) provides leadership, direction, and support for a standards committee hierarchy comprised of members from a balanced matrix of interests. The NSSC strategically focuses on industry challenges; a new nuclear regulatory system, deregulated energy markets, and industry restructuring. As the first phase of priority projects is nearing completion, the next phase of priorities is being identified. These priorities address radioactive waste management, environmental radiation management, decommissioning, structural, and seismic issues. As the CSA committees get established in the coming year, members and input will be solicited for the technical committees, subcommittees, and task forces for the following related subjects: Radioactive Waste Management; a) Dry Storage of Irradiated Fuel; b) Short-Term Radioactive Waste Management; c) Long-Term Storage and Disposal of Radioactive Waste. 2. Decommissioning Nuclear Power is highly regulated, and public scrutiny has focused Codes and Standards on public and worker safety. Licensing and regulation serves to control

  3. Technology transfer in CANDU marketing

    International Nuclear Information System (INIS)

    The author discusses how the CANDU system lends itself to technology transfer, the scope of CANDU technology transfer, and the benefits and problems associated with technology transfer. The establishment of joint ventures between supplier and client nations offers benefits to both parties. Canada can offer varying technology transfer packages, each tailored to a client nation's needs and capabilities. Such a package could include all the hardware and software necessary to develop a self-sufficient nuclear infrastructure in the client nation

  4. Using Advanced Fuel Bundles in CANDU Reactors

    International Nuclear Information System (INIS)

    Improving the exit fuel burnup in CANDU reactors was a long-time challenge for both bundle designers and performance analysts. Therefore, the 43-element design together with several fuel compositions was studied, in the aim of assessing new reliable, economic and proliferation-resistant solutions. Recovered Uranium (RU) fuel is intended to be used in CANDU reactors, given the important amount of slightly enriched Uranium (~0.96% w/o U235) that might be provided by the spent LWR fuel recovery plants. Though this fuel has a far too small U235 enrichment to be used in LWR's, it can be still used to fuel CANDU reactors. Plutonium based mixtures are also considered, with both natural and depleted Uranium, either for peacefully using the military grade dispositioned Plutonium or for better using Plutonium from LWR reprocessing plants. The proposed Thorium-LEU mixtures are intended to reduce the Uranium consumption per produced MW. The positive void reactivity is a major concern of any CANDU safety assessment, therefore reducing it was also a task for the present analysis. Using the 43-element bundle with a certain amount of burnable poison (e.g. Dysprosium) dissolved in the 8 innermost elements may lead to significantly reducing the void reactivity. The expected outcomes of these design improvements are: higher exit burnup, smooth/uniform radial bundle power distribution and reduced void reactivity. Since the improved fuel bundles are intended to be loaded in existing CANDU reactors, we found interesting to estimate the local reactivity effects of a mechanical control absorber (MCA) on the surrounding fuel cells. Cell parameters and neutron flux distributions, as well as macroscopic cross-sections were estimated using the transport code DRAGON and a 172-group updated nuclear data library. (author)

  5. The Korean strategy and experience in developing nuclear power generation capability

    International Nuclear Information System (INIS)

    The Korean nuclear energy development program and future prospects are discussed. Korea has achieved the substantial level of nuclear power plant localization through Korean Standard Nuclear Power (KSNP) Plant approach. The KSNP approach includes plant standardization, equipment, fuel and service localization and codes and standards development. Korea could develop her own decision making capability as Korea took the total project management responsibility in the KSNP approach. Current Korean nuclear R and D program includes next generation nuclear power plant development and advanced fuel development. The PWR-CANDU symbiosis is carefully considered to improve the nuclear power economy

  6. A review of CANDU plant lifetime management

    International Nuclear Information System (INIS)

    In recent years, plant lifetime management(PLIM) including life extension has become the focus of the nuclear industry worldwide due to a number of factors which have arisen over the past decade : new siting difficulties, imbalance of power supply and demand, and high construction costs. In order to solve the problems, the PLIM program is being developed for the purpose of life extension and improvement of plant availability and safety. This paper describes the current activities and prospects of AECL and CANDU utilities, the conceptional evaluation results for the degradation mechanisms, and PLIM regulatory aspects. In addition, this paper provides the applicability of CANDU PLIM to Wolsong Unit 1 which has been operated for 17 years

  7. Systems analysis of the CANDU 3 Reactor

    International Nuclear Information System (INIS)

    This report presents the results of a systems failure analysis study of the CANDU 3 reactor design; the study was performed for the US Nuclear Regulatory Commission. As part of the study a review of the CANDU 3 design documentation was performed, a plant assessment methodology was developed, representative plant initiating events were identified for detailed analysis, and a plant assessment was performed. The results of the plant assessment included classification of the CANDU 3 event sequences that were analyzed, determination of CANDU 3 systems that are ''significant to safety,'' and identification of key operator actions for the analyzed events

  8. Prospects for Nuclear Power

    OpenAIRE

    Lucas W. Davis

    2012-01-01

    Nuclear power has long been controversial because of concerns about nuclear accidents, storage of spent fuel, and how the spread of nuclear power might raise risks of the proliferation of nuclear weapons. These concerns are real and important. However, emphasizing these concerns implicitly suggests that unless these issues are taken into account, nuclear power would otherwise be cost effective compared to other forms of electricity generation. This implication is unwarranted. Throughout the h...

  9. Nuclear Power in China

    Institute of Scientific and Technical Information of China (English)

    2009-01-01

    China’s vigorous efforts to propel development of nuclear power are paying off as the country’s nuclear power sector advances at an amazing pace. At present, China has set up three enormous nuclear power bases, one each in Qinshan of Zhejiang Province, Dayawan of Guangdong

  10. CANDU development

    International Nuclear Information System (INIS)

    Evolution of the 950 MW(e) CANDU reactor is summarized. The design was specifically aimed at the export market. Factors considered in the design were that 900-1000 MW is the maximum practical size for most countries; many countries have warmer condenser cooling water than Canada; the plant may be located on coastal sites; seismic requirements may be more stringent; and the requirements of international, as well as Canadian, standards must be satisfied. These considerations resulted in a 600-channel reactor capable of accepting condenser cooling water at 320C. To satisfy the requirement for a proven design, the 950 MW CANDU draws upon the basic features of the Bruce and Pickering plants which have demonstrated high capacity factors

  11. The CANDU experience in Romania

    International Nuclear Information System (INIS)

    The CANDU program in Romania is now well established. The Cernavoda Nuclear Station presently under construction will consist of 5-CANDU 600 MWE Units and another similar size station is planned to be in operation in the next decade. Progress on the multi-unit station at Cernavoda was stalled for 18 months in 1982/83 as the Canadian Export Development Corporation had suspended their loan disbursements while the Romanian National debt was being rescheduled. Since resumption of the financing in August 1983 contracts worth almost 200M dollars have been placed with Canadian Companies for the supply of major equipment for the first two units. The Canadian design is that which was used in the latest 600 MWE CANDU station at Wolsong, Korea. The vast construction site is now well developed with the cooling water systems/channels and service buildings at an advanced stage of completion. The perimeter walls of the first two reactor buildings are already complete and slip-forming for the 3rd Unit is imminent. Many Romanian organizations are involved in the infrastructure which has been established to handle the design, manufacture, construction and operation of the CANDU stations. The Romanian manufacturing industry has made extensive preparations for the supply of CANDU equipment and components, and although a major portion of the first two units will come from Canada their intentions are to become largely self-supporting for the ensuing CANDU program. Quality assurance programs have been prepared already for many of the facilities

  12. Mitigating aging in CANDU plants

    International Nuclear Information System (INIS)

    Aging degradation is a phenomenon we all experience throughout life, both on a personal basis and in business. Many industries have been successful in postponing the inevitable impact on their related systems and components through programs to maintain long-term reliability, maintainability and safety. However, this has not always been the case for nuclear power. While all power plants are experiencing the world trend of increasing operating costs with age, few (if any) have been able to fully define the parameters that solve the aging equation, particularly in relation to major components. Inspection and preventive maintenance have not been effective in predicting life-limiting degradation and failure. In CANDU nuclear plants, utilities are taking a comprehensive approach in dealing with the aging problem. Programs have been established to identify the current condition and degradation mechanisms of critical components, the failure of which would impact negatively on station competitiveness and safety. These include subcomponents under the general headings of reactor components, civil structures, piping (nuclear and conventional), steam generators, turbines and cables. In support of these efforts, R and D projects have been defined under the CANDU Owners Group to deal with generic issues on aging common to its members (e.g., investigation of degradation mechanisms, development of tools and techniques to mitigate the effects of aging, etc.). This paper describes recent developments of this cost-shared program with specific reference to concrete aging and crack repairs, flow-assisted corrosion in piping, elastomer service life, cable aging, degradation mechanisms in steam generators and lubricant breakdown. (author)

  13. Cost comparison of 4x500 MW coal-fuelled and 4x850 MW CANDU nuclear generating stations

    International Nuclear Information System (INIS)

    The lifetime costs for a 4x850 MW CANDU generating station are compared to those for 4x500 MW bituminous coal-fuelled generating stations. Two types of coal-fuelled stations are considered; one burning U.S. coal which includes flue gas desulfurization and one burning Western Canadian coal. Current estimates for the capital costs, operation and maintenance costs, fuel costs, decommissioning costs and irradiated fuel management costs are shown. The results show: (1) The accumulated discounted costs of nuclear generation, although initially higher, are lower than coal-fuelled generation after two or three years. (2) Fuel costs provide the major contribution to the total lifetime costs for coal-fuelled stations whereas capital costs are the major item for the nuclear station. (3) The break even lifetime capacity factor between nuclear and U.S. coal-fuelled generation is projected to be 5%; that for nuclear and Canadian coal-fuelled generation is projected to be 9%. (4) Large variations in the costs are required before the cost advantage of nuclear generation is lost. (5) Comparison with previous results shows that the nuclear alternative has a greater cost advantage in the current assessment. (6) The total unit energy cost remains approximately constant throughout the station life for nuclear generation while that for coal-fuelled generation increases significantly due to escalating fuel costs. The 1978 and 1979 actual total unit energy cost to the consumer for several Ontario Hydro stations are detailed, and projected total unit energy costs for several Ontario Hydro stations are shown in terms of escalated dollars and in 1980 constant dollars

  14. Candu advanced fuel cycles: key to energy sustainability

    International Nuclear Information System (INIS)

    A primary rationale for Indonesia to proceed with a nuclear power program is to diversity its energy sources and achieve freedom from future resource constraints. While other considerations, such as economy of power supply, hedging against potential future increases in the price of fossil fuels, fostering the technological development of the Indonesia economy and minimizing greenhouse and other gaseous are important, the strategic resource issue is key. In considering candidate nuclear power technologies upon which to base such a program, a major consideration will be the potential for those technologies to be economically sustained in the face of large future increases in demand for nuclear fuels. the technology or technologies selected should be amenable to evaluation in a rapidly changing technical, economic, resource and environmental policy environment. the world's proven uranium resources which can be economically recovered represent a fairly modest energy resource if utilization is based on the currently commercialized fuel cycles, even with the use of recovered plutonium in mixed oxide fuels. In the long term, fuel cycles relying solely on the use of light water reactors will encounter increasing fuel supply constraints. Because of its outstanding neutron economy and the flexibility of on-power refueling, Candu reactors are the most fuel resource efficient commercial reactors and offer the potential for accommodating an almost unlimited variety of advanced and even more fuel efficient cycles. Most of these cycles utilize nuclear fuel which are too low grade to be used in light water reactors, including many products now considered to be waste, such as spent light water reactor fuel and reprocessing products such as recovered uranium. The fuel-cycle flexibility of the Candu reactor provides a ready path to sustainable energy development in both the short and the long terms. Most of the potential Candu fuel cycle developments can be accommodated in existing

  15. CANDU at the crossroads

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1990-11-01

    ''Ready for the challenge of the 90s'' was the theme of this year's gathering of the Canadian Nuclear Association held in Toronto, 3-6 June. What that challenge really entails is whether the CANDU system will survive as the last remaining alternative to the light water reactor in the world reactor market, or whether it will decline into oblivion along with the Advanced Gas Cooled reactor and so many other technically excellent systems which have fallen along the way. The fate of the CANDU system will not be determined by its technical merits, nor by its impeccable safety record. It will be determined by public perceptions and by the deliberations of an Environmental Assessment Panel established by the Government of Ontario. The debate at the Association meeting is reported. (author).

  16. Feasibility study of CANDU-9 fuel handling system

    International Nuclear Information System (INIS)

    CANDU's combination of natural uranium, heavy water and on-power refuelling is unique in its design and remarkable for reliable power production. In order to offer more output, better site utilization, shorter construction time, improved station layout, safety enhancements and better control panel layout, CANDU-9 is now under development with design improvement added to all proven CANDU advantages or applicable technologies. One of its major improvement has been applied to fuel handling system. This system is very similar to that of CANDU-3, and some parts of the system are applied to those of the existing CANDU-6 or CANDU-9. Design concepts and design requirements of fuel handling system for CANDU-9 have been identified to compare with those of the existing CANDU and the design feasibilities have been evaluated. (author). 4 tabs., 13 figs., 9 refs

  17. Enhanced candu 6 reactor: status

    International Nuclear Information System (INIS)

    The CANDU 6 power reactor is visionary in its approach, renowned for its on-power refuelling capability and proven over years of safe, economical and reliable power production. Developed by Atomic Energy of Canada Limited (AECL), the CANDU 6 design offers excellent performance utilizing state-of-the-art technology. The first CANDU 6 plants went into service in the early 1980s as leading edge technology and the design has been continuously advanced to maintain superior performance with an outstanding safety record. The first set of CANDU 6 plants - Gentilly 2 and Point Lepreau in Canada, Embalse in Argentina and Wolsong- Unit 1 in Korea - have been in service for more than 22 years and are still producing electricity at peak performance; to the end of 2004, their average Lifetime Capacity Factor was 83.2%. The newer CANDU 6 units in Romania (Cernavoda 1), Korea (Wolsong-Units 2, 3 and 4) and Qinshan (Phase III- Units 1 and 2) have also been performing at outstanding levels. The average lifetime Capacity Factor of the 10 CANDU 6 operating units around the world has been 87% to the end of 2004. Building on these successes, AECL is committed to the further development of this highly successful design, now focussing on meeting customers' needs for reduced costs, further improvements to plant operation and performance, enhanced safety and incorporating up-to-date technology, as warranted. This has resulted in AECL embarking on improving the CANDU 6 design through an upgraded product termed the ''Enhanced CANDU 6'' (EC6), which incorporates several attractive but proven features that make the CANDU 6 reactor even more economical, safer and easier to operate. Some of the key features that are being incorporated into the EC6 include increasing the plant's power output, shortening the overall project schedule, decreasing the capital cost, dealing with obsolescence issues, optimizing maintenance outages and incorporating lessons learnt through feedback obtained from the

  18. Nuclear power prospects

    International Nuclear Information System (INIS)

    A survey of the nuclear power needs of the less-developed countries and a study of the technology and economics of small and medium scale power reactors are envisioned by the General Conference. Agency makes its services available to Member States to assist them for their future nuclear power plans, and in particular in studying the technical and economic aspects of their power programs. The Agency also undertakes general studies on the economics of nuclear power, including the collection and analysis of cost data, in order to assist Member States in comparing and forecasting nuclear power costs in relation to their specific situations

  19. Solutions for nuclear & renewable power generation

    International Nuclear Information System (INIS)

    AREVA Group's business globally includes mining, reactors and services and renewables. In Canada, AREVA is a leading uranium producer and globally qualified for CANDU plants. AREVA's nuclear and renewables strategy is based on the development of nuclear and renewable energies.

  20. Independence and diversity in CANDU shutdown systems

    International Nuclear Information System (INIS)

    Atomic Energy Control Board regulations state that Canadian CANDU reactors shall have two fully effective, independent and diverse shutdown systems. The Darlington Nuclear Generating Station is the first power plant operated by Ontario Hydro to make use of software-based computer control in its shutdown systems. By virtue of the reliance placed on these systems to prevent exposure of the public to harmful radioactivity in the event of an accident, the shutdown system software has been categorized as safety critical software. An important issue that was considered in the design of the Darlington shutdown systems was how the software should be designed and incorporated into the systems to comply with the independence and diversity requirement. This paper describes how the independence and diversity requirement was complied with in previous CANDU shutdown system designs utilizing hardware components. The difference between systems utilizing hardware alone, and those utilizing both hardware and software are discussed. The results of a literature search into the issue of software diversity, the behaviour of multi-version software systems, and experience in other industries utilizing safety critical software are referred to. This paper advocates a systems approach to designing independent shutdown systems utilizing software. Opportunities exist at the system level for design decisions that can enhance software diversity and can reduce the likelihood of common mode faults in the systems. In the light of recent experience in implementing diverse safety critical software, potential improvements to the design process for CANDU shutdown systems are identified. (Author) 19 refs

  1. RETHINKING NUCLEAR POWER SAFETY

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The Fukushima nuclear accident sounds alarm bells in China’s nuclear power industry In the wake of the Fukushima nucleara ccident caused by the earthquake andt sunami in Japan,the safety of nuclearp ower plants and the development of nuclear power have raised concerns,

  2. CANDU operating experience

    International Nuclear Information System (INIS)

    The CANDU-PHW program is based upon 38 years of heavy water reactor experience with 35 years of operating experience. Canada has had 72 reactor years of nuclear-electric operations experience with 10 nuclear units in 4 generating stations during a period of 18 years. All objectives have been met with outstanding performance: worker safety, public safety, environmental emissions, reliable electricity production, and low electricity cost. The achievement has been realized through total teamwork involving all scientific disciplines and all project functions (research, design, manufacturing, construction, and operation). (auth)

  3. The role of nuclear power plant designers

    International Nuclear Information System (INIS)

    When design of a nuclear power plant begins its designers, owners, and regulators make a safety judgement based on their knowledge and collective experience. As time goes on safety criteria change, methods improve, new scientific understanding is gained, and the cost of safety increases in relation to the benefits gained. In spite of that, the fundamental safety of CANDU remains and will continue high. However, the designer's job has become more difficult. The process of designing a product to satisfy a customer using a perceived view of that benefits society is no longer simple. Is the customer the utility or an amalgam of government departments and various factions of the public? How is the designer to make judgements on social acceptability when society speaks with so many voices and so little leadership

  4. The Candu suppliers: Growing beyond Canada

    International Nuclear Information System (INIS)

    Canada has demonstrated its ability to successfully manage Candu projects. It has been shown domestically by Ontario Hydro over a period of many years. It has been demonstrated abroad by private sector service companies, under Nuclear Construction Managers, on the 600 MW Wolsung project in South Korea, where NPM companies carried out virtually all project and construction management, the plant was in service only 60 months after the first concrete was poured for the reactor building. In the past, however, the project management team for Candu nuclear plants overseas, and for some at home, was often assembled ad hoc. Though this approach can be successful, it does not guarantee success in project and construction management. Because of the size, diversity and flexibility of the private owners of NPM, they have been able to keep their experienced nuclear power teams on staff even though the nuclear power industry has been going through slow times, assigning these people to large projects in other industries that call for the same high level of project, construction and commissioning management skills. Yet they are in a position to reassemble this team at very short notice, and have them ready to go to work on a major project within weeks of the green light

  5. Nuclear Power in Sweden

    International Nuclear Information System (INIS)

    This book presents how Swedish technology has combined competence in planning, building, commissioning, maintenance, and operation of nuclear power and waste facilities. The items are elaborated in the following chapters: Nuclear power today and for the future, Sweden and its power supply, The history of nuclear power in Sweden, Nuclear Sweden today, Operating experience in 10 nuclear power units, Maintenance experience, Third-generation BWR-plants commissioned in five years, Personnel and training, Reactor safety, Quality assurance and quality control, Characteristic features of the ASEA-ATOM BWR, Experience of PWR steam generators, Nuclear fuel supply and management, Policy and techniques of radioactive waste management, Nuclear energy authorities and Inherently safe LWR. The publication is concluded by facts in brief and a statement by the Director General of IAEA. (G.B.)

  6. The Role of Nuclear Power in Pakistan

    International Nuclear Information System (INIS)

    Although the energy and electricity demand in Pakistan have been steadily growing, the per capita electricity consumption at around 300 kWh is still rather small when compared to most countries. The current installed capacity is around 17,700 MW with fossil fuels providing nearly two-third of this capacity, hydro a little less than one-third and nuclear around 2.5%. A major fraction of the oil used in Pakistan has to be imported while hydro remains subject to seasonal changes. The next 20 year projections point to a serious electrical energy generation shortfall even when the contribution from indigenous gas, coal, and hydro is increased optimistically. It is estimated that a deficit of some 3000-5000 MW may exist which will have to be met from an alternate energy resource like nuclear. Two small nuclear power plants (KANUPP, a 137 MWe CANDU which has been operating safely for nearly three decades, and CHASNUPP, the newly built 325 MWe PWR supplied by China) are already on-line. KANUPP has essentially been operated without any vendor support thanks to a systematic self-reliance program. The experience gained through procuring, operating and maintaining these power plants, coupled with the need to meet the projected electrical energy shortfall which cannot be met through conventional resources, makes nuclear a very viable option, and Pakistan an ideal case to study the current and future role of nuclear in a developing country with medium sized grid. This paper will describe an overview of the experience of development of nuclear power in Pakistan. Future strategies, which involve negotiating a case for nuclear with the energy policy makers, interacting with the vendor on matters of obtaining new plants, and increasing self-reliance in the area of nuclear power technology, will also be discussed. (author)

  7. Quality Products - The CANDU Approach

    International Nuclear Information System (INIS)

    The prime focus of the CANDU concept (natural uranium fuelled-heavy water moderated reactor) from the beginning has economy, heavy water losses and radiation exposures also were strong incentives for ensuring good design and reliable equipment. It was necessary to depart from previously accepted commercial standards and to adopt those now accepted in industries providing quality products. Also, through feedback from operating experience and specific design and development programs to eliminate problems and improve performance, CANDU has evolved into today's successful product and one from which future products will readily evolve. Many lessons have been learned along the way. On the one hand, short cuts of failures to understand basic requirements have been costly. On the other hand, sound engineering and quality equipment have yielded impressive economic advantages through superior performance and the avoidance of failures and their consequential costs. The achievement of lifetime economical performance demands quality products, good operation and good maintenance. This paper describes some of the basic approaches leading to high CANDU station reliability and overall excellent performance, particularly where difficulties have had to be overcome. Specific improvements in CANDU design and in such CANDU equipment as heat transport pumps, steam generators, valves, the reactor, fuelling machines and station computers, are described. The need for close collaboration among designers, nuclear laboratories, constructors, operators and industry is discussed. This paper has reviewed some of the key components in the CANDU system as a means of indicating the overall effort that is required to provide good designs and highly reliable equipment. This has required a significant investment in people and funding which has handsomely paid off in the excellent performance of CANDU stations. The close collaboration between Atomic Energy of Canada Limited, Canadian industry and the

  8. Nuclear power and safety

    International Nuclear Information System (INIS)

    The paper deals with the problem of necessity to develop nuclear power, conceivable consequences of this development, its disadvantages and advantages. It is shown that the nuclear power is capable of supplying the world's economy with practically unlimited and the most low-cost energy resources providing the transition from the epoch of organic fuel to the epoch with another energy sources. The analysis of various factors of nuclear power effects on population and environment is presented. Special attention is focused on emergency situations at NPPs. The problem of raising the nuclear power safety is considered. 11 refs.; 5 figs.; 2 tabs

  9. Thorium-Based Fuels Preliminary Lattice Cell Studies for Candu Reactors

    International Nuclear Information System (INIS)

    The choice of nuclear power as a major contributor to the future global energy needs must take into account acceptable risks of nuclear weapon proliferation, in addition to economic competitiveness, acceptable safety standards, and acceptable waste disposal options. Candu reactors offer a proven technology, safe and reliable reactor technology, with an interesting evolutionary potential for proliferation resistance, their versatility for various fuel cycles creating premises for a better utilization of global fuel resources. Candu reactors impressive degree of fuel cycle flexibility is a consequence of its channel design, excellent neutron economy, on-power refueling, and simple fuel bundle. These features facilitate the introduction and exploitation of various fuel cycles in Candu reactors in an evolutionary fashion. The main reasons for our interest in Thorium-based fuel cycles have been, globally, to extend the energy obtainable from natural Uranium and, locally, to provide a greater degree of energy self-reliance. Applying the once through Thorium (OTT) cycle in existing and advanced Candu reactors might be seen as an evaluative concept for the sustainable development both from the economic and waste management points of view. Two Candu fuel bundles project will be used for the proposed analysis, namely the Candu standard fuel bundle with 37 fuel elements and the CANFLEX fuel bundle with 43 fuel elements. Using the Canadian proposed scheme - loading mixed ThO2-SEU CANFLEX bundles in Candu 6 reactors - simulated at lattice cell level led to promising conclusions on operation at higher fuel burnups, reduction of the fissile content to the end of the cycle, minor actinide content reduction in the spent fuel, reduction of the spent fuel radiotoxicity, presence of radionuclides emitting strong gamma radiation for proliferation resistance benefit. The calculations were performed using the lattice codes WIMS and Dragon (together with the corresponding nuclear data

  10. Nuclear power debate

    International Nuclear Information System (INIS)

    A recent resurgence of interest in Australia in the nuclear power option has been largely attributed to growing concerns over climate change. But what are the real pros and cons of nuclear power? Have advances in technology solved the sector's key challenges? Do the economics stack up for Australia where there is so much coal, gas and renewable resources? Is the greenhouse footprint' of nuclear power low enough to justify its use? During May and June, the AIE hosted a series of Branch events on nuclear power across Sydney, Adelaide and Perth. In the interest of balance, and at risk of being a little bit repetitive, here we draw together four items that resulted from these events and that reflect the opposing views on nuclear power in Australia. Nuclear Power for Australia: Irrelevant or Inevitable? - a summary of the presentations to the symposium held by Sydney Branch on 8 June 2005. Nuclear Reactors Waste the Planet - text from the flyer distributed by The Greens at their protest gathering outside the symposium venue on 8 June 2005. The Case For Nuclear Power - an edited transcript of Ian Hore-Lacy's presentation to Adelaide Branch on 19 May 2005 and to Perth Branch on 28 June 2005. The Case Against Nuclear Power - an article submitted to Energy News by Robin Chappie subsequent to Mr Hore-Lacy's presentation to Perth Branch

  11. Development of CANDU Spent Fuel Disposal Concepts for the Improvement of Disposal Efficiency

    International Nuclear Information System (INIS)

    There are two types of spent fuels generated from nuclear power plants, CANDU type and PWR type. PWR spent fuels which include a lot of reusable material can be considered to be recycled. CANDU spent fuels are considered to directly disposed in deep geological formation, since they have little reusable material. In this study, based on the Korean Reference spent fuel disposal System(KRS) which is to dispose both PWR and CANDU spent fuels, the more effective CANDU spent fuel disposal systems have been developed. To do this, the disposal canister has been modified to hold the storage basket which can load 60 spent fuel bundles. From these modified disposal canisters, the disposal systems to meet the thermal requirement for which the temperature of the buffer materials should not be over have been proposed. These new disposals have made it possible to introduce the concept of long term storage and retrievability and that of the two-layered disposal canister emplacement in one disposal hole. These disposal concepts have been compared and analyzed with the KRS CANDU spent fuel disposal system in terms of disposal effectiveness. New CANDU spent fuel disposal concepts obtained in this study seem to improve thermal effectiveness, U-density, disposal area, excavation volume, and closure material volume up to 30 - 40 %.

  12. ACR technology for CANDU enhancements

    International Nuclear Information System (INIS)

    The ACR-1000 design retains many essential features of the original CANDU plant design. As well as further-enhanced safety, the design also focuses on operability and maintainability, drawing on valuable customer input and OPEX. The engineering development of the ACR-1000 design has been accompanied by a research and confirmatory testing program. This program has extended the database of knowledge on the CANDU design. The ACR-1000 design has been reviewed by the Canadian regulator, the Canadian Nuclear Safety Commission (CNSC) which concluded that there are no fundamental barriers to licensing the ACR-1000 design in Canada after completing three phases of the pre-project design review. The generic PSAR for the ACR-1000 design was completed in September 2009. The PSAR contains the ACR-1000 design details, the safety and design methodology, and the safety analysis that demonstrate the ACR-1000 safety case and compliance with Canadian and international regulatory requirements and expectations. The ACR technology developed during the ACR-1000 Engineering Program and the supporting development testing has had a major impact beyond the ACR program itself: Improved CANDU components and systems; Enhanced engineering processes and engineering tools, which lead to better product quality, and better project efficiency; and Improved operational performance. This paper provides a summary of technology arising from the ACR program that has been incorporated into new CANDU designs such as the EC6, or can be applied for servicing operating CANDU reactors. (author)

  13. Build your own Candu reactor

    International Nuclear Information System (INIS)

    The author discusses the marketing of Candu reactors, particularly the export trade. Future sales will probably be of the nuclear side of a station only, thus striking a compromise between licensing and 'turnkey' sales. It is suggested that AECL might have made more money in the past had it not given the right to manufacture Candu fuel away to Canadian industry. Future sales to certain potential customers may be limited by the requirement of strict safeguards, which will almost certainly never be relaxed. (N.D.H.)

  14. Nuclear power in Belgium

    International Nuclear Information System (INIS)

    In the energy sector Belgium is 90% dependent on imports. This was clearly felt by the electricity generating economy when the share of hydrocarbons in the energy resources used for electricity generation increased to more than 85% in 1973 as a consequence of rising electricity consumption. Although Belgium had been early to start employing nuclear power for peaceful purposes, only little use had initially been made of this possibility. After the first oil price crisis the Belgian electricity utilities turned more attention to nuclear power. To this day, seven nuclear power plants have been started up, and Belgian utilities hold a fifty percent share in a French nuclear power plant, while the French EdF holds fifty percent in one Belgian nuclear generating unit. The Belgian nuclear power plants, which were built mostly by Belgian industries, have an excellent operating record. Their availabilities are considerably above the worldwide average and they contributed some 60% to the electricity production in Belgium in 1985. Thanks to nuclear power, the cumulative percentage shares of heating oil and gas in electricity production were reduced to well over 15%, compared to 1973, thus meeting the objectives of using nuclear power, i.e., to save foreign exchange and become self-sufficient in supplying the country's needs. The use of nuclear power allowed the Belgian utilities to reduce the price per kilowatthour of electricity and, in this way, remain competitive with other countries. The introduction of nuclear power continues to have a stabilizing influence on electricity generating costs. In the light of the forecast future development of consumption it is regarded as probable that another nuclear power plant of 1390 MWe will have to be built and commissioned before the year 2000. (orig.)

  15. Sydkraft and nuclear power

    International Nuclear Information System (INIS)

    This article summarizes the report made by G. Ekberg for the Swedish Sydkraft Power Co. at the company's annual meeting in June 1976. The report comprises the year 1975 and the first five months of 1976 and largely discusses nuclear power. Experience with the running of Oskarshamn and Barsebaeck nuclear power stations is reported. Nuclear power has enabled production in the oil-fired power stations at Karlshamn and Malmoe to be reduced. 750 000 tons of oil have been saved. In the first five months of 1976, nuclear power accounted for 48% of Sydkraft's electricity production, water power 36% and oil only 16%. In 1975, Sydkraft produced 13% of Sweden's electricity. (H.E.G.)

  16. Nuclear Power Plants. Revised.

    Science.gov (United States)

    Lyerly, Ray L.; Mitchell, Walter, III

    This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. Among the topics discussed are: Why Use Nuclear Power?; From Atoms to Electricity; Reactor Types; Typical Plant Design Features; The Cost of Nuclear Power; Plants in the United States; Developments in Foreign…

  17. Economics of nuclear power

    International Nuclear Information System (INIS)

    A comparison of the economics of nuclear and coal-fired power plants operated by Commonwealth Edison was developed. In this comparison, fuel costs, total busbar costs and plant performance were of particular interest. Also included were comparisons of construction costs of nuclear and coal-fired power plants over the past two decades

  18. Talk About Nuclear Power

    Science.gov (United States)

    Tremlett, Lewis

    1976-01-01

    Presents an overview of the relation of nuclear power to human health and the environment, and discusses the advantages and disadvantages of nuclear power as an energy source urging technical educators to inculcate an awareness of the problems associated with the production of energy. Describes the fission reaction process, the hazards of…

  19. Nuclear Power Day '86

    International Nuclear Information System (INIS)

    The proceedings in two volumes of the event ''Nuclear Power Day '86'' held in the Institute of Nuclear Research, contain full texts of 13 papers which all fall under the INIS Scope. The objective of the event was to acquaint broad technical public with the scope of the State Research and Development Project called ''Development of Nuclear Power till the Year 2000''. The papers were mainly focused on increased safety and reliability of nuclear power plants with WWER reactors, on the development of equipment and systems for disposal and burial of radioactive wastes, the introduction of production of nuclear power facilities of an output of 1,000 MW, and on the construction of nuclear heat sources. (Z.M.)

  20. The role of NDT in nuclear power development in Pakistan

    International Nuclear Information System (INIS)

    Pakistan has two operating nuclear power plants namely, Karachi Nuclear Power Plant (KANUPP) which is 137 MW Candu type Canadian reactor using natural uranium fuel and the Chashma Nuclear Power Plant (CHASNUPP) which is a 300 MW PWR type Chinese built reactor using 3% enriched uranium fuel. A third nuclear power plant is being negotiated for construction. This would most probably be the twin unit of CHASNUPP and the construction might begin early next year.Non destructive testing (NDT) has an important role in the development and safe operation of the nuclear power plants by providing the Pre-Service Inspection (PSI) services during the manufacturing and installation phase, and the In-Service Inspection (ISI) services during the operation and maintenance phase. ISI of various components of nuclear power plants is an essential activity which has to be carried out either on emergency basis on as and when required basis or periodically at regular intervals described in the quality assurance QA manuals of the plant. There are numerous components and systems in the nuclear power plants working together. The failure of one system affects the performance of the whole plant. There are two main divisions, called the Nuclear Island and Conventional Island. Main components of Nuclear Island are reactor pressure vessel, reactor core, steam generators, pressurizer, primary coolant pumps and primary piping, etc. and the main components in Conventional Island are turbine, condensers, pre-heaters, moisture separators, secondary heat treatment system and piping etc. (Author)

  1. Management of a 600 MW CANDU project to facilitate electricity export

    International Nuclear Information System (INIS)

    The export of electricity from 600-MW CANDU nuclear power plants built in Canada remains feasible providing certain requirements continue to be met. The principal objective in developing nuclear power resources for export is that they must produce economically attractive electricity. A review of the experience of construction and operation of Point Lepreau Unit 1 suggests an inherent ability to reduce construction costs and shorten construction schedules so as to make electrical power output from these stations even more attractive to export customers

  2. CANDU refurbishment - managing the life cycle

    International Nuclear Information System (INIS)

    All utilities that operate a nuclear power plant have an integrated plan for managing the condition of the plant systems, structures and components. With a sound plant life management program, after about 25 years of operation, replacement of certain reactor core components can give an additional 25 to 30 years of operation. This demonstrates the long-term economic strength of CANDU technology and justifies a long-term commitment to nuclear power. Indeed, replacement of pressure tubes and feeders with the most recent technology will also lead to increased capacity factors - due to reduced requirements for feeder inspections and repair, and eliminating the need for fuel channel spacer relocation which have caused additional and longer maintenance outages. Continuing the operation of CANDU units parallels the successful life extensions of reactors in other countries and provides the benefits of ongoing reliable operation, at an existing plant location, with the continued support of the host community. The key factors for successful, optimum management of the life cycle are: ongoing, effective plant life management programs; careful development of refurbishment scope, taking into account system condition assessments and a systematic safety review; and, a well-planned and well-executed retubing and refurbishment outage, where safety and risk management is paramount to ensure a successful project The paper will describe: the benefits of extended plant life; the outlook for refurbishment; the life management and refurbishment program; preparations for retubing of the reactor core; and, enhanced performance post-retubing. Given the potential magnitude of the program over the next 10 years, AECL will maintain a lead role providing overall support for retubing and plant Life Cycle Management programs and the CANDU Owners Group will provide a framework for collaboration among its Members. (author)

  3. Nuclear Power in Space

    Science.gov (United States)

    1994-01-01

    In the early years of the United States space program, lightweight batteries, fuel cells, and solar modules provided electric power for space missions. As missions became more ambitious and complex, power needs increased and scientists investigated various options to meet these challenging power requirements. One of the options was nuclear energy. By the mid-1950s, research had begun in earnest on ways to use nuclear power in space. These efforts resulted in the first radioisotope thermoelectric generators (RTGs), which are nuclear power generators build specifically for space and special terrestrial uses. These RTGs convert the heat generated from the natural decay of their radioactive fuel into electricity. RTGs have powered many spacecraft used for exploring the outer planets of the solar system and orbiting the sun and Earth. They have also landed on Mars and the moon. They provide the power that enables us to see and learn about even the farthermost objects in our solar system.

  4. Commercial nuclear power 1990

    International Nuclear Information System (INIS)

    This report presents the status at the end of 1989 and the outlook for commercial nuclear capacity and generation for all countries in the world with free market economies (FME). The report provides documentation of the US nuclear capacity and generation projections through 2030. The long-term projections of US nuclear capacity and generation are provided to the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) for use in estimating nuclear waste fund revenues and to aid in planning the disposal of nuclear waste. These projections also support the Energy Information Administration's annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment, and are provided to the Organization for Economic Cooperation and Development. The foreign nuclear capacity projections are used by the DOE uranium enrichment program in assessing potential markets for future enrichment contracts. The two major sections of this report discuss US and foreign commercial nuclear power. The US section (Chapters 2 and 3) deals with (1) the status of nuclear power as of the end of 1989; (2) projections of nuclear capacity and generation at 5-year intervals from 1990 through 2030; and (3) a discussion of institutional and technical issues that affect nuclear power. The nuclear capacity projections are discussed in terms of two projection periods: the intermediate term through 2010 and the long term through 2030. A No New Orders case is presented for each of the projection periods, as well as Lower Reference and Upper Reference cases. 5 figs., 30 tabs

  5. Life Assurance Strategy for CANDU NPP

    International Nuclear Information System (INIS)

    Nuclear Plants have a nominal 'design life' that forms the basis of equipment specification, economic evaluations and licensing for some jurisdictions. Some component in the plant may require replacement, refurbishing and or rehabilitation during the plant 'design life'. Components which are extremely difficult or economically impossible to replace will place a limit on plant life. Rehabilitation programs completed to date on older CANDU plants to improve reliability of plant components, coupled with R and D programs, experimental data and advanced analytical methods form the basis for CANDU plant component life assurance. Life assurance is verified during plant operation by comprehensive in-service inspection programs and laboratory examinations. The paper provides an overview of the experiences to date on Refurbishment and Rehabilitation programs and some Canadian approaches on the main activities involved in scoping and managing nuclear plant life assurance. A number of proactive programs are underway to anticipate, detect and mitigate potential aging degradation at an early stage to ensure plant safety and reliability. Some of these programs include; systematic plant condition assessment, refurbishment and upgrading programs, environmental qualification programs and a program of examination of components from decommissioned reactors. These programs are part of an overall nuclear power plant maintenance strategy. Beyond life assurance, a longer term approach would be geared towards life extension as a viable option for the future. Recent CANDU designs have benefited from the early CANDU experience and are expected to require less rehabilitation. Examples of changes in CANDU 6 include fuel channel design and adopting a closed component cooling water system. New designs are based on 'design life' longer than that used for economic evaluations. The approach is to design for easy replace ability for components that can be economically replaced. Specific examples

  6. Review on the application of system engineer model in nuclear power plant

    International Nuclear Information System (INIS)

    system engineer was adopted deeply and play important roles in nuclear power plants in United States and Canada, the plant performance indicates that system engineer mode is a good practice. Qinshan CANDU nuclear power plant, established the system engineer mode since commissioning, as a core, system engineer took charge of the preparation of commissioning procedures, organization, coordination and guidance of commissioning execution. Unit 1 was put into commercial operation 43 days in advance and 112 days ahead of schedule for Unit 2 with excellent quality. Commissioning period are just 10.5 and 7.8 months for both Units respectively. Which is the shortest record in the history of CANDU nuclear power plant commissioning up to now. During operation, systems engineer has strength in routine operating and units reliability improvement. Based on the practice of Qinshan CANDU nuclear power plant commissioning and production technical management, the main form of the article in the era of knowledge: its characteristics and advantage and operating mode of the system engineer mode. System engineer is different from project engineer, he act as the master of systems and takes full responsibility for systems technical management. System engineer should do many jobs and improvement schedule to ensure his system in health status. System health monitor is a basic tool in system management, which is useful for equipment performance improvement. At last, the author made a forecast and comment on the prospects for the system engineer in the future. (author)

  7. Methodology for the control of equipment ageing in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Trudel, F. [Hydro-Quebec, Gentilly-2 Nuclear Generating Station, Gentilly, Quebec (Canada)]. E-mail: Trudel.Francis@hydro.qc.ca; Abdul-Nour, G. [Univ. du Quebec a Trois-Rivieres, Dept. of Industrial Engineering, Trois-Rivieres, Quebec (Canada); Vaillancourt, R.; Komljenovic, D. [Hydro-Quebec, Gentilly-2 Nuclear Generating Station, Gentilly, Quebec (Canada)

    2006-07-01

    This paper presents a methodology for the control of equipment ageing as it applies to CANDU 600 nuclear power plants. The methodology that has been developed is based mainly on the approach proposed in Nuclear Plant Ageing Research (NPAR), a program implemented by the Nuclear Regulatory Commission (NRC). It includes twelve steps covering the selection of the equipment, the understanding and the management of ageing. The methodology complies with the new Canadian nuclear regulations as well as recommendations made by world wide nuclear industry. It has been validated through application to three types of mechanical equipment, with results that are deemed significant. (author)

  8. Nuclear power experience

    International Nuclear Information System (INIS)

    The International Conference on Nuclear Power Experience, organized by the International Atomic Energy Agency, was held at the Hofburg Conference Center, Vienna, Austria, from 13 to 17 September 1982. Almost 1200 participants and observers from 63 countries and 20 organizations attended the conference. The 239 papers presented were grouped under the following seven main topics: planning and development of nuclear power programmes; technical and economic experience of nuclear power production; the nuclear fuel cycle; nuclear safety experience; advanced systems; international safeguards; international co-operation. The proceedings are published in six volumes. The sixth volume contains a complete Contents of Volume 1 to 5, a List of Participants, Authors and Transliteration Indexes, a Subject Index and an Index of Papers by Number

  9. 600 MW nuclear power database

    International Nuclear Information System (INIS)

    600 MW Nuclear power database, based on ORACLE 6.0, consists of three parts, i.e. nuclear power plant database, nuclear power position database and nuclear power equipment database. In the database, there are a great deal of technique data and picture of nuclear power, provided by engineering designing units and individual. The database can give help to the designers of nuclear power

  10. Nuclear power plant construction

    International Nuclear Information System (INIS)

    The legal aspects of nuclear power plant construction in Brazil, derived from governamental political guidelines, are presented. Their evolution, as a consequence of tecnology development is related. (A.L.S.L.)

  11. Safeguarding nuclear power stations

    International Nuclear Information System (INIS)

    The basic features of nuclear fuel accounting and control in present-day power reactors are considered. Emphasis is placed on reactor operations and spent-fuel characteristics for Light-Water Reactors (LWRs) and Heavy-Water Reactors (HWRs)

  12. Commercial nuclear power 1989

    International Nuclear Information System (INIS)

    This report presents historical data on commercial nuclear power in the United States, with projections of domestic nuclear capacity and generation through the year 2020. The report also gives country-specific projections of nuclear capacity and generation through the year 2010 for other countries in the world outside centrally planned economic areas (WOCA). Information is also presented regarding operable reactors and those under construction in countries with centrally planned economies. 39 tabs

  13. Turkey's nuclear power effort

    International Nuclear Information System (INIS)

    This paper discusses the expected role of nuclear energy in the production of electric power to serve the growing needs of Turkey, examining past activities and recent developments. The paper also reviews Turkey's plans with respect to nuclear energy and the challenges that the country faces along the way

  14. Nuclear Power Plant Technician

    Science.gov (United States)

    Randall, George A.

    1975-01-01

    The author recognizes a body of basic knowledge in nuclear power plant technoogy that can be taught in school programs, and lists the various courses, aiming to fill the anticipated need for nuclear-trained manpower--persons holding an associate degree in engineering technology. (Author/BP)

  15. No to nuclear power

    International Nuclear Information System (INIS)

    Kim Beazley has again stated a Labor Government would not pursue nuclear power because the economics 'simply don't stack up'. 'We have significant gas, coal and renewable energy reserves and do not have a solution for the disposal of low-level nuclear waste, let alone waste from nuclear power stations.' The Opposition Leader said developing nuclear power now would have ramifications for Australia's security. 'Such a move could result in our regional neighbours fearing we will use it militarily.' Instead, Labor would focus on the practical measures that 'deliver economic and environmental stability while protecting our national security'. Mr Beazley's comments on nuclear power came in the same week as Prime Minister John Howard declined the request of Indian Prime Minister Manmohan Singh for uranium exports, although seemingly not ruling out a policy change at some stage. The Prime Ministers held talks in New Delhi over whether Australia would sell uranium to India without it signing the Nuclear Non-Proliferation Treaty. An agreement reached during a visit by US President George W. Bush gives India access to long-denied nuclear technology and guaranteed fuel in exchange for allowing international inspection of some civilian nuclear facilities. Copyright (2006) Crown Content Pty Ltd

  16. Nuclear power and leukaemia

    International Nuclear Information System (INIS)

    This booklet describes the nature of leukaemia, disease incidence in the UK and the possible causes. Epidemiological studies observing rates of leukaemia near nuclear power stations in the UK and other parts of the world are discussed. Possible causes of leukaemia excesses near nuclear establishments include radioactive discharges into the environment, paternal radiation exposure and viral causes. (UK)

  17. Globalization and nuclear power

    International Nuclear Information System (INIS)

    Different aspects of the experience of nuclear power as recounted by well-known commentators and new contributors are included in two special issues. In general, the discussions are historical and theoretical and most are retrospective. The current position of nuclear power world wide is considered. Its future seems less than secure especially as it will have to compete alongside other energy sources with many problems of control of its materials still unresolved. (UK)

  18. Nuclear power in space

    International Nuclear Information System (INIS)

    The development of space nuclear power and propulsion in the United States started in 1955 with the initiation of the ROVER project. The first step in the ROVER program was the KIWI project that included the development and testing of 8 non-flyable ultrahigh temperature nuclear test reactors during 1955-1964. The KIWI project was precursor to the PHOEBUS carbon-based fuel reactor project that resulted in ground testing of three high power reactors during 1965-1968 with the last reactor operated at 4,100 MW. During the same time period a parallel program was pursued to develop a nuclear thermal rocket based on cermet fuel technology. The third component of the ROVER program was the Nuclear Engine for Rocket Vehicle Applications (NERVA) that was initiated in 1961 with the primary goal of designing the first generation of nuclear rocket engine based on the KIWI project experience. The fourth component of the ROVER program was the Reactor In-Flight Test (RIFT) project that was intended to design, fabricate, and flight test a NERVA powered upper stage engine for the Saturn-class lunch vehicle. During the ROVER program era, the Unites States ventured in a comprehensive space nuclear program that included design and testing of several compact reactors and space suitable power conversion systems, and the development of a few light weight heat rejection systems. Contrary to its sister ROVER program, the space nuclear power program resulted in the first ever deployment and in-space operation of the nuclear powered SNAP-10A in 1965. The USSR space nuclear program started in early 70's and resulted in deployment of two 6 kWe TOPAZ reactors into space and ground testing of the prototype of a relatively small nuclear rocket engine in 1984. The US ambition for the development and deployment of space nuclear powered systems was resurrected in mid 1980's and intermittently continued to date with the initiation of several research programs that included the SP-100, Space Exploration

  19. Nuclear power for tomorrow

    International Nuclear Information System (INIS)

    The evolution of nuclear power has established this energy source as a viable mature technology, producing at comparative costs more than 16% of the electricity generated world-wide. After outlining the current status of nuclear power, extreme future scenarios are presented, corresponding respectively to maximum penetration limited by technical-economic characteristics, and nuclear phase-out at medium term. The situation is complex and country specific. The relative perception of the importance of different factors and the compensation of advantages vs. disadvantages, or risk vs. benefits, has predominant influence. In order to proceed with an objective and realistic estimate of the future role of nuclear power worldwide, the fundamental factors indicated below pro nuclear power and against are assessed, including expected trends regarding their evolution: Nuclear safety risk; reduction to levels of high improbability but not zero risk. Reliable source of energy; improvements towards uniform standards of excellence. Economic competitiveness vs. alternatives; stabilization and possible reduction of costs. Financing needs and constraints; availability according to requirements. Environmental effects; comparative analysis with alternatives. Public and political acceptance; emphasis on reason and facts over emotions. Conservation of fossil energy resources; gradual deterioration but no dramatic crisis. Energy supply assurance; continuing concerns. Infrastructure requirements and availability; improvements in many countries due to overall development. Non-proliferation in military uses; separation of issues from nuclear power. IAEA forecasts to the year 2005 are based on current projects, national plans and policies and on prevailing trends. Nuclear electricity generation is expected to reach about 18% of total worldwide electricity generation, with 500 to 580 GW(e) installed capacity. On a longer term, to 2030, a stabilized role and place among available viable

  20. Country nuclear power profiles

    International Nuclear Information System (INIS)

    The preparation of Country Nuclear Power Profiles was initiated within the framework of the IAEA's programme for nuclear power plant performance assessment and feedback. It responded to a need for a database and a technical document containing a description of the energy and economic situation and the primary organizations involved in nuclear power in IAEA Member States. The task was included in the IAEA's programmes for 1993/1994 and 1995/1996. In March 1993, the IAEA organized a Technical Committee meeting to discuss the establishment of country data ''profiles'', to define the information to be included in the profiles and to review the information already available in the IAEA. Two expert meetings were convened in November 1994 to provide guidance to the IAEA on the establishment of the country nuclear profiles, on the structure and content of the profiles, and on the preparation of the publication and the electronic database. In June 1995, an Advisory Group meeting provided the IAEA with comprehensive guidance on the establishment and dissemination of an information package on industrial and organizational aspects of nuclear power to be included in the profiles. The group of experts recommended that the profiles focus on the overall economic, energy and electricity situation in the country and on its nuclear power industrial structure and organizational framework. In its first release, the compilation would cover all countries with operating power plants by the end of 1995. It was also recommended to further promote information exchange on the lessons learned from the countries engaged in nuclear programmes. For the preparation of this publication, the IAEA received contributions from the 29 countries operating nuclear power plants and Italy. A database has been implemented and the profiles are supporting programmatic needs within the IAEA; it is expected that the database will be publicly accessible in the future

  1. The nuclear power alternative

    International Nuclear Information System (INIS)

    The Director General of the IAEA stressed the need for energy policies and other measures which would help to slow and eventually halt the present build-up of carbon dioxide, methane and other so-called greenhouse gases, which are held to cause global warming. He urged that nuclear power and various other sources of energy, none of which contribute to global warming, should not be seen as alternatives, but should all be used to counteract the greenhouse effect. He pointed out that the commercially used renewable energies, apart from hydropower, currently represent only 0.3% of the world's energy consumption and, by contrast, the 5% of the world's energy consumption coming from nuclear power is not insignificant. Dr. Blix noted that opposition for nuclear power stems from fear of accidents and concern about the nuclear wastes. But no generation of electricity, whether by coal, hydro, gas or nuclear power, is without some risk. He emphasized that safety can never be a static concept, and that many new measures are being taken by governments and by the IAEA to further strengthen the safety of nuclear power

  2. Nuclear power in perspective

    International Nuclear Information System (INIS)

    The nuclear power debate hinges upon three major issues: radioactive waste disposal, reactor safety and proliferation. An alternative strategy for waste disposal is advocated which involves disposing of the radwaste (immobilized in SYNROC, a titanate ceramic waste form) in deep (4 km) drill-holes widely dispersed throughout the entire country. It is demonstrated that this strategy possesses major technical (safety) advantages over centralized, mined repositories. The comparative risks associated with coal-fired power generation and with the nuclear fuel cycle have been evaluated by many scientists, who conclude that nuclear power is far less hazardous. Considerable improvements in reactor design and safety are readily attainable. The nuclear industry should be obliged to meet these higher standards. The most hopeful means of limiting proliferation lies in international agreements, possibly combined with international monitoring and control of key segments of the fuel cycle, such as reprocessing

  3. Physics and nuclear power

    Science.gov (United States)

    Buttery, N. E.

    2008-03-01

    Nuclear power owes its origin to physicists. Fission was demonstrated by physicists and chemists and the first nuclear reactor project was led by physicists. However as nuclear power was harnessed to produce electricity the role of the engineer became stronger. Modern nuclear power reactors bring together the skills of physicists, chemists, chemical engineers, electrical engineers, mechanical engineers and civil engineers. The paper illustrates this by considering the Sizewell B project and the role played by physicists in this. This covers not only the roles in design and analysis but in problem solving during the commissioning of first of a kind plant. Looking forward to the challenges to provide sustainable and environmentally acceptable energy sources for the future illustrates the need for a continuing synergy between physics and engineering. This will be discussed in the context of the challenges posed by Generation IV reactors.

  4. Commercial nuclear power 1990

    Energy Technology Data Exchange (ETDEWEB)

    1990-09-28

    This report presents the status at the end of 1989 and the outlook for commercial nuclear capacity and generation for all countries in the world with free market economies (FME). The report provides documentation of the US nuclear capacity and generation projections through 2030. The long-term projections of US nuclear capacity and generation are provided to the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) for use in estimating nuclear waste fund revenues and to aid in planning the disposal of nuclear waste. These projections also support the Energy Information Administration's annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment, and are provided to the Organization for Economic Cooperation and Development. The foreign nuclear capacity projections are used by the DOE uranium enrichment program in assessing potential markets for future enrichment contracts. The two major sections of this report discuss US and foreign commercial nuclear power. The US section (Chapters 2 and 3) deals with (1) the status of nuclear power as of the end of 1989; (2) projections of nuclear capacity and generation at 5-year intervals from 1990 through 2030; and (3) a discussion of institutional and technical issues that affect nuclear power. The nuclear capacity projections are discussed in terms of two projection periods: the intermediate term through 2010 and the long term through 2030. A No New Orders case is presented for each of the projection periods, as well as Lower Reference and Upper Reference cases. 5 figs., 30 tabs.

  5. Object-oriented simulator of the dynamics of Embalse nuclear power plant

    International Nuclear Information System (INIS)

    LUDWIG is an object-oriented simulator of the dynamics of the CANDU Nuclear power plant Embalse Rio Tercero. The tool consists in a numerical plant analyzer by means of a model of the plant dynamics during normal operation, and a graphic environment for configuration and visualization of results. The simulator was validated against plant transients occurred in the plant and recorded in the past. (author)

  6. France without nuclear power

    International Nuclear Information System (INIS)

    As coal production declined and France found herself in a condition of energy dependency, the country decided to turn to nuclear power and a major construction program was undertaken in 1970. The consequences of this step are examined in this article, by imagining where France would be without its nuclear power. At the end of the sixties, fuel-oil incontestably offered the cheapest way of producing electricity; but the first petroleum crisis was to upset the order of economic performance, and coal then became the more attractive fuel. The first part of this article therefore presents coal as an alternative to nuclear power, describing the coal scenario first and then comparing the relative costs of nuclear and coal investment strategies and operating costs (the item that differs most is the price of the fuel). The second part of the article analyzes the consequences this would have on the electrical power market, from the supply and demand point of view, and in terms of prices. The third part of the article discusses the macro-economic consequences of such a step: the drop in the level of energy dependency, increased costs and the disappearance of electricity exports. The article ends with an analysis of the environmental consequences, which are of greater and greater concern today. The advantage here falls very much in favor of nuclear power, if we judge by the lesser emissions of sulfur dioxide, nitrogen oxides and especially carbon dioxide. 22 refs.; 13 figs.; 10 tabs

  7. Thermal fatigue screening criteria for identifying susceptible piping components in CANDU stations

    Energy Technology Data Exchange (ETDEWEB)

    Schefski, C.; Chen, Q.; Pentecost, S. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2011-07-01

    In December 1987, a fatigue failure in a non-isolable section of a safety injection line at the Farley-2 plant prompted the U.S. Nuclear Regulatory Commission (NRC) to issue Bulletin 88-08 requiring that U.S. utilities review all non-isolable branch lines to determine if they are susceptible to thermal fatigue. The thermal fatigue incident at Farley-2 was caused by stresses in the pipe wall resulting from large-scale temperature fluctuations. Shortly after the Farley-2 event, several other incidents with through-wall cracks due to thermal fatigue had occurred in plant subsystems and piping configurations similar to the Farley-2 safety injection line. Thermal fatigue cracks have also occurred in piping configurations with different geometries, such as drain, residual heat removal, and shutdown cooling suction lines in various pressurized water reactors (PWR) and boiling water reactors (BWR). Thermal fatigue, caused by local thermal stratification phenomena, has received significant attention in the PWR and BWR communities in the past two decades. Although CANDU stations have experienced relatively few thermal fatigue failures; the impact of this known fatigue mechanism for CANDU designs has not been rigorously assessed. Screening and evaluation methodology, which has been developed by Electric Power Research Institute (EPRI) to identify locations susceptible to thermal cycling in PWR systems, has recently been modified under a CANDU Owners Group (COG) project for application in CANDU piping systems. This paper describes a new software tool for evaluating locations susceptible to thermal fatigue in CANDU piping systems in an effort to avoid failures that lead to costly plant shutdowns. The software, combined with engineering judgement, will assist CANDU station staff to focus their inspections on key components, therefore reducing dose, time and cost during outages. Computational Fluid Dynamics (CFD) was used to form the basis for expanding the range of validity in

  8. Research and development for CANDU fuel channels and fuel

    International Nuclear Information System (INIS)

    The CANDU nuclear reactor is distinctly different from BWR and PWR reactors in that it uses many small pressure tubes rather than one large pressure vessel to contain the fuel and coolant. To exploit the advantages of the natural uranium fuel, the pressure tubes, like other core components, are manufactured from zirconium alloys which have low neutron capture cross sections. Also, because natural uranium fuel only achieves a modest burnup, a simple and inexpensive fuel design has been developed. The present paper reviews the features and the research that have led to the very satisfactory performance of the pressure tubes and the fuel in CANDU reactors. Reference is made to current research and development that may lead to further economies in the design and operation of future power reactors. (author)

  9. Nuclear power in Germany

    International Nuclear Information System (INIS)

    I want to give some ideas on the situation of public and utility acceptance of nuclear power in the Federal Republic of Germany and perhaps a little bit on Europe. Let me start with public perception. I think in Germany we have a general trend in the public perception of technology during the last decade that has been investigated in a systematic manner in a recent study. It is clear that the general acceptance of technology decreased substantially during the last twenty years. We can also observe during this time that aspects of the benefits of technology are much less reported in the media, that most reporting by the media now is related to the consequences of technologies, such as negative environmental consequences. hat development has led to a general opposition against new technological projects, in particular unusual and large. That trend is related not only to nuclear power, we see it also for new airports, trains, coal-fired plants. here is almost no new technological project in Germany where there is not very strong opposition against it, at least locally. What is the current public opinion concerning nuclear power? Nuclear power certainly received a big shock after Chernobyl, but actually, about two thirds of the German population wants to keep the operating plants running. Some people want to phase the plants out as they reach the end-of-life, some want to substitute newer nuclear technology, and a smaller part want to increase the use of nuclear power. But only a minority of the German public would really like to abandon nuclear energy

  10. Simulation of a power pulse during loss of coolant accident in a CANDU-6 reactor by coupling the neutronic code PUMA and the thermalhydraulic code CATHENA

    International Nuclear Information System (INIS)

    In the frame of the safety analysis for a joint feasibility study (between Nucleoelectrica Argentina and Atomic Energy of Canada) of using slightly enriched uranium fuel (0.9 w% U235), Loss of Coolant Accidents (LOCAs) simulations were performed for Embalse NPP, a CANDU-6 type reactor (648. MWe gross). Being a reactor with a positive void reactivity coefficient, the void generation during the first seconds of LOCAs leads to an initial power increase, which is larger in the half of the reactor affected by the break. In order to simulate the power transient, which has a strong spatial variation in the flux and power distributions due to CANDU reactor features, two computer codes were used: the 3 dimensional diffusion, spatial kinetics neutronic program PUMA (developed in Argentina) and the thermal-hydraulics program CATHENA (developed in Atomic Energy of Canada). The codes were coupled by an iterative methodology: the CATHENA thermal-hydraulic simulation results (mainly temperatures of fuel and temperatures and densities of coolant) were used as input of the PUMA neutronic calculation, then the time dependent power distribution calculated by PUMA was applied as input for a new CATHENA calculation. The process was repeated up to convergence, which was obtained in a short number of iterations due to the relative minor effect of the power pulse and the strong influence of the break on the thermal-hydraulics Plant behavior during the analyzed time period. The method was utilized to simulate different accidental scenarios (break size and location, and initial conditions). (author)

  11. How nuclear power began

    International Nuclear Information System (INIS)

    Many of the features of the story of nuclear power, both in nuclear weapons and nuclear power stations, derive from their timing. Usually, in the history of science the precise timing of discovery does not make much difference, but in the case of nuclear fission there was the coincidence that crucial discoveries were made and openly published in the same year, 1939, as the outbreak of the Second World War. It is these events of the 1930s and the early post-war era that are mainly discussed. However, the story began a lot earlier and even in the early 1900s the potential power within the atom had been foreseen by Soddy and Rutherford. In the 1930s Enrico Fermi and his team saw the technological importance of their discoveries and took out a patent on their process to produce artificial radioactivity from slow neutron beams. The need for secrecy because of the war, and the personal trusts and mistrusts run through the story of nuclear power. (UK)

  12. The advanced CANDU reactor: The next step in safety and economics

    International Nuclear Information System (INIS)

    The Advanced CANDU Reactor (ACRTM) is the 'Next Generation' CANDUR reactor, aimed at safe, reliable power production at a capital cost significantly less than that of current reactors such as the very successful CANDU 6 reactors (e.g., Wolsong 1-4). The Wolsong 1-4 units are being joined by the Qinshan Phase 3 units in China as the current successful examples of CANDU technology. The ACR design builds on this knowledge base, adding a selected group of innovations to obtain substantial cost reduction while retaining a proven design basis. The ACR maximizes the use of components and equipment applications that are well proven through CANDU and other nuclear experience. Joint development of equipment designs and specifications with manufactures has been emphasized. Similarly, the ACR design emphasizes constructability, and takes advantage of inherent CANDU features to enable short project and construction schedules. Overall, the ACR design represents a balance of proven design basis and innovations to give step improvements in safety, reliability and economics. The ACR development program, now well into the detail design stage, includes parallel formal licensing in the USA and Canada

  13. Nuclear power and nuclear safety 2007

    International Nuclear Information System (INIS)

    The report is the fifth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2007 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events of nuclear power, and international relations and conflicts. (LN)

  14. Nuclear power and nuclear safety 2006

    International Nuclear Information System (INIS)

    The report is the fourth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2006 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power, and international relations and conflicts. (LN)

  15. Nuclear power and nuclear safety 2005

    International Nuclear Information System (INIS)

    The report is the third report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2005 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power and international relations and conflicts. (ln)

  16. Nuclear power and nuclear safety 2008

    International Nuclear Information System (INIS)

    The report is the fifth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2008 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events of nuclear power, and international relations and conflicts. (LN)

  17. Nuclear power and nuclear safety 2004

    International Nuclear Information System (INIS)

    The report is the second report in a new series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2004 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power and international relations and conflicts. (ln)

  18. Improved operability of the CANDU 9 control centre

    Energy Technology Data Exchange (ETDEWEB)

    Macbeth, M. J.; Webster, A. [Atomic Energy of Canada Limited, Saskatoon (Canada)

    1996-04-15

    The next generation CANDU nuclear power plant being designed by AECL is the 900 MWe class CANDU 9 station. It is based upon the Darlington CANDU station design which is among the world leaders in capacity factor with low Operation, Maintenance and Administration (OM and A) costs. This Control Centre design includes the proven functionality of existing CANDU control centres (including the Wolsong 2,3, and 4 control centre improvements, such as the Emergency Core Cooling panels), the characteristics identified by systematic design with human factors analysis of operations requirements and the advanced features needed to improve station operability which is made possible by the application of new technology. The CANDU 9 Control Centre provides plant staff with an improved operability capability due to the combination of proveness, systematic design with human factors engineering and enhanced operating features. Significant features which contribute to this improved operability include: {center_dot} Standard NSP, BOP and F/H panels with controls and indicators integrated by a standard display/presentation philosophy. {center_dot} Common plant parameter signal database for extensive monitoring, checking, display and annunciation. {center_dot} Powerful annunciation system allowing alarm filtering, prioritizing and interrogation to enhance staff recognition of events, plant state and required corrective procedural actions. {center_dot} The use of an overview display to present immediate and uncomplicated plant status information to facilitate operator awareness of unit status in a highly readable and recognizable format. {center_dot} Extensive cross checking of similar process parameters amongst themselves, with the counterpart safety system parameters and as well as with 'signature' values obtained from known steady state conditions. {center_dot} Powerful calculation capabilities, using the plant wide database, providing immediate recognizable and readable and

  19. The abuse of nuclear power

    International Nuclear Information System (INIS)

    Different aspects of possible abuse of nuclear power by countries or individuals are discussed. Special attention is paid to the advantage of nuclear power, despite the risk of weapon proliferation or terrorism. The concepts of some nuclear power critics, concerning health risks in the nuclear sector are rejected as untrue and abusive

  20. Nuclear Power in Japan.

    Science.gov (United States)

    Powell, John W.

    1983-01-01

    Energy consumption in Japan has grown at a faster rate than in any other major industrial country. To maintain continued prosperity, the government has embarked on a crash program for nuclear power. Current progress and issues/reactions to the plan are discussed. (JN)

  1. Response strategy and hierarchy of Wolsong 2, 3, and 4 nuclear power plant abnormal operating manuals

    International Nuclear Information System (INIS)

    Wolsong 2, 3, and 4 are CANDU 6 pressurized heavy water nuclear power plants, each with a gross electrical output of 715 MW(e). The plants were constructed in the Republic of Korea during the 1990s. The three Wolsong units are based on the previous CANDU Wolsong Unit 1, declared in service in 1983. All four units are presently in commercial service. The Wolsong abnormal operating manuals were developed in a cooperative effort between Atomic Energy of Canada Limited, Korea Power Engineering Company staff, and Korea Electric Power Corporation. The role of Atomic Energy of Canada Limited in performing risk assessment studies and supporting CANDU stations for the preparation of emergency operating procedures has greatly benefited the Wolsong abnormal operating manual program. Korea Electric Power Corporation provided training and supervision, Korea Power Engineering Company Inc. prepared the documentation, and Korea Electric Power Corporation reviewed the draft reports. The Wolsong 2, 3, and 4 abnormal operating manuals have been successfully prepared and converted to Emergency Operating Procedures. The validation of the Emergency Operating Procedures via a simulator, is presently in progress at Wolsong site. The paper describes scope, response strategy to upsets and the hierarchy of the abnormal operating manuals. In addition, the structure of abnormal operating manuals is described. (author)

  2. Future fuel cycle development for CANDU reactors

    International Nuclear Information System (INIS)

    The CANDU reactor has proven to be safe and economical and has demonstrated outstanding performance with natural uranium fuel. The use of on-power fuelling, coupled with excellent neutron economy, leads to a very flexible reactor system with can utilize a wide variety of fuels. The spectrum of fuel cycles ranges from natural uranium, through slightly enriched uranium, to plutonium and ultimately thorium fuels which offer many of the advantages of the fast breeder reactor system. CANDU can also burn the recycled uranium and/or the plutonium from fuel discharged from light water reactors. This synergistic relationship could obviate the need to re-enrich the reprocessed uranium and allow a simpler reprocessing scheme. Fule management strategies that will permit future fuel cycles to be used in existing CANDU reactors have been identified. Evolutionary design changes will lead to an even greater flexibility, which will guarantee the continued success of the CANDU system. (author)

  3. Assessment of RELAP5/CANDU+ code for regulatory auditing analysis of CANDU reactors

    Energy Technology Data Exchange (ETDEWEB)

    Bang, Young Seok; Kim, Hho Jung; Yang, Chae Yong

    2001-12-15

    The objectives of this study are to undertake the verification and validation of RELAP5/CANDU+ code, which is developed in this project, by simulating the B8711 test of RD-14 facility, and to examine the properties of this code by doing the sensitivity analysis for experimental prediction modes about thermal-hydraulics phenomena in CANDU reactor systems added to this code. The B8711 test was an experiment of a 45% ROH break for simulating large LOCA. Also, in this study, the methods for making input cards related to CANDU options are described, so that some users can use the RELAP5/CANDU+ code with easy. RELAP/CANDU+ code can choose the options of Henry-Fauske mode, Ransom-Trapp model, and Moody model for prediction of the critical mass flow. It is examined that Henry-Fauske model and Ransom-Trapp model are considered properly, but Moody model is still required to be improved. Heat transfer correlations available in RELAP5/CANDU+ code for CANDU-type reactors are a horizontal stratified model, a fuel heat-up model and D2O/H2O CHF correlations, and these models take an important role to improve the predictability of the experimental procedures. It is concluded that RELAP5/CANDU+ code is useful for the auditing of the accident analysis of CANDU reactors, and the results of the sensitivity analysis for thermal-hydraulic models examined in this study are valuable for the actual auditing of real CANDU-type power plants.

  4. Extrapolating power-ramp performance criteria for current and advanced CANDU fuels

    Energy Technology Data Exchange (ETDEWEB)

    Tayal, M.; Chassie, G.G

    2000-06-01

    To improve the precision and accuracy of power-ramp performance criteria for high-burnup fuel, we have examined in-reactor fuel performance data as well as out-reactor test data. The data are consistent with some of the concepts used in the current formulations for defining fuel failure thresholds, such as size of power-ramp and extent of burnup. Our review indicates that there is a need to modify some other aspects of the current formulations; therefore, a modified formulation is presented in this paper. The improvements mainly concern corrodent concentration and its relationships with threshold stress for failure. The new formulation is consistent with known and expected trends such as strength of Zircaloy in corrosive environment, timing of the release of fission products to the pellet-to-sheath gap, CANLUB coating, and fuel burnup. Because of the increased precision and accuracy, the new formulation is better able to identify operational regimes that are at risk of power-ramp failures; this predictive ability provides enhanced protection to fuel against power-ramp defects. At die same time, by removing unnecessary conservatisms in other areas, the new formulation permits a greater range of defect-free operational envelope as well as larger operating margins in regions that are, in fact, not prone to power-ramp failures. (author)

  5. CANDU reactors, their regulation in Canada, and the identification of relevant NRC safety issues

    International Nuclear Information System (INIS)

    Atomic Energy of Canada, Limited (AECL) and its subsidiary in the US, are considering submitting the CANDU 3 design for standard design certification under 10 CFR Part 52. CANDU reactors are pressurized heavy water power reactors. They have some substantially different safety responses and safety systems than the LWRs that the commercial power reactor licensing regulations of the US Nuclear Regulatory Commission (NRC) have been developed to deal with. In this report, the authors discuss the basic design characteristics of CANDU reactors, specifically of the CANDU 3 where possible, and some safety-related consequences of these characteristics. The authors also discuss the Canadian regulatory provisions, and the CANDU safety systems that have evolved to satisfy the Canadian regulatory requirements as of December 1992. Finally, the authors identify NRC regulations, mainly in 10 CFR Parts 50 and 100, with issues for CANDU 3 reactor designs. In all, eleven such regulatory issues are identified. They are: (1) the ATWS rule (section 50.62); (2) station blackout (section 50.63); (3) conformance with Standard Review Plan (SRP); (4) appropriateness of the source term (section 50.34(f) and section 100.11); (5) applicability of reactor coolant pressure boundary (RCPB) requirements (section 50.55a, etc); (6) ECCS acceptance criteria (section 50.46)(b); (7) combustible gas control (section 50.44, etc); (8) power coefficient of reactivity (GDC 11); (9) seismic design (Part 100); (10) environmental impacts of the fuel cycle (section 51.51); and (11) (standards section 50.55a)

  6. Economics of nuclear power

    International Nuclear Information System (INIS)

    The economics of electricity supply and production in the FRG is to see on the background of the unique European interconnected grid system which makes very significant contributions to the availability of standby energy and peak load power. On this basis and the existing high voltage grid system, we can build large nuclear generating units and realise the favorable cost aspects per installed KW and reduced standby power. An example of calculating the overall electricity generating costs based on the present worth method is explained. From the figures shown, the sensitivity of the generating costs with respect to the different cost components can be derived. It is apparent from the example used, that the major advantage of nuclear power stations compared with fossil fired stations lies in the relatively small percentage fraction contributed by the fuel costs to the electricity generating costs. (orig.)

  7. Nuclear power and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    The report provides data and assessments of the status and prospects of nuclear power and the nuclear fuel cycle. The report discusses the economic competitiveness of nuclear electricity generation, the extent of world uranium resources, production and requirements, uranium conversion and enrichment, fuel fabrication, spent fuel treatment and radioactive waste management. A review is given of the status of nuclear fusion research

  8. Space Nuclear Power Systems

    Science.gov (United States)

    Houts, Michael G.

    2012-01-01

    Fission power and propulsion systems can enable exciting space exploration missions. These include bases on the moon and Mars; and the exploration, development, and utilization of the solar system. In the near-term, fission surface power systems could provide abundant, constant, cost-effective power anywhere on the surface of the Moon or Mars, independent of available sunlight. Affordable access to Mars, the asteroid belt, or other destinations could be provided by nuclear thermal rockets. In the further term, high performance fission power supplies could enable both extremely high power levels on planetary surfaces and fission electric propulsion vehicles for rapid, efficient cargo and crew transfer. Advanced fission propulsion systems could eventually allow routine access to the entire solar system. Fission systems could also enable the utilization of resources within the solar system.

  9. Nuclear Power Prospects

    International Nuclear Information System (INIS)

    The present trend is to construct larger plants: the average power of the plants under construction at present, including prototypes, is 300 MW(e), i.e. three times higher than in the case of plants already in operation. Examples of new large-scale plants ares (a) Wylfa, Anglesey, United Kingdom - scheduled power of 1180 MW(e) (800 MW to be installed by 1967), to be completed in 1968; (b) ''Dungeness B'', United Kingdom - scheduled power of 1200 MW(e); (c) second unit for United States Dresden power plant - scheduled power of 715 MW(e) minimum to almost 800 MW(e). Nuclear plants on the whole serve the same purpose as conventional thermal plants

  10. Nuclear power for desalination

    International Nuclear Information System (INIS)

    Water is one of the most important assets to mankind and without which the human race would cease to exist. Water is required by us right from domestic to industrial levels. As notified by the 'American Nuclear Society' and 'World Nuclear Association' about 1/5th of the world population does not access to portable water especially in the Asian and African subcontinent. The situation is becoming adverse day by day due to rise in population and industrialization. The need of alternative water resource is thus becoming vital. About 97.5% of Earth is covered by oceans. Desalination of saline water to generate potable water is thus an important topic of research. Currently about 12,500 desalination plants are operating worldwide with a capacity of about 35 million m3/day using mainly fossil fuels for generation of large amount of energy required for processing water. These thermal power station release large amount of carbon dioxide and other green house gases. Nuclear reactors are capable of delivering energy to the high energy-intensive processes without any environmental concerns for climate change etc., giving a vision to sustainable growth of desalination process. These projects are currently employed in Kazakhstan, India, Japan, and Pakistan and are coupled to the nuclear reactor for generating electricity and potable water as well. The current climatic scenario favors the need for expanding dual purpose nuclear power plants producing energy and water at the same location. (author)

  11. CANDU advanced fuel R and D programs for 1997 - 2006 in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Suk, H.C.; Yang, M.S.; Sim, K-S.; Yoo, K.J. [Korea Atomic Energy Research Inst., Yusong, Taejon (Korea, Republic of)

    1997-07-01

    KAERI has a comprehensive product development program of CANFLEX and DUPIC fuels to introduce them into CANDU reactors in Korea and a clear vision of how the product will evolve over the next 10 years. CANDU reactors are not the majority of nuclear power plants in Korea, but they produce significant electricity to contribute Korea's economic growth as well as to satisfy the need for energy. The key targets of the development program are safety enhancement, reduction of spent fuel volume, and economic improvements, using the inherent characteristics and advantages of CANDU technology The CANFLEX and DUPIC R and D programs are conducted currently under the second stage of Korea's Nuclear Energy R and D Project as a national mid- and long-term program over the next 10 years from 1997 to 2006. The specific activities of the programs have taken account of the domestic and international environment concerning on non-proliferation in the Peninsula of Korea. As the first of the development products in the short-term, the CANFLEX-NU fuel will be completely developed jointly by KAERI/AECL and will be useful for the older CANDU-6 Wolsong unit 1. As the second product, the CANFLEX-0.9 % equivalent SEU fuel is expected to be completely developed within the next decade. It will be used in CANDU-6 reactors in Korea immediately after the development, if the existing RU in the world is price competitive with natural uranium. The DUPIC R and D program, as a long term program, is expected to demonstrate the possibility of use of used PWR fuel in CANDU reactors in Korea during the next 10 years. The pilot scale fabrication facility would be completed around 2010. (author)

  12. Reactor physics and economic aspects of the CANDU reactor system

    International Nuclear Information System (INIS)

    A history of the development of the CANDU system is given along with a fairly detailed description of the 600 MW(e) CANDU reactor. Reactor physics calculation methods are described, as well as comparisons between calculated reactor physics parameters and those measured in research and power reactors. An examination of the economics of CANDU in the Ontario Hydro system and a comparison between fossil fuelled and light water reactors is presented. Some physics, economics and resources aspects are given for both low enriched uranium and thorium-fuelled CANDU reactors. Finally the RβD program in Advanced Fuel Cycles is briefly described

  13. Overview of nuclear power plant equipment qualification issues and practices

    International Nuclear Information System (INIS)

    This report presents a view of and commentary on the current status of equipment qualification (EQ) in nuclear industries of the major western nations. The introductory chapters discuss the concepts of EQ, the elements of EQ process and highlight some of the key issues in EQ. A brief review of industry practices and some of the prevalent industrial standards is presented, followed by an overview of current regulatory positions in the USA, France, Germany and Sweden. A summary and commentary on the latest research findings on issues relating to accident simulation, to aging simulation and some special topics related to EQ, has been contributed by Franklin Research Centre of Philadelphia. The last part of the report deals with equipment qualification in Canada and gives recommendations on EQ for new plants as well as currently operational CANDU nuclear power plants

  14. Destructive Examination of Experimental Candu Fuel Elements Irradiated in TRIGA-SSR Reactor

    International Nuclear Information System (INIS)

    The object of this work is the behaviour of CANDU fuel elements under power cycling conditions. The tests were run in the 14 MW(th) TRIGA-SSR (Steady State Reactor) reactor from Institute for Nuclear Research (INR) Pitesti. zircaloy-4 is the material used for CANDU fuel sheath. The importance of studying its behaviour results from the fact that the mechanical properties of the CANDU fuel sheath suffer modifications during normal and abnormal operation. In the nuclear reactor the fuel elements endure dimensional and structural changes as well as cladding oxidation, hydriding and corrosion. These changes can lead to defects and even to the loss of integrity of the cladding. This paper presents the results of examinations performed in the Post- irradiation Examination Laboratory (PIEL) from INR Pitesti, on samples from a fuel element irradiated in TRIGA-SSR reactor: (i) Dimensional and macrostructural characterization; (ii) Microstructural characterization by metallographic analyses; (iii) Determination of mechanical properties; (iv) Fracture surface analysis by scanning electron microscopy (SEM). The obtained data could be used to evaluate the security, reliability and nuclear fuel performance, and for CANDU fuel improvement. (author)

  15. Post Irradiation Examination of Experomental CANDU Fuel Elements Irradiated in TRIGA-SSR Reactor

    International Nuclear Information System (INIS)

    The object of this work is the behaviour of CANDU fuel elements under power cycling conditions. The tests were run in the 14 MW (th) TRIGA-SSR (Steady State Reactor) reactor from Institute for Nuclear Research (INR) Pitesti. Zircaloy-4 is the material used for CANDU fuel sheath. The importance of studying its behaviour results from the fact that the mechanical properties of the CANDU fuel sheath suffer modifications during normal and abnormal operation. In the nuclear reactor the fuel elements endure dimensional and structural changes as well as cladding oxidation, hydriding and corrosion. These changes can lead to defects and even to the loss of integrity of the cladding. This paper presents the results of examinations performed in the Post Irradiation Examination Laboratory (PIEL) from INR Pitesti, on samples from a fuel element irradiated in TRIGA-SSR reactor: (i) Dimensional and macrostructural characterization; (ii) Gamma scanning and tomography; (iii) Measurement of pressure, volume and isotopic composition of fission gas; (iv) Microstructural characterization by metallographic analyses; (v) Determination of mechanical properties; amd (vi) Fracture surface analysis by scanning electron microscopy (SEM). The obtained data could be used to evaluate the security, reliability and nuclear fuel performance, and for CANDU fuel improvement. (author)

  16. Proceedings of the Canadian Nuclear Society ninth annual conference, 1988

    International Nuclear Information System (INIS)

    The 74 papers presented at this conference covered the following topics: operational enhancements of existing nuclear power plants; design of small reactors; accident behaviour in CANDU reactor fuel channels; fuel storage and waste management; reactor commissioning and decommissioning; nuclear safety experiments and modelling; the next generation of CANDU reactors; advances in nuclear engineering education in Canada; safety of small reactors; current position and improvements of fuel channels; current issues in nuclear safety; and, medical and industrial radiation applications

  17. Validation of WIMS-CANDU using Pin-Cell Lattices

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Won Young; Min, Byung Joo; Park, Joo Hwan [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2006-07-01

    The WIMS-CANDU is a lattice code which has a depletion capability for the analysis of reactor physics problems related to a design and safety. The WIMS-CANDU code has been developed from the WIMSD5B, a version of the WIMS code released from the OECD/NEA data bank in 1998. The lattice code POWDERPUFS-V (PPV) has been used for the physics design and analysis of a natural uranium fuel for the CANDU reactor. However since the application of PPV is limited to a fresh fuel due to its empirical correlations, the WIMS-AECL code has been developed by AECL to substitute the PPV. Also, the WIMS-CANDU code is being developed to perform the physics analysis of the present operating CANDU reactors as a replacement of PPV. As one of the developing work of WIMS-CANDU, the U{sup 238} absorption cross-section in the nuclear data library of WIMS-CANDU was updated and WIMS-CANDU was validated using the benchmark problems for pin-cell lattices such as TRX-1, TRX-2, Bapl-1, Bapl-2 and Bapl-3. The results by the WIMS-CANDU and the WIMS-AECL were compared with the experimental data.

  18. Pragmatics of nuclear power

    International Nuclear Information System (INIS)

    In context of depletion of fossil fuels and continuous increase of global warming, nuclear power is highly solicited by world energy congress for solving energy crisis for ever. No doubt, a small amount of nuclear fuel can provide immense amount of energy but in exchange of what? Safety, security, large compensation and huge risk of lives, gift of radio-activity to environment and so many adverse effects. Yet are we in a position to reject or neglect it exclusively? Can we show such luxury? Again are we capable to control such a demon for the benefit of human being. Either is it magic lamp of Aladdin or a Frankenstein? Who will give the answer? Likely after nuclear war, is there anybody left in this planet to hide or is there any place available to hide. Answers are not yet known. (author)

  19. Ethical aspects of nuclear power

    International Nuclear Information System (INIS)

    The nuclear controversy comprises many ethical aspects, e.g. the waste disposal problem. Nuclear opponents should not neglect the environmental protection aspect; for example, the use of nuclear power alone brought about an 8% reduction of the CO2 burden in 1987. Our responsibility towards nature and humans in the Third World leaves us no alternative to nuclear power. On the other hand, the nuclear power debate should not become a matter of religious beliefs. (DG)

  20. Nuclear turbine power plant

    International Nuclear Information System (INIS)

    Purpose : To improve the heat cycle balance in a nuclear turbine power plant or the like equipped with a moisture separating and reheating device, by eliminating undesired overcooling of the drains in the pipes of a heat transmission pipe bundle. Constitution : A high pressure turbine is driven by main steams from a steam generator. The steams after driving the high pressure turbine are removed with moistures by way of a moisture separator and then re-heated. Extracted steams from the steam generator or the high pressure turbine are used as a heating source for the reheating. In the nuclear turbine power plant having such a constitution, a vessel for separating the drains and the steams resulted from the heat exchange is provided at the outlet of the reheating device and the steams in the vessel are introduced to the inlet of the moisture separator. (Aizawa, K.)

  1. Nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To suppress corrosion at the inner surfaces of equipments and pipeways in nuclear power plants. Constitution: An injection device comprising a chemical injection tank and a plunger type chemical injection pump for injecting hydrazine as an oxygen remover and ammonia as a pH controller is disposed to the downstream of a condensate desalter column for primary coolant circuits. Since dessolved oxygen in circuit water injected with these chemicals is substantially reduced to zero and pH is adjuted to about 10 - 11, occurrence of stress corrosion cracks in carbon steels and stainless steels as main constituent materials for the nuclear power plant and corrosion products are inhibited in high temperature water, and of corrosion products are inhibited from being introduced as they are through leakage to the reactor core, by which the operators' exposure does can be decreased significantly. (Sekiya, K.)

  2. Initiative against nuclear power plants

    International Nuclear Information System (INIS)

    This publication of the Initiative of Austrian Nuclear Power Plant Opponents contains articles on radiactive waste dispoasal in Austria and and discusses safety issues of the nuclear power plant 'Zwentendorf'. (kancsar)

  3. Nuclear power in Italy

    International Nuclear Information System (INIS)

    As is known to most of this audience in November of 1987 a referendum determined a rejection of nuclear power in Italy. The referendum may be taken into consideration here as a large scale experiment which offers points of interest to this conference and problems to be aware of, in approaching a severe confrontation with the public. To give a synopsis of the Italian perspective I will examine: first the public acceptance in the situation before Chernobyl, then the most disturbing and sensitive factors of Chernobyl's consequences; how the opposition to nuclear energy worked with the support of most media and the strong pressures of an anti-nuclear political party, the syllogism of the opponents and the arguments used, the causes of major weakness of the defenders and how a new perception of nuclear risk was generated in the public. I will come to the topic of utility acceptance by mentioning that ENEL, as the National Utility, in its role is bound to a policy of compliance with Government decisions. It is oriented today to performance of feasibility studies and development of requirements for the next generation of reactors in order to maintain an updated proposal for a future recovery of the nuclear option. I will then try to identify in general terms the factors determining the future acceptance of nuclear power. They will be determined in the interdisciplinary area of politics, media and public interactions with the utilities the uses of the technology are forced to follow, by political constraints, two main directives: working only in new projects to achieve, if possible, new safety goals

  4. Power systems with nuclear-electric generators - Modelling methods

    International Nuclear Information System (INIS)

    considered. The author makes use of various predictive models, search-forecasting, catastrophic, chaotic and risk approaches to select the most suitable analytic apparatus applicable to the nuclear power plant at Cernavoda. Recognizing in costs the most the essential element in decision making the author stresses the current aspects of nuclear systems engineering and refurbishment, aiming at raising the cost-efficiency and competitiveness of the nuclear power systems. Management and personnel aspects are also reviewed. By taking Cernavoda NPP as a case study for CANDU type reactors the author has worked out a valuable methodology for following up nuclear power issue starting from investment, construction, operation and development

  5. Nuclear power in Sweden

    International Nuclear Information System (INIS)

    The lecture describes the energy-political situation in Sweden after the change of Government in October 1976. The present announced nuclear power plant-hostile energy politic, has to face the viewpoints of a technical and economical dependent reality. Disagreements and transgressions of political competences must be reduced, due to the fact that a constructive cooperation between politicians and energy producing corporations is a necessity, to guarantee a safe energy supply in Sweden. (orig.)

  6. Thorium utilization in Candu reactors

    International Nuclear Information System (INIS)

    In this study, means of thorium utilization in a CANDU reactor are considered. A once through thorium-DUPIC cycle is analyzed in detail. CANDU has the best neutron economy among the commercially available power reactors, which makes it suitable for many different fuel cycle options. A review of the available fuel cycles is also done in the scope of this study to select an economically viable cycle which does not impose profound changes in the neutronic properties of the core that require remodeling of core and related systems. To create a good model ot the CANDU core for the necessary calculations, the steady state properties of CANDU reactor are analyzed. It is assumed that approximation ot refueling as moving the bundles at a constant velocity is valid. This approximation leads to a corollary; The average cross sections of two adjacent bidirectionally refueled channels are independent of axial location. This is also veritied. A result of this corollary the CANDU core can be modeled only in radial direction in cylindirical geometry. The steady state CANDU core model is prepared using the actual power values and these values are sought in the results. The control systems which effect the neutron flux shape are introduced into the model later in the form of additional absorption cross section and lower diffusion coefficient. The results are in good agreement with the actual values. Several different thorium-DUPIC fuel bundle configurations are considered and the one with 12 Th02 elements in the third ring is found to have similar burnup dependent cross-sections and location infinite multiplication factors. Using the model created, the bundle is tested also in the tull core model and it is tound that this bundle configuration complies with the current refueling scheme. That is, no changes are necessary in the refuelind rate or the control systems. A higher conversion ratio of 0.82 is attained, while the excess reactivity of the core is found to decrease by 0.01 Ak

  7. Submarine nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To provide a ballast tank, and nuclear power facilities within the containment shell of a pressure resistance structure and a maintenance operator's entrance and a transmission cable cut-off device at the outer part of the containment shell, whereby after the construction, the shell is towed, and installed by self-submerging, and it can be refloated for repairs by its own strength. Constitution: Within a containment shell having a ballast tank and a pressure resisting structure, there are provided nuclear power facilities including a nuclear power generating chamber, a maintenance operator's living room and the like. Furthermore, a maintenance operator's entrance and exit device and a transmission cable cut-off device are provided within the shell, whereby when it is towed to a predetermined a area after the construction, it submerges by its own strength and when any repair inspection is necessary, it can float up by its own strength, and can be towed to a repair dock or the like. (Yoshihara, H.)

  8. Implementation of Wolsong Pump Model, Pressure Tube Deformation Model and Off-take Model into MARS Code for Regulatory Auditing of CANDU Reactors

    International Nuclear Information System (INIS)

    Korea currently has four operating units of the CANDU-6 type reactor in Wolsong. However, the safety assessment system for CANDU reactors has not been fully established due to lack of self-reliance technology. Although the CATHENA code had been introduced from AECL, it is undesirable to use vendor's code for regulatory auditing analysis. In Korea, the MARS code has been developed for decades and is being considered by KINS as a thermal hydraulic regulatory auditing tool for nuclear power plants. Before this decision, KINS (Korea Institute of Nuclear Safety) had developed RELAP5/MOD3/CANDU code for CANDU safety analyses by modifying the model of existing PWR auditing tool, RELAP5/MOD3. The main purpose of this study is to transplant the CANDU models of RELAP5/MOD3/CANDU code to MARS code including quality assurance of the developed models. This first part of the research series presents the implementation and verification of the Wolsong pump model, the pressure tube deformation model, and the off-take model for arbitrary-angled branch pipes

  9. Implementation of Wolsong Pump Model, Pressure Tube Deformation Model and Off-take Model into MARS Code for Regulatory Auditing of CANDU Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, C.; Rhee, B. W.; Chung, B. D. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Cho, Y. J.; Kim, M. W. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2008-05-15

    Korea currently has four operating units of the CANDU-6 type reactor in Wolsong. However, the safety assessment system for CANDU reactors has not been fully established due to lack of self-reliance technology. Although the CATHENA code had been introduced from AECL, it is undesirable to use vendor's code for regulatory auditing analysis. In Korea, the MARS code has been developed for decades and is being considered by KINS as a thermal hydraulic regulatory auditing tool for nuclear power plants. Before this decision, KINS (Korea Institute of Nuclear Safety) had developed RELAP5/MOD3/CANDU code for CANDU safety analyses by modifying the model of existing PWR auditing tool, RELAP5/MOD3. The main purpose of this study is to transplant the CANDU models of RELAP5/MOD3/CANDU code to MARS code including quality assurance of the developed models. This first part of the research series presents the implementation and verification of the Wolsong pump model, the pressure tube deformation model, and the off-take model for arbitrary-angled branch pipes.

  10. Overview paper on nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Spiewak, I.; Cope, D.F.

    1980-09-01

    This paper was prepared as an input to ORNL's Strategic Planning Activity, ORNL National Energy Perspective (ONEP). It is intended to provide historical background on nuclear power, an analysis of the mission of nuclear power, a discussion of the issues, the technology choices, and the suggestion of a strategy for encouraging further growth of nuclear power.

  11. The future of nuclear power

    International Nuclear Information System (INIS)

    Nuclear power is an extremely sensitive issue and its future has been hotly debated. Conflicting arguments have been put forward regarding the viability of nuclear power. The question of whether the world should look to nuclear power for its electricity generating needs is addressed. 2 ills

  12. Overview paper on nuclear power

    International Nuclear Information System (INIS)

    This paper was prepared as an input to ORNL's Strategic Planning Activity, ORNL National Energy Perspective (ONEP). It is intended to provide historical background on nuclear power, an analysis of the mission of nuclear power, a discussion of the issues, the technology choices, and the suggestion of a strategy for encouraging further growth of nuclear power

  13. Standard compliance - NDE performance demonstration/inspection in the CANDU industry

    International Nuclear Information System (INIS)

    CANDU nuclear power plants are operated in 3 provinces in Canada for electric power generation. A table in the paper will show the built and operating plants in Ontario, Quebec, New Brunswick and overseas. The regulator for nuclear power in Canada is the Canadian Nuclear Safety Commission (CNSC). The CNSC holds the plant licensees accountable for compliance to CSA N285.4 for periodic inspections. The Standard basically specifies the 'what, when, where, how, how much and how frequently' NDE is to be done on pressure retaining systems and components in CANDU nuclear power plants. In inspection methods, the Standard specifies they must be non-destructive. The NDE methods were grouped into visual, dimensional, surface, volumetric and integrative. The Standard also specifies that the licensees are responsible for the performance demonstration (PD) of the adequacy of the procedures and the proficiency of the personnel. This paper describes the Standard's requirement in NDE qualification and presents a joint project participated by Canadian and overseas CANDU owners. The sub-project for NDE included providing evidence and technical justification on the adequacy of the procedures and the proficiency of the personnel. The paper describes the qualification methodology followed by the participants. This will be followed by how the participants produced Inspection Specification, tools and procedures, personnel training and qualification programs, test and qualification samples, independent peer reviews and Technical Justification. (author)

  14. Nuclear power renaissance or demise?

    Energy Technology Data Exchange (ETDEWEB)

    Dossani, Umair

    2010-09-15

    Nuclear power is going through a renaissance or demise is widely debated around the world keeping in mind the facts that there are risks related to nuclear technology and at the same time that is it environmentally friendly. My part of the argument is that there is no better alternative than Nuclear power. Firstly Nuclear Power in comparison to all other alternative fuels is environmentally sustainable. Second Nuclear power at present is at the dawn of a new era with new designs and technologies. Third part of the debate is renovation in the nuclear fuel production, reprocessing and disposal.

  15. The need for nuclear power

    International Nuclear Information System (INIS)

    This leaflet examines our energy future and concludes that nuclear power is an essential part of it. The leaflet also discusses relative costs, but it does not deal with social and environmental implications of nuclear power in any detail, since these are covered by other British Nuclear Forum publications. Headings are: present consumption; how will this change in future; primary energy resources (fossil fuels; renewable resources; nuclear); energy savings; availability of fossil fuels; availability of renewable energy resources; the contribution of thermal nuclear power; electricity; costs for nuclear power. (U.K.)

  16. Nuclear power and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Australian Nuclear Science and Technology Organization maintains an ongoing assessment of the world's nuclear technology developments, as a core activity of its Strategic Plan. This publication reviews the current status of the nuclear power and the nuclear fuel cycle in Australia and around the world. Main issues discussed include: performances and economics of various types of nuclear reactors, uranium resources and requirements, fuel fabrication and technology, radioactive waste management. A brief account of the large international effort to demonstrate the feasibility of fusion power is also given. 11 tabs., ills

  17. COG CANDU outage optimization project at Wolsong, Qinshan, Cernavoda, Point Lepreau, Darlington and Pickering

    Energy Technology Data Exchange (ETDEWEB)

    McWilliams, L. [CANDU Owners Group, Toronto, Ontario (Canada)

    2011-07-01

    This COG initiated project objective is to reduce the timeline CANDU power plants are shutdown for planned maintenance outages through knowledge sharing, benchmarking and completion of a Gap Analysis. The following CANDU Nuclear Power Stations/Facilities formed a partnership to achieve the objective: Korean Hydro and Nuclear Power Company (Wolsong), Qinshan, Societatea Nationala 'Nuclearelectrica' (Cernavoda), New Brunswick Power Nuclear (Point Lepreau), Candu Energy Inc. (formerly AECL) and Ontario Power Generation Inc. (Darlington and Pickering). Project participants selected ten focus areas to evaluate and optimize. Benchmarking studies were conducted at each utility. A Gap Analysis was performed between the stations and site specific recommendations have been made considering: Critical path improvement opportunities (Unit Shutdown, RBLRT and Unit Start up); Major work program improvement opportunities (Turbine/Generator, Electrical Maintenance, MOT, SST and the Valve Program); Recommended modifications to reduce outage durations; and, Process Improvements (standardized clearance process). A final report has been issued to each station identifying: Gap Analysis Comparison results; Best Practices for each area studied; Site specific improvement opportunities; Most Effective Process for Outage Preparation; Most Effective Outage Execution Practices; and, Contingency Plan Preparation. Results were discussed during the presentation.

  18. Nuclear power and nuclear safety 2011

    International Nuclear Information System (INIS)

    The report is the ninth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2011 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations and conflicts, and the Fukushima accident. (LN)

  19. Nuclear power and nuclear safety 2010

    International Nuclear Information System (INIS)

    The report is the eighth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2010 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations, and conflicts and the Fukushima accident. (LN)

  20. Nuclear power and nuclear safety 2009

    International Nuclear Information System (INIS)

    The report is the seventh report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2009 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations, conflicts and the European safety directive. (LN)

  1. Nuclear power and nuclear safety 2012

    International Nuclear Information System (INIS)

    The report is the tenth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is prepared in collaboration between DTU Nutech and the Danish Emergency Management Agency. The report for 2012 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations and conflicts, and the results of the EU stress test. (LN)

  2. Nuclear Security for Floating Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Skiba, James M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scherer, Carolynn P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-10-13

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  3. Is nuclear power acceptable

    International Nuclear Information System (INIS)

    The energy shortage forecast for the early 21st century is considered. Possible energy sources other than fossil fuel are stated as geothermal, fusion, solar and fission, of which only fission has been demonstrated technically and economically. The environmental impacts of fission are examined. The hazards are discussed under the following headings: nuclear accident, fatality risk, safe reactor, property damage, acts of God, low-level release of radioactivity, diversion of fissile material and sabotage, radioactive waste disposal, toxicity of plutonium. The public reaction to nuclear power is analyzed, and proposals are made for a programme of safety and security which the author hopes will make it acceptable as the ultimate energy source. (U.K.)

  4. Civil society involvement in informing population on potential risks of nuclear power

    International Nuclear Information System (INIS)

    In 1977 the town Cernavoda, Romania has been selected for the construction of the first Romanian Nuclear Power Plant provided with five CANDU type reactors, planned, at that time, to cover one third of the country power demand. The first Cernavoda Unit has been commissioned on December 2, 1996. The paper presents the preoccupation of different non-governmental organizations with respect to the impact of the nuclear plant operation on the environment and public health and, more generally, of the Uranium mining, heavy water production plants and radioactive waste disposal problems. Such issues, concerning the the energy efficiency and the nuclear power problems in Romania were not exposed so far to the public debate and little, if any, reliable information was provided to the population. The paper stresses the role of civil society in informing population on the risks implied by the nuclear power projects. 2 refs

  5. Alternative fuel cycle options: performance characteristics and impact on nuclear power growth potential

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y. I.; Till, C. E.; Rudolph, R. R.; Deen, J. R.; King, M. J.

    1977-09-01

    The fuel utilization characteristics for LWR, SSCR, CANDU and LMFBR reactor concepts are quantified for various fuel cycle options, including once-through cycles, thorium cycles, and denatured cycles. The implications of various alternative reactor deployment strategies on the long-term nuclear power growth potential are then quantified in terms of the maximum nuclear capacity that can be achieved and the growth pattern over time, subject to the constraint of a fixed uranium-resource base. The overall objective of this study is to shed light on any large differences in the long-term potential that exist between various alternative reactor/fuel cycle deployment strategies.

  6. Industrial process heat from CANDU reactors

    International Nuclear Information System (INIS)

    It has been demonstrated on a large scale that CANDU reactors can produce industrial process steam as well as electricity, reliably and economically. The advantages of cogeneration have led to the concept of an Industrial Energy Park adjacent to the Bruce Nuclear Power Development in the province of Ontario. For steam demands between 300,000 and 500,00 lb/h (38-63 kg/s) and an annual load factor of 80%, the estimated cost of nuclear steam at the Bruce site boundary is $3.21/MBtu ($3.04GJ), which is at least 30% cheaper than oil-fired steam at the same site. The most promising near term application of nuclear heat is likely to be found within the energy-intensive chemical industry. Nuclear energy can substitute for imported oil and coal in the eastern provinces if the price remains competitive, but low cost coal and gas in the western provinces may induce energy-intensive industries to locate near those sources of energy. In the long term it may be feasible to use nuclear heat for the mining and extraction of oil from the Alberta tar sands. (auth)

  7. International nuclear power status 2002

    International Nuclear Information System (INIS)

    This report is the ninth in a series of annual reports on the international development of nuclear power with special emphasis on reactor safety. For 2002, the report contains: 1) General trends in the development of nuclear power; 2) Decommissioning of the nuclear facilities at Risoe National Laboratory: 3) Statistical information on nuclear power production (in 2001); 4) An overview of safety-relevant incidents in 2002; 5) The development in West Europe; 6) The development in East Europe; 7) The development in the rest of the world; 8) Development of reactor types; 9) The nuclear fuel cycle; 10) International nuclear organisations. (au)

  8. International nuclear power status 2001

    International Nuclear Information System (INIS)

    This report is the eighth in a series of annual reports on the international development of nuclear power with special emphasis on reactor safety. For 2001, the report contains: 1) General trends in the development of nuclear power; 2) Nuclear terrorism; 3) Statistical information on nuclear power production (in 2000); 4) An overview of safety-relevant incidents in 2001; 5) The development in West Europe; 6) The development in East Europe; 7) The development in the rest of the world; 8) Development of reactor types; 9) The nuclear fuel cycle; 10) International nuclear organisations. (au)

  9. International nuclear power status 1999

    International Nuclear Information System (INIS)

    This report is the sixth in a series of annual reports on the international development of nuclear power with special emphasis on reactor safety. For 1999, the report contains: General trends in the development of nuclear power; The past and possible future of Barsebaeck Nuclear Power Plant; Statistical information on nuclear power production (in 1998); An overview of safety-relevant incidents in 1999; The development in Sweden; The development in Eastern Europe; The development in the rest of the world; Trends in the development of reactor types; Trends in the development of the nuclear fuel cycle. (au)

  10. ASSERT-PV 3.2: Advanced subchannel thermalhydraulics code for CANDU fuel bundles

    International Nuclear Information System (INIS)

    Highlights: • Introduction to a new version of the Canadian subchannel code, ASSERT-PV 3.2. • Enhanced models for flow-distribution, CHF and post-dryout heat transfer prediction. • Model changes focused on unique features of horizontal CANDU bundles. • Detailed description of model changes for all major thermalhydraulics models. • Discussion on rationale and limitation of the model changes. - Abstract: Atomic Energy of Canada Limited (AECL) has developed the subchannel thermalhydraulics code ASSERT-PV for the Canadian nuclear industry. The most recent release version, ASSERT-PV 3.2 has enhanced phenomenon models for improved predictions of flow distribution, dryout power and CHF location, and post-dryout (PDO) sheath temperature in horizontal CANDU fuel bundles. The focus of the improvements is mainly on modeling considerations for the unique features of CANDU bundles such as horizontal flows, small pitch to diameter ratios, high mass fluxes, and mixed and irregular subchannel geometries, compared to PWR/BWR fuel assemblies. This paper provides a general introduction to ASSERT-PV 3.2, and describes the model changes or additions in the new version to improve predictions of flow distribution, dryout power and CHF location, and PDO sheath temperatures in CANDU fuel bundles

  11. ASSERT-PV 3.2: Advanced subchannel thermalhydraulics code for CANDU fuel bundles

    Energy Technology Data Exchange (ETDEWEB)

    Rao, Y.F., E-mail: raoy@aecl.ca; Cheng, Z., E-mail: chengz@aecl.ca; Waddington, G.M., E-mail: waddingg@aecl.ca; Nava-Dominguez, A., E-mail: navadoma@aecl.ca

    2014-08-15

    Highlights: • Introduction to a new version of the Canadian subchannel code, ASSERT-PV 3.2. • Enhanced models for flow-distribution, CHF and post-dryout heat transfer prediction. • Model changes focused on unique features of horizontal CANDU bundles. • Detailed description of model changes for all major thermalhydraulics models. • Discussion on rationale and limitation of the model changes. - Abstract: Atomic Energy of Canada Limited (AECL) has developed the subchannel thermalhydraulics code ASSERT-PV for the Canadian nuclear industry. The most recent release version, ASSERT-PV 3.2 has enhanced phenomenon models for improved predictions of flow distribution, dryout power and CHF location, and post-dryout (PDO) sheath temperature in horizontal CANDU fuel bundles. The focus of the improvements is mainly on modeling considerations for the unique features of CANDU bundles such as horizontal flows, small pitch to diameter ratios, high mass fluxes, and mixed and irregular subchannel geometries, compared to PWR/BWR fuel assemblies. This paper provides a general introduction to ASSERT-PV 3.2, and describes the model changes or additions in the new version to improve predictions of flow distribution, dryout power and CHF location, and PDO sheath temperatures in CANDU fuel bundles.

  12. The Brazilian nuclear power programme

    International Nuclear Information System (INIS)

    The booklet contains survey articles on the nuclear power problems of Brazil, the German-Brazilian nuclear power agreement, the application of international safety measures, and 'Brazil and the non-proliferation of nuclear weapons'. The agreement is given in full wording. (HP)

  13. Nuclear power generation modern power station practice

    CERN Document Server

    1971-01-01

    Nuclear Power Generation focuses on the use of nuclear reactors as heat sources for electricity generation. This volume explains how nuclear energy can be harnessed to produce power by discussing the fundamental physical facts and the properties of matter underlying the operation of a reactor. This book is comprised of five chapters and opens with an overview of nuclear physics, first by considering the structure of matter and basic physical concepts such as atomic structure and nuclear reactions. The second chapter deals with the requirements of a reactor as a heat source, along with the diff

  14. Automated refueling simulations of a CANDU for the exploitation of thorium fuels

    Science.gov (United States)

    Holmes, Bradford

    CANDU nuclear reactors are in a unique circumstance where they are able to utilize and exploit a number of different fuel options to provide power as a utility. Thorium, a fertile isotope found naturally, is one option that should be explored. Thorium is more abundant than uranium, which is the typical fuel in the reactor and the availability of thorium makes nuclear energy desirable to more countries. This document contains the culmination of a project that explores, tests, and analyzes the feasibility of using thorium in a CANDU reactor. The project first develops a set of twodimensional lattice and three dimensional control rod simulations using the DRAGON Version 4 nuclear physics codes. This step is repeated for many concentrations of thorium. The data generated in these steps is then used to determine a functional enrichment of thorium. This is done via a procedural elimination and optimization of certain key parameters including but not limited to average exit burnup and reactivity evolution. For the purposes of this project, an enrichment of 1 % thorium was found viable. Full core calculations were done using the DONJON 4 code. CANFUEL, a program which simulates the refueling operations of a CANDU reactor for this fuel type was developed and ran for a simulation period of one hundred days. The program and the fuel selection met all selected requirements for the entirety of the simulation period. CANFUEL requires optimization for fuel selection before it can be used extensively. The fuel selection was further scrutinized when a reactivity insertion event was simulated. The adjuster rod 11 withdrawal from the core was analyzed and compared to classical CANDU results in order to ensure no significant deviations or unwanted evolutions were encountered. For this case, the simulation results were deemed acceptable with no significant deviations from the classical CANDU case.

  15. Obrigheim nuclear power plant

    International Nuclear Information System (INIS)

    The gross output of the 345MWe pressurized water nuclear power station at Obrigheim, operation on base load, amounted to about 2.57TWh in 1974, the net power fed to the grid being about 2.44TWh. The core was used to its full capacity until 10 May 1974. Thereafter, the reactor was on stretch-out operation with steadily decreasing load until refuelled in August 1974. Plant availability in 1974 amounted to 92.1%. Of the 7.9% non-availability, 7.87% was attributable to the refuelling operation carried out from 16 August to 14 September and to the inspection, overhaul and repair work and the routine tests performed during this period. The plant was in good condition. Only two brief shutdowns occurred in 1974, the total outage time being 21/2 hours. From the beginning of trial operation in March 1969 to the end of 1974, the plant achieved an availability factor of 85.2%. The mean core burnup at the end of the fifth cycle was 19600 MWd/tonne U, with one fuel element that had been used for four cycles achieving a mean burnup of 39000 MWd/tonne U. The sipping test on the fuel elements revealed defective fuel-rods in a prototype plutonium fuel element, a high-efficiency uranium fuel element and a uranium fuel element. The quantities of radioactive substances released to the environment in 1974 were far below the officially permitted values. In july 1974, a reference preparation made up in the nuclear power station in October 1973 was discovered by outsiders on the Obrigheim municipality rubbish tip. The investigations revealed that this reference preparation had very probably been abstracted from the plant in October 1973 and arrived at the rubbish tip in a most irregular manner shortly before its discovery

  16. Nuclear power and carbon dioxide free automobiles

    International Nuclear Information System (INIS)

    Nuclear energy has been developed as a major source of electric power in Canada. Electricity from nuclear energy already avoids the emission of about 100 million tonnes of carbon dioxide to the atmosphere in Canada. This is a significant fraction of the 619 million tonnes of Canadian greenhouse gas emissions in 1995. However, the current scope of application of electricity to end use energy needs in Canada limits the contribution nuclear energy can make to carbon dioxide emission reduction. Nuclear energy can also contribute to carbon dioxide emissions reduction through expansion of the use of electricity to less traditional applications. Transportation, in particular contributed 165 million tonnes of carbon dioxide to the Canadian atmosphere in 1995. Canada's fleet of personal vehicles consisted of 16.9 million cars and light trucks. These vehicles were driven on average 21,000 km/year and generated 91 million tonnes of greenhouse gases expressed as a C02 equivalent. Technology to improve the efficiency of cars is under development which is expected to increase the energy efficiency from the 1995 level of about 10 litres/100 km of gasoline to under 3 litres/100km expressed as an equivalent referenced to the energy content of gasoline. The development of this technology, which may ultimately lead to the practical implementation of hydrogen as a portable source of energy for transportation is reviewed. Fuel supply life cycle greenhouse gas releases for several personal vehicle energy supply systems are then estimated. Very substantial reductions of greenhouse gas emissions are possible due to efficiency improvements and changing to less carbon intensive fuels such as natural gas. C02 emissions from on board natural gas fueled versions of hybrid electric cars would be decreased to approximately 25 million t/year from the current 91 million tonnes/year. The ultimate reduction identified is through the use of hydrogen fuel produced via electricity from CANDU power

  17. Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Analia Bonelli

    2012-01-01

    Full Text Available A description of the results for a Station Black-Out analysis for Atucha 2 Nuclear Power Plant is presented here. Calculations were performed with MELCOR 1.8.6 YV3165 Code. Atucha 2 is a pressurized heavy water reactor, cooled and moderated with heavy water, by two separate systems, presently under final construction in Argentina. The initiating event is loss of power, accompanied by the failure of four out of four diesel generators. All remaining plant safety systems are supposed to be available. It is assumed that during the Station Black-Out sequence the first pressurizer safety valve fails stuck open after 3 cycles of water release, respectively, 17 cycles in total. During the transient, the water in the fuel channels evaporates first while the moderator tank is still partially full. The moderator tank inventory acts as a temporary heat sink for the decay heat, which is evacuated through conduction and radiation heat transfer, delaying core degradation. This feature, together with the large volume of the steel filler pieces in the lower plenum and a high primary system volume to thermal power ratio, derives in a very slow transient in which RPV failure time is four to five times larger than that of other German PWRs.

  18. Place and role of nuclear power in the strategy of economic development of Romania

    International Nuclear Information System (INIS)

    The paper presents the current world situation of the nuclear power production in comparison with other alternative energy sources. It is stressed the increasing nuclear power share to the total power production in countries like, for instance, France (75 %), Belgium (55.8 %), Spain (35 %) Germany (29.5 %), Russia (11.4 %), etc. Also there are underlined the advantages presented by the nuclear power among which the following are enumerated: the nuclear technology does not produce an aggression upon the environment, the soil, the air and the water are not affected significantly, no gaseous effluents are emitted to result in acid rains, radioactivity of cooling water is maintained under 1 % of maximum admissible concentration, and the arias occupied by the nuclear installations are minimal. Other arguments in favour of nuclear power and against the fossil fuel plants are quantitatively presented for the case of power production in Romania. Romania commissioned recently its first CANDU reactor type nuclear power plant at Cernavoda. Initially planned to operate with five reactors, the Cernavoda NPP is faced with financial difficulties and readjustment of the nuclear power program which, at its inception, in the years '80, provided facilities for nuclear fuel, heavy water, zirconium components and nuclear equipment production. There are presented the measures to dispose of the radioactive wastes. Romania is among a few of the European countries having a national geological disposal site approved by IAEA and OECD expertise. 6 refs

  19. Thermal-hydraulic interfacing code modules for CANDU reactors

    Energy Technology Data Exchange (ETDEWEB)

    Liu, W.S.; Gold, M.; Sills, H. [Ontario Hydro Nuclear, Toronto (Canada)] [and others

    1997-07-01

    The approach for CANDU reactor safety analysis in Ontario Hydro Nuclear (OHN) and Atomic Energy of Canada Limited (AECL) is presented. Reflecting the unique characteristics of CANDU reactors, the procedure of coupling the thermal-hydraulics, reactor physics and fuel channel/element codes in the safety analysis is described. The experience generated in the Canadian nuclear industry may be useful to other types of reactors in the areas of reactor safety analysis.

  20. Project construction and important technical innovation for Qinshan phase III (PHWR) nuclear power plant

    International Nuclear Information System (INIS)

    Qinshan Phase III (PHWR) Nuclear Power Plant, the first commercial heavy water reactor nuclear power plant in China, was the biggest trade project performed between the governments of China and Canada.As the owner, the Third Qinshan Nuclear Power Company (TQNPC) persisted in independent innovation management during the project construction, commissioning and self-dependent operation, efficiently realizing the three controls of the project, i. e. quality control, schedule control and investment control, and persisted in technical improvement on the basis of digestion and absorption of CANDU-6 technology to improve the unit safety and reliability. The project construction practice has helped China's nuclear power project management to becomeprogrammed, computerized,standardized and internationalized management from the existing basis.After completion of the project, with unit safe and steady operation as the prerequisite, TQNPC performed several technical modifications and innovations to continuously improve the unit performance. In the area of staff development, TQNPC paid much attention to cultivation of corporate culture, strengthed staff training and built up a good circulating mechanism with staff training and project construction promoting each other. Further to 'Zero Breakthrough' and a new step forward of locolization successfully realized in Qinshan Nuclear Power Plant and Nuclear Power Qinshan Joint Venture Company, the improvement and developemnt of nuclear power project management level in Qinshan Phase III (PHWR) Nuclear Power Plant provided reference for promotion of nuclear power development in China and standardized management of introducing large imported project. (authors)

  1. Physics and Control Assessment of AN 850 Mw(e) - Leu-Candu Reactor.

    Science.gov (United States)

    Barbone, Michelangelo

    The physics and control assessment of an 850 MW(e) Low Enriched Uranium CANDU Pressurized Heavy Water (LEU -CANDU-PHW) reactor constitute the major objective of this thesis. The use of Low Enriched Uranium fuel in the present CANDU nuclear power generating stations is recognized as economically beneficial due to reduced fuelling costs. The LEU fuel cycle is also recognized as a stepping stone to transit from the present CANDU-PHW once-through natural Uranium cycle to advanced cycles such as those based on Plutonium recycle, once-through Th + U-235 cycle, Thorium with Uranium recycle and net U-235 feed, Thorium with Uranium recycle and Plutonium feed. However, although the use of Low Enriched Uranium in the present CANDU-PHW reactor has economic advantages, and it would act as a technical bridge between the present cycle and advanced cycles, technical problems in different areas of reactor physics and fuel management were anticipated. The present thesis research work adresses the areas of reactor physics, fuel management, and control (in particular, the spatial control of large CANDU-PHW reactors). The main conclusions that have been drawn following these studies are as follows: (1) The Low Enriched Uranium Cycle is feasible in a CANDU-PHW reactor of present design and provided that: (a) The enrichment is kept relatively low (that is, about 1% instead of 0.711%); (b) the number of bundles to be replaced at every refuelling operation is about one-half that of the natural Uranium fuel case; (c) The channels are refuelled in the same direction as the coolant. (2) The response of an LEU-CANDU-PHW reactor to reactivity perturbation such as single- and two-channel refuelling operation, shim transient, shutdown-start-up transient with enrichment levels of 0.9% and 1.2% is essentially very similar {provided that certain conditions in (1) are respected} to that of the natural uranium reactor core case without any reactor reoptimization. The general behaviour of the reactor

  2. Discharges from nuclear power stations

    International Nuclear Information System (INIS)

    HM Inspectorate of Pollution commissioned, with authorising responsibilities in England and Wales, a study into the discharges of radioactive effluents from Nuclear Power Stations. The study considered arisings from nuclear power stations in Europe and the USA and the technologies to treat and control the radioactive discharges. This report contains details of the technologies used at many nuclear power stations to treat and control radioactive discharges and gives, where information was available, details of discharges and authorised discharge limits. (author)

  3. Manpower development for nuclear power

    International Nuclear Information System (INIS)

    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

  4. Nuclear power reactor physics

    International Nuclear Information System (INIS)

    The purpose of this book is to explain the physical working conditions of nuclear reactors for the benefit of non-specialized engineers and engineering students. One of the leading ideas of this course is to distinguish between two fundamentally different concepts: - a science which could be called neutrodynamics (as distinct from neutron physics which covers the knowledge of the neutron considered as an elementary particle and the study of its interactions with nuclei); the aim of this science is to study the interaction of the neutron gas with real material media; the introduction will however be restricted to its simplified expression, the theory and equation of diffusion; - a special application: reactor physics, which is introduced when the diffusing and absorbing material medium is also multiplying. For this reason the chapter on fission is used to introduce this section. In practice the section on reactor physics is much longer than that devoted to neutrodynamics and it is developed in what seemed to be the most relevant direction: nuclear power reactors. Every effort was made to meet the following three requirements: to define the physical bases of neutron interaction with different materials, to give a correct mathematical treatment within the limit of necessary simplifying hypotheses clearly explained; to propose, whenever possible, numerical applications in order to fix orders of magnitude

  5. Nuclear power in human medicine

    International Nuclear Information System (INIS)

    The public widely associate nuclear power with the megawatt dimensions of nuclear power plants in which nuclear power is released and used for electricity production. While this use of nuclear power for electricity generation is rejected by part of the population adopting the polemic attitude of ''opting out of nuclear,'' the application of nuclear power in medicine is generally accepted. The appreciative, positive term used in this case is nuclear medicine. Both areas, nuclear medicine and environmentally friendly nuclear electricity production, can be traced back to one common origin, i.e. the ''Atoms for Peace'' speech by U.S. President Eisenhower to the U.N. Plenary Assembly on December 8, 1953. The methods of examination and treatment in nuclear medicine are illustrated in a few examples from the perspective of a nuclear engineer. Nuclear medicine is a medical discipline dealing with the use of radionuclides in humans for medical purposes. This is based on 2 principles, namely that the human organism is unable to distinguish among different isotopes in metabolic processes, and the radioactive substances are employed in amounts so small that metabolic processes will not be influenced. As in classical medicine, the application of these principles serves two complementary purposes: diagnosis and therapy. (orig.)

  6. Instrumentation and control in the Canadian nuclear power program -1989 status

    International Nuclear Information System (INIS)

    Canada currently has 18 CANDU Pressurized Heavy Water Reactors in operation and 4 under construction, for an installed nuclear capacity of 15,500 MWe. Most of the reactors are in the province of Ontario where 50% of the electricity is nuclear generated. Atomic Energy of Canada is developing the CANDU-3, a 450 MWe reactor incorporating the latest available technologies, including distributed control. The three Canadian Utilities with CANDU reactors have made a major commitment to full-scope training simulators. In Canada there is a growing commitment to developing major improvements to the interface between the control systems, the field equipment and the operating staff. The development program underway makes extensive use of information technology, particularly expert systems and interactive media tools. Out of this will come an advanced CANDU control concept that should further improve the reliability and availability of CANDU stations. (author). 3 refs

  7. International nuclear power status 2000

    International Nuclear Information System (INIS)

    This report is the seventh in a series of annual reports on the international development of nuclear power with special emphasis on reactor safety. For 2000, the report contains: 1. General trends in the development of nuclear power. 2. Deposition of low-level radioactive waste. 3. Statistical information on nuclear power production (in 1999). 4. An overview of safety-relevant incidents in 2000. 5. The development in Sweden. 6. The development in Eastern Europe. 7. The development in the rest of the world. 8. Trends in the development of reactor types. 9. Trends in the development of the nuclear fuel cycle. (au)

  8. Nuclear Power Development in China

    Institute of Scientific and Technical Information of China (English)

    Lin Chengge; Li Shulan

    2009-01-01

    @@ China's nuclear power industry experienced such three stages as initiation, moderate development and active development. So far, there have been 11 nuclear power units in service in the Chinese mainland with a total installed capacity of 9 100 MW. In addition, there are 24 units being constructed or to be constructed as listed in the 11th Five-Year Plan.

  9. Assessment of ASSERT-PV for prediction of critical heat flux in CANDU bundles

    International Nuclear Information System (INIS)

    Highlights: • Assessment of the new Canadian subchannel code ASSERT-PV 3.2 for CHF prediction. • CANDU 28-, 37- and 43-element bundle CHF experiments. • Prediction improvement of ASSERT-PV 3.2 over previous code versions. • Sensitivity study of the effect of CHF model options. - Abstract: Atomic Energy of Canada Limited (AECL) has developed the subchannel thermalhydraulics code ASSERT-PV for the Canadian nuclear industry. The recently released ASSERT-PV 3.2 provides enhanced models for improved predictions of flow distribution, critical heat flux (CHF), and post-dryout (PDO) heat transfer in horizontal CANDU fuel channels. This paper presents results of an assessment of the new code version against five full-scale CANDU bundle experiments conducted in 1990s and in 2009 by Stern Laboratories (SL), using 28-, 37- and 43-element (CANFLEX) bundles. A total of 15 CHF test series with varying pressure-tube creep and/or bearing-pad height were analyzed. The SL experiments encompassed the bundle geometries and range of flow conditions for the intended ASSERT-PV applications for CANDU reactors. Code predictions of channel dryout power and axial and radial CHF locations were compared against measurements from the SL CHF tests to quantify the code prediction accuracy. The prediction statistics using the recommended model set of ASSERT-PV 3.2 were compared to those from previous code versions. Furthermore, the sensitivity studies evaluated the contribution of each CHF model change or enhancement to the improvement in CHF prediction. Overall, the assessment demonstrated significant improvement in prediction of channel dryout power and axial and radial CHF locations in horizontal fuel channels containing CANDU bundles

  10. Assessment of ASSERT-PV for prediction of critical heat flux in CANDU bundles

    Energy Technology Data Exchange (ETDEWEB)

    Rao, Y.F., E-mail: raoy@aecl.ca; Cheng, Z., E-mail: chengz@aecl.ca; Waddington, G.M., E-mail: waddingg@aecl.ca

    2014-09-15

    Highlights: • Assessment of the new Canadian subchannel code ASSERT-PV 3.2 for CHF prediction. • CANDU 28-, 37- and 43-element bundle CHF experiments. • Prediction improvement of ASSERT-PV 3.2 over previous code versions. • Sensitivity study of the effect of CHF model options. - Abstract: Atomic Energy of Canada Limited (AECL) has developed the subchannel thermalhydraulics code ASSERT-PV for the Canadian nuclear industry. The recently released ASSERT-PV 3.2 provides enhanced models for improved predictions of flow distribution, critical heat flux (CHF), and post-dryout (PDO) heat transfer in horizontal CANDU fuel channels. This paper presents results of an assessment of the new code version against five full-scale CANDU bundle experiments conducted in 1990s and in 2009 by Stern Laboratories (SL), using 28-, 37- and 43-element (CANFLEX) bundles. A total of 15 CHF test series with varying pressure-tube creep and/or bearing-pad height were analyzed. The SL experiments encompassed the bundle geometries and range of flow conditions for the intended ASSERT-PV applications for CANDU reactors. Code predictions of channel dryout power and axial and radial CHF locations were compared against measurements from the SL CHF tests to quantify the code prediction accuracy. The prediction statistics using the recommended model set of ASSERT-PV 3.2 were compared to those from previous code versions. Furthermore, the sensitivity studies evaluated the contribution of each CHF model change or enhancement to the improvement in CHF prediction. Overall, the assessment demonstrated significant improvement in prediction of channel dryout power and axial and radial CHF locations in horizontal fuel channels containing CANDU bundles.

  11. Solid-State Nuclear Power

    Science.gov (United States)

    George, Jeffrey A.

    2012-01-01

    A strategy for "Solid-State" Nuclear Power is proposed to guide development of technologies and systems into the second 50 years of nuclear spaceflight. The strategy emphasizes a simple and highly integrated system architecture with few moving parts or fluid loops; the leverage of modern advances in materials, manufacturing, semiconductors, microelectromechanical and nanotechnology devices; and the targeted advancement of high temperature nuclear fuels, materials and static power conversion to enable high performance from simple system topologies.

  12. Strategy for utilizing nuclear power

    International Nuclear Information System (INIS)

    One of the national goals is to achieve independence in the area of energy supplies in the next few years. It is believed that attaining this goal will require extensive utilization of nuclear power in conventional fission reactors. It is proposed that the best way to develop the nuclear resource is through government ownership of the reactors. It is argued that this will minimize the risks associated with the nuclear-power option and clear the way for its exploitation

  13. Nuclear power in developing countries

    International Nuclear Information System (INIS)

    In early 1988, 417 nuclear power plants were in opration worldwide, which is twenty more than in early 1987. The total installed power of 300 GWe corresponds to 11% of the total generating capacity and contributes more than 16% of the worldwide electricity production. Fifty of these nuclear power plants, with an aggregate 28 GWe, have been built in developing countries, where they contribute 7% to the electricity requirement. With respect to installed power, the growth of nuclear power lags behind the plans made ten years ago, because some developing countries have stretched out their nuclear power programs for the next decade. This is due to various reasons. In some cases, the availability of alternative energies has reduced the use of nuclear power. In other cases, the delay has been due to funding and to the long planning and construction periods. The main problem facing the developing countries, however, is financing nuclear power plant projects in the light of the high capital costs of nuclear power plants. (orig.)

  14. Developing countries curtail nuclear power

    International Nuclear Information System (INIS)

    The nuclear power programmes in developing countries, following the accident at the Chernobyl power plant are summarized. Many of these have abandoned plans for nuclear power (eg Gabon), mothballed existing reactors (eg Philippines) or deferred decisions on a reactor programme (eg Egypt, Taiwan, Libya). Economic and political pressures are usually the underlying reasons, but the Chernobyl incident has proved a useful excuse. Other countries (Nigeria, Korea, India, Pakistan) have not let the accident change their nuclear policy. In China, Israel and Turkey the debate about nuclear power has been sharpened by the accident. Although Chernobyl has hastened decisions on nuclear power in some countries it has not affected the long-term policies of developing countries. (UK)

  15. Climate change and nuclear power

    International Nuclear Information System (INIS)

    The nuclear industry has increased its efforts to have nuclear power plants integrated into the post- Kyoto negotiating process of the UN Framework Convention on Climate Change. The Nuclear Energy Institute (NEI) states: ''For many reasons, current and future nuclear energy projects are a superior method of generating emission credits that must be considered as the US expands the use of market- based mechanisms designed around emission credit creation and trading to achieve environmental goals ''. The NEI considers that nuclear energy should be allowed to enter all stages of the Kyoto ''flexibility Mechanisms'': emissions trading, joint implementation and the Clean Development Mechanism. The industry sees the operation of nuclear reactors as emission ''avoidance actions'' and believes that increasing the generation of nuclear power above the 1990 baseline year either through extension and renewal of operating licenses or new nuclear plant should be accepted under the flexibility mechanisms in the same way as wind, solar and hydro power. For the time being, there is no clear definition of the framework conditions for operating the flexibility mechanisms. However, eligible mechanisms must contribute to the ultimate objective of the Climate Convention of preventing ''dangerous anthropogenic interference with the climate system''. The information presented in the following sections of this report underlines that nuclear power is not a sustainable source of energy, for many reasons. In conclusion, an efficient greenhouse gas abatement strategy will be based on energy efficiency and not on the use of nuclear power. (author)

  16. Obrigheim nuclear power plant

    International Nuclear Information System (INIS)

    In 1973 the 345 MW pressurized water nuclear power plant at Obrigheim operated on base load, generating approximately 2.63 TWh, approximately 2.5 TWh of which was supplied to the KWO members. The plant availability for the year was 89.9%. Of the 10.1% non-availability, 6.4% (23 d) was caused by refuelling, including inspection, overhaul and repair operations and routine tests carried out in September 1973. 3.3% was due to stoppages for repairs to a steam generator and the two main cooling pumps, while 0.4% resulted from failures in the electrical section of the plant. The plant was shut down seven times in all, including three scrams. The average core burnup at the end of the fourth cycle (1 September 1973) was 18900 MWd/tU, representing an average burnup of approximately 37500 MWd/tU for a fuel element used in all four cycles. The operating performance of the steam generators and the result of the steam generator inspection carried out during refuelling in 1973 suggest no progressive damage. The quantities of radioactive materials released to the environment in 1973 were well below the officially permitted levels. The availability of the plant from the beginning of pilot operation in 1969 to the end of 1973 was 83.7 %

  17. Garigliano nuclear power plant

    International Nuclear Information System (INIS)

    During the period under review, the Garigliano power station produced 1,028,77 million kWh with a utilization factor of 73,41% and an availability factor of 85,64%. The disparity between the utilization and availability factors was mainly due to a shutdown of about one and half months owing to lack of staff at the plant. The reasons for nonavailability (14.36%) break down as follows: nuclear reasons 11,49%; conventional reasons 2,81%; other reasons 0,06%. During the period under review, no fuel replacements took place. The plant functioned throughout with a single reactor reticulation pump and resulting maximum available capacity of 150 MWe gross. After the month of August, the plant was operated at levels slightly below the maximum available capacity in order to lengthen the fuel cycle. The total number of outages during the period under review was 11. Since the plant was brought into commercial operation, it has produced 9.226 million kWh

  18. The CANTEACH project: preserving CANDU technical knowledge

    International Nuclear Information System (INIS)

    Almost sixty years have passed since the nuclear energy venture began in Canada. Fifty years have passed since the founding of AECL. Tens of thousands of dedicated people have forged a new and successful primary energy supply. CANDU technology is well into its second century. This specialty within the world's fission technology community is quite unique, first because it was established as a separate effort very early in the history of world fission energy, and second because it grew in an isolated environment, with tight security requirements, in its early years. Commercial security rules later sustained a considerable degree of isolation. The pioneers of CANDU development have finished their work. Most of the second generation also has moved on. As yet, we cannot point to a consistent and complete record of this remarkable achievement. We, as a nuclear enterprise, have not captured the design legacy in a form that is readily accessible to the current and future generation of professionals involved with CANDU reactors, be they students, designers, operations staff, regulators, consultants or clients. This is a serious failure. Young people entering our field of study must make do with one or two textbooks and a huge collection of diverse technical papers augmented by limited-scope education and training materials. Those employed in the various parts of the nuclear industry rely mostly on a smaller set of CANDU- related documents available within their own organization; documents that sometimes are rather limited in scope. University professors often have even more limited access to in-depth and up to date information. In fact, they often depend on literature published in other countries when preparing lectures, enhanced by guest lecturers from various parts of the industry. Because CANDU was developed mostly inside Canada, few of these text materials contain useful data describing processes important to the CANDU system. For many years it has been recognized that

  19. Nuclear power for environmental protection

    International Nuclear Information System (INIS)

    Nuclear power does not produce CO2 or other greenhouse gases, and also does not produce any SO2, NOx or other gases which contribute to acid rain. These characteristics of nuclear power are especially important in comparison to coal-fired generation of electricity. As an example, in comparison with a coal-fired power plant of the same size, with abatement systems, a 1300 MW(e) nuclear power plant eliminates annually emissions to the air of about: 2000 t of particulates; 8.5 million t of CO2: 12,000 t of SO2; and 6,000 t of NOx, the precise quantities being dependent on coal quality, power plant design and thermal efficiency, and on the effectiveness of the abatement systems. Opponents of nuclear power concede these facts, but argue that nuclear power is such a small part of the world energy balance that it is insignificant to the big issue of CO2. This is hardly correct. Today, 16% of the world's electricity (and 5% of the world's total primary energy) is generated using nuclear power. If this electricity were to have been generated using coal, it would have resulted in about 1600 million tons of CO2 annually. This is 8% of the 20,000 million tons of CO2 now emitted annually from the burning of fossil fuels, an amount which the Toronto Conference proposed should be cut by 20% up to the year 2005. A further major difference in the two energy systems is that the relatively smaller amount of nuclear wastes is fully isolated from the environment. In addition to discussing the global contributions of nuclear power to environmental improvement, the paper presents actual results achieved in a number of countries, demonstrating the positive contribution which nuclear power has made to reducing the environmental impacts of electricity production. 7 figs, 12 tabs

  20. Towards sustainable nuclear power development

    Energy Technology Data Exchange (ETDEWEB)

    Andrianov, Andrei A.; Murogov, Victor M.; Kuptsov, Ilya S. [Obninsk Institute for Nuclear Power Engineering of NNRU MEPhl, Obninsk, Kaluga Region (Russian Federation)

    2014-05-15

    The review of the current situation in the nuclear energy sector carried out in this article brings to light key problems and contradictions, development trends and prospects, which finally determine the role and significance of nuclear power as a factor ensuring a sustainable energy development. Authors perspectives on the most appropriate developments of nuclear power, which should be based on a balanced use of proven innovative nuclear technologies and comprehensive multilateral approaches to the nuclear fuel cycle are expressed. The problems of wording appropriate and essential requirements for new countries with respect to their preparedness to develop nuclear programs, taking into account their development level of industry and infrastructure as well as national heritages and peculiarities, are explained. It is also indicated that one of the major components of sustainability in the development of nuclear power, which legitimates its public image as a power technology, is the necessity of developing and promoting the concepts of nuclear culture, nuclear education, and professional nuclear ethics. (orig.)

  1. Nuclear power in the Midwest

    International Nuclear Information System (INIS)

    The Twelfth Annual Illinois Energy Conference, held in Chicago, Illinois, October 1984 was sponsored by the Energy Resources Center, University of Illinois at Chicago in cooperation with the U.S. Department of Energy, the Illinois Department of Energy and Natural Resources, the Illinois Energy Resources Commission, and the Illinois Commerce Commission. The theme for the conference was ''Nuclear Power in the Midwest.'' The topic of Nuclear Power is particularly appropriate in view of the fact that the State of Illinois, as well as the Midwest region, has made a major commitment to the use of this option for electric power generation. This is evidenced by the fact that some twenty-three of the eighty-six currently licensed nuclear reactors in the United States are located in the Midwest region. Illinois alone contains ten licensed nuclear reactors with four other nuclear plants either under construction or waiting for an operating license. In rated capacity of electric power generated by nuclear reactors, the region is capable of producing 21.5% of the national total of 70,000 MWe. The problems surrounding nuclear power involve complex technologies, environmental and public health concerns, economic and legal factors as well as numerous other policy questions. The goal of the 12th Annual Illinois Energy Conference was to review these issues in order to educate the public and to assist government policy makers in making rational judgements regarding the use and development of the nuclear power option

  2. Used CANDU fuel waste consumed and eliminated: environmentally responsible, economically sound, energetically enormous

    International Nuclear Information System (INIS)

    The 43,800 tonnes of currently stored CANDU nuclear fuel waste can all be consumed in fast-neutron reactors (FNRs) to reduce its long-term radioactive burden 100,000 times while extracting about 130 times more nuclear energy than the prodigious amounts that have already been gained from the fuel in CANDU reactors. The cost of processing CANDU fuel for use in FNRs plus the cost of recycling the FNR fuel is about 2.5 times less on a per kWh energy basis than the currently projected cost of disposal of 3.6 million used CANDU fuel bundles in a deep geological repository. (author)

  3. An integrated CANDU system

    International Nuclear Information System (INIS)

    Twenty years of experience have shown that the early choices of heavy water as moderator and natural uranium as fuel imposed a discipline on CANDU design that has led to outstanding performance. The integrated structure of the industry in Canada, incorporating development, design, supply, manufacturing, and operation functions, has reinforced this performance and has provided a basis on which to continue development in the future. These same fundamental characteristics of the CANDU program open up propsects for further improvements in economy and resource utilization through increased reactor size and the development of the thorium fuel cycle

  4. On PA of nuclear power

    International Nuclear Information System (INIS)

    Present state of things relating to the nuclear power generation are described first, focusing on the Chernobyl accident, power control test, old-wave and new-wave antinuclear movements, move toward elimination of nuclear power plants, and trend in government-level argument concerning nuclear power generation. Then the importance of public relations activities for nuclear power generation is emphasized. It is stressed that information should be supplied positively to the public to obtain public understanding and confidence. Various activities currently made to promote public relations for nuclear power generation are also outlined, focusing on the improvement in the nuclear power public relations system and practical plans for these activities. Activities for improvement in the public relations system include the organization of public relations groups, establishment and effective implementation of an overall public relations plan, training of core workers for public relations, and management of the public relations system. Other practical activities include the encouragement of the public to come and see the power generation facilities and distribution of pamphlets, and use of the media. (N.K.)

  5. Greenfield nuclear power for Finland

    Energy Technology Data Exchange (ETDEWEB)

    Saarenpaa, Tapio

    2010-09-15

    In Finland, licensing for new nuclear power is ongoing. The political approval is to be completed in 2010. Fennovoima's project is unique in various ways: (i) the company was established only in 2007, (ii) its ownership includes a mixture of local energy companies, electricity-intensive industries and international nuclear competence through E.ON, and (iii) it has two alternative greenfield sites. There are five prerequisites for a successful nuclear power project in a transparent democracy of today: (1) need for additional power capacity, (2) actor prepared to invest, (3) established competence, (4) available site, (5) open communications, and (6) favorable public opinion.

  6. Fuel for advanced CANDU reactors

    International Nuclear Information System (INIS)

    The CANDU reactor system has proven itself to be a world leader in terms of station availability and low total unit energy cost. In 1985 for example, four of the top ten reactor units in the world were CANDU reactors operating in South Korea and Canada. This excellent operating record requires an equivalent performance record of the low-cost, natural uranium fuel. Future CANDU reactors will be an evolution of the present design. Engineering work is under way to refine the existing CANDU 600 and to incorporate state-of-the-art technology, reducing the capital cost and construction schedule. In addition, a smaller CANDU 300 plant has been designed using proven CANDU 600 technology and components but with an innovative new plant layout that makes it cost competitive with coal fired plants. For the long term, work on advanced fuel cycles and major system improvements is underway ensuring that CANDU plants will stay competitive well into the next century

  7. Prospects of nuclear power development in Romania

    International Nuclear Information System (INIS)

    Romania is owner of a CANDU type reactor operated at Cernavoda NPP, a nuclear research TRIGA reactor at Pitesti and a Wwr-S research reactor at Ifi-H H at Mergal, now under conservation in view of decommissioning. In Romania there are also two facilities for radioactive waste processing at INR Pitesti and Ifi-H H Mergal, an intermediary repository for spent fuel at Cernavoda and a radioactive waste disposal facility at Ba ita, Bi hor county. With the management of radioactive wastes is in charge the newly formed authority, the National Agency for the Radioactive Waste Management, Adorn. The Cernavoda NPP Unit 1 (Unit 2 is under construction now and planned to be finished in 2006) was commissioned on December 2, 1996 and it ensures about 10% of the electricity demand in Romania. It is operated with the nuclear fuel produced at the Nuclear Fuel Plant, F CN, at Pitesti and the heavy water produced at Heavy Water Plant, ROMAG at Drobeta Turnu Severin. The construction of Unit 3 at Cernavoda NPP was also initiated in cooperation with AECL Canada, Adeline's, Italy and Khap, Republic of Korea, financial aspects, technical improvements of the design, based on the experience gained with Unit 1 and 2, and economical conditions forecast for the years 2010-2015 being taken into consideration. In case of the Research Reactor TRIGA at Pitesti a total conversion from He to Leu fuel of the reactor core is planned under an IAEA Technical Assistance Project, with domestic and foreign (USA) financing. Studies of feasibility were completed for the conservation and decommissioning of the research reactor Wwr-S at Ifi-H H Mergal. Also a Pare project is underway for refurbishment of the National Repository for Nuclear Waste at Ba ita as well for the construction within the Cernavoda NPP area of the Spent Fuel Intermediate Storage Facility, now under construction within a contract with AECL Canada. The paper also reviews the objectives, contingencies and the issues connected to the

  8. Nuclear power stations licensing

    International Nuclear Information System (INIS)

    The judicial aspects of nuclear stations licensing are presented. The licensing systems of the United States, Spain, France and Federal Republic of Germany are focused. The decree n0 60.824 from July 7 sup(th), 1967 and the following legislation which define the systematic and area of competence in nuclear stations licensing are analysed

  9. Nuclear information seminar

    International Nuclear Information System (INIS)

    The fourth meeting of this type (previous ones were held in 1976, 1977, and 1980) presented papers from ten speakers representing Canadian nuclear power utilities, contractors, and Atomic Energy of Canada Limited. Topics discussed were: the development of nuclear power in Canada and elsewhere, potential use of CANDU reactors for steam generation, waste management, public perceptions, and comparison of nuclear power with coal-fired plants in western Canada

  10. Nuclear power: An evolving scenario

    International Nuclear Information System (INIS)

    The past two years have found the IAEA often in the spotlight - primarily because of our role as the world's 'nuclear watchdog', as we are sometimes referred to on the evening news. The most visible, and often controversial, peaceful nuclear application is the generation of electricity, the focus of this article largely from a European perspective. At the end of last year there were 440 nuclear power units operating worldwide. Together, they supply about 16% of the world's electricity. That percentage has remained relatively steady for almost 20 years. Expansion and growth prospects for nuclear power are centred in Asia. Of the 31 units under construction worldwide, 18 are located in India, Japan, South Korea and China, including Taiwan. Twenty of the last 29 reactors to be connected to the grid are also in the Far East and South Asia. That is probably more active construction than most Europeans would guess, given how little recent growth has occurred in the West. For Western Europe and North America, nuclear construction has been a frozen playing field - the last plant to be completed being Civaux-2 in France in 1999. That should raise a question: with little to no new construction, how has nuclear power been able to keep up with other energy sources, to maintain its share of electricity generation? Interestingly enough, the answer is tied directly to efforts to improve safety performance. The accident at Chernobyl in 1986 prompted the creation of the World Association of Nuclear Operators (WANO), and revolutionized the IAEA approach to nuclear power plant safety. Some analysts believe the case for new nuclear construction in Europe is gaining new ground, for a number of reasons: efforts to limit greenhouse gas emissions and reduce the risk of climate change; security of energy supply; Comparative Public Health Risk; different set of variables when choosing Each country's and region energy strategy. Looking to the future, certain key challenges are, of direct

  11. Proceedings of the international conference on CANDU fuel

    International Nuclear Information System (INIS)

    These proceedings contain full texts of all paper presented at the first International Conference on CANDU Fuel. The Conference was organized and hosted by the Chalk River Branch of the Canadian Nuclear Society and utilized Atomic Energy of Canada Limited's facilities at Chalk River Nuclear Laboratories. Previously, informal Fuel Information Meetings were used in Canada to allow the exchange of information and technology associated with CANDU. The Chalk River conference was the first open international forum devoted solely to CANDU and included representatives of overseas countries with current or potential CANDU programs, as well as Canadian participants. The keynote presentation was given by Dr. J.B. Slater, who noted the correlation between past successes in CANDU fuel cycle technology and the co-operation between researchers, fabricators and reactor owner/operators in all phases of the fuel cycle, and outlined the challenges facing the industry today. In the banquet address, Dr. R.E. Green described the newly restructured AECL Research Company and its mission which blends traditional R and D with commercial initiatives. Since this forum for fuel technology has proven to be valuable, a second International CANDU Fuel Conference is planned for the fall of 1989, again sponsored by the Canadian Nuclear Society

  12. Nuclear power and sustainable development

    International Nuclear Information System (INIS)

    Nuclear Power is a new, innovative technology for energy production, seen in the longer historic perspective. Nuclear technology has a large potential for further development and use in new applications. To achieve this potential the industry needs to develop the arguments to convince policy makers and the general public that nuclear power is a real alternative as part of a sustainable energy system. This paper examines the basic concept of sustainable development and gives a quality review of the most important factors and requirements, which have to be met to quality nuclear power as sustainable. This paper intends to demonstrate that it is not only in minimising greenhouse gas emissions that nuclear power is a sustainable technology, also with respect to land use, fuel availability waste disposal, recycling and use of limited economic resources arguments can be developed in favour of nuclear power as a long term sustainable technology. It is demonstrated that nuclear power is in all aspects a sustainable technology, which could serve in the long term with minimal environmental effects and at minimum costs to the society. And the challenge can be met. But to achieve need political leadership is needed, to support and develop the institutional and legal framework that is the basis for a stable and long-term energy policy. Industry leaders are needed as well to stand up for nuclear power, to create a new industry culture of openness and communication with the public that is necessary to get the public acceptance that we have failed to do so far. The basic facts are all in favour of nuclear power and they should be used

  13. CANDU safety analysis system establishment

    Energy Technology Data Exchange (ETDEWEB)

    Min, Byung Joo; Rhee, B. W.; Park, J. H.; Kim, H. T.; Choi, H. B.; Shim, J. I.; Yoon, C.; Yang, M. K

    2002-03-01

    To develop CANDU safety analysis system, methodology, and assessment technology, GAIs from CNSC and GSIs drived by IAEA are summarized. Furthermore, the following safety items are investigated in the present study. - It is intended to secure credibility of the void reactivity in the stage of nuclear design and analysis. The measurement data concerned with the void reactivity were reviewed and used to assess the physics code such as POWDERPUFS-V/RFSP, and the lattice code such as WIMS-AECL and MCNP-4B. - Reviewing the Final Safety Analysis Report for Wolsong-2/3/4 Units, the safety analysis methodology, classification for accident scenarios, safety analysis codes, their interface, etc. were examined. - The development of 3D CFD transient analysis model has been performed to predict local subcooling of the moderator in the vicinity of Calandria tubes in a CANDU-6 reactor in the case of Large LOCA transient. - The trip coverage analysis methodology based on CATHENA code is developed. The simulation of real plant transient showed good agreement. The trip coverage map was generated successfully for two typical depressurization and pressurization event. - The multi-dimensional analysis methodology for hydrogen distribution and hydrogen burning phenomena in PHWR containment is developed using GOTHIC code. The multi-dimensional analysis predicts the local hydrogen behaviour compared to the lumped parameter model.

  14. The economics of nuclear power

    International Nuclear Information System (INIS)

    Nuclear power is seen by some as a partial solution to climate change. The obvious supporters include nuclear establishments, but the 'surprising' supporters comprise some environmentalists like James Lovelock. One of the 15 strategies proposed by Stephen Pacala and Robert Socolow as part of their wedge model is to substitute nuclear power for coal power. The addition of 700 GW of nuclear power, i.e. roughly twice the current global capacity, would constitute one wedge and could reduce one billion tonnes of carbon by mid-century. (The other 14 strategies include: efficient vehicles; reduced use of vehicles; efficient buildings; efficient baseload coal plants; gas baseload power for coal baseload power capture CO2 at baseload power plant capture CO2 at H2 plant; capture CO2 at coal-to-synfuels plant and geological storage; wind power for coal power; PV power for coal power; wind H2 in fuel-cell car for gasoline in hybrid car; biomass fuel for fossil fuel; reduced deforestation, plus reforestation, afforestation, and new plantations, and conservation tillage

  15. Nuclear power and the environment

    International Nuclear Information System (INIS)

    The environmental impacts and the impacts on man are compared for nuclear power plants and solid-fossil-fuel power plants. Practical experience points to significant advantages of nuclear power facilities. While coal-fired power plants in normal operation pollute the environment up to 30% of the permissible limits, the actual exposures caused by nuclear power plants are less than one per mille of the limits given by legal regulations. Some problems are also discussed of radiation protection. It is stated that thanks to the systematic research in this field which has been carried out for nearly sixty years, the knowledge of ionizing radiation hazards is now much more profound and complex than, e.g., that of toxic chemical pollutants released from fossil-fuel power plants and from chemical plants or contained in vehicle exhaust gases. (Z.M.). 5 tabs

  16. The debate on nuclear power

    International Nuclear Information System (INIS)

    The need for nuclear power is pointed out. The Study Group on Nuclear Fuel Cycles of the American Physical Society has studied the problem of waste disposal in detail and has found that geological emplacement leads to safe waste disposal. The relation between nuclear power and weapons proliferation is discussed. The problem of preventing proliferation is primarily a political problem, and the availability of nuclear power will contribute little to the potential for proliferation. However, to further reduce this contribution, it may be desirable to keep fast-breeder reactors under international control and to use only converters for national reactors. The desirable converter is one which has a high conversion ratio, probably one using the thorium cycle, 233U, and heavy water as the moderator. The nuclear debate in the United States of America is discussed. Work on physical and technical safeguards in the USA against diversion of fissile materials is mentioned. (author)

  17. Nuclear power - razing and creating

    International Nuclear Information System (INIS)

    In the book a studies fulfilled by the author is summarized, and issues of modern status for nuclear reactors safety; worldwide statement of nuclear power; nuclear waste disposal; radiation ecology; military polygons infrastructure conversion are considered. Works - fulfilled under scientific supervision of the author - on getting a new information about nuclear tests consequences on the Kazakhstan territory, its effect on the environment and human health, problems of determination of radiation contamination levels of the Republic's regions, suffered population rehabilitation from these tests, reimbursement of former agricultural areas after nuclear tests activity into national economy are discussed, and implementation of up-to-date technologies is given. The book is intended for a wide circle of readers, specialists, teachers, postgraduates and students and all who are interesting of nuclear power use issues for a prosperity and well-being of mankind

  18. History on foundation of Korea nuclear power

    International Nuclear Information System (INIS)

    This reports the history on foundation of Korea nuclear power from 1955 to 1980, which is divided ten chapters. The contents of this book are domestic and foreign affairs before foundation of nuclear power center, establishment of nuclear power and research center, early activity and internal conflict about nuclear power center, study for nuclear power business and commercialization of the studying ordeal over nuclear power administration and new phase, dispute for jurisdiction on nuclear power business and the process, permission for nuclear reactor, regulation and local administration, the process of deliberation and decision of reactor 3. 4 in Yonggwang, introduction of nuclear reprocessing facilities and activities for social organization.

  19. Investor perceptions of nuclear power

    International Nuclear Information System (INIS)

    Evidence is provided that investor concerns about nuclear power have recently been reflected in the common stock returns of all utilities with such facilities and have resulted in a risk premium. In particular, over the 1978-1982 period, three nuclear-related events occurred at the same time as, and therefore appear to have caused, significant drops in the market values of nuclear utilities relative to their non-nuclear counterparts. The three events were as follows: the accident at TMI, which occurred in March 1979; the realization in the summer of 1980 that an accident of the magnitude of TMI could result in cleanup costs of over $1 billion, which are not completely insurable and could therefore result in substantial losses; and the summer 1982 decision by the Tennessee Valley Authority (TVA) to cancel some if its nuclear power plant construction projects, and the Nuclear Regulatory Commission (NRC) decision to stop work on the construction of the Zimmer reactor, followed by a warning that it might close the Indian Point 2 and 3 reactors. If an individual had invested $100 in an average nuclear utility on the day before the TMI accident and reinvested all dividends, the value of this investment would have fallen by 10% relative to an identical investment in the average non-nuclear utility. The risk of investments in nuclear power versus conventional generating technologies shows nuclear power to be a relatively risky investment. However, relative to all investments, nuclear power was less risky in terms of the type of risk that would cause investors to require a premium before purchasing their securities. 6 figures, 6 tables

  20. Nuclear Power Plant Simulation Game.

    Science.gov (United States)

    Weiss, Fran

    1979-01-01

    Presents a nuclear power plant simulation game which is designed to involve a class of 30 junior or senior high school students. Scientific, ecological, and social issues covered in the game are also presented. (HM)

  1. Trends in the capital costs of CANDU generating stations

    International Nuclear Information System (INIS)

    This paper consolidates the actual cost experience gained by Atomic Energy of Canada Limited, Ontario Hydro, and other Canadian electric utlities in the planning, design and construction of CANDU-PHWR (CANada Deuterium Uranium-Pressurized Heavy Water Reactor) generating stations over the past 30 years. For each of the major CANDU-PHWR generating stations in operation and under construction in Canada, an analysis is made to trace the evolution of the capital cost estimates. Major technical, economic and other parameters that affect the cost trends of CANDU-PHWR generating stations are identified and their impacts assessed. An analysis of the real cost of CANDU generating stations is made by eliminating interest during construction and escalation, and the effects of planned deferment of in-service dates. An historical trend in the increase in the real cost of CANDU power plants is established. Based on the cost experience gained in the design and construction of CANDU-PHWR units in Canada, as well as on the assessment of parameters that influence the costs of such projects, the future costs of CANDU-PHWRs are presented

  2. Space nuclear power systems

    International Nuclear Information System (INIS)

    Materials of the 19-th Symposium on Space Nuclear Energetic and Engine Units taking place in 2002, in Albuquerque, USA are reviewed. Reports on transformation of heat energy produced by nuclear reactors in electrical one are presented in the reports. Result of works on improvement as traditional (Brayton and Rankine cycles, thermoelectricity and thermionic emission), so innovation converter systems (Stirling engine, alkali metal thermal to electric converter - AMTEC, thermoacoustic engine) are represented

  3. Is nuclear power safe enough

    International Nuclear Information System (INIS)

    The vice-chairman of the Nuclear Power Safety Commission presents here the background for the Commission's work. He summarises informally the conclusions reached and quotes the minority dissensions. He also criticises many of the arguments made by anti-nuclear organisations. (JIW)

  4. Sustainable development and nuclear power

    International Nuclear Information System (INIS)

    The sustainability of specific technology became the important issue in future developement perspective as the environmental issue occupies the most priority in adopting the relevant technology. This study summarizes the concepts of sustainable development and analyses the nuclear future under the pressure of sustainable development. Also, it shows the fields that need the concentrated research in nuclear power

  5. Nuclear power and childhood leukaemia

    Energy Technology Data Exchange (ETDEWEB)

    Grimston, M. (AEA Technology, London (UK))

    1991-06-19

    The possibility of illness caused by exposure to emissions from nuclear power plants continues to raise enormous public concern. Nowhere is this more evident than in the debate over the aetiology of childhood leukaemias. This review explores the evidence in relation to this and other diseases which are linked in the public's mind to nuclear power. The scientific evidence presented suggests that these links are more tenuous than is commonly believed. (author).

  6. Nuclear Power Development in China

    Institute of Scientific and Technical Information of China (English)

    2009-01-01

    China's nuclear power industry experienced such three stages as initiation,moderate development and active development.So far,there have been 11 nuclear power units in service in the Chinese mainland with a total installed capacity of 9 100 MW.In addition,there are 24 units being constructed or to be constructed as listed in the 11th Five-Year Plan.

  7. Nuclear power: Issues and misunderstandings

    International Nuclear Information System (INIS)

    A sizeable sector of the public remains hesitant or opposed to the use of nuclear power. With other groups claiming nuclear power has a legitimate role in energy programs, there is a need to openly and objectively discuss the concerns limiting its acceptance: the perceived health effects, the consequences of severe accidents, and the disposal of high level waste. This paper discusses these concerns using comparisons with other energy sources. (author)

  8. Value added services to CANDU plants

    International Nuclear Information System (INIS)

    Over the last decade or so, nuclear power plants, just like other types of electricity generating plants, have been facing a number of challenges. Depending on the operating environment of the utility, these challenges are forcing plant owners to examine all facets of the operating costs. Privatization, deregulation and economics of alternative electricity generation methods are exerting enormous pressure on nuclear power plants to streamline costs and improve their operational performance. CANDU reactors are no exception to these forces and face similar pressures. In particular, operating plants that are contemplating plant life extensions are being required to clearly demonstrate the economics of continued operation over other forms of power generation available to the utility. Improvement of capacity factors has the effect of increasing the revenues from the plant and as these revenues increase, the fixed portion of the plant costs including OM and A costs become a smaller percentage of the total revenues. Similar results can be achieved by aiming to reduce the plant OM and A costs. In reality, most well-planned intervention schemes directed at reducing OM and A costs tend to also increase the plant availability. Following plant turnover after commissioning, AECL has been supporting the CANDU owners and utilities with an assortment of products and services dealing with plant operations and outage management issues. AECL has taken the lead in arranging specialized resources, products and services by teaming with other complementary organizations to provide a complete suite of services. Recent examples of such support to operating CANDU plants will be described in the paper. AECL is responding to this changing business environment in two important ways. First, AECL is changing from simply providing a service to its clients towards providing value, something much more important. To this end, AECL is looking to other organizations to form alliances, partnerships and

  9. Key thrusts in next generation CANDU. Annex 10

    International Nuclear Information System (INIS)

    Current electricity markets and the competitiveness of other generation options such as CCGT have influenced the directions of future nuclear generation. The next generation CANDU has used its key characteristics as the basis to leap frog into a new design featuring improved economics, enhanced passive safety, enhanced operability and demonstrated fuel cycle flexibility. Many enabling technologies spinning of current CANDU design features are used in the next generation design. Some of these technologies have been developed in support of existing plants and near term designs while others will need to be developed and tested. This paper will discuss the key principles driving the next generation CANDU design and the fuel cycle flexibility of the CANDU system which provide synergism with the PWR fuel cycle. (author)

  10. Nuclear power - the glittering prizes

    Energy Technology Data Exchange (ETDEWEB)

    Horton, C.C.

    The paper on the benefits of nuclear power is based on a lecture given for the Institution of Nuclear Engineers, London, 1986. Suggestions for short term benefits include a clean environment and a cheap energy source, whereas suggestions for long term benefits include freedom from want in the world and avoidance of 'energy wars'. These benefits are discussed along with alternative energy sources, the financial savings to be saved from nuclear power, world energy wealth, depletion of world energy reserves, and risks due to radiation exposure.

  11. Nuclear power - the glittering prizes

    International Nuclear Information System (INIS)

    The paper on the benefits of nuclear power is based on a lecture given for the Institution of Nuclear Engineers, London, 1986. Suggestions for short term benefits include a clean environment and a cheap energy source, whereas suggestions for long term benefits include freedom from want in the world and avoidance of 'energy wars'. These benefits are discussed along with alternative energy sources, the financial savings to be saved from nuclear power, world energy wealth, depletion of world energy reserves, and risks due to radiation exposure. (UK)

  12. 'Nuclearelectrica' Company messages for a broadly acceptable nuclear power program

    International Nuclear Information System (INIS)

    to build the credibility and how easily this credibility, if something wrong occurs in a nuclear facility, can go down to zero, or worst, can turn exactly into its opposite. Now the new organization of the electrical sector determines 'a new look' for our messages. This paper presents the messages that our company uses trying to maintain its credibility gained over the years. This messages are approaching major issues as for instance: - Cernavoda NPP, first; - Cernavoda NPP, striving for maximum safety; - Cernavoda NPP an ecological source of power; - CANDU, a safe and optimum concept for Romania; - Five years of commercial operation, a contribution of Cernavoda NPP Unit 1 to a cleaner environment; - Nuclear power, cheap, safe and environment friendly; - Nuclear power a valid economic safe and ethical option; - Nuclear power a technology for sustainable development. All these messages were very well received by population with the occasion of the public hearings at Constanta, Cernavoda, Medgidia related with the issue of completion of Cernavoda NPP Unit 2. (authors)

  13. Training Nuclear Power Specialists

    International Nuclear Information System (INIS)

    Situation of preparation of nuclear energy specialists in Lithuania is presented. Nuclear engineers are being prepared at Kaunas University of Technology. In view with decision to shut down Unit 1, the Ignalina NPP is limiting the number of new personnel to fill in vacancies. The main attention is given to the training courses for improvement skills of existing Ignalina NPP, VATESI personnel. Main topics of the training courses are listed. Information on number of the personnel who extended their knowledge and improved skills by the type of training is presented

  14. Infrastructure needs for nuclear power

    International Nuclear Information System (INIS)

    Nuclear power is a significant component of electricity systems world-wide and in OECD countries as a whole it accounts for about 25% of the electricity supply. The current stagnation in nuclear power orders and the expectation of diminishing nuclear programmes in several countries might jeopardize industrial infrastructures based on nuclear activities. Questions arise as to whether special measures are needed to ensure that the nuclear option will be available when wanted and if so, who would take these measures. This paper provides at first an attempt to define what can be considered as ''structure'' and ''infrastructure'' and then a review of relevant issues related to industrial and governmental supporting infrastructure. In particular, the manpower availability and educational implications are examined

  15. Public attitudes to nuclear power

    International Nuclear Information System (INIS)

    The public is influenced against nuclear power by fear of a large accident, fear of radiation, worry about nuclear waste, and by the fact that it is a symbol of the bureaucratic, impersonal aspects of industrialized society. The nuclear industry must do several things to overcome this public concern. It must be more articulate in speaking to the public in a language the public understands and not in nuclear jargon; it must be strictly accurate and truthful in all statements, and if it believes the case it is putting forward is sound, it should defend the proposal and not promise to do even more to buy off criticism. Acceptance of nuclear power will either have to wait until the energy situation is desperate, or until the industry puts enough effort into presenting and defending its case to convince all objective people

  16. Nuclear Power and Sustainable Development

    International Nuclear Information System (INIS)

    Any discussion of 21st century energy trends must take into account the global energy imbalance. Roughly 1.6 billion people still lack access to modern energy services, and few aspects of development - whether related to living standards, health care or industrial productivity - can take place without the requisite supply of energy. As we look to the century before us, the growth in energy demand will be substantial, and 'connecting the unconnected' will be a key to progress. Another challenge will be sustainability. How can we meet these growing energy needs without creating negative side effects that could compromise the living environment of future generations? Nuclear power is not a 'fix-all' option. It is a choice that has a place among the mix of solutions, and expectations for the expanding use of nuclear power are rising. In addition to the growth in demand, these expectations are driven by energy security concerns, nuclear power's low greenhouse gas emissions, and the sustained strong performance of nuclear plants. Each country must make its own energy choices; one size does not fit all. But for those countries interested in making nuclear power part of their sustainable development strategies, it is important that the nuclear power option be kept open and accessible

  17. Nuclear power infrastructure and planning

    International Nuclear Information System (INIS)

    There are several stages in the process of introducing nuclear power in a country. These include feasibility studies; technology evaluation; request for proposals and proposal evaluation; project and contracts development and financing; supply, construction, and commissioning; and finally operation. The IAEA is developing guidance directed to provide criteria for assessing the minimum infrastructure necessary for: a) a host country to consider when engaging in the implementation of nuclear power, or b) a supplier country to consider when assessing that the recipient country would be in an acceptable condition to begin the implementation of nuclear power. There are Member States that may be denied the benefits of nuclear energy if the infrastructure requirements are too large or onerous for the national economy. However if co-operation could be achieved, the infrastructure burden could be shared and economic benefits gained by several countries acting jointly. The IAEA is developing guidance on the potential for sharing of nuclear power infrastructure among countries adopting or extending nuclear power programme

  18. Sustainable development and nuclear power

    International Nuclear Information System (INIS)

    Although there is an awareness on both the technical and political levels of the advantages of nuclear power, it is not a globally favoured option in a sustainable energy future. A sizeable sector of public opinion remains hesitant or opposed to its increased use, some even to a continuation at present levels. With various groups calling for a role for nuclear power, there is a need openly and objectively to discuss the concerns that limit its acceptance: the perceived health effects, the consequences of severe accidents, the disposal of high level waste and nuclear proliferation. This brochure discusses these concerns, and also the distinct advantages of nuclear power. Extensive comparisons with other energy sources are made

  19. Topics in nuclear power

    International Nuclear Information System (INIS)

    The 101 nuclear plants operating in the US today are far safer than they were 20-30 years ago. For example, there's been about a 100-fold reduction in the occurrence of 'significant events' since the late 1970s. Although the youngest of currently operating US plants was designed in the 1970s, all have been significantly modified over the years. Key contributors to the safety gains are a vigilant culture, much improved equipment reliability, greatly improved training of operators and maintenance workers, worldwide sharing of experience, and the effective use of probabilistic risk assessment. Several manufacturers have submitted high quality new designs for large reactors to the U.S. Nuclear Regulatory Commission (NRC) for design approval, and several companies are vigorously working on designs for smaller, modular reactors. Although the Fukushima reactor accident in March 2011 in Japan has been an almost unmitigated disaster for the local population due to their being displaced from their homes and workplaces and also due to the land contamination, its 'lessons learned' have been important for the broader nuclear industry, and will surely result in safer nuclear plants worldwide - indeed, have already done so, with more safety improvements to come

  20. Nuclear power: in perspective

    International Nuclear Information System (INIS)

    Dr. Agnew, former director of Los Alamos Scientific Lab., observes that modern communications have made the over-populated and less-developed countries impatient to have the energy-intensive living standards enjoyed by Europe and the US. More cartels can be expected, he feels, to give these people economic leverage unless they are supplied with cheap, available energy. He notes that all energy sources, including nuclear, have a role and must be developed. The economic and environmental impacts of nuclear energy compare favorably with other major energy sources, but the public neds to be given factual rather than sensational information about nuclear energy so that realistic comparisons can be made. Dr. Agnew points to new types of reactors for land-based facilities that can be designed and that will be safer than the water-cooled design and eliminate some risks. He also finds fuel reprocessing removing some risks, in contrast to the failing nonproliferation policy. He admonishes opponents of nuclear energy to recognize that their position has serious social and economic implications for developing countries and possibly grave political and security repercussions for the US

  1. Nuclear power plant

    International Nuclear Information System (INIS)

    The nuclear part with the negative pressure control system is installed in an underground chamber of a mountain. The containment consists of a sealing concrete layer directly sprayed to the rock and containing reinforcement inserts as well as of a consolidating concrete shell. The sealing concrete layer is combined with the rock by means of prestressed concrete tie rods. (DG)

  2. Topics in nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Budnitz, Robert J. [Earth Sciences Division, Lawrence Berkeley National Laboratory, Berkeley, CA 94720 (United States)

    2015-03-30

    The 101 nuclear plants operating in the US today are far safer than they were 20-30 years ago. For example, there's been about a 100-fold reduction in the occurrence of 'significant events' since the late 1970s. Although the youngest of currently operating US plants was designed in the 1970s, all have been significantly modified over the years. Key contributors to the safety gains are a vigilant culture, much improved equipment reliability, greatly improved training of operators and maintenance workers, worldwide sharing of experience, and the effective use of probabilistic risk assessment. Several manufacturers have submitted high quality new designs for large reactors to the U.S. Nuclear Regulatory Commission (NRC) for design approval, and several companies are vigorously working on designs for smaller, modular reactors. Although the Fukushima reactor accident in March 2011 in Japan has been an almost unmitigated disaster for the local population due to their being displaced from their homes and workplaces and also due to the land contamination, its 'lessons learned' have been important for the broader nuclear industry, and will surely result in safer nuclear plants worldwide - indeed, have already done so, with more safety improvements to come.

  3. Providing emergency supply of nuclear power plants

    OpenAIRE

    ROZMILER, Jiří

    2013-01-01

    Work "Providing emergency power nuclear power plant" describes how solving their own consumption nuclear power plant, as emergency power supply is designed and how it should be a solution of known states of emergency, having an immediate impact on the power consumption of their own nuclear power plants. The aim of this thesis is to propose options to strengthen its own emergency power consumption of nuclear power plants, one might say-more resistant to harsh extremes, which could lead to loss...

  4. CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR. PART 9 - CUTTING AND EXTRACTING DEVICE FUNCTIONING

    Directory of Open Access Journals (Sweden)

    Constantin POPESCU

    2015-05-01

    Full Text Available This paper presents a constructive solution proposed by the authors in order to achieve of a cutting and extracting device for the decommissioning of the horizontal fuel channels in the CANDU 6 nuclear reactor. The Cutting and Extraction Device (CED performs the dismantling, cutting and extraction of the fuel channel components. It's a flexible and modular device, which is designed to work inside the fuel channel and has the following functions: moving with variable speed, temperature monitoring and video surveillance inside the pipe, unblock and extract the channel closure plug (from End Fitting - EF, unblock and extract the channel shield plug (from Lattice Tube - LT, block and cut the middle of the pressure tube, block and cut the end of the pressure tube, block and extract the half of pressure tube. The Cutting and Extraction Device (CED consists of following modules: guiding-fixing module, traction modules, cutting module, guiding-extracting module and flexible elements for modules connecting. The guiding-fixing module is equipped with elastic guiding rollers and fixing claws in working position, the traction modules are provided with variable pitch rollers for allowing variable travel speed through the fuel channel. The cutting module is positioned in the middle of the device and it is equipped with three knife rolls for pressure tube cutting, using a system for cutting place video surveillance and pyrometers for monitoring cutting place temperature. The Cutting and Extraction Device (CED is fully automated, connected by wires to a Programmable Logic Controller (PLC and controlled from a Human Machine Interface (HMI. The design of the Cutting and Extraction Device (CED shall be achieved according to the particular features of the fuel channel components to be dismantled and to ensure radiation protection of workers.

  5. Environmental aspects of nuclear power

    International Nuclear Information System (INIS)

    Nuclear power provides the world with an important option for generating electricity. To successfully and safely utilize this power, engineering and environmental factors should be carefully considered throughout a nuclear power plant project, especially during the planning stages. This paper discusses the major environmental aspects of a nuclear power plant project from site selection to retirement. During the site selection process, both engineering and environmental resources must be identified and evaluated. Environmental resources include areas that support agricultural or aquatic commercial activities, habitats for commercial or endangered species, population centers, transportation systems, and recreational areas. Also, during the site selection process, the potential impacts of both construction and operating activities must be considered. In addition to the area actually disturbed by construction, construction activities also affect local services, such as transportation systems, housing, school systems, and other social services. Since nuclear power plants use a 'clean fuel,' generally the most significant operating activity having a potential environmental impact is the discharge of cooling water. The potential effect of this discharge on commercial activities and sensitive habitats should be thoroughly evaluated. Lastly, the method of decommissioning can affect long-range land use planning and should therefore be considered during the planning process. With appropriate planning, nuclear power plants can be constructed and operated with minimum environmental impact. (author)

  6. Starting of nuclear power stations

    International Nuclear Information System (INIS)

    The procedure is briefly characterized of jobs in nuclear power plant start-up and the differences are pointed out from those used in conventional power generation. Pressure tests are described oriented to tightness, tests of the secondary circuit and of the individual nodes and facilities. The possibility is shown of increased efficiency of such jobs on an example of the hydraulic tests of the second unit of the Dukovany nuclear power plant where the second and the third stages were combined in the so-colled integrated hydraulic test. (Z.M.). 5 figs

  7. Licensing assessment of the Candu Pressurized Heavy Water Reactor. Preliminary safety information document. Volume II. [USA

    Energy Technology Data Exchange (ETDEWEB)

    1977-06-01

    ERDA has requested United Engineers and Constructors (UE and C) to evaluate the design of the Canadian natural uranium fueled, heavy water moderated (CANDU) nuclear reactor power plant to assess its conformance with the licensing criteria and guidelines of the U.S. Nuclear Regulatory Commission (USNRC) for light water reactors. This assessment was used to identify cost significant items of nonconformance and to provide a basis for developing a detailed cost estimate for a 1140 MWe, 3-loop Pressurized Heavy Water Reactor (PHWR) located at the Middletown, USA Site.

  8. Licensing assessment of the Candu Pressurized Heavy Water Reactor. Preliminary safety information document. Volume II

    International Nuclear Information System (INIS)

    ERDA has requested United Engineers and Constructors (UE and C) to evaluate the design of the Canadian natural uranium fueled, heavy water moderated (CANDU) nuclear reactor power plant to assess its conformance with the licensing criteria and guidelines of the U.S. Nuclear Regulatory Commission (USNRC) for light water reactors. This assessment was used to identify cost significant items of nonconformance and to provide a basis for developing a detailed cost estimate for a 1140 MWe, 3-loop Pressurized Heavy Water Reactor (PHWR) located at the Middletown, USA Site

  9. Fuel condition in Canadian CANDU 6 reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hu, R.H.; Macici, N [Hydro-Quebec, Montreal, Quebec (Canada); Gibb, R. [New Brunswick Power, Lepreau, NB (Canada); Purdy, P.L.; Manzer, A.M. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Kohn, E. [Ontario Hydro, Toronto, Ontario (Canada)

    1997-07-01

    The cornerstone of the CANDU concept is its natural uranium fuel, and the success of its reactor operation hinges on the fuel condition in the reactor. Neutron economy, on power refuelling, and simple fuel design are among the unique characteristics of CANDU fuel. In Canadian CANDU 6 reactors (Gentilly 2 and Point Lepreau), the 37-element fuel has provided an enviable record of safe, economic and reliable plant operation for 29 reactor years to date. The fuelling cost is among the lowest in the world - a corollary of high neutron economy, simple fuel design, and judicial fuelling scheme. The reliability of fuel is high: only 21 of the 60000 bundles discharged from Gentilly 2 were confirmed defective and the five-year period from March 1992 to February 1997 saw no defect at all at Gentilly-2. Also, thanks to the inherent on-power refuelling capability and an effective defect detection and removal system, the primary coolant loops are kept extremely clean (very low activity level) - benefiting both maintenance and safety. Moreover, the inventories of fission products in the core and in the channel are maintained within the safety analysis envelope, due to on-power fuelling and sophisticated fuel management. In this paper, CANDU 6 fuel performance is reviewed against the feedback from post-irradiation examinations, and the findings from our ongoing R and D program. The results suggest that the fuel behavior m reactor are basically as originally anticipated, despite an evolutionary 3% increase in bundle uranium mass in the 1980's. For operating conditions within the CANDU 6 37-element experience, the average strains are typically 0.09%; and fission gas release, 2.7%. The UO{sub 2} fuel remains stoichiometric after irradiation. In-core measurements of pressure tube fitting are generally low. All these observations are consistent with the excellent fuel performance statistics coming out of the two Canadian CANDU 6 reactors. Additionally, this paper will briefly

  10. Fuel condition in Canadian CANDU 6 reactors

    International Nuclear Information System (INIS)

    The cornerstone of the CANDU concept is its natural uranium fuel, and the success of its reactor operation hinges on the fuel condition in the reactor. Neutron economy, on power refuelling, and simple fuel design are among the unique characteristics of CANDU fuel. In Canadian CANDU 6 reactors (Gentilly 2 and Point Lepreau), the 37-element fuel has provided an enviable record of safe, economic and reliable plant operation for 29 reactor years to date. The fuelling cost is among the lowest in the world - a corollary of high neutron economy, simple fuel design, and judicial fuelling scheme. The reliability of fuel is high: only 21 of the 60000 bundles discharged from Gentilly 2 were confirmed defective and the five-year period from March 1992 to February 1997 saw no defect at all at Gentilly-2. Also, thanks to the inherent on-power refuelling capability and an effective defect detection and removal system, the primary coolant loops are kept extremely clean (very low activity level) - benefiting both maintenance and safety. Moreover, the inventories of fission products in the core and in the channel are maintained within the safety analysis envelope, due to on-power fuelling and sophisticated fuel management. In this paper, CANDU 6 fuel performance is reviewed against the feedback from post-irradiation examinations, and the findings from our ongoing R and D program. The results suggest that the fuel behavior m reactor are basically as originally anticipated, despite an evolutionary 3% increase in bundle uranium mass in the 1980's. For operating conditions within the CANDU 6 37-element experience, the average strains are typically 0.09%; and fission gas release, 2.7%. The UO2 fuel remains stoichiometric after irradiation. In-core measurements of pressure tube fitting are generally low. All these observations are consistent with the excellent fuel performance statistics coming out of the two Canadian CANDU 6 reactors. Additionally, this paper will briefly discuss our

  11. Speciation of iodine (I-127) in the natural environment around Canadian CANDU sites

    Energy Technology Data Exchange (ETDEWEB)

    Kramer, S.J.; Kotzer, T.G.; Chant, L.A

    2001-06-01

    In Canada, very little data is available regarding the concentrations and chemical speciation of iodine in the environment proximal and distal to CANDU Nuclear Power Generating Stations (NPGS). In the immediate vicinity of CANDU reactors, the short-lived iodine isotope {sup 131}I (t{sub 1/2} = 8.04 d), which is produced from fission reactions, is generally below detection and yields little information about the environmental cycling of iodine. Conversely, the fission product {sup 129}I has a long half-life (t{sub 1/2} = 1.57x10{sup 7} y) and has had other anthropogenic inputs (weapons testing, nuclear fuel reprocessing) other than CANDU over the past 50 years. As a result, the concentrations of stable iodine ({sup 127}I) have been used as a proxy. In this study, a sampling system was developed and tested at AECL's Chalk River Laboratories (CRL) to collect and measure the particulate and gaseous inorganic and organic fractions of stable iodine ({sup 127}I) in air and associated organic and inorganic reservoirs. Air, vegetation and soil samples were collected at CRL, and at Canadian CANDU Nuclear Power Generating Stations (NPGS) at OPG's (Ontario Power Generation) Pickering (PNGS) and Darlington NPGS (DNGS) in Ontario, as well as at NB Power's Pt. Lepreau NPGS in New Brunswick. The concentrations of particulate and inorganic iodine in air at CRL were extremely low, and were often found to be below detection. The concentrations are believed to be at this level because the sediments in the CRL area are glacial fluvial and devoid of marine ionic species, and the local atmospheric conditions at the sampling site are very humid. Concentrations of a gaseous organic species were comparable to worldwide levels. The concentrations of particulate and inorganic iodine in air were also found to be low at PNGS and DNGS, which may be attributed to reservoir effects of the large freshwater lakes in southern Ontario, which might serve to dilute the atmospheric iodine

  12. CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR. PART 6 - PRESENTATION OF THE DECOMMISSIONING DEVICE

    Directory of Open Access Journals (Sweden)

    Gabi ROSCA FARTAT

    2015-05-01

    Full Text Available The objective of this paper is to present a possible solution for the designing of a device for the decommissioning of the horizontal fuel channels in the CANDU 6 nuclear reactor. The decommissioning activities are dismantling, demolition, controlled removal of equipment, components, conventional or hazardous waste (radioactive, toxic in compliance with the international basic safety standards on radiation protection. One as the most important operation in the final phase of the nuclear reactor dismantling is the decommissioning of fuel channels. For the fuel channels decommissioning should be taken into account the detailed description of the fuel channel and its components, the installation documents history, adequate radiological criteria for decommissioning guidance, safety and environmental impact assessment, including radiological and non-radiological analysis of the risks that can occur for workers, public and environment, the description of the proposed program for decommissioning the fuel channel and its components, the description of the quality assurance program and of the monitoring program, the equipments and methods used to verify the compliance with the decommissioning criteria, the planning of performing the final radiological assessment at the end of the fuel channel decommissioning. These will include also, a description of the proposed radiation protection procedures to be used during decommissioning. The dismantling of the fuel channel is performed by one device which shall provide radiation protection during the stages of decommissioning, ensuring radiation protection of the workers. The device shall be designed according to the radiation protection procedures. The decommissioning device assembly of the fuel channel components is composed of the device itself and moving platform support for coupling of the selected channel to be dismantled. The fuel channel decommissioning device is an autonomous device designed for

  13. World nuclear power plant capacity

    International Nuclear Information System (INIS)

    This report provides the background information for statistics and analysis developed by NUKEM in its monthly Market Report on the Nuclear Fuel Cycle. The assessments in this Special Report are based on the continuous review of individual nuclear power plant projects. This Special Report begins with tables summarizing a variety of nuclear power generating capacity statistics for 1990. It continues with a brief review of the year's major events regarding each country's nuclear power program. The standard NUKEM Market Report tables on nuclear plant capacity are given on pages 24 and 25. Owing to space limitations, the first year shown is 1988. Please refer to previous Special Reports for data covering earlier years. Detailed tables for each country list all existing plants as well as those expected by NUKEM to be in commercial operation by the end of 2005. An Appendix containing a list of abbreviations can be found starting on page 56. Only nuclear power plants intended for civilian use are included in this Special Report. Reactor lifetimes are assumed to be 35 years for all light water reactors and 30 years for all other reactor types, unless other data or definite decommissioning dates have been published by the operators. (orig./UA)

  14. The abuse of nuclear power

    International Nuclear Information System (INIS)

    This paper reproduces an address by Sir John Hill, Chairman of the United Kingdom Atomic Energy Authority, at a conference in London organised by the Financial Times in July 1976. Actions that, in the author's view, could be regarded as constituting abuse of nuclear power are first summarised, and the various aspects of the use and abuse of nuclear power are discussed. The author considers that achieving the maximum degree of acceptance of the Non-Proliferation Treaty is the most important political objective in nuclear power, but considers that nuclear terrorism would be abortive and that, so far as the UK is concerned, the present precautions are adequate and will remain so. It is considered that much abuse of nuclear power arises from the prevalence of its critics, particularly with reference to Pu hazards, the health of nuclear employees, and possible damage to the health of the public. The Pu problem is considered to be far more emotive than rational. The possibility of lung cancer and leukaemia is discussed. It is concluded that atomic energy is one of the best of industries in which to work, both from the health and interest points of view. (U.K.)

  15. Nuclear power in the frame of sustainable development

    International Nuclear Information System (INIS)

    Sustainable development conception defines a development aiming at fulfilment of aspirations, requirements and exigencies of the present society under the stringent condition of not jeopardizing further development of the next generations. An analysis of the nuclear field implies taking into account comparatively the following indicators: 1. availability distribution of resources; 2. the power utilization rate and the raw materials intake; 3. the impact upon population health; 4. the critical limits to environmental release; 5. land utilization and impacts upon habitats; 6. risk potential of generating major and irreversible phenomena. By taking into account the economic, social and environmental factors the following indicators proper for nuclear energy analysis were established: 1. capital (USD/kWe), marginal cost (USD/kWe); 2. cumulated dose to the public (Sv/kWh), number of employees (pers/kWh), education (number of university courses); 3. volume of solid waste (m3/kWh), activity level of solid waste (Bq/kWh), fuel utilization rate (tU/kWh), gaseous and liquid effluent activity (Bq/kWh). A comparison of capital investments for NPPs (CANDU type reactors), natural gas and coal thermal power plants is given. One of the economic advantages of nuclear power is the stability of production cost due to the fact that the uranium cost amounts only some percents of the total cost of electricity. External costs of a severe nuclear accident with a probability of 5 x 10-5 per year are given. The waste resulting from nuclear power electricity generation represents only one percent from the total volume of noxious waste in countries with nuclear industry. At the same time radioactive waste can be isolated from biosphere at reasonable costs and with well established technologies. Socially nuclear power appears to be attracting because it implies a knowledge core and intellectual level of high quality. The nuclear technology and science interact successfully with other cultural

  16. Nuclear power data; Kernenergie in Zahlen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-05-15

    The report ''nuclear power data'' includes data on the following issues: nuclear power plants in Germany including their operational characteristics, gross data on electricity generation in Germany, primary energy consumption in Germany, nuclear power plants worldwide, top ten nuclear power plants worldwide with respect to electricity generation in 2012.

  17. Desktop Severe Accident Graphic Simulator Module for CANDU6 : PSAIS

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. Y.; Song, Y. M. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The ISAAC ((Integrated Severe Accident Analysis Code for CANDU Plant) code is a system level computer code capable of performing integral analyses of potential severe accident progressions in nuclear power plants, whose main purpose is to support a Level 2 probabilistic safety assessment or severe accident management strategy developments. The code has the capability to predict a severe accident progression by modeling the CANDU6- specific systems and the expected physical phenomena based on the current understanding of the unique accident progressions. The code models the sequence of accident progressions from a core heatup, pressure tube/calandria tube rupture after an uncovery from inside and outside, a relocation of the damaged fuel to the bottom of the calandria, debris behavior in the calandria, corium quenching after a debris relocation from the calandria to the calandria vault and an erosion of the calandria vault concrete floor, a hydrogen burn, and a reactor building failure. Along with the thermal hydraulics, the fission product behavior is also considered in the primary system as well as in the reactor building.

  18. Elections: nuclear power confirmed

    International Nuclear Information System (INIS)

    2007 was an election year in France and the presidential campaign was an opportunity to bring in the debate a lot of topics, it appears that this year sustainable development was a concern shared by a lot of politicians. Candidate Sarkozy said that nuclear energy is consistent with the preservation of the environment and must be an essential part of the energy mix. He compelled himself to pursue the construction of the EPR reactor on the Flamanville site and to organize as soon as possible a large debate on all the topics involved in sustainable development. (A.C.)

  19. Technology development for nuclear material safeguards -A study on the direct use of spent PWR fuel in CANDU-

    International Nuclear Information System (INIS)

    The research contents of the passed one year were the conceptual design of nuclear material measurement points, of near real time accounting system and of unattended monitoring system for detection of nuclear material diversion. The passive neutron detection system was decided as a proper way of detection of plutonium in the spent fuels and the neutrons emitted by each isotopes were investigated. Also, material balance area and major measurement points were selected and related computer code was used for the near real time accounting in DUPIC facility. (Author)

  20. CANDU 9-meeting evolving safety and licensing requirements

    International Nuclear Information System (INIS)

    To date the safety and licensing experience with CANDU has been good, with plants successfully licensed and operating safely both domestically and in other countries. Nevertheless it is now clearly recognized that the utilities need more formal evidence that the licensing risk is low, if they are to proceed with new nuclear power projects. The CANDU 9 is an evolutionary design generating over 900 MWe. It is based on already-operating CANDUs, with improvements in the areas of construct ability, economics, plant layout, operations and maintenance, and safety. Even so, both domestic and foreign potential users require evidence of safety and licensability in Canada as of 'today'. For CANDU 9, this involves two main activities : · incorporation by designers not just of new Canadian safety regulations, but also of world trends in areas such as severe accidents and human factors, and · a two-year formal intensive review by the Canadian regulatory agency, the AECB (Atomic Energy Control Board) which will end in January 1997, with a first report mid-1996. In the severe accident area, CANDU 9 has improved the ability of the water-filled shield tank to act as a 'core catcher' for accidents such as a combined failure of the reactor cooling system piping, plus loss of emergency core cooling, plus loss of the moderator as a backup heat sink. A reserve water tank supplies sufficient water to the shield tank to remove decay heat and prevent melt-through. The licensing review documents encompass all of the Safety Design Guides, Design Requirements and flowsheets of the major systems, a preliminary Safety Analysis Report, a preliminary Probabilistic Safety Assessment, a Human Factors Engineering Programme Plan, the procedures for producing safety-critical software, and others. The licensing review scope includes comparison of the design and safety assessment results with current Canadian licensing requirements. The review will be complete once there is a finding that there are 'no

  1. Nuclear power world report 2013

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2014-07-15

    At the end of 2013, 435 nuclear power plants were available for energy supply in 31 countries of the world. This means that the number decreased by 2 units compared to the previous year's number on 31 December 2012. The aggregate gross power of the plants amounted to approx. 398,861 MWe, the aggregate net power, to 378,070 MWe (gross: 392,793 MWe, net: 372,572 MWe, new data base as of 2013: nameplate capacities). Four units were commissioned in 2014; three units in China and one in India. Eight units were shut down permanently in 2013; 2 units in Japan, and four units in the USA. Two units in Canada were declared permanently shut-down after a long-term shutdown. 70 nuclear generating units - 2 more than at the end of 2012 - were under construction in late 2013 in 15 countries with an aggregate gross power of approx. 73,814 MWe and net power of approx. 69,279 MWe. Six new projects have been started in 2013 in four countries (Belarus, China, the Republic of Korea, and the United Arab Emirates). Worldwide, some 125 new nuclear power plants are in the concrete project design, planning, and licensing phases; in some of these cases license applications have been submitted or contracts have already been signed. Some 100 further projects are planned. Net electricity generation in nuclear power plants worldwide in 2013 achieved a level of approx. 2,364.15 billion (109) kWh (2012: approx. 2,350.80 billion kWh). Since the first generation of electricity in a nuclear power plant in the EBR-I fast breeder (USA) on December 20, 1951, cumulated net production has reached approx. 70,310 billion kWh, and operating experience has grown to some 15,400 reactor years. (orig.)

  2. Nuclear power in Canada : an examination of risks, impacts and sustainability

    Energy Technology Data Exchange (ETDEWEB)

    Winfield, M.; Jamison, A.; Wong, R.; Czajkowski, P.

    2006-12-15

    This study examines the environmental impacts of the use of nuclear energy for electricity generation in Canada through each of the four major stages of nuclear energy production: uranium mining and milling; uranium refining, conversion and fuel fabrication; nuclear power plant operation; and waste fuel management. It is intended to inform public debate over the future role of nuclear energy in Canada, and to facilitate comparisons of nuclear energy with other potential energy sources. The study examines waste generation, atmospheric releases, impacts on water quality and water use, and landscape and ecosystem impacts of nuclear energy production. It also examines the occupational and community health impacts of nuclear power and key long-term challenges to its sustainability, including security and weapons proliferation risks. Specific environmental impacts are examined in the context of CANDU nuclear technology, the only reactor type currently in use in Canada. The study findings likely underestimate the overall impacts of the use of nuclear energy for electricity production in Canada. This is a result of significant gaps in the publicly available information on releases of pollutants and contaminants, as well as on the fate of certain waste streams related to the nuclear industry. In addition, the study relies on what are likely conservative estimates in a number of key areas, particularly with respect to the generation of greenhouse gas (GHG) emissions.

  3. Nuclear power generation incorporating modern power system practice

    CERN Document Server

    Myerscough, PB

    1992-01-01

    Nuclear power generation has undergone major expansion and developments in recent years; this third edition contains much revised material in presenting the state-of-the-art of nuclear power station designs currently in operation throughout the world. The volume covers nuclear physics and basic technology, nuclear station design, nuclear station operation, and nuclear safety. Each chapter is independent but with the necessary technical overlap to provide a complete work on the safe and economic design and operation of nuclear power stations.

  4. The benefits of nuclear power

    International Nuclear Information System (INIS)

    The object of the article is to indicate in fairly general terms the nature and magnitude of the benefits of nuclear power. The paper argues that significant economic gains have been obtained and that investment in civil nuclear development has fully justified itself. The justification for these claims is discussed under the topic headings: scale of the industry and world fuel savings, environment, health, fuel prices, United Kingdom benefits, generation costs, security of fuel supply, and the third world. (U.K.)

  5. Nuclear fuel procurement management at nuclear power plant

    International Nuclear Information System (INIS)

    The market situation of nuclear fuel cycles is highlighted. It also summarises the possible contract models and the elements of effective management for nuclear fuel procurement at nuclear power station based upon the nuclear fuel procurement practice of Guangdong Daya Bay Nuclear Power Station (GNPS)

  6. Manufacturing industry and nuclear power

    International Nuclear Information System (INIS)

    The manufacturing industry and nuclear power is discussed at two levels. There is the supplier level where the problems tend to be orthodox but take on a special peculiarity when applied to the nuclear market, and there is the level that may be termed nuclear politics and which has a number of aspects including energy policy, choice of reactor system, efficient uses of industrial resources and public acceptability. The role of the supplier is seen as searching for new orders, having secured an order performing the contract, and finally looking at the long term requirements of the industry. The choice of thermal reactor system, PWR, AGR, or BWR is discussed. (author)

  7. Generation 'Next' and nuclear power

    International Nuclear Information System (INIS)

    My generation was labeled by Russian mass media as generation 'Next.' My technical education is above average. My current position is as a mechanical engineer in the leading research and development institute for Russian nuclear engineering for peaceful applications. It is noteworthy to point out that many of our developments were really first-of-a-kind in the history of engineering. However, it is difficult to grasp the importance of these accomplishments, especially since the progress of nuclear technologies is at a standstill. Can generation 'Next' be independent in their attitude towards nuclear power or shall we rely on the opinions of elder colleagues in our industry? (authors)

  8. Examination and testing requirements for concrete containment structures for CANDU nuclear power plants

    International Nuclear Information System (INIS)

    This Standard provides the examination and testing requirements that will apply to the work of any organization participating in the construction, installation, and fabrication of parts or components of concrete containment structures, or both, that are defined as class containment. 2 tabs

  9. An integrated seismic design approach for modules in candu nuclear power plants

    International Nuclear Information System (INIS)

    Based on a comparative study of the different approaches which can be employed for obtaining the response of a modularized reactor building under a Design Basis Earthquake (DBE), the following can be concluded: 1) The seismic response of steel-supported equipment can be significantly different from those which are concrete-supported as a result of steel flexibility. b) The time-history method gives the most reasonable response accelerations for a modularized reactor building. The Complete Quadratic Combination (CQC) method gives acceleration values which are slightly on the conservative side. The 10 % method (current practice) consistently overpredicts the response compared to both the time-history method and the CQC methods. c) At lower elevations of the building, both the CQC and the 10 % methods underestimate the response accelerations compared to the time-history method. d) The approach of decoupling a steel module and subjecting it to the Floor Response Spectrum (FRS) can lead to relatively high response acceleration results and member forces. e) The response of different parts of the building may be governed by the case of hard or soft rock conditions. In general the higher parts of the building are governed by the hard rock conditions while the lower parts are governed by the soft soil conditions. f) Using the response spectrum method and for the particular module investigated, the member forces were found to be higher in the coupled analysis compared to the decoupled analysis when the 10 % method is used. On the other hand the opposite is true for the CQC method. (J.P.N.)

  10. Nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To prevent liquid wastes from being discharged out of the system by processing to recover them in the nuclear reactor and reusing them. Constitution: Discharge of liquid wastes to the surrounding atmosphere are completely eliminated by collecting floor drains, a part of processing water for the regeneration of liquid wastes, non-radioactive steam drains and laundry drains conventionally discharged so far out of the system, processing them in a concentrator, a desalter or the like into water of a high purity and extremely low radioactive concentration, storing the water in an exclusive storage tank and supplying it as a steam or supplementing water to each portion in the plant that requires water of such high purity and extremely low radioactivity. (Yoshihara, H.)

  11. Nuclear power, society and environment

    International Nuclear Information System (INIS)

    This rubric reports on 12 short notes about sociological and environmental aspects of nuclear power in France and other countries: the epidemiological inquiry widened to all French nuclear sites; the sanitary and radioecological effects of nuclear activities in Northern Cotentin (France); the WONUC (World National Council of Nuclear Workers) anger with the French government about the shutdown of Superphenix reactor; the new more informative promotional campaign of Electricite de France (EdF) for nuclear power; the scientific and research prices attributed by the French Atomic Energy Commission (CEA) to its searchers; the creation of a committee of inquiry in the French senate for the careful examination of the economical, social and financial consequences of the shutdown of Superphenix; the 31.2% increase of CEA-Industrie benefits for 1997; the decrease of nuclear contestation in Germany; the French-German communication efficiency during the Fessenheim accident simulation in October 7, 1997; the 3.5% increase of CO2 emissions in the USA; the decommissioning of 3 Russian reactors for military plutonium production; Greenpeace condemnation for abusive purposes against British Nuclear Fuel plc (BNFL) and its activities at Sellafield (UK). (J.S.)

  12. The future of nuclear power

    CERN Document Server

    Mahaffey, James

    2012-01-01

    Newly conceived, safer reactor designs are being built in the United States (and around the world) to replace the 104 obsolete operating nuclear power reactors in this country alone. The designs--which once seemed exotic and futuristic--are now 40 years old, and one by one these vintage Generation II plants will reach the end of productive service in the next 30 years. The Future of Nuclear Power examines the advanced designs, practical concepts, and fully developed systems that have yet to be used. This book introduces readers to the traditional, American system of units, with some archaic te

  13. Safe and green nuclear power

    International Nuclear Information System (INIS)

    Energy development plays an important role in the national economic growth. Presently the per capita consumption of energy in our country is about 750 kWh including captive power generation which is low in comparison to that in the developed countries like USA where it is about 12,000 kWh. As of now the total installed capacity of electricity generation is about 152,148 MW(e) which is drawn from Thermal (65%), Hydel (24%), Nuclear (3%) power plants and Renewables (8%). It is expected that by the end of year 2020, the required installed capacity would be more than 3,00,000 MW(e), if we assume per capita consumption of about 800-1000 kWh for Indian population of well over one billion. To meet the projected power requirement in India, suitable options need to be identified and explored for generation of electricity. For choosing better alternatives various factors such as availability of resources, potential to generate commercial power, economic viability, etc. need to be considered. Besides these factors, an important factor which must be taken into consideration is protection of environment around the operating power stations. This paper attempts to demonstrate that the nuclear power generation is an environmentally benign option for meeting the future requirement of electricity in India. It also discusses the need for creating the public awareness about the safe operations of the nuclear power plants and ionising radiation. (author)

  14. Advancing CANDU experience to the world steam generator market

    International Nuclear Information System (INIS)

    Tube degradation in certain recirculating nuclear steam generators has provided a market for steam generator replacement. Prior to this need, B and W supplied over 200 steam generators for CANDU nuclear plants. With this experience, and implementing extensive research and development improvements in material selection, design enhancements, and new manufacturing and analytical methods, B and W has supplied or secured orders for the replacement of 26 steam generators. Along with plans for new replacement orders, B and W will continue to supply steam generators for future CANDU plants. This paper will review the progression of B and W's CANDU experience to meet the replacement steam generator market, and examine the continuous improvements required for today's increasingly demanding nuclear specifications. (author). 1 tab., 4 figs

  15. CANDU Safety R&D Status, Challenges, and Prospects in Canada

    Directory of Open Access Journals (Sweden)

    W. Shen

    2015-01-01

    Full Text Available In Canada, safe operation of CANDU (CANada Deuterium Uranium; it is a registered trademark of Atomic Energy of Canada Limited reactors is supported by a full-scope program of nuclear safety research and development (R&D in key technical areas. Key nuclear R&D programs, facilities, and expertise are maintained in order to address the unique features of the CANDU as well as generic technology areas common to CANDU and LWR (light water reactor. This paper presents an overview of the CANDU safety R&D which includes background, drivers, current status, challenges, and future directions. This overview of the Canadian nuclear safety R&D programs includes those currently conducted by the COG (CANDU Owners Group, AECL (Atomic Energy of Canada Limited, Candu Energy Inc., and the CNSC (Canadian Nuclear Safety Commission and by universities via UNENE (University Network of Excellence in Nuclear Engineering sponsorship. In particular, the nuclear safety R&D program related to the emerging CANDU ageing issues is discussed. The paper concludes by identifying directions for the future nuclear safety R&D.

  16. Nuclear power generation cost methodology

    International Nuclear Information System (INIS)

    A simplified calculational procedure for the estimation of nuclear power generation cost is outlined. The report contains a discussion of the various components of power generation cost and basic equations for calculating that cost. An example calculation is given. The basis of the fixed-charge rate, the derivation of the levelized fuel cycle cost equation, and the heavy water charge rate are included as appendixes

  17. Absorber materials in CANDU PHWRs

    International Nuclear Information System (INIS)

    In a CANDU reactor the fuel channels are arranged on a square lattice in a calandria filled with heavy water moderator. This arrangement allows five types of tubular neutron absorber devices to be located in the relatively benign environment of low pressure, low temperature heavy water between neighbouring rows or columns of fuel channels. This paper will describe the roles of the devices and outline the design requirements of the absorber component from a reactor physics viewpoint. Nuclear heating and activation problems associated with the different absorbers will be briefly discussed. The design and manufacture of the devices will be also discussed. The control rod absorbers and shut off materials are cadmium and stainless steel. In the tubular arrangement, the cadmium is sandwiched between stainless steel tubes. This type of device has functioned well, but there is now concern over the availability and expense of cadmium which is used in two types of CANDU control devices. There are also concerns about the toxicity of cadmium during the fabrication of the absorbers. These concerns are prompting AECL to study alternatives. To minimize design changes, pure boron-10 alloyed in stainless steel is a favoured option. Work is underway to confirm the suitability of the boron-loaded steel and identify other encapsulated absorber materials for practical application. Because the reactivity devices or their guide tubes span the calandria vessel, the long slender components must be sufficiently rigid to resist operational vibration and also be seismically stable. Some of these components are made of Zircaloy to minimize neutron absorption. Slow irradiation growth and creep can reduce the spring tension, and periodic adjustments to the springs are required. Experience with the control absorber devices has generally been good. In one instance liquid zone controllers had a problem of vibration induced fretting but a redesigned back-fit resolved the problem. (author). 3 refs, 8

  18. Governmental strategy of sustainable development of Romanian nuclear power sector

    International Nuclear Information System (INIS)

    nuclear sector starting from research and design, in institutes with well trained and highly specialized personnel, by developing sophisticated testing facilities, which all culminated with launching in operation the first power reactor of CANDU type at Cernavoda NPP in December 12, 1996. It was operated at high level of safety and performance while the nuclear fuel, the heavy water, the associated nuclear equipment and materials were ensured by Romanian institutions, plants, and facilities. A prominent role was played by Romanian Nuclear Activities Authority, RAAN, and its subsidiaries: the Institute for Nuclear Research, INR, at Mioveni, Arges, the Center of Technology and Engineering for Nuclear Projects, CITON, at Bucharest, the ROMAG-PROD Heavy Water Plant and ROMAG-TERMO at Drobeta Turnu Severin. RAAN is in charge with continuing the research and design for Cernavoda NPP Unit 2 and 3 and for ensuring the necessary reserve of heavy water. These new objectives once realized will raise the production of electric energy and will lower accordingly the prices on electric and thermic energy market

  19. Nuclear power program in Indonesia

    International Nuclear Information System (INIS)

    The nuclear program in Indonesia is derived from the long-range national development plan. The main aim of this plan is to realize a just and prosperous society within a united and democratic nation, and to contribute to world peace. A research and development infrastructure is being developed to establish the necessary technological foundations, to train technical personnel, and to develop the capacity for technical adaptation and innovation. BATAN, the National Atomic Energy Agency, is responsible for nuclear R and D, and also has a regulatory function and implements the national nuclear program. The author describes the functions of the eight BATAN laboratories, and surveys the energy resources available to Indonesia. In the ten years preceding 1983 electric energy consumption increased at a rate of 12.4 percent per year. It is projected that an electric capacity of 42,000 MW(e) will be required in the year 2003. The nuclear contribution could be around 10 percent. The decision to adopt nuclear power generation depends, among other factors, on financial considerations, the perception that nuclear power would perpetuate the dependence on developed nations, and safety concerns

  20. QA programs in nuclear power plants

    International Nuclear Information System (INIS)

    As an overview of quality assurance programs in nuclear power plants, the energy picture as it appears today is reviewed. Nuclear power plants and their operations are described and an attempt is made to place in proper perspective the alleged ''threats'' inherent in nuclear power. Finally, the quality assurance programs being used in the nuclear industry are described

  1. Benefits and hazards of nuclear power

    International Nuclear Information System (INIS)

    Compilation of a seminar at the KFA Juelich on topical problems of nuclear power. Subjects: Energy demand, its expected development and possibilities of coverage; physical fundamentals and technical realisation of power generation by nuclear fission; fuel cycle problems and solutions; effects of radioactive radiation; safety of nuclear power plants and the nuclear hazard as compared with other hazards. (orig./RW)

  2. A renaissance in nuclear power

    International Nuclear Information System (INIS)

    This paper presents an analysis of the worldwide evolution of the fleet of nuclear power plants until the 1980s; the reasons why in the same era this contingent was rejected in various developed countries due to a complete lack of public acceptance, being condemned to a phaseout planned to eliminate more than half of the operating power plants by 2020; and finally, what are the reasons for this competent base-load power source to silently resist for more than a quarter of a century, having been the focus of studies and improvements in the most renowned research centers in the world and the most traditional universities of the developed countries, resurging as one of the main allies of worldwide sustainable development, even with all the difficulties of deployment, ecological risks, and nuclear proliferation. However, after more than 30 years of intense debates involving a wide variety of interrelated problems, scientists have collected irrefutable proof that the actions of humankind have caused climate changes that represent an imminent threat to the survival of the human species on Earth, requiring coordinated international action that seeks to determine the economic aspects of the stabilization of levels of GHGs (greenhouse gases) in the atmosphere. The transition to a worldwide low-carbon economy presents political challenges, where, the most complex political question, is the supply of energy which would depends on a change in the supply of energy from fossil fuels to renewable, hydro and nuclear. Undoubtedly the nuclear power plants are, by far, the most controversial. (author)

  3. How safe is nuclear power

    International Nuclear Information System (INIS)

    The subject is discussed, with particular reference to nuclear power in the UK, as follows: ionising radiations; components of the radiation dose to which on average each person in the UK is exposed; regulation and control; mining; reactor operations - accidents, safety; transport of spent fuel; radioactive wastes; fast reactors and plutonium; insurance. (U.K.)

  4. Nuclear Power on Energy Agenda

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    The big debate on whether or not to use nuclear power as an energy option has raged among countries like the U.S., Britain, and Germany for decades, with not even the advent and threat of global warming forcing a conclusion. China, however, has always stressed energy diversity and been determined to develop and use this alternative energy source.

  5. Nuclear power and its alternatives

    International Nuclear Information System (INIS)

    For nuclear power to contribute significantly to the alleviation of demands for increased electricity by the year 2000, a further obstacle must be overcome, namely the present nuclear phobia of the American public. This phobia can be addressed only through public education leading to a balanced perspective of the benefits and hazards of nuclear power compared with those of alternate sources of energy and to the risks associated with an insufficient supply of energy in a few years. Also to be considered in a public education effort should be the precarious and capricious nature of this country's continued reliance on energy sources imported from politically unstable countries, as well as the risk this importation poses for the nation's economic, social and military security

  6. The future for nuclear power

    International Nuclear Information System (INIS)

    Lord Marshall explains how the situation for nuclear power in late 1989 in the United Kingdom had come about. Despite warnings that for a successful nuclear programme a large generator which has the obligation to supply in a defined geographical area should operate, this is not what will happen under the plans to privatise the electricity supply industry in the UK. Under these no body will have the obligation to supply electricity and the distribution Company will not have the obligation to supply after the first few years. Other problems with the privatisation plans are discussed. The implications of the government's decisions on nuclear power, first to maintain the Magnox stations in the government sector, second to abandon the full PWR construction programme and thirdly not to transfer the AGRs to the private sector, are discussed. (UK)

  7. Nuclear power: tomorrow's energy source

    International Nuclear Information System (INIS)

    In France, 76% of electricity is produced by nuclear power. The industry's pricing levels are among the most competitive in Europe. Thanks to its 58 nuclear reactors France enjoys almost 50% energy autonomy thus ensuring a highly stable supply. Equally, as a non-producer of greenhouse gases, the nuclear sector can rightfully claim to have an environmentally friendly impact. Against a background to increasing global demand with predictions that fossil fuels will run out and global warming a central issue, it is important to use production methods which face up to problems of this nature. There is no question that nuclear energy has a vital role to play alongside other energy sources. (authors)

  8. Contribution of international cooperation in achieving the Romanian nuclear power objectives

    International Nuclear Information System (INIS)

    The international cooperation implied by the Romanian nuclear power program has on the short term the goal of supporting the Romanian effort of obtaining new nuclear fuels, improving the radioactive waste management, developing the technology and software transfer, training of Romanian researchers and participations in international projects. On long term the international cooperation is aiming at rising the scientific standards and the degree of global integration of Romanian research and technology. This policy is supported also by the agreements convened with different international organizations as for instance 'The Agreement for Nuclear Safety' or 'Common agreement for safe management of spent fuel and radioactive waste'. The INR at Pitesti and CITON - Bucharest are involved in works for cooperation technical projects supported by IAEA Vienna aiming at the nuclear safe and safeguard and power programs. At present underway are research contracts concerning the CANDU pressure tube, the corrosion in the primary cooling circuit of the CANDU reactors, as well as, the behavior under irradiation and intermediate disposal of oxide fuels. In the frame of IAEA assisted technical programs the TRIGA reactor of INR Pitesti is transferred from HEU to LEU fuels, new technologies for using recovered uranium and slightly enriched uranium fuels are developed, as well as a data acquisition system with advanced on-line characteristics. The cooperation between INR Pitesti and AECL Canada comprised in the frame of the 1998 agreement is oriented towards three fields of common interest: nuclear safety, nuclear fuel and management of in-service life of NPPs. Already transferred were computer codes from AECL devoted to accident analysis (WIMS, CATHENA and ELOCA) which were implemented and reproduced accurately all the test cases provided by AECL. For installing these codes specialists from our institute participated in training courses, on-the-job training, as well as, in validation

  9. Nuclear power consensus and nuclear transports

    International Nuclear Information System (INIS)

    Transports of spent fuel elements to the reprocessing plants of La Hague, France, and Sellafield, UK, as well as of casks with vitrified high-level waste returned to Germany were resumed in early 2001. These transports had been interrupted in 1998 after elevated levels of surface contamination had been found on the out-sides of the shipping casks. The transport issue was settled immediately in all countries affected except Germany, after the situation had been clarified. Numerous agencies involved as well as independent ones found that the increased contamination had to be removed, but had been neither dangerous nor, at that time, notifiable. The outcome of the German federal parliamentary elections in 1998 had produced a new government majority, thus changing the political environment for nuclear power. Opting out of the peaceful use of nuclear power in a properly arranged way and without having to pay compensation is the declared goal of the federal government. Accordingly, also transports of fuel elements for reprocessing are to be abandoned from 2005 on, and transports of spent fuel elements are to be minimized, for the time being, by building on-site-interim stores. The government's policy and opt-out legislation raise a number of questions which will have to be answered in a satisfactory way in the future. (orig.)

  10. Nuclear power and energy planning

    International Nuclear Information System (INIS)

    With the rapid depletion of conventional energy sources such as coal and oil and the growing world demand for energy the question of how to provide the extra energy needed in the future is addressed. Relevant facts and figures are presented. Coal and oil have disadvantages as their burning contributes to the greenhouse gases and they will become scarcer and more expensive. Renewable sources such as wind and wave power can supply some but not all future energy requirements. The case made for nuclear power is that it is the only source which offers the long term prospect of meeting the growing world energy demand whilst keeping energy costs close to present levels and which does not add to atmospheric pollution. Reassurance as to the safety of nuclear power plants and the safe disposal of radioactive wastes is given. (UK)

  11. Global warming and nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Wood, L., LLNL

    1998-07-10

    Nuclear fission power reactors represent a potential solution to many aspects of global change possibly induced by inputting of either particulate or carbon or sulfur oxides into the Earth`s atmosphere. Of proven technological feasibility, they presently produce high-grade heat for large-scale electricity generation, space heating and industrial process-energizing around the world, without emitting greenhouse gases or atmospheric particulates; importantly, electricity production costs from the best nuclear plants presently are closely comparable with those of the best fossil-fired plants. However, a substantial number of issues currently stand between nuclear power and widespread substitution for large stationary fossil fuel-fired systems. These include perceptual ones regarding both long-term and acute operational safety, plant decommissioning, fuel reprocessing, radwaste disposal, fissile materials diversion to military purposes and - perhaps most seriously- readily quantifiable concerns regarding long-term fuel supply and total unit electrical energy cost. We sketch a road-map for proceeding from the present situation toward a nuclear power-intensive world, addressing along the way each of the concerns which presently impede widespread nuclear substitution for fossil fuels, particularly for coal in the most populous and rapidly developing portions of the world, e.g., China and India. This `design to societal specifications` approach to large-scale nuclear fission power systems may lead to energy sources meeting essentially all stationary demands for high-temperature heat. Such advanced options offer a human population of ten billion the electricity supply levels currently enjoyed by Americans for 10,000 years. Nuclear power systems tailored to local needs-and-interests and having a common advanced technology base could reduce present-day world-wide C0{sub 2} emissions by two-fold, if universally employed. By application to small mobile demands, a second two

  12. Swedish Opinion on Nuclear Power 1986 - 2011

    Energy Technology Data Exchange (ETDEWEB)

    Holmberg, Soeren

    2012-11-01

    This report contains the Swedish opinion on Nuclear Power and European Attitudes on Nuclear Power. It also includes European Attitudes Towards the Future of Three Energy Sources; Nuclear Energy, Wind Power and Solar Power - with a focus on the Swedish opinion. Results from measurements done by the SOM Inst. are presented.

  13. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    This 2003 version of Elecnuc contents information, data and charts on the nuclear power plants in the world and general information on the national perspectives concerning the electric power industry. The following topics are presented: 2002 highlights; characteristics of main reactor types and on order; map of the French nuclear power plants; the worldwide status of nuclear power plants on 2002/12/3; units distributed by countries; nuclear power plants connected to the Grid by reactor type groups; nuclear power plants under construction; capacity of the nuclear power plants on the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear plants by country at the end 2002; performance indicator of french PWR units; trends of the generation indicator worldwide from 1960 to 2002; 2002 cumulative Load Factor by owners; nuclear power plants connected to the grid by countries; status of license renewal applications in Usa; nuclear power plants under construction; Shutdown nuclear power plants; exported nuclear power plants by type; exported nuclear power plants by countries; nuclear power plants under construction or order; steam generator replacements; recycling of Plutonium in LWR; projects of MOX fuel use in reactors; electricity needs of Germany, Belgium, Spain, Finland, United Kingdom; electricity indicators of the five countries. (A.L.B.)

  14. Experience in the application of NUSS and Canadian quality assurance standards for overseas CANDU projects

    International Nuclear Information System (INIS)

    The Canadian QA standards - the CSA Z299 series for manufacture, which first appeared in 1975, and the CSA N286 series for all other phases of plant life which appeared in 1979, have been based on experience with the CANDU reactor program. The CSA Technical Committee responsible for issue and for updating the two series have a direct liaison with the IAEA Technical Review Committee for Quality Assurance. Ontario Hydro, which has a substantial commitment to nuclear power using CANDU reactors, has played a large part in the Canadian QA standards program. Atomic Energy of Canada Limited has also taken a major part in the development of CSA QA standards. As a main contractor the Company has supplied CANDU plants in Canada and to Argentina, South Korea and Romania. Because of the compatibility of the Canadian QA standards used, the Embalse plant in Argentina and the Wolsung 1 plant in Korea, are essentially in compliance with NUSS QA standards. The plant under construction at Cernavoda in Romania similarly follows Canadian QA standards

  15. Nuclear power in rock. Principal report

    International Nuclear Information System (INIS)

    In September 1975 the Swedish Government directed the Swedish State Power Board to study the question of rock-siting nuclear power plants. The study accounted for in this report aims at clarifying the advantages and disadvantages of siting a nuclear power plant in rock, compared to siting on ground level, considering reactor safety, war protection and sabotage. The need for nuclear power production during war situations and the closing down of nuclear power plants after terminated operation are also dealt with. (author)

  16. International marketing of CANDU

    International Nuclear Information System (INIS)

    During the 1960's and 70's the nuclear industry all over the world increased its capacity to meet anticipated orders resulting from expected economic growth. When these orders did not materialize, the industry was left with excess capacity, and competition grew fierce. The outlook is good, however, since it has become imperative for the world to move away from oil to nuclear power. In advanced but oil-deficient nations such as Japan the shift to nuclear has already begun, and the same is happening in rapidly industrializing countries such as Korea, Yugoslavia and Romania. Major oil-exporting countries such as Mexico are looking at nuclear power as a method of preserving their petroleum for export. There are opportunities for Canada in all these markets, and they are being pursued aggressively. Ways in which Canada can assist in the development of a nuclear industry in a country such as Indonesia, and meet the needs of a country with a fully-developed nuclear industry such as Japan, are discussed

  17. Applications of ASTEC integral code on a generic CANDU 6

    Energy Technology Data Exchange (ETDEWEB)

    Radu, Gabriela, E-mail: gabriela.radu@nuclear.ro [Institute for Nuclear Research, Campului 1, 115400 Mioveni, Arges (Romania); Prisecaru, Ilie [Power Engineering Department, University “Politehnica” of Bucharest, 313 Splaiul Independentei, Bucharest (Romania)

    2015-05-15

    Highlights: • Short overview of the models included in the ASTEC MCCI module. • MEDICIS/CPA coupled calculations for a generic CANDU6 reactor. • Two cases taking into account different pool/concrete interface models. - Abstract: In case of a hypothetical severe accident in a nuclear power plant, the corium consisting of the molten reactor core and internal structures may flow onto the concrete floor of containment building. This would cause an interaction between the molten corium and the concrete (MCCI), in which the heat transfer from the hot melt to the concrete would cause the decomposition and the ablation of the concrete. The potential hazard of this interaction is the loss of integrity of the containment building and the release of fission products into the environment due to the possibility of a concrete foundation melt-through or containment over-pressurization by the gases produced from the decomposition of the concrete or by the inflammation of combustible gases. In the safety assessment of nuclear power plants, it is necessary to know the consequences of such a phenomenon. The paper presents an example of application of the ASTECv2 code to a generic CANDU6 reactor. This concerns the thermal-hydraulic behaviour of the containment during molten core–concrete interaction in the reactor vault. The calculations were carried out with the help of the MEDICIS MCCI module and the CPA containment module of ASTEC code coupled through a specific prediction–correction method, which consists in describing the heat exchanges with the vault walls and partially absorbent gases. Moreover, the heat conduction inside the vault walls is described. Two cases are presented in this paper taking into account two different heat transfer models at the pool/concrete interface and siliceous concrete. The corium pool configuration corresponds to a homogeneous configuration with a detailed description of the upper crust.

  18. Insurance of nuclear power stations

    International Nuclear Information System (INIS)

    Electrical utility companies have invested large sums in the establishment of nuclear facilities. For this reason it is normal for these companies to attempt to protect their investments as much as possible. One of the methods of protection is recourse to insurance. For a variety of reasons traditional insurance markets are unable to function normally for a number of reasons including, the insufficient number of risks, an absence of meaningful accident statistics, the enormous sums involved and a lack of familiarity with nuclear risks on the part of insurers, resulting in a reluctance or even refusal to accept such risks. Insurers have, in response to requests for coverage from nuclear power station operators, established an alternative system of coverage - insurance through a system of insurance pools. Insurers in every country unite in a pool, providing a net capacity for every risk which is a capacity covered by their own funds, and consequently without reinsurance. All pools exchange capacity. The inconvenience of this system, for the operators in particular, is that it involves a monopolistic system in which there are consequently few possibilities for the negotiation of premiums and conditions of coverage. The system does not permit the establishment of reserves which could, over time, reduce the need for insurance on the part of nuclear power station operators. Thus the cost of nuclear insurance remains high. Alternatives to the poor system of insurance are explored in this article. (author)

  19. 77 FR 76541 - Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station

    Science.gov (United States)

    2012-12-28

    ... COMMISSION Entergy Nuclear Operations, Inc.; Pilgrim Nuclear Power Station AGENCY: Nuclear Regulatory... requested by Entergy Nuclear Operations, Inc. (the licensee), for operation of the Pilgrim Nuclear Power... Impact Statement for ] License Renewal of Nuclear Plants Regarding Pilgrim Nuclear Power Station,...

  20. Loviisa nuclear power plant analyzer

    International Nuclear Information System (INIS)

    The APROS Simulation Environment has been developed since 1986 by Imatran Voima Oy (IVO) and the Technical Research Centre of Finland (VTT). It provides tools, solution algorithms and process components for use in different simulation systems for design, analysis and training purposes. One of its main nuclear applications is the Loviisa Nuclear Power Plant Analyzer (LPA). The Loviisa Plant Analyzer includes all the important plant components both in the primary and in the secondary circuits. In addition, all the main control systems, the protection system and the high voltage electrical systems are included. (orig.)

  1. Nuclear power a reference handbook

    CERN Document Server

    Henderson, Harry R

    2014-01-01

    In the 21st century, nuclear power has been identified as a viable alternative to traditional energy sources to stem global climate change, and condemned as risky to human health and environmentally irresponsible. Do the advantages of nuclear energy outweigh the risks, especially in light of the meltdown at the Fukushima plant in 2011? This guide provides both a comprehensive overview of this critical and controversial technology, presenting reference tools that include important facts and statistics, biographical profiles, a chronology, and a glossary. It covers major controversies and proposed solutions in detail and contains contributions by experts and important stakeholders that provide invaluable perspective on the topic.

  2. Nuclear power in New Brunswick

    International Nuclear Information System (INIS)

    New Brunswick Power is a medium-utility with gross production for the past fiscal year for domestic and external sales of about 16.5 billion kilowatt hours. Of this figure 33.5% was supplied through nuclear generation. The financial risks involved with the production of the Point Lepreau nuclear generating station were discussed. Further, questions of assurances given for schedule and cost, licencing, and long-term plant performance of the Point Lepreau no. 2 unit were addressed. These were discussed with particular emphasis on the competition for the New England market

  3. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    This small booklet summarizes in tables all the numerical data relative to the nuclear power plants worldwide. These data come from the French CEA/DSE/SEE Elecnuc database. The following aspects are reviewed: 1997 highlights; main characteristics of the reactor types in operation, under construction or on order; map of the French nuclear power plants; worldwide status of nuclear power plants at the end of 1997; nuclear power plants in operation, under construction and on order; capacity of nuclear power plants in operation; net and gross capacity of nuclear power plants on the grid and in commercial operation; forecasts; first power generation of nuclear origin per country, achieved or expected; performance indicator of PWR units in France; worldwide trend of the power generation indicator; nuclear power plants in operation, under construction, on order, planned, cancelled, shutdown, and exported; planning of steam generators replacement; MOX fuel program for plutonium recycling. (J.S.)

  4. Economic competitiveness of nuclear power in China

    International Nuclear Information System (INIS)

    Development of nuclear power in China has made a good progress. Currently, economic competitiveness of nuclear power compared to fossil-fuelled power plants is one of the major problems which hamper its development. This article presents the economic competitiveness of nuclear power in China with two-level analyses. First, levelized lifetime cost method is adopted for electricity generation cost comparisons. Important factors influencing economic competitiveness of nuclear power are described. Furthermore, a broad economic evaluation of the full fuel chain of nuclear power and fossil-fuelled plants is discussed concerning macro social-economic issues, environmental and health impacts. The comprehensive comparative assessment would be carried out for decision making to implement nuclear power programme. In consideration of external costs and carbon value, the economic competitiveness of nuclear power would be further improved. Facing swift economic growth, huge energy demand and heavy environmental burden, nuclear power could play a significant role in sustainable development in China. (authors)

  5. Docommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    The German utilities operating nuclear power plants have long concerned themselves with aspects of decommissioning and for this purpose an engineering company was given a contract to study the entire spectrum of decommissioning. The results of this study have been available in autumn 1980 and it is possible to discuss all the aspects of decommissioning on a new basis. Following these results no change in the design concept of LWR nuclear power plants in operation or under construction is necessary because the techniques, necessary for decommissioning, are fully available today. The technical feasibility of decommissioning for power plants of Biblis A and KRB type has been shown in detail. The calculations of the quantity of waste produced during removal of a nuclear power plant could be confirmed and it could be determined with high procedure. The radiation dose to the decommissioning personnel is in the range of the radiation protection regulations and is in the same range as the radiation dose to the personnel within a yearly inservice inspection. (AF)

  6. Economic challenges of nuclear power

    International Nuclear Information System (INIS)

    The costs of nuclear power is detailed. Concerning the construction costs, the mean value over the French fleet of reactors is 1,2 billions euros/GWe and 1.5 billions euros/GWe when the engineering and pre-exploitation costs are included. The construction costs of future reactors will be far higher than expected: 6 billion euros versus 3.5 billions euros for the EPR. The Audit Office has recently made public the real cost of today's nuclear electricity in France: 54 euros/MWh, this value is given by the CCE method and includes all the aspects of nuclear energy: construction, operation, dismantling, maintenance, upgrading works required for life extension, new safety requirements due to Fukushima feedback and long-term managing of wastes. The cost of nuclear accidents is not taken into account. The costs of dismantling can be estimated from the feedback experience from the dismantling of nuclear reactors in the Usa, the value obtained is consistent with the OECD rule that states that it represents 15% of the construction cost. The economic impact of decommissioning a plant after 40 years of operating life while its operating life could have been extended to reach 50 or even 60 years has a cost of losing 1 billion to 2 billion euros per reactor. Despite the fact that tomorrow's nuclear systems will be more expensive than today's, it will stay in a competitive range. (A.C.)

  7. Fuel management simulation for CANFLEX-RU in CANDU 6

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Chang Joon; Suk, Ho Chun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-12-31

    Fuel management simulations have been performed for CANFLEX-09% RU fuel in the CANDU 6 reactor. In this study, the bi-directional 4-bundle shift fuelling scheme was assumed. The lattice cell and time-average calculation were carried out. The refuelling simulation calculations were performed for 600 full power days. Time-averaged results show good axial power profile with the CANFLEX-RU fuel. During the simulation period, the maximum channel and bundle power were maintained below the licensing limit of CANDU 6 reactor. 7 refs., 4 figs. (Author)

  8. ICRP publication 26. Its applicability in a nuclear power programme

    International Nuclear Information System (INIS)

    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)

  9. Elecnuc. Nuclear power plants in the world

    International Nuclear Information System (INIS)

    This small booklet summarizes in tables all data relative to the nuclear power plants worldwide. These data come from the IAEA's PRIS and AREVA-CEA's GAIA databases. The following aspects are reviewed: 2007 highlights; Main characteristics of reactor types; Map of the French nuclear power plants on 2007/01/01; Worldwide status of nuclear power plants (12/31/2007); Units distributed by countries; Nuclear power plants connected to the Grid- by reactor type groups; Nuclear power plants under construction on 2007; Evolution of nuclear power plants capacities connected to the grid; First electric generations supplied by a nuclear unit in each country; Electrical generation from nuclear power plants by country at the end 2007; Performance indicator of French PWR units; Evolution of the generation indicators worldwide by type; Nuclear operator ranking according to their installed capacity; Units connected to the grid by countries at 12/31/2007; Status of licence renewal applications in USA; Nuclear power plants under construction at 12/31/2007; Shutdown reactors; Exported nuclear capacity in net MWe; Exported and national nuclear capacity connected to the grid; Exported nuclear power plants under construction; Exported and national nuclear capacity under construction; Nuclear power plants ordered at 12/31/2007; Long term shutdown units at 12/31/2007; COL (combined licences) applications in the USA; Recycling of Plutonium in reactors and experiences; Mox licence plants projects; Appendix - historical development; Meaning of the used acronyms; Glossary

  10. Alternative institutional arrangements for nuclear power

    International Nuclear Information System (INIS)

    This paper investigates how alternative organizations of nuclear power generation would effect the regulatory environment for nuclear power production, how it would effect financial constraints on new construction, and what governmental barriers to such reorganization exist

  11. Argentine nuclear program

    International Nuclear Information System (INIS)

    The paper describes Argentina's nuclear program, detailing its objectives, the schedule of construction of nuclear plants and local production of required equipment. The technologies adopted so far, the local industrial and engineering participation, the preliminary study for the construction of the next power station and Argentina's nonproliferation nuclear policy are analyzed. Argentina's point of view on Canadian nonproliferation policy and CANDU reactor export is discussed

  12. Sabotage at Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Purvis, James W.

    1999-07-21

    Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented.

  13. Sabotage at Nuclear Power Plants

    International Nuclear Information System (INIS)

    Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented

  14. Nuclear power plants and environment

    International Nuclear Information System (INIS)

    The question of nuclear power plants is analysed in details. The fundamental principles of reactors are described as well as the problems of safety involved with the reactor operation and the quantity and type of radioactive released to the environment. It shows that the amount of radioactive is very long. The reactor accidents has occurred, as three mile island, are also analysed. (M.I.A.)

  15. Maintenance of nuclear power plants

    International Nuclear Information System (INIS)

    This Safety Guide provides detailed guidance on the provisions of the Code on the Safety in Nuclear Power Plants: Operation, IAEA Safety Series No. 50-C-O(Rev.1) on the maintenance of structures, systems and components. Like the Code, the Guide forms part of the IAEA's programme, referred to as the NUSS programme, for establishing Codes and Safety Guides relating to nuclear power plants. Effective maintenance is essential for safe operation of a nuclear power plant. It not only ensures that the level of reliability and effectiveness of all plant structures, systems and components having a bearing on safety remains in accordance with design assumptions and intent, but also that the safety status of the plant is not adversely affected after commencement of operation. Nuclear power plant maintenance requires special attention because of: Limitations set by requirements that a minimum number of components remain operable even when the plant is shut down in order to ensure that all necessary safety functions are guaranteed; Difficulty of access to some plant items even when the plant is shut down, due to radiation protection constraints; Potential radiological hazards to site personnel and the public. This Guide covers the organizational and procedural aspects of maintenance but does not give detailed technical advice on the maintenance of particular plant items. It gives guidance on preventive and remedial measures necessary to ensure that all structures, systems and components important to safety are capable of performing as intended. The Guide covers the organizational and administrative requirements for establishing and implementing preventive maintenance schedules, repairing defective plant items, selecting and training maintenance personnel, providing maintenance facilities and equipment, procuring stores and spare parts, reviewing, controlling and carrying out plant modifications, and generating, collecting and retaining maintenance records for establishing and

  16. Nuclear power and the environment

    International Nuclear Information System (INIS)

    Power demands throughout the world are increasing: energy is essential to assure public health and to provide for the quality of life to which man aspires. Interest in the environmental aspects of nuclear power stations led the IAEA, in co-operation with the US Atomic Energy Commission, to convene a symposium in New York on this topic in August 1970. The enthusiastic response both during and after that meeting, and the interest in environmental matters evidenced by the convening of the United Nations Conference on the Human Environment in Stockholm in June this year, led to a decision to summarize the information presented in New York in a condensed and readily understandable form for those not engaged directly in this field of work. The resultant booklet, prepared in co-operation with the World Health Organization, has now been published under the title of this note. It is intended for wide distribution, especially among delegates and others attending the Stockholm conference. This initial distribution is free; it is probable that the booklet will be up-dated later for re-issue as a sales publication at a price to be fixed. 'Nuclear Power and the Environment' is presented in five sections, each treating a specific aspect of the general topic: the role of atomic energy in meeting future power needs; radiation protection standards; safe handling of radioactive materials; other impacts of the nuclear power industry; and public health considerations. The booklet concludes with a summary of the material presented, and annexes listing pertinent publications of the IAEA, WHO and other international organizations, for further reading. Contributions to the booklet were supplied by 28 experts from the IAEA and WHO and a number of Member States; these were compiled and edited in house. The interests and technical background of the prospective audience have a broader spectrum than one would normally try to cover with a single publication. For the lay public the IAEA has

  17. Nuclear power in Czech and Slovak Republics

    International Nuclear Information System (INIS)

    The nuclear power in Czech and Slovak Republics has been described. Nuclear power plants contribute 28% to the whole energy production (12.1 TWh in Czech republic and 11.7 in Slovak Republic). The Czech and Slovak Republics' nuclear power generation programme assumes to build in these Republics further nuclear power stations with higher efficiency and better safety parameters. 12 figs, 5 tabs

  18. Czechoslovakia: nuclear power in a socialist society

    OpenAIRE

    Carter, F. W.

    1988-01-01

    This paper is an evaluation of the impact nuclear power planning policies have had on Czechoslovakia's socialist society, particularly for the post-Chernobyl era. Poor indigenous energy resources and the leading role that nuclear power has played in the COMECON's energy-intensive manufacturing sector has made nuclear power into an attractive proposition from the 1960s onwards. Discussion in this paper centres around nuclear-power plant siting and operation, and media coverage of the industry ...

  19. Nuclear power revolution is far away

    International Nuclear Information System (INIS)

    The real nuclear debate is as much about money and time as it is about radioactivity and security. While the industry's own people want nuclear power plant to be recognized as climate initiative, said UNFCCC currently no. Nuclear power is virtually CO2-free. The world has 436 nuclear reactors and build 44 new right now. Total this will give a capacity of over 400 G Wh of power. But straightforward power is it not. (AG)

  20. Nuclear power development in the Far East

    International Nuclear Information System (INIS)

    The nuclear power development of selected Far Eastern countries is presented in this paper. This paper consists of three sections. Section 1 describes the current power/nuclear power status of Japan, South Korea, Taiwan and China. The first three countries already have operating nuclear power units, while mainland China will have a nuclear power commissioned this year according to their schedule. The power development plan for these countries is also presented. All of them have included nuclear power as part of their energy sources for the future. Section 2 briefly describes the nuclear power industry in these countries which basically covers design, manufacturing and R and D activities. Public Acceptance programs (PAPs) will play a significant role in the future of nuclear power. Section 3 discusses the PAPs of these countries. (author)

  1. Current status of nuclear power development

    International Nuclear Information System (INIS)

    Nuclear power is not a viable energy source for Sri Lanka at present because of a number of reasons, the main reason being the non-availability of small and economically viable nuclear power plants. However several suppliers of nuclear power plants are in the process of developing small and medium power plants (SMPRs) which could be economically competitive with coal. The paper deals with past and future trends of nuclear power plants, their economics and safety. It also deals with environmental effects and public acceptance of nuclear power plants

  2. Proceedings of the Canadian Nuclear Association 28. annual conference held in Winnipeg, Manitoba, June 12-15, 1988

    International Nuclear Information System (INIS)

    The proceedings of the 28. CNA (Canadian Nuclear Association) conference contain 28 papers under the following headings: power reactors; fuel cycles; nuclear power and public understanding; future trends; and, applications of nuclear technology. CANDU reactors are emphasized. The individual papers have been abstracted separately

  3. The status of the Canadian nuclear power program and possible future strategies

    International Nuclear Information System (INIS)

    Canada is fortunate in having developed a versatile and flexible power reactor concept-one which can be kept economically competitive into the distant future, while at the same time offering opportunities for large reductions in uranium requirements. The one CANDU concept provides a range of alternatives, at least as extensive in terms of adaptation to changing economic and uranium supply conditions as that of most other nuclear power programs consisting of two or more distinct reactor types. The range includes reduced capital costs through use of boiling light water and organic cooled options, better thermal efficiency through use of the organic cooled option, and the ability to minimize the impact of changing economic parameters and improve uranium utilization through use of Pu recycle and/or thorium fuel with uranium recycle. AECL has devoted considerable effort over the last few years to study of advanced fuel cycles in the various CANDU reactor types. Very few feasibility questions have been uncovered. A detailed conceptual study of our currently favoured vehicle for Pu recycle, CANDU-BLW (PB), a plutonium burning, boiling light water cooled CANDU, has indicated that it could be initiated with no major problems. Development would be required in a number of areas-notably, fuel design and computational methods for fuel management. The results indicate a savings of some 15-20% in plant capital costs over the natural uranium CANDU-PHW and a reduction of almost a factor of two in uranium requirements. More general studies of thorium fuelled concepts are also encouraging. The reactor designs are almost identical to those for uranium CANDU reactors and so no new feasibility problems are introduced. We recognize feasibility problems associated with specific fuels in specific CANDU types, but there appear to be none in the areas of reactor physics, control, safety and fuel management. These concepts are competitive with CANDU-PHWs even for current economic conditions

  4. A future for nuclear power

    International Nuclear Information System (INIS)

    Two decades after the Chernobyl accident, Tony Goddard believes that nuclear power must continue to be used to generate electricity. Exactly 20 years ago this month, on 21 April 1986, workers at the Chernobyl nuclear plant in the former Soviet Union carried out an experiment at very low power with one of the facility's two 'RBMK' reactors. They were, however, unaware that their actions would make the reactor dangerously unstable. Its power rapidly increased, leading to the destruction of the core and a massive chemical explosion. The World Health Organisation estimates that between 40 and 50 staff and emergency workers died as a result of radiation released during the accident. It also resulted in widespread contamination and radiation exposure. The Chernobyl disaster was a significant moment in the development of nuclear power, particularly in terms of the public's attitude to this form of energy. It also highlighted how the Soviet nuclear industry was badly regulated, suffered from lax operation and training, and tolerated weak reactor designs. Surprisingly, one power station in Lithuania and three in Russia are still using RBMK reactors after design deficiencies related to Chernobyl were corrected, although the former is due to close in 2009 following appeals by the European Union on safety grounds. Now, however, it appears that the tide is turning back in favour of nuclear power as countries contemplate the problems of climate change, rising energy prices and the fact that many nuclear plants are reaching the end of their lives. The review contains a consultation document entitled 'Our energy challenge' that sets out four goals: to cut carbon-dioxide emissions; to ensure reliable supplies of energy; to achieve sustainable economic growth; and to ensure that every home is adequately and affordably heated. While the UK hesitates, several other countries are already taking action. Finland has commissioned a new European pressurised water (EPR) reactor at Olkiluoto

  5. Public enlightment seminar on nuclear power. Proceedings

    International Nuclear Information System (INIS)

    The seminar considered different aspects of nuclear power development, including the following issues: electricity generation, power supply and demand, energy sources, consumption of electricity, energy outlook in Europe, comparative analysis of energy options, safety of modern nuclear power plants, radiation and human health, radioactive waste management, nuclear techniques to promote world food security, public information issues

  6. Nuclear power newsletter. Vol. 1, no. 1

    International Nuclear Information System (INIS)

    This first issue of newsletter describes the Nuclear Power Division of the Department of Nuclear Energy responsible for implementation of the IAEA programme on Nuclear Power. The mission of the Division is to increase the capability of interested Member States to implement and maintain competitive and sustainable nuclear power programmes and to develop and apply advanced nuclear technologies. The topics covered in this publication are: Engineering and Management Support for Competitive Nuclear Power; Improving Human Performance, Quality and Technical Infrastructure; Co-ordination of International Collaboration for the Development of Innovative Nuclear Technology; Technology Developments and Applications for Advanced Reactors; The International Conference on 'Fifty Years of Nuclear Power - the Next Fifty Years'. A list of documents published recently by the Nuclear Power Division in enclosed

  7. Cost and schedule reduction for next-generation Candu

    International Nuclear Information System (INIS)

    AECL has developed a suite of technologies for CanduR reactors that enable the next step in the evolution of the Candu family of heavy-water-moderated fuel-channel reactors. These technologies have been combined in the design for the Advanced Candu Reactor TM1 (ACRTM), AECL's next generation Candu power plant. The ACR design builds extensively on the existing Candu experience base, but includes innovations, in design and in delivery technology, that provide very substantial reductions in capital cost and in project schedules. In this paper, main features of next generation design and delivery are summarized, to provide the background basis for the cost and schedule reductions that have been achieved. In particular the paper outlines the impact of the innovative design steps for ACR: - Selection of slightly enriched fuel bundle design; - Use of light water coolant in place of traditional Candu heavy water coolant; - Compact core design with unique reactor physics benefits; - Optimized coolant and turbine system conditions. In addition to the direct cost benefits arising from efficiency improvement, and from the reduction in heavy water, the next generation Candu configuration results in numerous additional indirect cost benefits, including: - Reduction in number and complexity of reactivity mechanisms; - Reduction in number of heavy water auxiliary systems; - Simplification in heat transport and its support systems; - Simplified human-machine interface. The paper also describes the ACR approach to design for constructability. The application of module assembly and open-top construction techniques, based on Candu and other worldwide experience, has been proven to generate savings in both schedule durations and overall project cost, by reducing premium on-site activities, and by improving efficiency of system and subsystem assembly. AECL's up-to-date experience in the use of 3-D CADDS and related engineering tools has also been proven to reduce both engineering and

  8. Basic research and industrialization of CANDU advanced fuel

    International Nuclear Information System (INIS)

    Wolsong Unit 1 as the first heavy water reactor in Korea has been in service for 17 years since 1983. It would be about the time to prepare a plan for the solution of problems due to aging of the reactor. The aging of CANDU reactor could lead especially to the steam generator cruding and pressure tube sagging and creep and then decreases the operation margin to make some problems on reactor operations and safety. The counterplan could be made in two ways. One is to repair or modify reactor itself. The other is to develop new advanced fuel to increase of CANDU operation margin effectively, so as to compensate the reduced operation margin. Therefore, the first objectives in the present R and D is to develop the CANFLEX-NU (CANDU Flexible fuelling-Natural Uranium) fuel as a CANDU advanced fuel. The second objectives is to develop CANDU advanced fuel bundle to utilize advanced fuel cycles such as recovered uranium, slightly enriched uranium, etc. and so to raise adaptability for change in situation of uranium market. Also, it is to develop CANDU advanced fuel technology which improve uranium utilization to cope with a world-wide imbalance between uranium supply and demand, without significant modification of nuclear reactor design and refuelling strategies. As the implementations to achieve the above R and D goal, the work contents and scope of technology development of CANDU advanced fuel using natural uranium (CANFLEX-NU) are the fuel element/bundle designs, the nuclear design and fuel management analysis, the thermalhydraulic analysis, the safety analysis, fuel fabrication technologies, the out-pile thermalhydraulic test and in-pile irradiation tests performed. At the next, the work scopes and contents of feasibility study of CANDU advanced fuel using recycled uranium (CANFLEX-RU) are the fuel element/bundle designs, the reactor physics analysis, the thermalhydraulic analysis, the basic safety analysis of a CANDU-6 reactor with CANFLEX-RU fuel, the fabrication and

  9. Basic research and industrialization of CANDU advanced fuel

    Energy Technology Data Exchange (ETDEWEB)

    Chun, Suk Ho; Park, Joo Hwan; Jun, Ji Su [and others

    2000-04-01

    Wolsong Unit 1 as the first heavy water reactor in Korea has been in service for 17 years since 1983. It would be about the time to prepare a plan for the solution of problems due to aging of the reactor. The aging of CANDU reactor could lead especially to the steam generator cruding and pressure tube sagging and creep and then decreases the operation margin to make some problems on reactor operations and safety. The counterplan could be made in two ways. One is to repair or modify reactor itself. The other is to develop new advanced fuel to increase of CANDU operation margin effectively, so as to compensate the reduced operation margin. Therefore, the first objectives in the present R and D is to develop the CANFLEX-NU (CANDU Flexible fuelling-Natural Uranium) fuel as a CANDU advanced fuel. The second objectives is to develop CANDU advanced fuel bundle to utilize advanced fuel cycles such as recovered uranium, slightly enriched uranium, etc. and so to raise adaptability for change in situation of uranium market. Also, it is to develop CANDU advanced fuel technology which improve uranium utilization to cope with a world-wide imbalance between uranium supply and demand, without significant modification of nuclear reactor design and refuelling strategies. As the implementations to achieve the above R and D goal, the work contents and scope of technology development of CANDU advanced fuel using natural uranium (CANFLEX-NU) are the fuel element/bundle designs, the nuclear design and fuel management analysis, the thermalhydraulic analysis, the safety analysis, fuel fabrication technologies, the out-pile thermalhydraulic test and in-pile irradiation tests performed. At the next, the work scopes and contents of feasibility study of CANDU advanced fuel using recycled uranium (CANFLEX-RU) are the fuel element/bundle designs, the reactor physics analysis, the thermalhydraulic analysis, the basic safety analysis of a CANDU-6 reactor with CANFLEX-RU fuel, the fabrication and

  10. Survey of considerations involved in introducing CANDU reactors into the United States

    Energy Technology Data Exchange (ETDEWEB)

    Till, C E; Bohn, E M; Chang, Y I; van Erp, J B

    1977-01-01

    The important issues that must be considered in a decision to utilize CANDU reactors in the U.S. are identified in this report. Economic considerations, including both power costs and fuel utilization, are discussed for the near and longer term. Safety and licensing considerations are reviewed for CANDU-PHW reactors in general. The important issues, now and in the future, associated with power generation costs are the capital costs of CANDUs and the factors that impact capital cost comparisons. Fuel utilization advantages for the CANDU depend upon assumptions regarding fuel recycle at present, but the primary issue in the longer term is the utilization of the thorium cycle in the CANDU. Certain safety features of the CANDU are identified as intrinsic to the concept and these features must be examined more fully regarding licensability in the U.S.

  11. Hitachi turbine technology for nuclear applications

    Energy Technology Data Exchange (ETDEWEB)

    Yamashita, Y. [Hitachi, Ltd. Power Systems, Energy and Environmental Systems Lab., Hitachi (Japan); Kudo, T. [Hitachi, Ltd. Power Systems, Hitachi Works, Hitachi (Japan); Akane, N. [Hitachi, Ltd. Power Systems, Nuclear Systems Division, Hitachi (Japan)

    2010-07-01

    Hitachi has supplied more than 1200 steam turbines and generators in the past 70 years for both thermal and nuclear applications. Hitachi nuclear steam turbines have been applied to all major reactor types including BWR's and PHWR's (CANDU). Hitachi's recent experience has included supplying the steam turbines for Qinshan Phase III Unit 1 and 2 in China, powered by two CANDU 6 reactors, as well as several ABWR projects in Japan. Hitachi has focused significant R and D efforts on continuous improvement of nuclear steam turbine technology capitalizing on its continuous supply history and sound technical capability. This paper addresses some of the key developments and newest technologies to be employed for new-build nuclear projects, including the ACR-1000 and Enhanced CANDU 6, and focuses on longer Last Stage Blade (LSB) development, Continuous Cover Blades (CCB), and other enhancements in product reliability and performance. (author)

  12. Hitachi turbine generator technology for nuclear applications

    Energy Technology Data Exchange (ETDEWEB)

    Nakamura, T.; Kudo, T. [Hitachi, Ltd., Power Systems, Hitachi Works, Hitachi (Japan); Akane, N. [Hitachi, Ltd. Power Systems, Nuclear Systems Division, Hitachi (Japan)

    2009-07-01

    Hitachi has supplied more than 1200 steam turbines and generators in the past 70 years for both thermal and nuclear applications. Hitachi nuclear steam turbines have been applied to all major reactor types including PWR's, BWR's and PHWR's (CANDU). Hitachi's recent experience has included supplying the steam turbines for Qinshan Phase III Unit 1 and 2 in China, powered by two CANDU 6 reactor, as well as several ABWR projects in Japan. Hitachi has focused significant R and D efforts on continuous improvement of nuclear steam turbine technology capitalizing on its continuous supply history and sound technical capability. This paper addresses some of the key developments and new technologies to be employed for new-build nuclear projects, including the ACR-1000 and Enhanced CANDU6, and focuses on longer Last Stage Blade (LSB) development, Continuous Cover Blades (CCB), and other enhancements in product reliability and performance. (author)

  13. Installation of an irradiated fuel bundle discharge counter at Bruce NGS-B 3 000 MW(e) CANDU power station

    International Nuclear Information System (INIS)

    Design, manufacture and installation of an irradiated fuel bundle discharge counter for the multi-unit CANDU Bruce NGS-B Generating Station involved contributions from the International Atomic Energy Agency (Agency), designers (AECL), contractors, manufacturers, utility and the regulatory agency. The installation at Bruce NGS-B was the first made by the Agency as a retrofit to a multi-unit CANDU reactor approaching its fist critical operation, where the whole project was the responsibility of the Agency and where the original design of the reactor had not had provision for the Agency equipment. The scheduling and integration of the installation into the normal activities involved in starting up a 3 000 MW(e) multi-unit generating station were successfully achieved. The Agency has demonstrated the capability and performance of the fuel discharge counter

  14. Improving activity transport models for water-cooled nuclear power reactors

    Energy Technology Data Exchange (ETDEWEB)

    Burrill, K.A

    2001-08-01

    Eight current models for describing radioactivity transport and radiation field growth around water-cooled nuclear power reactors have been reviewed and assessed. A frequent failing of the models is the arbitrary nature of the determination of the important processes. Nearly all modelers agree that the kinetics of deposition and release of both dissolved and particulate material must be described. Plant data must be used to guide the selection and development of suitable improved models, with a minimum of empirically-based rate constraints being used. Limiting case modelling based on experimental data is suggested as a way to simplify current models and remove their subjectivity. Improved models must consider the recent change to 'coordinated water chemistry' that appears to produce normal solubility behaviour for dissolved iron throughout the fuel cycle in PWRs, but retrograde solubility remains for dissolved nickel. Profiles are suggested for dissolved iron and nickel concentrations around the heat transport system in CANDU reactors, which operate nominally at constant chemistry, i.e., pH{sub T} constant with time, and which use carbon steel isothermal piping. These diagrams are modified for a CANDU reactor with stainless steel piping, in order to show the changes expected. The significance of these profiles for transport in PWRs is discussed for further model improvement. (author)

  15. The economics of nuclear power

    Science.gov (United States)

    Horst, Ronald L.

    We extend economic analysis of the nuclear power industry by developing and employing three tools. They are (1) compilation and unification of operating and accounting data sets for plants and sites, (2) an abstract industry model with major economic agents and features, and (3) a model of nuclear power plant operators. We build a matched data set to combine dissimilar but mutually dependant bodies of information. We match detailed information on the activities and conditions of individual plants to slightly more aggregated financial data. Others have exploited the data separately, but we extend the sets and pool available data sets. The data reveal dramatic changes in the industry over the past thirty years. The 1980s proved unprofitable for the industry. This is evident both in the cost data and in the operator activity data. Productivity then improved dramatically while cost growth stabilized to the point of industry profitability. Relative electricity prices may be rising after nearly two decades of decline. Such demand side trends, together with supply side improvements, suggest a healthy industry. Our microeconomic model of nuclear power plant operators employs a forward-looking component to capture the information set available to decision makers and to model the decision-making process. Our model includes features often overlooked elsewhere, including electricity price equations and liability. Failure to account for changes in electricity price trends perhaps misled earlier scholars, and they attributed to other causes the effects on profits of changing price structures. The model includes potential losses resulting from catastrophic nuclear accidents. Applications include historical simulations and forecasts. Nuclear power involves risk, and accident costs are borne both by plant owners and the public. Authorities regulate the industry and balance conflicting desires for economic gain and safety. We construct an extensible model with regulators, plant

  16. Evolution of the CANDU ICS-90+ control room design

    International Nuclear Information System (INIS)

    The design of the CANDU Control Room and the associated design process has evolved considerably over several generations of plants, from the first commercial scale demonstration CANDU at Douglas Point through to the large scale CANDUs at Darlington, and beyond, for the next generation of CANDU plant, ICS-90+, represented by new designs like CANDU 3. In the early plants, the control room configuration was based on designers' projections of control interface requirements. With succeeding generations, of designs, there has been an evolution towards: increasing attention to formal requirements definition, incorporation into the Human Machine Interface (HMI) of a larger base of operational experience, more systematic consideration of Human Factors (HF) aspects of the design and the application of a more powerful computer based HMI. For the newest plant, the CANDU 3, a Human Factors Engineering Program Plan (HFEPP) defines the overall HF engineering process, the associated requirements and HF engineering standards to be followed in each stage, and for all HMI aspects of the control room and plant design. The CANDU 3 control room also incorporates several new design innovations that will facilitate operating crew performance improvements. These are based on past experience with operating CANDU plants, incorporated with the use of formal design and validation methods plus results from Canadian research program to support control centre design and operation. For example, there are design improvements to facilitate: operator tracking of plant state, problem solving, alarm filtering, annunciation system interrogation, special safety system testing features, etc. The present paper will expand and elaborate on each of the above topics. (author). 7 refs, 2 figs, 1 tab

  17. Nuclear power data 2016; Kernenergie in Zahlen 2016

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-04-15

    The brochure on nuclear power data 2016 covers the following topics: (I) nuclear power in Germany: nuclear power plants in Germany; shut-down and decommissioned nuclear power plants, gross electricity generation, primary energy consumption; (II) nuclear power worldwide: nuclear electricity production, nuclear power plants.

  18. Modelling of nuclear power plant decommissioning financing.

    Science.gov (United States)

    Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. PMID:25979740

  19. Country Nuclear Power Profiles - 2013 Edition

    International Nuclear Information System (INIS)

    The Country Nuclear Power Profiles compile background information on the status and development of nuclear power programmes in Member States. The CNPP summarizes organizational and industrial aspects of nuclear power programs and provides information about the relevant legislative, regulatory, and international framework in each country. Its descriptive and statistical overview of the overall economic, energy, and electricity situation in each country and its nuclear power framework is intended to serve as an integrated source of key background information about nuclear power programs in the world. This 2013 edition, issued on CD-ROM and Web pages, contains updated country information for 51 countries

  20. Nuclear power development, safety and environmental problems

    International Nuclear Information System (INIS)

    The current state is described of power production by conventional power plants and the problems of burning fossil fuels are discussed. A survey is presented of the development of world nuclear power production and of the planned construction of nuclear power plants in Czechoslovakia. The questions of the safety of nuclear installations and their environmental impacts in normal operation and in case of accident are outlined. In the analysis of these aspects of nuclear power production the probability data on the potential hazards of operating nuclear reactors as published in the Rasmussen Safety Report are discussed. (O.K.)

  1. Similarities and differences between conventional power and nuclear power

    International Nuclear Information System (INIS)

    As the implementation of the national guideline of 'proactively promoting nuclear power development', especially after China decided in 2006 to introduce Westinghouse's AP1000 technology, some of the power groups specialized in conventional power generation, have been participating in the preliminary work and construction of nuclear power projects in certain degrees. Meanwhile, such traditional nuclear power corporations as China National Nuclear Corporation (CNNC) and China Guangdong Nuclear Power Corporation (CGNPC) have also employed some employees with conventional power generation experience. How can these employees who have long been engaged in conventional power generation successfully adapt to the new work pattern, ideology, knowledge, thinking mode and proficiency of nuclear power, so that they can fit in with the work requirements of nuclear power and become qualified as soon as possible? By analyzing the technological, managerial and cultural features of nuclear power, as well as some issues to be kept in mind when engaged in nuclear power, this paper intends to make some contribution to the nuclear power development in the specific period. (author)

  2. A generalized perturbation program for CANDU reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Do Heon; Kim, Jong Kyung [Hanyang University, Seoul (Korea, Republic of); Choi, Hang Bok; Roh, Gyu Hong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Yang, Won Sik [Chosun University, Kwangju (Korea, Republic of)

    1998-12-31

    A generalized perturbation program has been developed for the purpose of estimating zonal power variation of a CANDU reactor upon refueling operation. The forward and adjoint calculation modules of RFSP code were used to construct the generalized perturbation program. The numerical algorithm for the generalized adjoint flux calculation was verified by comparing the zone power estimates upon refueling with those of forward calculation. It was, however, noticed that the truncation error from the iteration process of the generalized adjoint flux is not negligible. 2 refs., 1 figs., 1 tab. (Author)

  3. Neutronics-thermalhydraulics coupling in a CANDU SCWR

    Science.gov (United States)

    Adouki, Pierre

    In order to implement new nuclear technologies as a solution to the growing demand for energy, 10 countries agreed on a framework for international cooperation in 2002, to form the Generation IV International Forum (GIF). The goal of the GIF is to design the next generation of nuclear reactors that would be cost effective and would enhance safety. This forum has proposed several types of Generation IV reactors including the Supercritical Water-Cooled Reactor (SCWR). The SCWR comes in two main configurations: pressure vessel SCWR and pressure tube SCWR (PT-SCWR). In this study, the CANDU SCWR (a PT-SCWR) is considered. This reactor is oriented vertically and contains 336 channels with a length of 5 m. The target coolant inlet and outlet temperatures are 350 Celsius and 625 Celsius, respectively. The coolant flows downwards, and the reactor power is 2540 MWth. Various fuel designs have been considered in order not to exceed the linear element rating. However, the dependency between the core power and thermalhydraulics parameters results in the necessity to use a neutronics/thermalhydaulics coupling scheme to determine the core power and the thermalhydraulics parameters. The core power obtained has a power peaking factor of 1.4. The bundle power distribution for all channels has a peak at the third bundle from the inlet, but the value of this peak increases with the channel power. The heat-transfer coefficient and the specific-heat capacity have a peak at the same location in a channel, and this location shifts toward the inlet as the channel power increases. The exit coolant temperature increases with the channel power, while the exit coolant density and pressure decrease with the channel power. Also, higher channel powers lead to higher fuel and cladding temperatures. Moreover, as the coupling method is applied, the effective multiplication factor and the values of thermalhydaulics parameters oscillate as they converge.

  4. Evolution of the CANDU control centre retrofit and new stations

    International Nuclear Information System (INIS)

    Significant event data from operating nuclear plants in many countries consistently indicates human errors are the root cause for 40-60% of operating station significant events. Because so much information is already in digital form, opportunities exist to improve the CANDU control centre with retrofits that exploit this information. These opportunities are enhanced because of rapid technological development in computers and electronics, coupled with significant progress in the behavioural sciences that greatly increases our knowledge of the cognitive strengths and weaknesses of human beings. CANDU control rooms are undergoing retrofits and for future CANDU stations, a new concept of the control centre is emerging. The objective is to significantly reduce the incidence of human error, reduce operations and maintenance costs and improve both reliability and safety

  5. The future of nuclear power in Mexico

    International Nuclear Information System (INIS)

    The future of nuclear power in Mexico shows interesting aspects: the nuclear power is the source of energy that can supply large proportions of energy, that the country needs; the Kw/h of nuclear power is the most economic energy; the installation of 20 nucleoelectric plants will grant future jobs, the associated nuclear industry can be nationally integrated in the natural uranium cycle. (author)

  6. Design of nuclear power plants

    International Nuclear Information System (INIS)

    The criteria of design and safety, applied internationally to systems and components of PWR type reactors, are described. The main criteria of the design analysed are: thermohydraulic optimization; optimized arrangement of buildings and components; low costs of energy generation; high level of standardization; application of specific safety criteria for nuclear power plants. The safety criteria aim to: assure the safe reactor shutdown; remove the residual heat and; avoid the release of radioactive elements for environment. Some exemples of safety criteria are given for Angra-2 and Angra-3 reactors. (M.C.K.)

  7. Stochastic modeling of deterioration in nuclear power plant components

    Science.gov (United States)

    Yuan, Xianxun

    2007-12-01

    The risk-based life-cycle management of engineering systems in a nuclear power plant is intended to ensure safe and economically efficient operation of energy generation infrastructure over its entire service life. An important element of life-cycle management is to understand, model and forecast the effect of various degradation mechanisms affecting the performance of engineering systems, structures and components. The modeling of degradation in nuclear plant components is confounded by large sampling and temporal uncertainties. The reason is that nuclear systems are not readily accessible for inspections due to high level of radiation and large costs associated with remote data collection methods. The models of degradation used by industry are largely derived from ordinary linear regression methods. The main objective of this thesis is to develop more advanced techniques based on stochastic process theory to model deterioration in engineering components with the purpose of providing more scientific basis to life-cycle management of aging nuclear power plants. This thesis proposes a stochastic gamma process (GP) model for deterioration and develops a suite of statistical techniques for calibrating the model parameters. The gamma process is a versatile and mathematically tractable stochastic model for a wide variety of degradation phenomena, and another desirable property is its nonnegative, monotonically increasing sample paths. In the thesis, the GP model is extended by including additional covariates and also modeling for random effects. The optimization of age-based replacement and condition-based maintenance strategies is also presented. The thesis also investigates improved regression techniques for modeling deterioration. A linear mixed-effects (LME) regression model is presented to resolve an inconsistency of the traditional regression models. The proposed LME model assumes that the randomness in deterioration is decomposed into two parts: the unobserved

  8. Nuclear power and nuclear safety 2003 (in Danish)

    International Nuclear Information System (INIS)

    The report, 'Kernekraft og nuklear sikkerhed 2003' (Nuclear power and nuclear safe-ty 2003) is the first report in a new series of annual reports on the international devel-opment of nuclear power production, with special emphasis on safety issues and nu-clear emergency preparedness. The report series is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency and re-places the previous series, 'International kernekraftstatus' (International Nuclear Po-wer Status). The report for 2003 covers the following topics: status of nuclear power production and regional trends, development of reactors and emergency management systems, safety-related events with nuclear power production, and international rela-tions and conflicts. (au)

  9. Development of Czechoslovak nuclear power complex

    International Nuclear Information System (INIS)

    The research project ''Development of the Czechoslovak nuclear power complex'' was undertaken by several Czechoslovak institutions and was coordinated by the Research Institute of the Fuel and Power Complex in Bratislava. Involved in the project was a staff of 170 people. 274 reports were pulished and the cost approached 70 mill. Czechoslovak crowns. The results are characterized of all six partial tasks. Basic information was prepared for the forecast of the solution of fuel and power problems in Czechoslovakia up to the year 2000 and their prospects up to the year 2020. Program MORNAP was written for the development of nuclear power, which models the operation of a power generation and transmission system with a selectable number of nuclear power plants. Another partial task related to the fuel cycle of nuclear power plants with respect to long-term provision and management of nuclear fuel. Nuclear safety was split into three problem groups, viz.: system safety of nuclear power plant operation; radiation problems of nuclear power plant safety; quality assurance of nuclear power plant components. The two remaining tasks were devoted to nuclear power engineering and to civil engineering. (Z.M.). 3 tabs., 1 refs

  10. Worldwide advanced nuclear power reactors with passive and inherent safety: What, why, how, and who

    International Nuclear Information System (INIS)

    The political controversy over nuclear power, the accidents at Three Mile Island (TMI) and Chernobyl, international competition, concerns about the carbon dioxide greenhouse effect and technical breakthroughs have resulted in a segment of the nuclear industry examining power reactor concepts with PRIME safety characteristics. PRIME is an acronym for Passive safety, Resilience, Inherent safety, Malevolence resistance, and Extended time after initiation of an accident for external help. The basic ideal of PRIME is to develop power reactors in which operator error, internal sabotage, or external assault do not cause a significant release of radioactivity to the environment. Several PRIME reactor concepts are being considered. In each case, an existing, proven power reactor technology is combined with radical innovations in selected plant components and in the safety philosophy. The Process Inherent Ultimate Safety (PIUS) reactor is a modified pressurized-water reactor, the Modular High Temperature Gas-Cooled Reactor (MHTGR) is a modified gas-cooled reactor, and the Advanced CANDU Project is a modified heavy-water reactor. In addition to the reactor concepts, there is parallel work on super containments. The objective is the development of a passive ''box'' that can contain radioactivity in the event of any type of accident. This report briefly examines: why a segment of the nuclear power community is taking this new direction, how it differs from earlier directions, and what technical options are being considered. A more detailed description of which countries and reactor vendors have undertaken activities follows. 41 refs

  11. Simulators of nuclear power stations

    International Nuclear Information System (INIS)

    The report deals with the simulators of nuclear power stations used for the training of operators and for the analysis of operations. It reviews the development of analogical, hybrid and digital simulators up to the present, indicating the impact resulting from the TMI-2 accident. It indicates, the components of simulators and the present accepted terminology for a classification of the various types of simulators. It reviews the present state of the art of the technology: how a basic mathematical model of a nuclear power system is worked out and what are the technical problems associated with more accurate models. Examples of elaborate models are given: for a PWR pressurizer, for an AGR steam generator. It also discusses certain problems of hardware technology. Characteristics of present replica simulators are given with certain details: simulated transient evolutions and malfunctions, accuracy of simulation. The work concerning the assessment of the validity of certain simulators is reported. A list of simulator manufacturers and a survey of the principal simulators in operation in the countries of the European Community, in the United States, and in certain other countries are presented. Problem associated with the use of simulators as training facilities, and their use as operational devices are discussed. Studies and research in progress for the expected future development of simulators are reviewed

  12. Country Nuclear Power Profiles - 2009 Edition

    International Nuclear Information System (INIS)

    The Country Nuclear Power Profiles compiles background information on the status and development of nuclear power programs in Member States. It consists of organizational and industrial aspects of nuclear power programs and provides information about the relevant legislative, regulatory, and international framework in each country. Its descriptive and statistical overview of the overall economic, energy, and electricity situation in each country, and its nuclear power framework is intended to serve as an integrated source of key background information about nuclear power programs in the world. The preparation of Country Nuclear Power Profiles (CNPP) was initiated in 1990s. It responded to a need for a database and a technical publication containing a description of the energy and economic situation, the energy and the electricity sector, and the primary organizations involved in nuclear power in IAEA Member States. This is the 2009 edition issued on CD-ROM and Web pages. It updates the country information for 44 countries. The CNPP is updated based on information voluntarily provided by participating IAEA Member States. Participants include the 30 countries that have operating nuclear power plants, as well as 14 countries having past or planned nuclear power programmes (Bangladesh, Egypt, Ghana, Indonesia, the Islamic Republic of Iran, Italy, Kazakhstan, Nigeria, Philippines, Poland, Thailand, Tunisia, Turkey and Vietnam). For the 2009 edition, 26 countries provided updated or new profiles. For the other countries, the IAEA updated the profile statistical tables on nuclear power, energy development, and economic indicators based on information from IAEA and World Bank databases

  13. Automatic ultrasonic inspection system for wear determination in calandria tubes of Embalse Nuclear Power Plant

    Science.gov (United States)

    Katchadjian, Pablo; Desimone, Carlos; Garcia, Alejandro; Antonaccio, Carlos; Schroeter, Fernando; Molina, Héctor

    2015-03-01

    Embalse Nuclear Power Plant (CNE) (CANDU design) is reaching its end of life and due to elapsed operating time the problem of deformation by accelerated creep occurs in the pressure tubes (PT), leading to a possible contact between calandria tubes (CT), concentric to the PT, and some Liquid Injection Shutdown System (LISS) nozzles that pass underneath them. With determination of CT wear, after the predicted contact occurs, the wear rate of the TC could be determined and thus take less conservative measures over the remaining life of the component. This paper presents the development of an ultrasonic technique for measuring wear in CT, with nominal thickness of 1.34 mm. Because the only access is through the interior of PT, to perform this measurement it is necessary to pass through three different interfaces.

  14. Automatic ultrasonic inspection system for wear determination in calandria tubes of Embalse Nuclear Power Plant

    International Nuclear Information System (INIS)

    Embalse Nuclear Power Plant (CNE) (CANDU design) is reaching its end of life and due to elapsed operating time the problem of deformation by accelerated creep occurs in the pressure tubes (PT), leading to a possible contact between calandria tubes (CT), concentric to the PT, and some Liquid Injection Shutdown System (LISS) nozzles that pass underneath them. With determination of CT wear, after the predicted contact occurs, the wear rate of the TC could be determined and thus take less conservative measures over the remaining life of the component. This paper presents the development of an ultrasonic technique for measuring wear in CT, with nominal thickness of 1.34 mm. Because the only access is through the interior of PT, to perform this measurement it is necessary to pass through three different interfaces

  15. Automatic ultrasonic inspection system for wear determination in calandria tubes of Embalse Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Katchadjian, Pablo, E-mail: katcha@cnea.gov.ar; Desimone, Carlos, E-mail: katcha@cnea.gov.ar; Garcia, Alejandro, E-mail: katcha@cnea.gov.ar [Comisión Nacional de Energía Atómica, Depto. ENDE - INEND, Av. Gral. Paz 1499, Buenos Aires (Argentina); Antonaccio, Carlos; Schroeter, Fernando; Molina, Héctor [Nucleoeléctrica Argentina-SA, Arribeños 3619, Buenos Aires (Argentina)

    2015-03-31

    Embalse Nuclear Power Plant (CNE) (CANDU design) is reaching its end of life and due to elapsed operating time the problem of deformation by accelerated creep occurs in the pressure tubes (PT), leading to a possible contact between calandria tubes (CT), concentric to the PT, and some Liquid Injection Shutdown System (LISS) nozzles that pass underneath them. With determination of CT wear, after the predicted contact occurs, the wear rate of the TC could be determined and thus take less conservative measures over the remaining life of the component. This paper presents the development of an ultrasonic technique for measuring wear in CT, with nominal thickness of 1.34 mm. Because the only access is through the interior of PT, to perform this measurement it is necessary to pass through three different interfaces.

  16. Nuclear proliferation and the future of nuclear power

    International Nuclear Information System (INIS)

    The author expresses concerns felt worldwide, both within and outside the nuclear industry, that expansion of nuclear power systems will be impossible without safeguards against nuclear weapons proliferation. Present problems include: countries with nuclear programs who are not full participants in the non-proliferation regime; the ease with which countries can withdraw from the treaty; obtaining accurate nuclear material inventories; and compliance. He discusses conditions and improvements that would address many of the proliferation concerns

  17. Advanced nuclear power plants for the 21st century

    Energy Technology Data Exchange (ETDEWEB)

    Graham, J. [BNFL, Inc. (United States)

    1996-10-01

    This paper examines, following four issues: capacity; the closure of the fuel cycle; deregulation; and the need to maintain the development of the advanced systems. Demand is a governing parameter: if one doesn`t need the power then there is no need to increase generating capacity. However, there is no question but that the population is growing. All predictions are that new generating capacity will be needed -- the questions are when and how? Until the various issues involved in deregulation are played through it is not clear what form markets will take for the longer term or how investment in large-capital-cost facilities will fit into the financial structure. Deregulation needs the time to throw light on these matters and to gain some experience in the various financial options. The lack of closure of the fuel cycle is both a cost and public perception issue. The US program, as a result of a cold-war paranoia against recycling the partially used fuel, is based upon the final disposal of useful supplies of energy. However, the program itself is plagued with poor management, delays, and uncertainties that are due, in no small measure, to half-uttered thoughts by all concerned, that this is the wrong policy. Current efforts to rethink the policy, and its implementing projects, are welcome. Finally, if it is important to keep design options for advanced nuclear power plants open for the future, then it necessary to maintain valid research and development programs for those designs. Current US policy is damaging to a number of the more advanced options. This paper discusses the candidate systems: LWR, ALMR, HTGR, and CANDU systems for the special contributions they may each provide in an ideal electrical generating industry of the mid-twenty-first century, and makes suggestions for the future. (J.P.N.)

  18. Thirty years of Czechoslovak nuclear power

    International Nuclear Information System (INIS)

    Nuclear power in the CSSR in its 30 years old history has occupied an important position in the current power base of the country. In 1987, the nuclear power plant share of the total installed capacity was roughly 16% and their share of the total electricity production was 24.3%. By the year 2000, the installed capacity of nuclear power plants should reach a minimum of 10,000 MW and it is envisaged that this value might be exceeded by another 1,000 MW. In addition to the completion of the Mochovce and Temelin nuclear power plants currently under construction, this would require putting into operation two more WWER-1000 units in other localities. It has been decided that new nuclear power plants will be sited at Kecerovce in Eastern Slovakia and at Blahutovice in Northern Moravia. The preparation has considerably progressed of sites for other nuclear power plants. With the envisaged rate of nuclear power plant construction, the production of nuclear electric power should inscrease to 15 TWh in 1990, 41 TWh in 1995 and 58 TWh in the year 2000. Thus, nuclear power plant share of the total electricity production would be more than 50% in the year 2000 and the plant would cover about 16 to 17% of needs of primary power resources. (Z.M.). 3 tabs., 4 refs

  19. Development of Regulatory Requirements and Inspection Guides for CANDU Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kim, M. W.; Kim, K.; Ryu, Y. H. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Ro, H. Y.; Jin, T. E. [Korea Power Engineering Co., Yongin (Korea, Republic of)

    2009-05-15

    The first domestic CANDU power reactor, Wolsong unit 1, has been operated for about twenty years since commercial operation in 1983, and has been raised common aging issues of CANDU reactors in pressure tubes, calandria tubes, feeder pipes, etc. To solve these aging issues, utility is promoting the refurbishment activities for these major components. Therefore, confirmation and improvement for insufficient requirements considering the CNSC regulatory documents, regulatory principles between regulatory body and utilities related with refurbishment activities are required. These review contents are described herein, and representative review results are presented.

  20. Second International Conference on CANDU Fuel

    International Nuclear Information System (INIS)

    Thirty-four papers were presented at this conference in sessions dealing with international experience and programs relating to CANDU fuel; fuel manufacture; fuel behaviour; fuel handling, storage and disposal; and advanced CANDU fuel cycles. (L.L.)

  1. Future generations of CANDU: advantages and development with passive safety

    International Nuclear Information System (INIS)

    Atomic Energy of Canada Limited (AECL) advances water reactor and CANDLT technology using an evolutionary development strategy. This strategy ensures that innovations are based firmly on current experience and keeps our development programs focused on one reactor concept, reducing risks, development costs, and product development cycle times. It also assures our customers that our products will never become obsolete or unsupported, and the continuous line of water reactor development is secure and supported into the future. Using the channel reactor advantage of modularity, the subdivided core has the advantage of passive safety by heat removal to the low- pressure moderator. With continuous improvements, the Advanced CANDU Reactor TM (ACR-1000TM) concept will likely remain highly competitive for a number of years and leads naturally to the next phase of CANDU development, namely the Generation IV CANDU -SCWR concept. This is conventional water technology, since supercritical boilers and turbines have been operating for some time in coal-fired power plants. Significant cost, safety, and performance advantages would result from the CANDU-SCWR concept, plus the flexibility of a range of plant sizes suitable for both small and large electric grids, and the ability for co-generation of electric power, process heat, and hydrogen. In CANDU-SCWR, novel developments are included in the primary circuit layout and channel design. The R and D in Canada is integrated with the Generation IV international Forum (GIF) plans, and has started on examining replaceable insulating liners that would ensure channel life, and on providing completely passive reactor decay heat removal directly to the moderator heat sink without forced cooling. In the interests of sustainability, hydrogen production by a CANDU- SCWR is also be included as part of the system requirements, where the methods for hydrogen production will depend on the outlet temperature of the reactor

  2. Development of the advanced CANDU technology

    Energy Technology Data Exchange (ETDEWEB)

    Suk, Soo Dong; Min, Byung Joo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Na, Y. H.; Lee, S. Y.; Choi, J. H.; Lee, B. C.; Kim, S. N.; Jo, C. H.; Paik, J. S.; On, M. R.; Park, H. S.; Kim, S. R. [Korea Electric Power Co., Taejon (Korea, Republic of)

    1997-07-01

    The purpose of this study is to develop the advanced design technology to improve safety, operability and economy and to develop and advanced safety evaluation system. More realistic and reasonable methodology and modeling was employed to improve safety margin in containment analysis. Various efforts have been made to verify the CATHENA code which is the major safety analysis code for CANDU PHWR system. Fully computerized prototype ECCS was developed. The feasibility study and conceptual design of the distributed digital control system have been performed as well. The core characteristics of advanced fuel cycle, fuel management and power upgrade have been studied to determine the advanced core. (author). 77 refs., 51 tabs., 108 figs.

  3. Application of microprocessor based technology in CANDU Stations

    International Nuclear Information System (INIS)

    In early 80s, absence of more efficient, cost effective, reliable control hardware was experienced by the nuclear industry. Usage of microprocessor based technology was not prevalent in the nuclear industry due to lack of experience and infancy of the new technology at that time. In 1985, microprocessor based technology, 'Chameleon micro DCI Controllers' manufactured by Fischer and Porter was the 1st application of such technology in any safety related applications in a CANDU Station. The application was for In-Core LOCA logic in Emergency Coolant Injection System (ECIS) modification in Pickering A Nuclear Station. This was followed by use of the same hardware for modification of 'Dump-Arrest' logic for shut-down system in Pickering A in 1986. Other applications were 'Heat Transport Pump Trip Logic' in Bruce A in 1989. The hardware performed very well and far exceeded its predicted availability during the last 22 years of operation. In early 90's Power House Emergency Venting system used 22 micro DCI controllers for Pickering A and B Stations. The use of microprocessor based technology helped meeting the timing requirements of initiating Powerhouse Emergency Venting within 3 seconds of a steam break accident in reactor auxiliary bay. Development of digital trip meter was undertaken in 1991 to solve human-factors related issue of interpretation of HT system saturation trip margin as the analog indicator lacked accuracy and resolution. This was a significant milestone in use of digital technology in safety related applications in any CANDU Station. The process offered an opportunity of trial use of software standards developed by OPG and AECL for category 1 safety critical software systems. This application generated significant learning experience for OPG (then Ontario Hydro) and the industry. OPG was ahead of other nuclear utilities in implementation of microprocessor based technology in early 80s and 90s. OPG initiatives generated lot of design, maintenance and

  4. Nuclear power a very short introduction

    CERN Document Server

    Irvine, Maxwell

    2011-01-01

    With the World desperate to find energy sources that do not emit carbon gasses, nuclear power is back on the agenda and in the news, following the increasing cost of fossil fuels and concerns about the security of their future supply. However, the term 'nuclear power' causes anxiety in many people and there is confusion concerning the nature and extent of the associated risks. Here, Maxwell Irvine presents a concise introduction to the development of nuclear physics leading up to the emergence of the nuclear power industry. He discusses the nature of nuclear energy and deals with various aspec

  5. Space nuclear power and man's extraterrestrial civilization

    International Nuclear Information System (INIS)

    This paper examines leading space nuclear power technology candidates. Particular emphasis is given the heat-pipe reactor technology currently under development at the Los Alamos National Laboratory. This program is aimed at developing a 10-100 kWe, 7-year lifetime space nuclear power plant. As the demand for space-based power reaches megawatt levels, other nuclear reactor designs including: solid core, fluidized bed, and gaseous core, are considered

  6. Review on the role of nuclear power

    International Nuclear Information System (INIS)

    This report consists of 2 parts. The first part reviews opinions against nuclear power on the aspects: waste disposal, safety and environment, financial; technology, etc. and gives results of a preliminary survey for nuclear power in Vietnam among scientists in 1990. The second part presents advanced reactor concepts and advantages of nuclear power to economy and environment in comparison with other energy sources. (N.H.A). 39 refs, 9 figs, 2 tabs

  7. Getting More Out Of Nuclear Power

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    China’s first nuclear power plant generated 31 billion kw/h electricity from 1991 to 2007 Major repair work on the first phase of the Qinshan nuclear power plant,which began operation in 1991 as China’s first nuclear power plant,was completed on January 13,2008.The overhaul has improved the reliability and safety of the reactors and given the oper- ators experience for running,repairing

  8. Nuclear power: the moral question

    International Nuclear Information System (INIS)

    Reference is made to an article under this title by P. Searby, the UKAEA Secretary, which appeared in the May 1978 issue of Atom and which considered some of the moral and ethical aspects of the current public discussion of nuclear power and, in particular, the position adopted on these by the British Council of Churches. This article had previously appeared in the Church of England publication 'Crucible'. The July issue of 'Crucible' contained a letter from Dr. D. Gosling of the Theology Department of Hull University (UK) commenting on the article together with a reply from Searby. These letters are here produced, together with a letter from Dr. J. Davoll, Director of the U.K. Conservation Society, commenting on Searby's views. (U.K.)

  9. Nuclear power: consolidation or change

    International Nuclear Information System (INIS)

    Currently about 45% of the electricity consumed in Scotland comes from nuclear sources and when the power station at Torness, near Edinburgh, is fully commissioned it will be about 60%. Torness is an AGR type reactor and the Scottish Electricty Board (SSEB) consider that there is no case for changing to a PWR type design for any future reactor built in the UK. The economics of 'a next AGR' and a PWR reactor are compared. The construction times for the Torness programme, the electrical output, station life, load factor, fuel costs and additional support costs are also considered, and compared with costs estimated by the Central Elecricity Generating Board (CEGB) for the proposed Sizewell-B reactor. Exposure of station staff to radiation, safety, public acceptibility and development potential, impact on industry, job creation and export potential are also discussed briefly. (UK)

  10. Steels for nuclear power. I

    International Nuclear Information System (INIS)

    trend regarding new materials for nuclear power installations is briefly indicated. (J.B.)

  11. Nuclear power: necessity or self-interest?

    International Nuclear Information System (INIS)

    In part one of this document a survey is presented, via a number of articles, of the power balances in the Netherlands with respect to nuclear power, the role of various institutions and concerns therein and the consequences of the parliamental decision-making in the Netherlands. In part two the development of nuclear power in the third world is explained by means of some examples, the interests of Western industrial countries in the stimulation of nuclear power in the developing countries and the power structures in these countries which play a role with respect to the atom lobby. Part three starts the discussion on the strategy to be followed by the Anti Nuclear Power movement with three strategies for resistance against the building of new nuclear power plants: via the parliamentary route, by means of direct action (base groups), by combining direct action with broadening and actions against supply industries. 59 refs.; 41 figs.; 6 tabs

  12. Environmental impacts of nuclear power

    International Nuclear Information System (INIS)

    The principal effects of radiation on people are acute radiation sickness, cancer, and genetic effects. Acute radiation sickness results from exposures in excess of 100 rem and can be fatal in a matter of days. There have been about ten deaths in the U.S. from this malady. Cancer induction by radiation has been a much broader threat, the largest single source being the Japanese atomic bomb victims--about 24,000 persons exposed to about 130 rem resulting in over a hundred excess deaths. There is no evidence from human data for genetic defects in offspring from radiation to parents, so the estimate--150 x 10-6 eventual defects per man-rem exposure of the entire population--is based on animal tests. Studies of the survivors of the Japanese bombings have yielded no evidence for additional genetic defects among offspring, a result which assures that the above estimate is not too small; a recent assessment indicates it may be an order-of-magnitude too large. Routine emissions of long half-life radionuclides, power plant accidents, transportation accidents, hazards from plutonium dispersal, theft of plutonium for weapons fabrication, and radioactive waste disposal are ways discussed that members of the public can receive radiation exposure from the nuclear industry. The likelihood of death from these situations is shown to be very small compared to other-than-nuclear situations, namely: automobile driving and riding, smoking cigarettes, the generation of electricity from coal, and coal mining. 82 references

  13. Guidebook on the introduction of nuclear power

    International Nuclear Information System (INIS)

    This ''Guidebook on the Introduction of Nuclear Power'' has been structured into three parts. The first part contains a survey of nuclear power, with the objective of providing general background information to the reader on the present status and future prospects of nuclear power and on the technical and economic aspects of available power reactor types and nuclear fuel cycles. In the second part of the Guidebook, the special aspects and considerations relevant to the introduction of nuclear power in a country are discussed. The subject is subdivided into three main headings: the technical aspects and national requirements; the safety and environmental considerations; and the international aspects of nuclear power. Emphasis is placed on the tasks to be performed within the country introducing nuclear power, on responsibilities that cannot be delegated and on the need for adequate national infrastructures and long-term commitments. Finally, the third part of the Guidebook contains more detailed information and guidance on the planning and preparatory stages of launching a first nuclear power project, including in particular: nuclear power programme planning, siting, feasibility studies, bidding and contracting. Design, construction and operation are covered in a brief overview for the sake of completeness

  14. Benefits and risks of nuclear power

    International Nuclear Information System (INIS)

    Discussion, in a popular form, of issues of interest for an unemotional information of the public on problems of nuclear power: 1) Energy consumption, its assumed growth, and possible ways of supply; 2) the physical fundamental and technical realisation of power generation by nuclear fission; 3) problems of the fuel cycle and possible solutions; 4) the effects of radioactive radiation; 5) the safety of nuclear power plants and the risks of nuclear power as compared to other technical and natural risks. (orig./HP)

  15. Small nuclear power: challenges and solutions

    International Nuclear Information System (INIS)

    Estimates show that, for remote localities difficult of access, nuclear power technologies offer a reasonable alternative to conventional power based on fossil fuels. Still, the deployment of nuclear power sources in the country's northern and eastern territories with hard climatic and complicated social conditions calls for novel designs that satisfy to the requirements beyond the scope of those for the conventional nuclear plant designs. A small nuclear power plant with a water-cooled water-moderated reactor facility, called Unitherm, is one of the most advanced autonomous nuclear heat and power supply designs that satisfies the best to the above requirements, based on the experience in design, manufacture and operation of nuclear propulsion systems. (author)

  16. 77 FR 18271 - Terrestrial Environmental Studies for Nuclear Power Stations

    Science.gov (United States)

    2012-03-27

    ... COMMISSION Terrestrial Environmental Studies for Nuclear Power Stations AGENCY: Nuclear Regulatory Commission... revision to Regulatory Guide (RG) 4.11, ``Terrestrial Environmental Studies for Nuclear Power Stations... environmental studies and analyses supporting licensing decisions for nuclear power reactors. ADDRESSES:...

  17. Advanced nuclear power plants in Korea

    International Nuclear Information System (INIS)

    Full text: Korea Hydro and Nuclear Power Co., Ltd (KHNP) is the largest power company among the six subsidiaries that separated from Korea Electric Power Corporation (KEPCO) in 2001, accounting for approximately 25% of electricity producing facilities, hydro and nuclear combined. KHNP operates 20 nuclear power plants in Kori, Yonggwang, Ulchin and Wolsong site and several hydroelectric power generation facilities, providing approximately 36% of the national power supply. As a major source of electricity generation in Korea, nuclear energy contributes greatly to the stability of national electricity supply and energy security. KHNP's commercial nuclear power plant operation, which started with Kori Unit 1 in 1978, has achieved an average capacity factor more than 90% since 2000 and a high record of 93.4% in 2008. Following the introduction of nuclear power plants in the 1970's, Korea accumulated its nuclear technology in the 1980's, developed OPR 1000(Optimized Power Reactor) and demonstrated advanced level of its nuclear technology capabilities in the 2000's by developing an advanced type reactor, APR 1400(Advanced Power Reactor) which is being constructed at Shin-Kori Unit 3 and 4 for the first time. By 2022, KHNP will construct additional 12 nuclear power plants in order to ensure a stable power supply according to the Government Plan of Long-Term Electricity supply and Demand. 4 units of OPR 1000 reactor model will be commissioned by 2013 and 8 units of APR 1400 are under construction and planned. At the end of 2022, the nuclear capacity will reach 33% share of total generation capacity in Korea and account for 48% of national power generation. (author)

  18. Nuclear Power in the 21st Century

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency helps its Member States to use nuclear technology for a broad range of peaceful purposes, one of the most important of which is generating electricity. The accident at the Fukushima Daiichi nuclear power plant in Japan in March 2011 caused anxiety about nuclear safety throughout the world and raised questions about the future of nuclear power. Two years on, it is clear that the use of nuclear power will continue to grow in the coming decades, although growth will be slower than was anticipated before the accident. Many countries with existing nuclear power programmes plan to expand them. Many new countries, both developed and developing, plan to introduce nuclear power. The factors contributing to this growing interest include increasing global demand for energy, as well as concerns about climate change, volatile fossil fuel prices, and security of energy supply. It will be difficult for the world to achieve the twin goals of ensuring sustainable energy supplies and curbing greenhouse gases without nuclear power. The IAEA helps countries that opt for nuclear power to use it safely and securely. Countries that have decided to phase out nuclear power will have to deal with issues such as plant decommissioning, remediation, and waste management for decades to come. The IAEA also assists in these areas. I am grateful to the Russian Federation for hosting the 2013 International Ministerial Conference on Nuclear Power in the 21st Century in St Petersburg in June. This timely conference provides a valuable opportunity to take stock of nuclear power in the wake of the Fukushima Daiichi accident. A high level of public confidence in the safety of nuclear power is essential for the future of the sector. Much valuable work has been done in the past two years to improve safety. But much remains to be done. It is vitally important that the momentum is maintained and that everything is done to ensure that nuclear power is as safe as humanly

  19. Program increasing of nuclear power plant safeness

    International Nuclear Information System (INIS)

    The results achieved within the project of national task 'Program increasing of nuclear power plant safeness' are presented in the document. The project was aimed to extend and deepen activities relating to safety increase of nuclear power units WWER-440 which play significant part in electricity production in the Slovak Republic. The application of advanced foreign calculating programs and calculation of radionuclide spreading in environment and techniques will influence the increase of extent, quality and international acceptance of safety analysis of nuclear power plant blocks WWER-440 and the risk valuation from operating nuclear power plants. Methodic resources for coping in emergency situation in nuclear energetics will be used for support in decision making in real time during radiation emergency on nuclear plant, region and state level. A long-term strategy in dealing with burnt fuel and radioactive substance formatting during nuclear power plant liquidation particularly with waste which is un acceptable in regional dump, has developed into a theoretical and practical preparation of solvable group for operating the converting centre Bohunice and in inactivating the nuclear power plant A-1. The diagnostic activities in nuclear power plants in the Slovak Republic have been elaborated into a project of norm documents in accordance with international norms for diagnostic systems. Presentation of new technologies and materials for repairs and reconstructions of components and nuclear power plant knots qualify increase in their reliability, safety and life. New objective methods and criterions for valuation and monitoring of the residual life and safety of fixed nuclear power plants. Results of problem solving linked with connecting the blocks of nuclear power plants to frequency regulation in electric network in the Slovak Republic are also presented in the document

  20. Under control. An archeology of nuclear power

    International Nuclear Information System (INIS)

    The volume includes a variety of photographs from different German research and power reactors, simulators, the infrastructure of power plants, working situations in the power plant, including fuel exchange and inspection procedures, the dismantling of decommissioned power nuclear facilities and radioactive waste storage facilities. The second part includes interviews with scientists concerning radiobiology, nuclear waste storage, fuel reprocessing, reactor physics, reactor operation, training in the simulator and risk research.

  1. GENERAL TURBO S. A., active participant to the nuclear and classic power program

    International Nuclear Information System (INIS)

    GENERAL TURBO S. A. is a Romanian company involved in the nuclear program since its inception as a manufacturer and supplier of nuclear equipment for Cernavoda NPP. The GENERAL TURBO S. A continues the cooperation as supplier of the 700 MW turbine-generator group for Unit 2. GENERAL TURBO S. A., the late Power Equipment Plant, split off the IMGB in 1992, was involved in the CANDU power program ever since. On the basis of the Contract of Manufacture and License from General Electric for the 700 MW turbine generator group, GENERAL TURBO S. A. proceeded in assimilating the know-how for turbine and electric generators sub-assemblies and components for the five nuclear power units planned initially for Cernavoda NPP. During 1985-1989 all the sub-assemblies associated to Unit 1 were supplied and some of them for Unit 2 and 3. After 1989 the activity pace at GENERAL TURBO S. A. slowed down but never stopped. At present, GENERAL TURBO S. A. is credited as manufacturer, supplier and entrepreneur for the classical part of Cernavoda NPP Unit 2 (author)

  2. Example of Environmental Monitoring Approaches: Case of the Cernavoda Nuclear Power Plant. Annex IV

    International Nuclear Information System (INIS)

    An example of a monitoring programme is provided and its constituents is taken from the Cernavoda operational monitoring of Canada deuterium-uranium (CANDU) reactor units 1 and 2 (heavy water moderated reactors). Routine Environmental Radiation Monitoring Programme: The purpose of a routine environmental radiation monitoring programme is to provide reliable and accurate data, including statistically valid datasets for significant nuclide and environmental media on an annual basis. The monitoring programme is designed to meet the following objectives under normal nuclear power plant operating conditions: (a) To measure the radionuclide concentrations in environmental media and to assess the increased radiation levels in specified environmental pathways, which might be modified as a result of the Cernavoda nuclear power plant operation; (b) To provide an independent assessment of the effectiveness of the source control, effluent control and monitoring based on measurements in the environment; (c) To validate the models and parameters used to calculate the derived emission limits (DELs); (d) To demonstrate the negligible environmental impact of the Cernavoda nuclear power plant operation and, hence, to contribute to public reassurance; (e) To provide data to aid in the development and evaluation of models and methodologies that adequately describe the movement of radionuclides through the environment

  3. Energy situation in Latin America and nuclear power

    International Nuclear Information System (INIS)

    Greenhouse Gas emission levels. As an example, C02 emission levels in South America were dominated by a 38% increase in Brazil in the period of 1990-2003. Regarding Nuclear Power generation, at present, only Mexico (1.300 MWe), Brazil (1.900 MWe) and Argentina (950 MWe) have NPP's in operation, representing 5%, 3% and 8% of total electricity generation share respectively. Argentina has 1 reactor (750 MWe) under construction, while Brazil has 1 (1.200 MWe) planned. In the near future Argentina is planning to finish its Third Nuclear Power Plant Atucha 2 for 2010, to extend the life of the CANDU type Embalse NPP for another 20 years and start studies for a future fourth plant in 2015

  4. Nuclear power newsletter Vol. 2, no. 1

    International Nuclear Information System (INIS)

    This newsletter presents information on the following topics: 7th meeting of the INPRO Steering Committee; Nuclear Power Plant Operating Performance and Life Cycle Management; Improving Human Performance, Quality and Technical Infrastructure; Co-ordination of International Collaboration for the Development of Innovative Nuclear Technology; Technology Developments and Applications for Advanced Reactors; 1st European Nuclear Assembly

  5. A Basic Guide to Nuclear Power.

    Science.gov (United States)

    Martocci, Barbara; Wilson, Greg

    More than 100 nuclear power plants supply over 17 percent of the electricity in the United States. The basic principles of how nuclear energy works and how it is used to make electricity are explained in this profusely illustrated booklet written for the average sixth grade reader. Discussions include: (1) atomic structure; (2) nuclear fission;…

  6. Methods of estimating nuclear power costs

    International Nuclear Information System (INIS)

    An international panel of experts appointed by the Agency's Director General, after examining costing methods in detail, has recently produced a report entitled 'Introduction to Methods of Estimating Nuclear Power Generating Costs'. The report is intended to help the Agency's Member States, particularly those which are less-developed in nuclear technology, in making a preliminary economic assessment before the construction of a nuclear power station. It gives a description of the different cost items involved in a nuclear power project, some suggestions as to the extrapolation of available data, and an evaluation of different methods of allocating the costs to the units of energy produced

  7. Questions and Answers About Nuclear Power Plants.

    Science.gov (United States)

    Environmental Protection Agency, Washington, DC.

    This pamphlet is designed to answer many of the questions that have arisen about nuclear power plants and the environment. It is organized into a question and answer format, with the questions taken from those most often asked by the public. Topics include regulation of nuclear power sources, potential dangers to people's health, whether nuclear…

  8. Foundations of nuclear power engineering safety

    International Nuclear Information System (INIS)

    Report is devoted to justification of nuclear power industry safety. The maximum improvement of safety may be ensured by accident prevention in one of reactor functional units. One presents four basic physical principles ensuring the limiting safety and economical expedience of nuclear power industry

  9. Nuclear power plants for protecting the atmosphere

    International Nuclear Information System (INIS)

    Some figures are presented comparing date on the CO2 emission and oxygen consumption of nuclear, natural gas fired, advanced coal fired and oil fired power plants, for the same amounts of electricity generated. The data were deduced from the Paks Nuclear Power Plant, Hungary. (R.P.)

  10. Engineering and science education for nuclear power

    International Nuclear Information System (INIS)

    The Guidebook contains detailed information on curricula which would provide the professional technical education qualifications which have been established for nuclear power programme personnel. The core of the Guidebook consists of model curricula in engineering and science, including relevant practical work. Curricula are provided for specialization, undergraduate, and postgraduate programmes in nuclear-oriented mechanical, chemical, electrical, and electronics engineering, as well as nuclear engineering and radiation health physics. Basic nuclear science and engineering laboratory work is presented together with a list of basic experiments and the nuclear equipment needed to perform them. Useful measures for implementing and improving engineering and science education and training capabilities for nuclear power personnel are presented. Valuable information on the national experiences of IAEA Member States in engineering and science education for nuclear power, as well as examples of such education from various Member States, have been included

  11. Nuclear energy technology: theory and practice of commercial nuclear power

    International Nuclear Information System (INIS)

    Reviews Nuclear Energy Technology: Theory and Practice of Commercial Nuclear Power by Ronald Allen Knief, whose contents include an overview of the basic concepts of reactors and the nuclear fuel cycle; the basics of nuclear physics; reactor theory; heat removal; economics; current concerns at the front and back ends of the fuel cycle; design descriptions of domestic and foreign reactor systems; reactor safety and safeguards; Three Mile Island; and a brief overview of the basic concepts of nuclear fusion. Both magnetic and inertial confinement techniques are clearly outlined. Also reviews Nuclear Fuel Management by Harry W. Graves, Jr., consisting of introductory subjects (e.g. front end of fuel cycle); core physics methodology required for fuel depletion calculations; power capability evaluation (analyzes physical parameters that limit potential core power density); and fuel management topics (economics, loading arrangements and core operation strategies)

  12. Sustaining the nuclear power option in Malaysia

    International Nuclear Information System (INIS)

    This paper describes the approach taken to establish the information base required prior to a decision on a nuclear power programme, and the strategy adopted and the rationale behind the development of the basic core expertise on nuclear reactor technology. The effect of a lack of decision on the question of nuclear power generation on efforts to build this core technical expertise is also described. (author)

  13. Nuclear Power: Africa and the Future

    International Nuclear Information System (INIS)

    Africa is a home to around 800 million people. The total population is expected to reach 1.3 billion by 2020. Efficient, clean energy forms are vital to Africa's sustainable development and fight against poverty. Nuclear power is a sustainable, clean, safe and economic way to met the African countries demand for electrical energy and water desalination As of 29 January 2007, there were 435 nuclear power plants in operation around the world. They total about 369 G We of generating capacity and supply about 16% of the world electricity. Of the 435 nuclear power plants in operation, just two are in Africa: Koeberg-1 and Koeberg-2 in South Africa. Both are 900 M We PWRs.There are also 28 new nuclear power plants under construction none in Africa. In this paper, varies factors , which support the attractiveness of nuclear power for African countries are identified and discussed

  14. TOSHIBA CAE system for nuclear power plant

    International Nuclear Information System (INIS)

    TOSHIBA aims to secure safety, increase reliability and improve efficiency through the engineering for nuclear power plant using Computer Aided Engineering (CAE). TOSHIBA CAE system for nuclear power plant consists of numbers of sub-systems which had been integrated centering around the Nuclear Power Plant Engineering Data Base (PDBMS) and covers all stage of engineering for nuclear power plant from project management, design, manufacturing, construction to operating plant service and preventive maintenance as it were 'Plant Life-Cycle CAE System'. In recent years, TOSHIBA has been devoting to extend the system for integrated intelligent CAE system with state-of-the-art computer technologies such as computer graphics and artificial intelligence. This paper shows the outline of CAE system for nuclear power plant in TOSHIBA. (author)

  15. Beyond designed functional margins in CANDU type NPP. Radioactive nuclei assessment in an LOCA type accident

    Directory of Open Access Journals (Sweden)

    Budu Andrei Razvan

    2015-01-01

    Full Text Available European Union's energy roadmap up to year 2050 states that in order to have an efficient and sustainable economy, with minimum or decreasing greenhouse gas emissions, along with use of renewable resources, each constituent state has the option for nuclear energy production as one desirable option. Every scenario considered for tackling climate change issues, along with security of supply positions the nuclear energy as a recommended option, an option that is highly competitive with respect to others. Nuclear energy, along with other renewable power sources are considered to be the main pillars in the energy sector for greenhouse gas emission mitigation at European level. European Union considers that nuclear energy must be treated as a highly recommended option since it can contribute to security of energy supply. Romania showed excellent track-records in operating in a safe and economically sound manner of Cernavoda NPP Units 1&2. Both Units are in top 10 worldwide in terms of capacity factor. Due to Romania's need to ensure the security of electricity supply, to meet the environmental targets and to move to low carbon generation technologies, Cernavoda Units 3&4 Project appears as a must. This Project was started in 2010 and it is expected to have the Units running by 2025. Cost effective and safety operation of a Nuclear Power Plant is made taking into consideration functional limits of its equipment. As common practice, every nuclear reactor type (technology used is tested according to the worse credible accident or equipment failure that can occur. For CANDU type reactor, this is a Loss of Cooling Accident (LOCA. In a LOCA type accident in a CANDU NPP, using RELAP/SCDAP code for fuel bundle damage assessment the radioactive nuclei are to be quantified. Recently, CANDU type NPP accidents are studied using the RELAP/SCDAP code only. The code formerly developed for PWR type reactors was adapted for the CANDU geometry and can assess the

  16. U.S. Forward Operating Base Applications of Nuclear Power

    International Nuclear Information System (INIS)

    This paper provides a high level overview of current nuclear power technology and the potential use of nuclear power at military bases. The size, power ranges, and applicability of nuclear power units for military base power are reviewed. Previous and current reactor projects are described to further define the potential for nuclear power for military power.

  17. U.S. Forward Operating Base Applications of Nuclear Power

    Energy Technology Data Exchange (ETDEWEB)

    Griffith, George W. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-01-01

    This paper provides a high level overview of current nuclear power technology and the potential use of nuclear power at military bases. The size, power ranges, and applicability of nuclear power units for military base power are reviewed. Previous and current reactor projects are described to further define the potential for nuclear power for military power.

  18. Modelling of the tritium dispersion from postulated accidental release of nuclear power plants; Modelagem da dispersao de tritio a partir de liberacoes acidentais postuladas de centrais nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Soares, Abner Duarte; Simoes Filho, Francisco Fernando Lamego; Cunha, Tatiana Santos da [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Aguiar, Andre Silva de; Lapa, Celso Marcelo Franklin, E-mail: asoares@cnen.gov.b, E-mail: flamego@ien.gov.b, E-mail: lapa@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2011-07-01

    This study has the aim to assess the impact of accidental release of tritium postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models to simulation of tritium dispersion caused by an accident in a Candu reactor located in the ongoing Angra 3 site. The Candu reactor is one that uses heavy water (D{sub 2}O) as moderator and coolant of the core. It was postulated, then, the LOCA accident (without fusion), where was lost 66 m3 of soda almost instantaneously. This inventory contained 35 P Bq and was released a load of 9.7 TBq/s in liquid form near the Itaorna beach, Angra dos Reis - RJ. The models mentioned above were applied in two scenarios (plant stopped or operating) and showed a tritium plume with specific activities larger than the reference level for seawater (1.1 MBq/m{sup 3}) during the first 14 days after the accident. (author)

  19. Maintenance of nuclear power plant

    International Nuclear Information System (INIS)

    Maintenance action of nuclear power plant (NPP) was described. Maintenance of NPP aimed at assurance of required function of NPP's equipment so as to prevent release of radioactive materials into the environment as well as attainment of stable operation of NPP. Philosophy of NPP safety was based on defense-in-depth or multiple barriers requiring specified function for the equipment. Preventive maintenance was essential to NPP's equipment and the scope of maintenance was decided on priority with adequate method and frequency of inspection. Most inspection was conducted during periodic inspection at outage. Repair or improvement works were performed if needed. Periodic inspection period was very long and then capacity factor of NPP was low in Japan compared with foreign data although frequency of unscheduled shutdown was very low. Introduction of reability- centered maintenance was requested based on past experiences of overhaul inspection. Technical evaluation of aged NPP had been conducted on aging phenomena and promotion of advanced maintenance was more needed. (T. Tanaka)

  20. Citizens contra nuclear power plants

    International Nuclear Information System (INIS)

    Is Wyhl the beginning of a new citizens' movement against official policies concerning atomic energy or is it the end of citizens' initiatives of latter years. Did democracy pass its test in Wyhl, or was the state's authority undermined. The danger of atomic energy was not the only concern of the citizens of the Rhine valley who demonstrated against the planned nuclear power plant, but also the quality of industrial and energy planning in which the democratic foundations have to be safeguarded. In the meantime, the doubts increase that this source of energy is of a not dangerous nature, and the myth of supposedly cheap atomic energy has been scattered. The dangers in connection with waste transport and storage were made public beyond the boundaries of the places in question, in particular as a result of the demonstrations. The publication documents the course of the demonstration and the site occupation from the beginning of Febuary 1975 onwards. The occupation still continued when the booklet was published despite the decision of the Administrative Court in Freiburg at the end of March (prohibition of commencement of building until the verdict on the principal suit against the overall project has been reached, the final decision to be made by the Higher Administrative Court in Mannheim). The author aims at describing the new quality of citizens' commitments in this booklet. (orig./LN)

  1. Country Nuclear Power Profiles - 2010 Edition

    International Nuclear Information System (INIS)

    The Country Nuclear Power Profiles compiles background information on the status and development of nuclear power programs in Member States. It consists of organizational and industrial aspects of nuclear power programs and provides information about the relevant legislative, regulatory, and international framework in each country. Its descriptive and statistical overview of the overall economic, energy, and electricity situation in each country, and its nuclear power framework is intended to serve as an integrated source of key background information about nuclear power programs in the world. The preparation of Country Nuclear Power Profiles (CNPP) was initiated in 1990s. It responded to a need for a database and a technical publication containing a description of the energy and economic situation, the energy and the electricity sector, and the primary organizations involved in nuclear power in IAEA Member States. This is the 2010 edition issued on CD-ROM and Web pages. It updates the country information for 48 countries. The CNPP is updated based on information voluntarily provided by participating IAEA Member States. Participants include the 29 countries that have operating nuclear power plants, as well as 19 countries having past or planned nuclear power programmes (Bangladesh, Belarus, Chile, Egypt, Ghana, Indonesia, the Islamic Republic of Iran, Italy, Jordan, Kazakhstan, Lithuania, Morocco, Nigeria, Philippines, Poland, Thailand, Tunisia, Turkey and Vietnam). For the 2010 edition, 24 countries provided updated or new profiles. For the other countries, the IAEA updated the profile statistical tables on nuclear power, energy development, and economic indicators based on information from IAEA and World Bank databases. The CNPP reports have been prepared by each Member State in accordance with the IAEA format. The IAEA is not responsible for the content of these reports

  2. Country Nuclear Power Profiles - 2011 Edition

    International Nuclear Information System (INIS)

    The Country Nuclear Power Profiles compiles background information on the status and development of nuclear power programs in Member States. It consists of organizational and industrial aspects of nuclear power programs and provides information about the relevant legislative, regulatory, and international framework in each country. Its descriptive and statistical overview of the overall economic, energy, and electricity situation in each country, and its nuclear power framework is intended to serve as an integrated source of key background information about nuclear power programs in the world. The preparation of Country Nuclear Power Profiles (CNPP) was initiated in 1990s. It responded to a need for a database and a technical publication containing a description of the energy and economic situation, the energy and the electricity sector, and the primary organizations involved in nuclear power in IAEA Member States. This is the 2011 edition issued on CD-ROM and Web pages. It updates the country information for 50 countries. The CNPP is updated based on information voluntarily provided by participating IAEA Member States. Participants include the 29 countries that have operating nuclear power plants, as well as 21 countries having past or planned nuclear power programmes (Bangladesh, Belarus, Chile, Egypt, Ghana, Indonesia, the Islamic Republic of Iran, Italy, Jordan, Kazakhstan, Kuwait, Lithuania, Morocco, Nigeria, Philippines, Poland, Syrian Arab Republic, Thailand, Tunisia, Turkey and Vietnam). For the 2011 edition, 23 countries provided updated or new profiles. For the other countries, the IAEA updated the profile statistical tables on nuclear power, energy development, and economic indicators based on information from IAEA and World Bank databases.

  3. Applications of power from Temelin nuclear power plant

    International Nuclear Information System (INIS)

    The proceedings contain 10 papers of which 9 fall under the INIS scope. They all concern the intentions and possibilities of using heat from nuclear power plants, especially from the Temelin power plant. Waste heat will be used for district heating of adjacent conurbations and for agricultural purposes. Various projects are presented using heat from nuclear power plants, such as greenhouse heating, soil heating, cultivation of algae and fish in warmed-up water. The existing experience is described with the use of heat from the Bohunice nuclear power plant. (M.D.). 15 figs., 6 tabs., 17 refs

  4. Methodology Improvement of Reactor Physics Codes for CANDU Channels Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Myung Hyun; Choi, Geun Suk; Win, Naing; Aung, Tharndaing; Baek, Min Ho; Lim, Jae Yong [Kyunghee University, Seoul (Korea, Republic of)

    2010-04-15

    As the operational time increase, pressure tubes and calandria tubes in CANDU core encounter inevitably a geometrical deformation along the tube length. A pressure tube may be sagged downward within a calandria tube by creep from irradiation. This event can bring about a problem that is serious in integrity of pressure tube. A measurement of deflection state of in-service pressure tube is, therefore, very important for the safety of CANDU reactor. In this paper, evaluation of impacts on nuclear characteristic due to fuel channel deformation were aimed in order to improve nuclear design tools for concerning the local effects from abnormal deformations. It was known that sagged pressure tube can cause the eccentric configuration of fuel bundles in pressure tube by O.6cm maximum. In this case, adverse pin power distribution and reactivity balance can affect reactor safety under normal and accidental condition. Thermal and radiation-induced creep in pressure tube would expand a tube size. It was known that maximum expansion may be 5% in volume. In this case, more coolant make more moderation in the deformed channel resulting in the increase of reactivity. Sagging of pressure tube did not cause considerable change in K-inf values. However, expansion of the pressure tube made relatively large change in K-inf. Modeling of eccentric and enlarged configuration is not easy in preparation of input geometry at both HELlOS and MCNP. On the other hand, there is no way to consider this deformation in one-dimensional homogenization tool such as WIMS code. The way of handling this deformation was suggested as the correction method of expansion effect by adjusting the number density of coolant. The number density of heavy water coolant was set to be increased as the rate of expansion increase. This correction was done in the intact channel without changing geometry. It was found that this correction was very effective in the prediction of K-inf values. In this study, further

  5. Liberation of electric power and nuclear power generation

    International Nuclear Information System (INIS)

    In Japan, as the Rule on Electric Business was revised after an interval of 35 years in 1995, and a competitive bid on new electric source was adopted after 1996 fiscal year, investigation on further competition introduction to electric power market was begun by establishment of the Basic Group of the Electric Business Council in 1997. By a report proposed on January, 1999 by the Group, the Rule was revised again on March, 1999 to start a partial liberation or retail of the electric power from March, 2000. From a viewpoint of energy security and for solution of global environmental problem in Japan it has been decided to positively promote nuclear power in future. Therefore, it is necessary to investigate how the competition introduction affects to development of nuclear power generation and what is a market liberation model capable of harmonizing with the development on liberation of electric power market. Here was elucidated on effect of the introduction on previous and future nuclear power generation, after introducing new aspects of nuclear power problems and investigating characteristic points and investment risks specific to the nuclear power generation. And, by investigating some possibilities to development of nuclear power generation under liberation models of each market, an implication was shown on how to be future liberation on electric power market in Japan. (G.K.)

  6. Government support for the export of nuclear power plants after Fukushima Daiichi nuclear power accident

    International Nuclear Information System (INIS)

    Depending on the surge of a global evaluation for the nuclear power generation, our country strengthened government support for the export of nuclear power plants. However, under the influence of a Fukushima Daiichi Nuclear Power Plant accident, the internal and external situation surrounding nuclear power has been changing. Should our country continue government support for the nuclear power plant export according to this? This report outlined the world trend around nuclear power before the Fukushima accident, surveyed merits and problems of the nuclear power plant export, and introduced what kind of export aid package the government took. And then, it showed the situation change after the Fukushima accident and the point at issue on thinking about the way of the government support. The Fukushima accident raised concern for the safety of the nuclear power plant and might have a big influence on the construction trend of the world nuclear power plant in the future. The criticism to conventional government support for the nuclear power plant export has risen, too. However, the role of government support for the nuclear power plant export was not the problem that should be discussed only by the side of safety and the economy. The nuclear power plant export carried an international contribution, reinforcement of the thickness of a technique and the talented person of the nuclear power industry, and a role such as the contribution to economic growth in medium-and-long term energy policy and nuclear energy policy until now. It may be said that we were asked how was placed nuclear power plant export again while these policies were reviewed after the Fukushima accident. (T. Tanaka)

  7. Building infrastructure for new nuclear power programmes

    International Nuclear Information System (INIS)

    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

  8. Nuclear Power Sources for Space Systems

    Science.gov (United States)

    Kukharkin, N. E.; Ponomarev-Stepnoi, N. N.; Usov, V. A.

    This chapter contains the information about nuclear power sources for space systems. Reactor nuclear sources are considered that use the energy of heavy nuclei fission generated by controlled chain fission reaction, as well as the isotope ones producing heat due to the energy of nuclei radioactive decay. Power of reactor nuclear sources is determined by the rate of heavy nuclei fission that may be controlled within a wide range from the zero up to the nominal one. Thermal power of isotope sources cannot be controlled. It is determined by the type and quantity of isotopes and decreases in time due to their radioactive decay. Both, in the reactor sources and in the isotope ones, nuclear power is converted into the thermal one that may be consumed for the coolant heating to produce thrust (Nuclear Power Propulsion System, NPPS) or may be converted into electricity (Nuclear Power Source, NPS) dynamically (a turbine generator) or statically (thermoelectric or thermionic converters). Electric power is supplied to the airborne equipment or is used to produce thrust in electric (ionic, plasma) low-thrust engines. A brief description is presented of the different nuclear systems with reactor and isotopic power sources implemented in Russia and the USA. The information is also given about isotopic sources for the ground-based application, mainly for navigation systems.

  9. Country Nuclear Power Profiles - 2007 Edition

    International Nuclear Information System (INIS)

    The preparation of Country Nuclear Power Profiles (CNPP) was initiated within the framework of the IAEA's programme on assessment and feedback of nuclear power plant performance. It responded to a need for a database and a technical publication containing a description of the energy and economic situation, the energy and the electricity sector, and the primary organizations involved in nuclear power in IAEA Member States. It covers background information on the status and development of nuclear power programmes in countries having nuclear plants in operation and/or plants under construction. This is the 2007 edition issued on CD-ROM and Web pages. It updates the country information, in general, to the end of 2006 for 39 countries. The CNPP is updated based on information voluntarily provided by participating IAEA Member States. Participants include the 30 countries that have operating nuclear power plants, as well as nine countries having past or planned nuclear power programmes (Bangladesh, Egypt, Indonesia, the Islamic Republic of Iran, Italy, Kazakhstan, Poland, Turkey, and Vietnam). For the 2007 edition, 21 countries provided information to the IAEA to update their profiles. For the 18 other countries, the IAEA updated the profile statistical tables on nuclear power, energy development, and economic indicators based on information from IAEA and World Bank databases. These 18 countries are Argentina, Belgium, Bulgaria, Canada, China, Egypt, Finland, Indonesia, Japan, Mexico, Netherlands, Poland, Romania, Slovenia, South Africa, Spain, Switzerland, and Ukraine. Overall, the CNPP reviews the organizational and industrial aspects of nuclear power programmes in participating countries, and provides information about the relevant legislative, regulatory and international frameworks in each country. It compiles the current issues in the new environment within which the electricity and nuclear sector operates, i.e. energy policy, and privatization and deregulation in

  10. Ludwig: A Training Simulator of the Safety Operation of a CANDU Reactor

    Directory of Open Access Journals (Sweden)

    Gustavo Boroni

    2011-01-01

    Full Text Available This paper presents the application Ludwig designed to train operators of a CANDU Nuclear Power Plant (NPP by means of a computer control panel that simulates the response of the evolution of the physical variables of the plant under normal transients. The model includes a close set of equations representing the principal components of a CANDU NPP plant, a nodalized primary circuit, core, pressurizer, and steam generators. The design of the application was performed using the object-oriented programming paradigm, incorporating an event-driven process to reflect the action of the human operators and the automatic control system. A comprehensive set of online graphical displays are provided giving an in-depth understanding of transient neutronic and thermal hydraulic response of the power plant. The model was validated against data from a real transient occurring in the Argentine NPP Embalse Río Tercero, showing good agreement. However, it should be stressed that the aim of the simulator is in the training of operators and engineering students.

  11. Nuclear power newsletter Vol. 4, no. 1, March 2007

    International Nuclear Information System (INIS)

    The topics presented in this newsletter are: Workshop on Issues for the Introduction of Nuclear Power; Message from the Director of the Division of Nuclear Power: The Nuclear Energy Series documents: Structure and the process; Nuclear power plant operation; Strengthening nuclear power infrastructures; Technology developments and applications for advanced reactors; New staff in Nuclear Power Division; Current vacancy notice for professional posts in Nuclear Power Division; Meetings in 2007

  12. 78 FR 61400 - Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station, Issuance of Director's Decision

    Science.gov (United States)

    2013-10-03

    ... COMMISSION Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station, Issuance of Director's Decision... and ML102210411, respectively), concerns the operation of Pilgrim Nuclear Power Station (Pilgrim... (non- EQ) inaccessible cables at Pilgrim Nuclear Power Station (Pilgrim) are capable of...

  13. Nuclear power planning study for Saudi Arabia

    International Nuclear Information System (INIS)

    The prospects of application of nuclear energy for production of electricity and desalinated water in the Kingdom are evaluated. General economic development of the country and data on reserves, production and consumption of oil and natural gas are reviewed. Electrical power system is described with data on production and consumption. Estimates of future power demand are made using Aoki method. Costs of production of electricity from 600 MW, 900 MW and 1200 MW nuclear and oil-fired power plants are calculated along with the costs of production of desalinated water from dual purpose nuclear and oil-fired plants. The economic analysis indicates that the cost of production of electricity and desalinated water are in general cheaper from the nuclear power plants. Suggests consideration of the use of nuclear energy for production of both electricity and desalinated water from 1415 H. Further detailed studies and prepartory organizational steps in this direction are outlined. 38 Ref

  14. Public opinion factors regarding nuclear power

    International Nuclear Information System (INIS)

    This paper is an effort to identify, as comprehensively as possible, public concerns about nuclear power, and to assess, where possible, the relative importance of these concerns as they relate to government regulation of and policy towards nuclear power. It is based on some two dozen in-depth interviews with key communicators representing the nuclear power industry, the environmental community, and government, as well as on the parallel efforts in our research project: (1) review of federal court case law, (2) a selective examination of the Nuclear Regulatory Commission (NRC) administrative process, and (3) the preceding George Mason University research project in this series. The paper synthesizes our findings about public attitudes towards nuclear power as expressed through federal court case law, NRC administrative law, public opinion surveys, and direct personal interviews. In so doing, we describe the public opinion environment in which the nuclear regulatory process must operate. Our premise is that public opinion ultimately underlies the approaches government agencies take towards regulating nuclear power, and that, to the degree that the nuclear power industry's practices are aligned with public opinion, a more favorable regulatory climate is possible

  15. Nuclear power and the logic of globalization

    International Nuclear Information System (INIS)

    The article discusses effects and results of globalization for nuclear power and other options of electricity generation. According to the present state of knowledge, it will not be possible to meet the growing worldwide energy requirement with fossil and renewable energy sources only - also because of the CO2 problem. Consequently, nuclear power will remain an important alternative. On an international scale, this applies in particular to large countries, such as China and India, as large national economies particularly benefit from the economies of scale offered by nuclear power. This could well make Chinese nuclear technology a product for the world market. Thinking along these lines has not really gained ground in Germany, as nuclear power, being a technology requiring considerably capital outlay, is considered unsuitable for southern countries. It is an illusion to believe that Germany's opting out of the use of nuclear power could be a model to others. Instead, we are faced by the ethical question of how we can help to minimize the accident risks of nuclear facilities worldwide. We can do so only by maintaining the use of nuclear power and exporting our level of safety, for the risks will not become any smaller merely as a result of our opting out. (orig.)

  16. Public opinion factors regarding nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Benson, B.

    1991-12-31

    This paper is an effort to identify, as comprehensively as possible, public concerns about nuclear power, and to assess, where possible, the relative importance of these concerns as they relate to government regulation of and policy towards nuclear power. It is based on some two dozen in-depth interviews with key communicators representing the nuclear power industry, the environmental community, and government, as well as on the parallel efforts in our research project: (1) review of federal court case law, (2) a selective examination of the Nuclear Regulatory Commission (NRC) administrative process, and (3) the preceding George Mason University research project in this series. The paper synthesizes our findings about public attitudes towards nuclear power as expressed through federal court case law, NRC administrative law, public opinion surveys, and direct personal interviews. In so doing, we describe the public opinion environment in which the nuclear regulatory process must operate. Our premise is that public opinion ultimately underlies the approaches government agencies take towards regulating nuclear power, and that, to the degree that the nuclear power industry`s practices are aligned with public opinion, a more favorable regulatory climate is possible.

  17. Public opinion factors regarding nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Benson, B.

    1991-01-01

    This paper is an effort to identify, as comprehensively as possible, public concerns about nuclear power, and to assess, where possible, the relative importance of these concerns as they relate to government regulation of and policy towards nuclear power. It is based on some two dozen in-depth interviews with key communicators representing the nuclear power industry, the environmental community, and government, as well as on the parallel efforts in our research project: (1) review of federal court case law, (2) a selective examination of the Nuclear Regulatory Commission (NRC) administrative process, and (3) the preceding George Mason University research project in this series. The paper synthesizes our findings about public attitudes towards nuclear power as expressed through federal court case law, NRC administrative law, public opinion surveys, and direct personal interviews. In so doing, we describe the public opinion environment in which the nuclear regulatory process must operate. Our premise is that public opinion ultimately underlies the approaches government agencies take towards regulating nuclear power, and that, to the degree that the nuclear power industry's practices are aligned with public opinion, a more favorable regulatory climate is possible.

  18. Innovation design of power nuclear systems

    International Nuclear Information System (INIS)

    Efforts to ensure design and manufacturing innovations in the sphere of power reactors have reached the level of the large-scale inter-state cooperation. Some nuclear power systems are under evaluation in terms of the IAEA International Project dealing with the innovative power reactors and fuel cycles. In Japan the efforts to design fast sodium low-power reactor to serve as a power source in high-cost power regions and in developing power low-consuming countries are in progress. In South Korea the efforts to design a high-power reactor, that is, the APR1400 reactor based on the KSNP Korean available standard plant are in progress

  19. Climate Change and Nuclear Power 2013

    International Nuclear Information System (INIS)

    Climate change is one of the most important issues facing the world today. Nuclear power can make an important contribution to reducing greenhouse gas emissions while delivering energy in the increasingly large quantities needed for global socioeconomic development. Nuclear power plants produce virtually no greenhouse gas emissions or air pollutants during their operation and only very low emissions over their entire life cycle. The accident at the Fukushima Daiichi nuclear power plant of March 2011 caused deep public anxiety and raised fundamental questions about the future of nuclear energy throughout the world. It was a wake-up call for everyone involved in nuclear power - a reminder that safety can never be taken for granted. Yet, in the wake of the accident, it is clear that nuclear energy will remain an important option for many countries. Its advantages in terms of climate change mitigation are an important reason why many countries intend to introduce nuclear power in the coming decades, or to expand existing programmes. All countries have the right to use nuclear technology for peaceful purposes, as well as the responsibility to do so safely and securely. The International Atomic Energy Agency provides assistance and information to countries that wish to introduce nuclear power. It also provides information for broader audiences engaged in energy, environmental and economic policy making. This report has been substantially revised, updated and extended since the 2012 edition. It summarizes the potential role of nuclear power in mitigating global climate change and its contribution to other development and environmental challenges. The report also examines broader issues relevant to the climate change-nuclear energy nexus, such as cost, safety, waste management and non-proliferation. New developments in resource supply, innovative reactor technologies and related fuel cycles are also presented

  20. Nuclear power. Protest and violence

    International Nuclear Information System (INIS)

    Following an introductory survey of the anti-nuclear movement, its activities in the following countries are discussed in detail: USA, West Germany, France, United Kingdom. Motives, methods and organization - including international organization - are considered. The interaction of environmental and political motives, and the contrast between peaceful and violent approaches are analyzed. Appendices cover the following: brief description of the nuclear fuel cycle; chronology of 40 anti-nuclear incidents in the above and other countries between February 1975 and September 1978; brief statement on the 'neutron bomb' controversy. In the course of the document reference is made to anti-nuclear activities in 18 countries in all. (U.K.)