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Sample records for cernavoda npp unit

  1. Integrated maintenance program at Cernavoda NPP - Unit 1

    International Nuclear Information System (INIS)

    The purpose of this paper is to provide the information related to the integrated maintenance program in the Cernavoda Candu plant. The integrated maintenance strategy is the one to provide guidance that can be used to enhance an existing maintenance program by improving the responsibility for plant components and systems maintenance while optimizing resources. The implementation of this guidance will help ensure that tasks for important components are applicable for the types of expected failures and are effective in controlling the failures. This document is showing how the maintenance program is controlled, integrated, enhanced and optimized in Cernavoda NPP. The content of the paper includes: A. The general description of the maintenance program including the main phases as follows: I. MAINTENANCE STRATEGY; II. MAINTENANCE PROGRAMS; Ill. MAINTENANCE PLANS; IV. INTEGRATED MAINTENANCE; V. MAINTENANCE EXECUTION; VI. MAINTENANCE OPTIMIZATION. B. Maintenance Program Objectives. C. Maintenance Performance Indicators. The paper also presents how technical assessment programs can be optimized and interfaced with the executions programs. It also includes a detailed one page description of the strategy plan (appendix one). The final conclusion of this paper is that only a complex comprehensive and integrated maintenance program as it was started and will be applied in NPP Cernavoda is assuring a safe and reliable production for the unit. (author)

  2. Risk management solutions for Cernavoda Unit #2 NPP completion

    International Nuclear Information System (INIS)

    The greatest risk facing today's electric utilities is change. Utility risk managers are being challenged to address the changes of deregulation, new technologies and changing work force. The utilities must be more aware of where all its costs are located to face with the challenge of competition, forcing them to respond with lower prices and innovative services. For completion of large projects, like Cernavoda NPP, Unit 2, the utilities are facing also with certain specific risks: politic, economic, social. The natural perils or machinery breakdown are common risks for operation as well as for construction-commissioning projects. Beyond the explicit challenges associated with the completion of a nuclear power plant in a transition economy environment, the utilities are facing with new risk factors such as professional liability, political risk, product warranty and liability, international exposure, etc. Changes in other governmental policies are also affecting large projects, mentioning healthcare, workplace safety, workers' compensation, environmental clean up, etc.(author)

  3. Reviewing NPP Cernavoda site evaluation

    International Nuclear Information System (INIS)

    The Nuclear Power Plant Cernavoda site was selected before the IAEA Safety Guide issue, during NUSS program development. The Romanian codes issued in 1976, as a regulatory body requirements, establish general criteria regarding safety concept and concentration limits of different radionuclides in air and water body and limits of individual or collective dose. In 1979 the Romanian Authority signed the contract with AECL to improve the CANDU-600 concept in the nuclear development programme and erection of 4 units on the Cernavoda site. The construction work started in 1980. In 1983 the former Romanian Government decided to build up another unit (finally it will be 5 units) on Cernavoda site, so the total gross electrical power we have 3,500 MW. The Canadian safety and quality standards or requirements was harmonized with the Romanian rules and regulations. Many studies, investigations and research were done to qualify the site and have a good knowledge about its characteristics coupled with CANDU-600 performance. The new evolution of the site was performed by Romanian technical staff in CITON and the final conclusions were favourable for erection and operation of NPP. The first unit of Cernavoda NPP is on operation and now the efforts are concentrated to continue the works for the unit 2. The paper underlines how the Cernavoda site characteristics meet IAEA Code of Practice and Safety Guides issued until now. (author)

  4. Cernavoda NPP Unit 2 and Romanian nuclear industry

    International Nuclear Information System (INIS)

    On 18 May 2001, in the presence of Mr. Adrian Nastase, the Prime-Minister of Romania, the presidents of AECL, ANSALDO and Director General of SN Nuclearelectrica, the commercial and management contract for completing the Cernavoda NPP Unit 2 was signed. This document stipulates the goal and the partners' commitments, leadership organization, the SN Nuclearelectrica's control of the Budget, costs for the technical assistance (around 180 specialists from abroad), as well as the costs of equipment supplied from Canada and Italy. Services and equipment supplied by Canada and Italy amounts up to around USD 300 millions. Efforts are currently undertaken to obtain a loan of USD 300 millions from EURATOM, beginning from 2003. An auction process, implying around 10 companies, is underway and by the completion of the process, in February 2002, the practical delivery of equipment will start. The so-far invested capital amounts around USD 650 millions while the capital funds remaining to be invested amounts up to about USD 689 millions. From the latter figure, around USD 100 millions represent the costs for heavy water and the initial nuclear fuel charging. The personnel dynamics is presented as well as problems relating with recruitment and salary policy. Romanian nuclear industry is engaged for supply of a series of important components. General Turbo SA, supplied already components of some tens USD millions for the turbogenerator complex. PETROTUB company from Roman, Romania supplied already one thousand tones of non-nuclear carbon steel tubing valued at about USD 300 millions. ARIO, Bistrita, Romania, has signed contracts valued at about USD 400,000 for non-nuclear reinforcing materials. Other companies like AVERSA SA and Ventilatorul SA supplied reliable equipment for Unit 1 and will continue to do the same for Unit 2. Contracts of over one million USD are carried on with VULCAN for carbon steel fittings and with TITAN Nuclear Equipment for components of the fueling

  5. Cernavoda NPP Unit 2: 'A year of progress'

    International Nuclear Information System (INIS)

    available for installation. An unfortunate incident in shipping of the generator stator from the USA at the end of 2003 meant a delay in the delivery by 10 months. Through a major team effort by all concerned the unit was rebuilt and delivery successfully effected in November. All of the major obstacles have been overcome and the project is currently on schedule. The project has now completed 482 days of work without a lost time accident which is notable considering that over 4 million man-hours were worked during this period. AECL Canada and ANSALDO Energia have worked hard to support the project. The foreign engineering scope of work is nearing completion and all contract scope purchase orders have been placed with most deliveries now completed. Work still continues on procurement to support the commissioning of the plant systems. The success to date is attributed partly to providing a strong Management Team consisting of personnel who bring experience from similar projects in China, Italy and of course Cernavoda Unit 1. The client and Romanian ministry of trade and industry are fully supportive of the project and working as a team with the MT is a key element to meeting the challenges that exist on a large project such as the Cernavoda 2 Plant and has been a key factor in the success to date. The coming year will be no less demanding, by the end of 2005 virtually all systems will be transferred from the construction to the commissioning group. The key issue that will have to be addressed by the project will be acquiring sufficient site construction contractor's manpower to meet the demands imposed by the aggressive systems turn over schedule and delivery of large amounts of materials. Commissioning will also have a major challenge to keep up with some 25 systems being turned over on a monthly basis. Staffing levels for Construction Division will be reduced while a similar increase will occur in Commissioning. With the support of the client SNN the Management Team at

  6. Appendix II: Training of personnel for the commissioning of Cernavoda NPP Unit 2 (Romania)

    International Nuclear Information System (INIS)

    Nuclear power generation is a reliable source of energy for Romania and an important contributor to the national electricity supply. Romania has one nuclear power plant, Cernavoda, which operates one CANDU 6 reactor, 707 MWe, designed by Atomic Energy of Canada Ltd (AECL). It provides about 10% of the total country electricity generation. The state-owned company responsible for the production and supply of energy from Cernavoda NPP, as well as for its development, is Societatea Nationala 'Nuclearelectrica'. The plant was designed to have five similar units. The studies performed for the plant, prior to the construction's start, established feasible technical solutions for all problems related to a 5- units plant, including the environmental impact, which was determined to be entirely acceptable. Construction of the first unit started in 1980, and units 2-5 in 1982. The pressing problems encountered during construction of Unit 1 (import restrictions, delays etc.) restrained the progress at Unit 2. Starting in 1990, the work on Cernavoda site was focused on Unit 1. Construction at the other units was suspended; during many years; only preservation works were carried-out. The re-start of work at Unit 2 began in 1995, under the management of the AECLANSALDO Consortium. Some work to further construction progress was carried-out (e.g. installation of the fuel channels) and a thorough assessment was performed of the condition of the equipment procured for Unit 2 and stored on site, or already installed. The absence of a clear contractual framework and the lack of resources hindered significant advances in the construction of Unit 2. Recently, estimates in Romania are that annual electricity production will become insufficient unless Unit 2 of Cernavoda NPP is commissioned. In this environment and considering the relatively low cost of the electricity produced at Unit 1 of Cernavoda NPP versus the energy cost in the conventional thermal stations, the Romanian Government

  7. The International Cooperation and Partnership, Keystones for Engineering and Procurement for Cernavoda NPP Unit 2

    Energy Technology Data Exchange (ETDEWEB)

    Stiopol, Mihaela; Vatamanu, Mariana; Bucur, Cristina [Nuclearelectrica SA, 65 Polona Street, 010494 Bucharest (Romania)

    2008-07-01

    Romania is starting the second year as a MS of the EU, and is crossing a crucial year in implementing the national energy strategy. The EC documents from last year, as an energy policy for Europe or the nuclear illustrative programme provided the guidelines for the new Romanian energy strategy, based on the principles of security of supply, competitiveness, environment protection and optimization of the use of domestic natural resources. In the line with the right of each European state to choose the proper energy mix, in order to face the predicted deployment of natural gas and oil resources, Romania has to redirect its strategy to improve the energy efficiency, develop the renewable energies and to extend the use of nuclear. Romania has developed the national infrastructure for implementation, management and supervision of the nuclear power projects, including the environment protection aspects. The Ministry of Economy and Finance is responsible for the national strategy in the energy field, including NPP projects implementation and operation. Other important actors are the Ministry of the Environment, the Nuclear Agency, the Nuclear Regulatory Body - CNCAN and the National Agency for Radioactive Waste - ANDRAD. For Romania, the nuclear energy represents an obvious reality, strongly proved by good performances registered by Cernavoda NPP Unit 1 during over 12 years of commercial operation: High quality of the nuclear fuel produced by Nuclear Fuel Plant in Pitesti - as demonstrated by the 7 consecutive years of operation of Cernavoda Unit 1 without detecting a single fuel bundle with nuclear defect, the very good quality of heavy water produced in Romania based on Romanian concept and technology and, by the most recently success of the Romanian nuclear industry: commissioning of the second Unit at Cernavoda NPP on October 5. 2007. All those represent achievements of entire Romanian society for which the education, research, design engineering and operation of

  8. Public debates - key issue in the environmental licensing process for the completion of the Cernavoda NPP Unit 2

    International Nuclear Information System (INIS)

    SN 'NUCLEARELECTRICA' S.A., the owner of Cernavoda NPP, organized, in 2001, several public consultations related to environmental impact of the completion of the Cernavoda NPP Unit 2, as required by the Romanian environmental law, part of project approval. Public consultations on the environmental assessment for the completion of the Cernavoda NPP - Unit 2 took place in 2001 between August 15 and September 21 in accordance with the provisions of Law No. 137/95 and Order No. 125/96. Romanian environmental legislation, harmonization of national environmental legislation with European Union, Romanian legislative requirements, information distributed to the public, issues raised and follow-up, they all are topics highlighted by this paper and they are addressing the environmental licensing process of the Cernavoda 2 NPP. The public consultation process described fulfils all the Romanian requirements for carrying out meaningful consultation with its relevant shareholders. The process also satisfies EDC (Export Development Corporation - Canada) requirements for public consultation and disclosure with relevant shareholders in the host country. SNN is fully committed to consulting as necessary with relevant shareholders throughout the construction and operation of the Project. Concerns of the public have been taken into account with the operations of Unit 1 and will continue to be addressed during the Unit 2 Project

  9. Review of site data for Cernavoda NPP

    International Nuclear Information System (INIS)

    The review of CANDU-PHWR-700 standard design according to the geological and seismic conditions of Cernavoda NPP site was made during the period 1980-1985 based on the geological, geotechnical, seismological design data as well as based on the design data for ground dynamics assessed in 1980. During the construction period of Unit 1 and partially of Unit 2-5, some observations ad in-situ and lab determinations have been done, resulting in additional information as to the ones determined during the period of site studies. Considering all the geological, geotechnical, seismic and ground dynamics data obtained both during the site investigation period and the construction period of Unit 1 and partially of Unit 2-5, a review of the site data was made in order to determine a representative set of data for Cernavoda NPP site, as well as to reduce the conservatory degree existing in the initial data. (author). 1 fig., 1 tab., 6 refs

  10. Works on ageing management for Cernavoda NPP

    International Nuclear Information System (INIS)

    The document presents a general overview of the activities realized by CITON in the area of ageing management for Cernavoda NPP components. There are considered especially safety related components. The initial activity in this field started with general analyses of ageing phenomena implication on NPP safety and establishment of a general program for ageing management. During 1994-2000 period a series of research and development works included in 'Nuclear Safety Research and Development Program' financed by Ministry of Industry and Resources allowed the completion of important steps in ageing management: condition indicators definition, selection of systems and components necessary of ageing monitoring and evaluation, establishment of initial reference values for selected components monitoring, etc. Starting with 2001 year the ageing program includes evaluation of the service life for main of components (one system after the other approach), evaluation of present surveillance and data collection and proposal for improvement by computerized data acquisition and processing, extension of system, ageing evaluation for the whole plant critical components, both from safety and availability point of view. This program, with proper support and cooperation from the NPP owner, will allow first evaluation of the whole Cernavoda NPP - Unit 1 ageing, safety and availability implications and presentation of recommendations for operating conditions and maintenance optimization. The document emphasizes also the status of Cernavoda units, from ageing management point of view and the necessary actions to be adopted (in CITON opinion). (authors)

  11. Romanian contribution to the design of Cernavoda NPP

    International Nuclear Information System (INIS)

    The Cernavoda NPP is the first nuclear power unit built in Romania. It resulted as implementation of the national nuclear program provisions worked out in the period 1960-1978. The Center of Technology and Engineering for Nuclear Projects operated in the Cernavoda NPP construction in its capacity of general and specialty designer. It conducted studies and design works to select optimal nuclear reactor system, nuclear fuel cycle and associated nuclear materials (D2O, Zr), aiming particularly to the introduction of CANDU type power reactors in the Romanian power system. In the period 1977-1990 basic technical and economical documentation were worked out concerning the site of construction, technical annexes to the commercial contracts, procurement order documents, technical assistance on site of construction, design for equipment fabrication, etc. In 1990-2002 significant changes in conducting the project have taken place. In the period August 1991- June 1996 the project management was taken over by the ACC consortium formed of AECL (Canada) and ANSALDO (Italy), while CITON was acting as principal contractor of ACC for design services and technological engineering. The paper presents the following main achievements in the design work: site selection and NPP general layout; nuclear safety and environmental protection; structure and infrastructure works; anti-seismic design; design of process systems; thermomechanical equipment for the NPP nuclear sector; design for electrical systems and automation. In conclusion, the contribution to the design and construction of the Romanian specialists for realization of Cernavoda NPP Unit 1 was decisive, while the cooperation with Canadian and Italian teams was extremely fruitful. These constitute a valuable potential to be used in building the Cernavoda NPP Unit 2 and Units 3-5

  12. Training needs analysis at Cernavoda NPP - Romania

    International Nuclear Information System (INIS)

    The paper is mainly on training needs analysis applied at Cernavoda NPP and will outline the Cernavoda (CNPP) approach in establishing what kind of training is necessary for CNPP employees, from the moment they are hired until they become qualified. The training methodology adapted at CNPP is one which adheres to the principles of the Systematic Approach to Training (SAT). SAT adoption at CNPP provides a broad integrated approach emphasizing not only technical knowledge and skills but also human factors knowledge, skills and attitudes. The analysis of SAT at CNPP consists of a 'table-top' analysis of training and qualification requirements. This paper will illustrate how a 'table-top' analysis by Subject Matter Experts is organized, carried out and recorded, and which categories of staff have begun this table-top analysis at CNPP. It will also give an example how this analysis is done: how the tasks of each job are rated, which are the used criteria, and how to proceed with the incorporation of the tasks into initial and continuing training, as appropriate. (author)

  13. Management of occupational exposure at Cernavoda NPP

    International Nuclear Information System (INIS)

    Ionising radiation presents a particular risk associated with nuclear power plant operation. An effective and efficient radiation protection program should: - prevent the detriment of health due to deterministic effects; - keep all the exposures as low as reasonably achievable in order to limit the detriment of health due to stochastic effects; - provide safety and health conditions as good as other safe industries. Radiation protection of occupationally exposed workers is part of Health and Safety of Work Program. Effective dose limits, as recommended by ICRP and required by CNCAN regulations are reasonably low in order to avoid deterministic effects and to limit the probability of stochastic effects to an acceptable level. The health status of Cernavoda NPP employees is appropriately surveyed. There were not recorded cases of occupational diseases and/or other indicators of relevant biological effects in order to establish the specific response of the human body to the occupational illness risk factors. Starting in 2002 the cytogenesis blood analysis for occupationally exposed individuals was performed at the beginning of their employment and then periodically for those working for more than five years in the plant. Up to 1900 employees have been investigated with no indication of genetic modifications. (author)

  14. Appendix III: Cernavoda Nuclear Power Plant: Phased implementation of similar units - Human resource management and training programmes (Romania) (Case study of human resource issues faced by NPP operating organizations, and how they were (or are being) addressed)

    International Nuclear Information System (INIS)

    Nuclear power generation is a reliable source of energy for Romania and an important contributor to the national electricity supply. Romania has one nuclear power plant, Cernavoda, which operates one CANDU 6 reactor, 707 MW(e), designed by Atomic Energy of Canada Ltd (AECL). Provides about 10 percent of the total country energy consumption. The state-owned company responsible for the production and supply of energy from Cernavoda NPP, as well as for its development, is Societatea Nationala 'Nuclearelectrica'. The plant was designed to have five similar units. The studies performed for the plant, prior to the construction's start, established feasible technical solutions for all problems related to a 5-unit site, including the environmental impact, which would be entirely acceptable. Construction of the first unit started in 1980 and of units 2-5 in 1982. The pressing problems encountered during construction of Unit 1 (import restrictions, delays etc.) restrained the progress at Unit 2. Starting with 1990, the work on Cernavoda site was focused on Unit 1 and the construction at the other units was suspended. Since then, only preservation activities have been carried-out. The re-start of work at Unit 2 took place in 1995, under the management of the AECLANSALDO Consortium. Some construction work was carried-out (e.g. installation of the fuel channels) and a thorough assessment was performed concerning the condition of the equipment procured for Unit 2 and stored on site, or already installed. The absence of a clear contractual framework and the lack of resources hindered significant advance in the construction of Unit 2. Since then, many economic estimates foresee that, starting with winter 2005 when Romanian electricity consumption is expected to increase with about 1000 MW(e), the annual electricity production will become insufficient and will be not covered unless Unit 2 of Cernavoda NPP is commissioned. In this environment and considering the relatively low cost

  15. Elements and strategies of Knowledge Management at Cernavoda NPP

    International Nuclear Information System (INIS)

    The paper highlights that there are Knowledge Management (KM) elements already implemented at Cernavoda NPP, ensuring the safe operation of the plant. The KM process is not formalized yet, but the following elements are part of existing KM practices for Cernavoda NPP organization: Plant policies and procedures are in place; Document control is in place using Document Management system; Configuration management is a complex and well structured process; Training and qualification is based on SAT; Learning from operating experience internal and external is a day by day practice, (procedures, PJB, PROEM, Simulator, RCA, Training, etc.); Work control system is implemented via Ventrix Work Management System; Corrective action tracking is implemented; Workforce planning and human resources management is a continuous process; Communications are implemented by the plant personnel; Company intranet and other web-based solutions (CBT) are put in place; Human performance improvement programme is on going. Also, it is reinforced the need to develop and implement a structured knowledge transfer and retention process for the Cernavoda NPP in order to preserve unique knowledge and skills that could be lost through attrition or planned staffing changes. (author)

  16. Environmental radiological impact of Cernavoda NPP operation

    International Nuclear Information System (INIS)

    The release of any potential radioactive pollutant to the environment during routine operation of a Nuclear Power Plant should be the subject of appropriate controls and assessments. It is impossible to monitor directly the dose contribution of normal releases because the environmental radioactivity levels are very small but source monitoring provides a means of assessing the radiation exposure of population groups, critical groups and individual members of the public. Derived emissions limits ( DELs ) are used to quantify the relationship between releases of radioactivity and doses to public - critical groups. CNE-PROD DELs are based on a pathway analysis conducted for Cernavoda site specific conditions and they were computed using a compartment transfer model. Annual air and water emissions for the most significant radionuclides between 1996 and 2000 are presented in terms of %DELs and can be observed that population doses are far below the authorized limit and negligible in comparison with average annual population dose from natural sources. (authors)

  17. Ageing of electronic equipment used in Cernavoda NPP

    International Nuclear Information System (INIS)

    This paper presents some ageing mechanisms and an evaluation of systems and electronic equipment from Instrumentation and Control (I and C) system, taking into account their importance in command, control and safety operation of NPP. Concepts regarding lifetime, single and multiple stresses, experimental evaluation methods of lifetime, evaluation norms, measurement methods and constraints of lifetime evaluation techniques are also presented. The analysis highlights the factors that influence the operational safety, improvements in the methods of design, manufacture and operation, typical causes of failures and a case study on ASFD modules (Amplifier for Flux Detectors Self-supplied). In order to create a data base regarding the behaviour in time of modules and equipment in similar conditions as those of Cernavoda NPP, measurements of the operational parameters, without input current and with injection of current, depending on the type of module designed for each type of detector self-supplied (with vanadium or platinum ) were carried out. (authors)

  18. Contributions of INC-DTCI from ICSI Rm. Valcea to Cernavoda NPP's progress

    International Nuclear Information System (INIS)

    Development of Romanian Nuclear Programme was the basic objective of our institution, 'G' plant - Rm. Valcea at present the National Institute of Research-Development for Cryogenics and Isotopic Technologies. Initially constituted as an experimental pilot for developing the technology of heavy water production, a task solved and later transferred to the newly created ROMAG Heavy Water Plant, our institution collaborated to the technical project of heavy water reconcentration at Cernavoda NPP Unit 1 as well as to reconcentration of moderator and coolant facility. The objective of these two installations was to guarantee a as high as possible isotopic purity of the moderator and coolant and thus to reach a high burnup coefficient of natural uranium in the CANDU reactor. The main contributions in the stage of construction of the D2O reconcentration tower were the following: elaboration and patenting of phosphorous bronze; designing the ordered packing of phosphorous bronze with 800 mm diameter; preparation of phosphorous bronze packing; elaboration of activation/reactivation technologies for obtaining phosphorous bronze packing; preparation of column sections, internal equipment for their mounting, etching and passivation; activation of potassium permanganate packing; mountain g the activation packings in the column sections and their passivation; designing and construction of heavy water analyzers; realization and certification of heavy water control samples for the entire concentration range; supplying of heavy water of nuclear quality. In collaboration with Cernavoda NPP for tritium extraction from heavy water a detritiation facility has been developed. Romania is participating also to European and international fusion programs

  19. Estimation of radionuclide releases in atmosphere from Cernavoda NPP based on continuous gaseous effluent monitoring

    International Nuclear Information System (INIS)

    Monitoring of gaseous effluents from Cernavoda NPP is performed to assess the environmental impact of the plant operation. The results of the monitoring program are used to evaluate the population doses in order to ensure that the emissions of radionuclides in air are below regulatory limits and radiation doses are maintained ALARA. It complements, but is independent from the Operational Environmental Monitoring Program for Cernavoda NPP. Gaseous effluent monitors provide continuous indication of the radioactivity content in atmospheric emissions. Except for noble gases, these monitors also collect samples for later detailed analysis in the station Health Physics Laboratory. This paper presents the main equipment and the results of the gaseous effluents monitoring program in order to assess the impact of Cernavoda NPP operation and to predict the future releases as function of radionuclides concentrations in CANDU systems, based on the identified trends.(author)

  20. New issues in radioactive waste management legal frame and challenges for CNE-PROD Cernavoda NPP

    International Nuclear Information System (INIS)

    This paper presents national legal frame governing radioactive waste management activities (including spent fuel), legislative newness, introduced during last two years, current status of radioactive waste management at CNE-PROD Cernavoda, as radioactive waste main producer and associated responsibilities and derived actions for CNE-PROD radioactive waste program. Romania has only one nuclear power plant, Cernavoda NPP, equipped with five PHWR - CANDU-6 Canadian type reactors - with a 700 MW(e) gross capacity each, in different implementation stages. Unit 1 is in commercial operation since December 2, 1996, Unit 2 is under construction and Units 3, 4, 5 are under preservation. Spent fuel management facilities at CNE-PROD consist of Spent Fuel Bays and The Intermediate Dry Spent Fuel Storage facility. Radioactive waste management facilities at CNE - PROD consist of Solid Radioactive Waste Interim Storage Facility. Objective of Romanian radioactive waste management policy is to assure safe management of radioactive waste, according to the principles stated in IAEA SS No. 111-F. The Romanian radioactive waste management policy and strategy are fully taking into account the general and radioactive waste management specific IAEA requirements. New legislative issues from last two years establish clear responsibilities for the different institutions involved in the different steps of spent fuel and of radioactive waste management. (author)

  1. Reliability problems in the recirculated cooling water system at Cernavoda NPP and corrective maintenance operations adopted

    International Nuclear Information System (INIS)

    Between February 18 and March 5, 2002 the Unit 1 of Cernavoda NPP was shutdown in an un-planned outage necessary to repair a crack on the piping of the Recirculated Cooling Water System. The large pipe diameter and the requirement of maintaining the system in operation during the outage, imposed a special technology for fixing the leak (isolation of the line with ice plugs). The paper presents information about the performed repair work. After repair operations the failed duct was checked by non-destructive methods and the results were submitted and approved by regulation authorities. The repair was considered successfully completed and the Unit restarted on March 5, 2002 at 0.57 am when the electric generator was switched on in parallel to the national electric power system. (authors)

  2. Automatic control of the D20 vapor recovery dryers at Cernavoda NPP U2 (CANDU Project 82)

    International Nuclear Information System (INIS)

    The 'D20 vapor Recovery System' is built in the frame of CANDU NPP Cernavoda, Romania, in order to preserve the atmosphere dry inside the Reactor Building. The system includes ten dryers, four tanks and three pumps grouped in thirteen equipment units with cyclic operation. When desiccant bed of the dryers is full of humidity the operating regime is switched automatically from absorption to regeneration. During regeneration, the air from blower discharge is passed through electric heaters and desiccant bed to condenser where the D20 vapor is recovered, and again to fan inlet. The dryer regeneration is completed when its desiccant bed is hot. Also, transferring the contents of the tanks is a batch processing operation. Considering the Cernavoda U1 operating experience, the CANDU project 82, for Cernavoda NPP U2, is now under an improving process, which implies an Automatic Control for the 'D20 vapor Recovery System'. This Automatic Control, performed by Industrial Computers and Data Acquisition System, is able automatically to detect the completion of the equipment unit phases, to switch the equipment unit to appropriate operation mode, to check the proper operating mode and to trip the equipment unit if necessary. This paper intends to present the problems surmounted during the technical specification issuing for designing process. (author)

  3. Estimation of the future nuclear power research in Romania, based on the present Cernavoda NPP evolution

    International Nuclear Information System (INIS)

    For more than four decades, the electric power needs of Romania were evaluated on the basis of the State Plan for Economic Development. To identify the optimal solution, the 'least price per produced MWh' was practically the only criterion. Now, there is no convincing estimation of the future economic development and at least two additional criteria play a significant role, 'the safety in the supply of the needed electric power', and 'the need of limiting the environmental impact of electricity generation'. The analysis dedicated to evaluation of future electric power solutions must take into account several features of the present situation. There are no available internal funds to finance the construction of new generating units of the order of several hundreds of MW. Even the so-called 'refurbishing' of the existing thermal power plants is based on foreign loan. In the 2000 year, about 80 electricity generation units reached 30 years of operation, i.e., the design life. Other thermal power plants proved very modest performances during 15-20 years of operation. Consequently, the future of almost 100 generating units is either in shutdown + decommissioning or shutdown + modernization situation. The Government analyzed the situation and decided to continue the completion of the Cernavoda NPP. The Unit 2 will be commissioned in a couple of years, and there is a schedule of negotiations relating the future of the Unit 3. After almost five years of successful operation of the Unit 1, the collaboration between RDT Institutes and NPP has clear features. Based on the experience related to this collaboration and taking into account the evolution of the Cernavoda NPP, we estimated that five research domains have significant chances to obtain a stable (and, hopefully, consistent) financial support. 1. Nuclear Safety, in particular Accident Analysis. As the Government re-iterated the firm decision to meet the conditions required for European integration, most of the nuclear

  4. The influence of increased temperature of waters from Cernavoda NPP on underground water sources

    International Nuclear Information System (INIS)

    The operation of Cernavoda NPP implies the change of thermal regime of waters in the Danube-Black Sea channel zone. The Danube water is used to cool the NPP systems before being delivered into channel and used in irrigations. The temperature increase of water in Cernavoda NPP installations is between 7 and 12 deg. C. The negative effects of this warming are: 1. limitation of water use for irrigations; 2. occurrence and persistence of fog in channel area; 3. thermal pollution of underground waters and limitation of underground potable water supply. The paper presents a general approach of thermal pollution problems of an aquifer and a mathematical model of forecasting the underground water temperature variation in Danube-Black Sea channel area. (authors)

  5. Intermediate storage and some issues concerning the final storage of spent nuclear fuel at Cernavoda NPP

    International Nuclear Information System (INIS)

    A major objective of 'Nuclearelectrica' National Society (SNN) is to implement nuclear power projects with respect to the sustainable development concept. Examples are given regarding spent fuel and radioactive waste management. Managing the spent fuel according with the concept of sustainable development is demonstrated by the SNN's policy and target objectives of the associated strategy. Spent fuel management strategy is implemented through an optimized staged process. One of the most important stages was completed by commissioning the first unit of the Dry Interim Spent Fuel Storage Facility at Cernavoda NPP site. The dry storage facility is based on the MACSTOR technology , the best proved design of Atomic Energy of Canada Limited and consists of concrete modules, each of them having a 12,000 spent fuel bundles capacity. The designed lifetime of the facility is, at least, 50 years and the present site can accommodate the spent fuel generated by two units during 30 years of operation. Spent fuel storage is the last and the most important stage of disposal. In Romania, by the Government's Ordinance 11/2003 approved by the Law 320/2003 there were assigned the responsibilities within the national waste management system. The newly established National Agency for Radioactive Waste Management will have a fundamental task, being responsible for the end stage of fuel cycle by selecting for the spent fuel disposal an appropriate repository site accepted by the public and a safe and efficient technology with a reasonable acceptable environmental impact. (author)

  6. Ethics of the management of low and intermediate radioactive wastes generated by Cernavoda NPP, a challenge for the Romanian specialists

    International Nuclear Information System (INIS)

    This paper presents the design criteria and the prerequisites for the development of the Radioactive Waste Treatment Plant - RWTP which will comply with L/ILW Final Repository requirements to be built near Cernavoda NPP. The RWTP will be designed to satisfy the main performance objectives in accordance to IAEA recommendation and on basis of the Repository's Waste Acceptance Criteria resulted from the local conditions. One of the most important technological aspect is related to the selection of technologies, which implies, on the one hand, the impact on present generation respectively incineration, radwaste transfer from the SS drums to CS drums, SS drums super compaction and spent filter cartridges cutting, and on the other hand, technologies that isolate for 300 years the tritium and C-14 in the Repository with impact for the next generations. The Saligny Repository will be commissioned in 2014 and in order to accept radwastes from Cernavoda NPP it is necessary that the radwastes are suitably treated for long-term radionuclides isolation. The conditions and requirements including many uncertainties and constraints reduce the possibilities to select the suitable treatment technologies for the Waste Treatment Plant designed for the radwastes generated by Cernavoda NPP, this selection being a critical case due to the limited storage capacity of existing Radioactive Waste Storage Facility. The necessary Radioactive Waste Treatment Plant implies a detailed analysis including ethical aspects of the selected technologies. (author)

  7. Consuming for production - Procurement for power production at Cernavoda NPP - Nuclear Sector

    International Nuclear Information System (INIS)

    The paper presents some aspects relating to the importance of a good communication and cooperation between all factors involved in procurement process at Societatea Nationala 'Nuclearelectrica', SNN. In order to comply with the internal and international rules related to safety in nuclear field and public procurement requirements and for maintaining a high standard of operational performance of Cernavoda NPP, adequate procurement systems were developed by SNN SA. The importance of human factor and the training activities for all personnel from this chain of procurement process is the main key issue to maintain high quality of their activities considering that procurement documents are reviewed and approved before to be issued by all departments involved in procurement process. The specialized department for public acquisition is supervising that the procurement processes initiated at the level of branches, in accordance with their needs and with respect to the requirements of the public acquisition laws and regulations, as well as the specific requirements imposed by the internal Regulatory Body. (authors)

  8. A 3D electronic model for unit 2 Cernavoda plant lay-out design

    International Nuclear Information System (INIS)

    Based on the designed and construction experience of Cernavoda Unit 1, in order to provide an integrated approach in performing system, structural and lay-out engineering/construction activities, it is going to be implemented the CAD 3D electronic model of the Turbine Building and associated auxiliary systems. It is suggested a strongly recommended to perform the same approach also for the Reactor/Service Buildings lay-out configuration. This activity is actually developed on the CAD Computer Vision based on a dedicated intelligent date base properly developed for Cernavoda Unit 2 CANDU Nuclear power plant. The main purpose of this integrated approach is hereafter summarized: i. to implement the as built Unit 2 lay-out configuration of the civil structure previously erected and to modify properly the nominal design reference documentation; ii. to optimize properly the plant lay-out anticipating interference check between piping/equipment/cables trays; iii. to produce automatically isometric drawings for the plant construction area by area; iv. to implement automatically the as built lay-out drawings for piping/cables trays saving all the man hours effort required to develop the Unit 1 as built out; v. to provide an automatic input for piping structural qualification just connecting lay-out computer codes (Computer Vision) and Piping Stress Analysis Computer Codes; vi. to provide a complete and detailed design for the plant construction that might be split in portions whose realisation would be transferred to Romanian Contractors on the bases of 'turn-key' contracts. Additionally this effort, even if it might be judged expensive in terms of required man hours effort, should become an important investment, from economical point of view, for the future design and construction activities of Units 3/4/5 in Cernavoda site. (Author)

  9. Cernavoda NPP Unit 1: Operating experience program and plant specific performance indicators (level 2)

    International Nuclear Information System (INIS)

    The basis for the Operating Experience Program was set in place since early stages of the commissioning phase (1993), when a system based on the Canadian approach was implemented for reporting, reviewing, assessing and establishing of the necessary corrective action for unplanned events. This system provided excellent opportunity to train staff in unplanned event assessment methodology, and prepare the station for the formal reporting process following criticality in accordance with the licensing requirements. The formal process, set in place after criticality is described in Station Instruction Procedure SI-01365-P13 'Unplanned Event Report' and was developed under the supervision of Safety and Compliance Department. In parallel, a program for information exchange and trending of performance indicators was developed by Technical Services Department. The WANO recommendations following August 1997 Peer Review provided the opportunity for a better understanding and reconsideration of the Operating Experience Program. As a result, all the activities related to this topic were assigned to a new structure, within Safety and Compliance Department. As such an Operating Experience Group was created and a new program is now being developed in an integrated and centralized manner. The content of the paper is the following: - Overview; - Operating Experience Program; - Event Analysis (Unplanned Events Assessment System - UEIR Process- and Systematic Analysis of Operational Events - ACR Process); - Information Exchange Program; - Monitoring of Operating Experience - Plant Specific Performance Indicators; - Purpose; - Level 2 Performance Indicators. Four appendices are added containing: - A. Station performance indicators/targets (Level 2); - B. SPI (Station Performance Indicators - Level 2) - Graphics; - C. UEIR, LRS (Safety and Licensing Review Sheet), UEFR (Unplanned Event Follow-up Report), ACR and OPEX forms. (authors)

  10. Analyses of thermal plume of Cernavoda nuclear power plant by satellite remote sensing data

    Science.gov (United States)

    Zoran, M. A.; Nicolae, D. N.; Talianu, C. L.; Ciobanu, M.; Ciuciu, J. G.

    2005-10-01

    The synergistic use of multi-temporal and multi-spectral remote sensing data offers the possibility of monitoring of environment quality in the vicinity of nuclear power plants (NPP). Advanced digital processing techniques applied to several LANDSAT, MODIS and ASTER data are used to assess the extent and magnitude of radiation and non-radiation effects on the water, near field soil, vegetation and air for NPP Cernavoda , Romania . Cernavoda Unit 1 power plant, using CANDU technology, having 706.5 MW power, is successfully in operation since 1996. Cernavoda Unit 2 which is currently under construction will be operational in 2007. Thermal discharge from nuclear reactor cooling is dissipated as waste heat in Danube-Black -Sea Canal and Danube river. Water temperature distributions captured in thermal IR imagery are correlated with meteorological parameters. Additional information regarding flooding events and earthquake risks is considered . During the winter, the thermal plume is localized to an area within a few km of the power plant, and the temperature difference between the plume and non-plume areas is about 1.5 oC. During the summer and fall, there is a larger thermal plume extending 5-6 km far along Danube Black Sea Canal, and the temperature change is about 1.0 oC. Variation of surface water temperature in the thermal plume is analyzed. The strong seasonal difference in the thermal plume is related to vertical mixing of the water column in winter and to stratification in summer. Hydrodynamic simulation leads to better understanding of the mechanisms by which waste heat from NPP Cernavoda is dissipated in the environment.

  11. Update on Cernavoda

    International Nuclear Information System (INIS)

    The Cernavoda project in Romania is for five 700 MWe CANDU units. Construction began in 1980, but because of problems occurring, many of them associated with political, social, and economic changes in Romania, in 1991 the management of construction of Unit 1 was transferred from RENEL (Regia Nationala de Electricitate) to a consortium formed by AECL and Ansaldo. This had been one of the chief recommendations of a pr-operational safety review conducted by the I.A.E.A. By May 1994, Unit 1 was 93.4% complete, but progress was hampered by the need to rework a number of components, mainly piping. A continuous quality assurance program was in place. Ninety-two Romanian operators were trained by New Brunswick Power at Point Lepreau. As of the date of the conference, the target date for grid connection was March 1995, nine months ahead of the contractual target

  12. Update from Cernavoda

    International Nuclear Information System (INIS)

    On April 16 1995 Cernavoda Unit 1 achieved criticality. This event marked the culmination of roughly 17 years of effort and one of the most troubled histories experienced by any nuclear construction project worldwide. It was also a major milestone in the program begun by AAC (AECL-ANSALDO CONSORTIUM) in 1991 and due to end in June 1997 with the hand-over to RENEL (The Romanian National Electric Utility) of a fully operational CANDU 600 Power Plant. This paper briefly outlines the history of the project, the organisational structure in place and the funding schemes used to ensure its completion. Most attention is given to the present status of the project and those areas and/or issues which have been or continue to be significant problem areas. The future program for the achievement of 100% power and hand-over of the station to RENEL is outlined and potential future problem areas are discussed. (author). 9 appendices

  13. Mochovce NPP unit 1 and 2 completion project

    International Nuclear Information System (INIS)

    History of Mochovce NPP is quite long and reflects political changes that happened in Europe in the end of 80'ties. The plant site was chosen in south-west of Slovakia in the frame of Nuclear Industry Development Plan adopted by former Czechoslovak government in 70'ties. In that time was decided to build in Mochovce four VVER 440/213 units together with other NPP's (Dukovany, Temelin, Kecerovce)

  14. Construction prospects of new power units at Khmelnitskij NPP site

    International Nuclear Information System (INIS)

    According to the Energy Strategy of Ukraine for a period up to 2030 it is planned to put into operation power units 3 and 4 of Khmelnitskij NPP by year 2016. In this work considerations are presented on the possible options while selecting reactor unit type for Khmelnitskij NPP power units 3 and 4, which is the main determinant of the cost, construction and commissioning time, and utilization of the existent civil structures. To optimize Khmelnitskij-3 and 4 construction, a survey of the data has been conducted with regard to the possibility of construction of new power units of PWR/VVER type at Khmelnitskij NPP site. The multivariable analysis has been performed based on the projects technical and cost data, construction time and conditions, as well as their compliance with the IAEA and EUR safety requirements for new power units. (author)

  15. Progress in Decommissioning of Ignalina NPP Unit 1

    International Nuclear Information System (INIS)

    The aim of the paper is to present the Lithuanian legal framework regarding the nuclear safety in Decommissioning and Waste Management, and the progress in the Decommissioning Programme of the unit 1 of Ignalina Nuclear Power Plant (INPP). INPP is the only nuclear plant in Lithuania. It comprises two RBMK-1500 reactors. After Lithuania has restored its independence, responsibility for Ignalina NPP was transferred to the Republic of Lithuania. To ensure the control of the Nuclear Safety in Lithuania, The State Nuclear Power Safety Inspectorate (VATESI) was created on 18 October 1991, by a resolution of the Lithuanian Government. Significant work has been performed over the last decade, aiming at upgrading the safety level of the Ignalina NPP with reference to the International standards. On 5 October 1999 the Seimas (Parliament) adopted the National Energy Strategy: It has been decided that unit 1 of Ignalina NPP will be closed down before 2005, The conditions and precise final date of the decommissioning of Unit 2 will be stated in the updated National Energy strategy in 2004. On 20-21 June 2000, the International Donors' Conference for the Decommissioning of Ignalina NPP took place in Vilnius. More than 200 Millions Euro were pledged of which 165 M funded directly from the European Union's budget, as financial support to the Decommissioning projects. The Decommissioning Program encompasses legal, organizational, financial and technical means including the social and economical impacts in the region of Ignalina. The Program is financed from International Support Fund, State budget, National Decommissioning Fund of Ignalina NPP and other funds. Decommissioning of Ignalina NPP is subject to VATESI license according to the Law on Nuclear Energy. The Government established the licensing procedure in the so-called 'Procedure for licensing of Nuclear Activities'; and the document 'General Requirements for Decommissioning of the Ignalina NPP' has been issued by VATESI. A

  16. Life extension program of KORI Unit 1 NPP in Korea

    International Nuclear Information System (INIS)

    The two phases of Life extension program for KORI Unit 1 NPP are presented. Phase I is completed. It was concluded that life extension is a feasible option in technical and economic aspects. Detailed analysis of RPV is underway, plan for Phase II is finished. It deals with screening and sorting of all relevant SSCs, detailed life evaluation of SSCs, ageing management program and documentation for license renewal application

  17. Systems turnover activities at NPP-Cernavoda

    International Nuclear Information System (INIS)

    The erection of a nuclear power plant requires the utilisation of complex Quality Assurance (QA) programs. These programs implement specific standards, procedures and laws to ensure that the plant is constructed to the highest possible safety level attainable. Some procedures and standards have a narrow field of action while others cover a large area of operation. Such is the case with the turnover procedure presented in this paper, which is one component of the QA program. (Author)

  18. Full scale dynamic testing of Kozloduy NPP unit 5 structures

    International Nuclear Information System (INIS)

    As described in this report, the Kozloduy NPP western site has been subjected to low level earthquake-like ground shaking - through appropriately devised underground explosions - and the resulting dynamic response of the NPP reactor Unit 5 important structures appropriately measured and digitally recorded. In-situ free-field response was measured concurrently more than 100 m aside the main structures of interest. The collected experimental data provide reference information on the actual dynamic characteristics of the Kozloduy NPPs main structures, as well as give some useful indications on the dynamic soil-structure interaction effects for the case of low level excitation. Performing the present full-scale dynamic structural testing activities took advantage of the experience gained by ISMES during similar tests, lately performed in Italy and abroad (in particular, at the Paks NPP in 1994). The IAEA promoted dynamic testing of the Kozloduy NPP Unit 5 by means of pertinently designed buried explosion-induced ground motions which has provided a large amount of data on the dynamic structural response of its major structures. In the present report, the conducted investigation is described and the acquired digital data presented. A series of preliminary analyses were undertaken for examining in detail the ground excitation levels that were produced by these weak earthquake simulation experiments, as well as for inferring some structural characteristics and behaviour information from the collected data. These analyses ascertained the high quality of the collected digital data. Presumably due to soil-structure dynamic interaction effects, reduced excitation levels were observed at the reactor building foundation raft level with respect to the concurrent free-field ground motions. measured at a 140 m distance from the reactor building centre. Further more detailed and systematic analyses are worthwhile to be performed for extracting more complete information about the

  19. New appraisement of siting for a NPP on Mures river

    International Nuclear Information System (INIS)

    The studies for a second NPP siting on inner Romanian rivers began in a careful manner since 1982 as a first part of the Nuclear Power Plant Romanian Program adopted by political and governmental authorities at the time. The experience gained from Cernavoda NPP siting, the first mission of new multi-branch of specialists team was to choose new NPP sites adapting the CANDU type NPP Cernavoda project to the new parameters of close water cooling circuit and of hard less or no rock foundation strata. The new sites conditions mean a lot of changes of CANDU license and a decrease the output power supplied to the national electric grid. The studies on the Mures river as alternative site of Olt river in Transylvania region began in 1986 and were stopped after 1990. This paper tries to reconsider shortly the old analysis focused on geological and geotechnical aspects and other local sites characteristics according to the last IAEA Safety Standards taking into account also the last types of NPP generations and the number of units. (author)

  20. Sitting Safety Aspects of Second Romanian NPP

    International Nuclear Information System (INIS)

    The first Romanian NPP CANDU 6 type reactor gone to erection in 1980 on Cernavoda site planned to have 5 units like the Wolsong applied design project for nuclear island. For the BOP parts the ASALDO-GE project was applied with the careful about the interface connection NSP requirements. The new NPP sitting studies began from 1982 in a serious manner as first part on Nuclear Power Plant Romanian Program adopted by political and governmental authorities at the time. For develop the all package of the studies in concordance with the first IAEA Safety Standards recommendations. Till the 1982 the first mission of design and research multi-branch of specialists team was to adapt the NPP Cernavoda project having a open water cooling circuit to the new parameters of close water cooling circuit. But the team was looking at the other type of NPP for sitting. Also in the same time was studied the possibility of NSP foundation on hard less or soft soil foundation strata in connection with safety aspects. The close circuit of cooling water means others parameters of systems and need very large cooling towers. Also must be reconsidering the safety systems design and performance as new solution. In the south of Transylvania historical region in Romania the Olt River run from west to east having medium multi annual flow around 70 m3/s. The Olt River has a chain of small hydropower in operation and other planned. From geological and geophysical points of view two main faults, along the Olt river valley, one of this having seismically small activities was detected. Site region geotechnical studies show small quantity underground natural gas, salt and peat. The initial nuclear program has imposed 4 NPP units site near Olt River. Taking into account the orogenesis, water cooling needs and other local feature can't be built more than two NPP units on a site. This paper tries to reconsider the old analysis from the last IAEA Safety Standards point of view taking into account the new

  1. Readiness of the Mochovce NPP for unit 1 start-up with regards to meeting the requirements for increased safety

    International Nuclear Information System (INIS)

    A safety and reliability of operation of NPP type VVER 440/213, differences between Mochovce NPP and other VVER 440/213 NPPs contributing to the safety improvement, organization of the completion works of Mochovce NPP units 1 and technical condition of the installations are discussed

  2. Reconsidering the site requirements for NPP on Olt River

    International Nuclear Information System (INIS)

    Site studies for CANDU type NPP began in a careful manner since 1982 as a first part of the Nuclear Power Plant Romanian Program adopted by political and governmental authorities at the time. A team was charged to develop all packages of the necessary main studies. The first Romanian NPP CANDU 6 type reactor gone to erection on Cernavoda site, planned to have 5 units and, like Wolsong NPP, applied the same design for the nuclear island. For the BOP parts the ANSALDO-GE project was applied with a thorough concern about requirements raised by connection to NSP. The first mission of design and research multi-branch team was to adapt the NPP Cernavoda project having an open water cooling circuit 'once-through' to the new parameters of a close recirculation water cooling circuit. Also, the structural design was re-evaluated for the case of soft foundation strata instead of hard rock ones. The close recirculation water cooling circuit system was applied for PWR NPP type like in French or other nuclear projects where a rich water source was not available. In case of CANDU type projects cooling water loops were not built so far. The close recirculation circuit of water cooling implies other parameters of the cooled systems and for turbine steam as well, needing very large cooling towers. The initial Romanian nuclear program implied the construction of a 4 units NPP sited near Olt river. This river runs in Transylvania region of Romania from east to west near Boitza village on the northern side of Fagaras Mountains. From geological and geophysical points of view the following main characteristics were found by surveying the Olt River valley: there exist two faults having about east-west direction, one of these having small seismic activities; the stratum for foundation consists of marls or sandy marls; there exist also underground small bags of natural gas or salty strata here and there, as detected by geotechnical borings near the Olt river. The average multiannual water

  3. Some specific features of building work organization during the Khmelnitskij NPP first unit construction

    International Nuclear Information System (INIS)

    Specific feature of the excavation process during the Khmelnitskij NPP first unit construction, as well as the scheme of mechanization of the main building construction, production of special constructions and their assmbly into mounting units, features of ventilation organizing, preparation, transportation and placement of monolithic concrete are considered. Basic technical-and-economic indices are presented

  4. Seismic soil-structure-equipment interaction analysis of unit 5/6, Kozloduy NPP

    International Nuclear Information System (INIS)

    This research project is aimed to analyse problems of soil-structure-equipment interaction under seismic excitation in case of Kozloduy NPP. Reevaluation and upgrading of Kozloduy NPP has started after 1977 Vrancea earthquake. New Safe Shutdown Earthquake (SSE) level was defined, upgrading most of structural equipment was performed, seismic instrumentation was installed. New investigations were initiated after 1990 IAEA mission visited the site. A comprehensive site confirmation project was started with a subsequent structural and equipment reevaluation and upgrading. This work deals with Units 5 and 6 of WWER-1000 type only

  5. Analysis of service experience of OPC-417000/750 main unit transformers of NPP units of Ukraine

    International Nuclear Information System (INIS)

    Statistics, design- and technological characteristics of main transformers of NPP units were compiled and analyzed.An algorithm for estimation of the unit transformer state was developed. Reasons of unit transformer failures resulting in forced outage of the units were found.Sensitive zones and probable factors of degradation of electromagnetic, electric insulation and mechanical systems, as well as areas of extreme heat generation were revealed

  6. Report of the ASSET (Assessment of Safety Significant Events Team) mission to the Cernavoda nuclear power plant in Romania 8-12 August 1994 Division of Nuclear Safety. Root cause analysis of a significant event that occurred during commissioning of unit 1

    International Nuclear Information System (INIS)

    The IAEA Assessment of Safety Significant Events Team (ASSET) report presents the results of the team's investigation of a significant event that occurred during commissioning of Unit 1 of Cernavoda nuclear power plant. The results, conclusions and suggestions presented herein reflect the views of the ASSET experts. They are provided for consideration by the responsible authorities in Romania. The ASSET team's views presented in this report are based on visits to the plant, on review of documentation made available by the operating organization and on discussions with utility personnel. The report is intended to enhance operational safety at Cernavoda by proposing improvements to the policy for the prevention of incidents at the plant. The report includes, as a usual practice, the official response of the Regulatory Body and Operating Organization to the ASSET recommendations. Figs

  7. Modern practice of cost estimates for the NPP units decommissioning

    International Nuclear Information System (INIS)

    The results of analysis of current practices of cost estimates for decommissioning of nuclear power units with different reactor types present is reviewed. Cost estimates intervals are shown for decommissioning of units with PWR,BWR and AP1000 reactors and the main factors influencing the cost amount are analyzed

  8. Results from modernization of the containment localization systems of the Kozloduy NPP units 3 and 4

    International Nuclear Information System (INIS)

    The improvements of the Accident Localization System (SLA) of units 3 and 4 systematically implemented by Kozloduy NPP shows an important direction for increasing the safety of NPP with WWER-440/V-230 containments. During the years Kozloduy NPP implemented a large scope of activities aimed in full resolution of all generic shortcomings identified in the original design of these containments. These activities allowed already in 2002 to justify that integrity of the containment is assured for all postulated events and the radiological consequences for all DBAs and BDBAs without core degradation are within the regulatory limits. The last phase of this modernization was oriented toward achieving the same goals in case of severe accidents by installation of systems for avoiding long term pressurization of the SG compartments and by installation of a system for keeping of negative pressure (slight vacuum) during the late phases of development of the accidents thus minimizing significantly the uncontrolled radioactive releases from the containment and assured controlled purified release of radioactivity to environment, and for elimination of conditions for H2 deflagration within the localization system. This paper summarizes the results of the whole modernization process with an emphasis of the implementation of the latest phase successfully completed by Kozloduy NPP in first quarter of 2005 which allowed the plant to demonstrate remarkable mitigation capability for a comprehensive set of very low probability severe accidents scenarios in line with the approach now being promoted for the modern design NPPs

  9. Fast neutron fluences determination for Khmelnitskaya NPP Unit 1 surveillance specimens

    International Nuclear Information System (INIS)

    Fast neutron fluences on surveillance specimens of Khmelnitskaya NPP Unit 1 were determined by results of measurements of neutron-activation indicators accompanied surveillance specimens irradiation. It was shown that reliable transfer of results from surveillance specimens to reactor pressure vessel is impossible and for this purpose, it is necessary to determine space-energy characteristics not only for surveillance specimens locations but for reactor pressure vessel also

  10. Probabilistic soil-structure interactions (SSI) analysis of Kozloduy NPP unit 5/6

    International Nuclear Information System (INIS)

    This work is part of an on-going PSA project on the WWER-1000 units of Kozloduy NPP. Results are presented from the probabilistic response analysis of the reactor building. The probabilistic seismic excitation definition and the probabilistic soil-structure interaction analysis are described. A comprehensive multiple time history analysis procedure is applied. The Latin Hypercube Sampling is used for preparation of the data base for the numerical computation of the reactor building response. (author). 6 refs., 8 figs

  11. Cernavoda NPP - A competitive energy source for sustainable development

    International Nuclear Information System (INIS)

    At present a trend manifests world wide toward promoting nuclear power, for increasing its performances, toward maintaining competitiveness and sustaining the programs of development and application of advanced nuclear technologies. These objectives will be achieved by improving: operation performances; management of life-cycle, quality management; technical infrastructure; human resource performances; international cooperation for developing innovative nuclear technologies; technologies and applications of advanced reactors. Fostering the Romanian nuclear power on the basis of CANDU 6 type rectors, the developing in Romania of an advanced industrial infrastructure, the economical, environmental and social aspects and their interplay with nuclear power development are the main subjects presented in this work

  12. Safety enhancement of Kozloduy NPP units 5 and 6 using PSA-1 and other studies

    International Nuclear Information System (INIS)

    The paper describes briefly the background, objectives and organisation of the Kozloduy NPP 'Upgrading Programme for Units 5 and 6' developed in 1994. The classical probabilistic safety analysis (level 1) of these units have been used as criteria for evaluation of the changes already made. This PSA-1 study is the first of the kind for WWER-1000 reactors. It is based on a methodology of IAEA and includes internal and external initiators of accidents. Results from seismic probabilistic risk assessments are also reported. (author)

  13. Foreign Material Exclusion Program at CNE Cernavoda Nuclear Generating Station

    Energy Technology Data Exchange (ETDEWEB)

    Urjan, Daniel [S.N. ' Nuclearelectrica' SA, CNE Cernavoda Nuclear Power Plant, Medgidiei 2 Street, 905200 Cernavoda, Constanta (Romania)

    2008-07-01

    In the face of a continuing attention to operations and maintenance costs at nuclear power plants, the future of the industry depends largely upon increasing plant availability and improving operating efficiency. The success in achieving these objectives is dependent upon the success of each plant's equipment maintenance program. Preventing the introduction of foreign materials into a nuclear power plant system or component requires a careful, thoughtful, and professional approach by all site personnel. This paper describes a proactive approach to prevent the introduction of foreign material into systems and components, by providing an overview of technical considerations required to develop, implement, and manage a foreign material exclusion program at CNE Cernavoda Unit 1 and 2 Nuclear Power Station. It is also described an example of Foreign Material Intrusion which happened during the 2003 planned maintenance outage at Cernavoda Unit no.1. This paper also defines personnel responsibilities and key nomenclature and a means for evaluating prospective work tasks and activities against standardized criteria, in order to identify the appropriate level of the required FME controls. (author)

  14. Foreign Material Exclusion Program at CNE Cernavoda Nuclear Generating Station

    International Nuclear Information System (INIS)

    In the face of a continuing attention to operations and maintenance costs at nuclear power plants, the future of the industry depends largely upon increasing plant availability and improving operating efficiency. The success in achieving these objectives is dependent upon the success of each plant's equipment maintenance program. Preventing the introduction of foreign materials into a nuclear power plant system or component requires a careful, thoughtful, and professional approach by all site personnel. This paper describes a proactive approach to prevent the introduction of foreign material into systems and components, by providing an overview of technical considerations required to develop, implement, and manage a foreign material exclusion program at CNE Cernavoda Unit 1 and 2 Nuclear Power Station. It is also described an example of Foreign Material Intrusion which happened during the 2003 planned maintenance outage at Cernavoda Unit no.1. This paper also defines personnel responsibilities and key nomenclature and a means for evaluating prospective work tasks and activities against standardized criteria, in order to identify the appropriate level of the required FME controls. (author)

  15. Results from probabilistic safety analysis level 2 for Kozloduy NPP units 3 and 4

    International Nuclear Information System (INIS)

    The study considers full power operation analysis results and impact of strategies and modernisation implementations of Kozloduy NPP units 3 and 4. In this paper the following issues are discussed: the development of Severe Accident Management Guidelines and Symptom Based Emergency Operating Procedures, installation of brand new system as Emergency Filter Ventilation System, Passive Autocatalytic Hydrogen recombiners, etc. In order to respond to the objectives of the study, the analyses assets the impact of different initiating events on risk based on the frequencies of various plant damage states, the confinement failure and the radiological release frequencies and finally estimates the total risk as frequency of radiological releases

  16. Study of environmental impact assessment for Mochovce NPP Units 3 and 4. Executive summary. September 2007

    International Nuclear Information System (INIS)

    SE/ENEL, on a voluntary basis, has prepared new EIA Study for the completion of Units 3 and 4 of Mochovce Nuclear Power Plant (MO34 NPP) according to International current practices and European Directives. The results of the analysis, according to SE/ENEL Environment and Corporate Social Responsibility policies, will be provided to local Communities and Public Authorities. The Environmental Impact Assessment is performed: - in compliance with appendix 11 of Slovak Act. No. 24/2006 'On the assessment of the effects on the environment and on the modification and enlargement of some laws'; - meeting the requirements of the Exhibit II 'Illustrative list of potential social and environmental issues to be addressed in the Social and Environmental Assessment documentation' as reported in the document 'Equator Principles' of 2006 July developed by the International Finance Corporation (IFC). The area of Mochovce NPP is situated in Central Europe in the south-western region of the Slovak Republic (SR) at the western border of the Levice district. The area lies in the south-western part of the Kozmalovske hills mainly in the Hron highlands. From the point of view of the terrestrial and administrative organization of the SR, Mochovce NPP is situated in the eastern part of the Nitra region, in the north-western part of the Levice district, close to the border with the Nitra and Zlate Moravce districts. Mochovce NPP is approx. 12 km from the district capital Levice, which is the largest town within a 20 km distance from the power plant. Initial site preparation began in August 1983. In April 1998 the first fuel was loaded into Unit 1 of Mochovce NPP. The operation started in August 1998. Unit 2 started operation in January 2000. The original Construction Permit No. Vyst. 2010/86 for MO 34 was issued by the District National Committee in Levice on the basis of the Land Planning Decisions on 12 November 1986. This Permit has been renewed firstly on 5 May 1997 by letter of the

  17. Project Management Unit for decommissioning of NPP Bohunice VI (2003-2014)

    International Nuclear Information System (INIS)

    From October 2003 until december 2014 the Consortium consisting of Iberdrola Engineering and Construction (leader). Empresarios Agrupados Internacional, and Indra Sistemas has carried out the project Project Management Unit ((PMU) for the decommissioning of Bohunice V1 NPP (units 1 and 2), type VVER-440/V-230 in Slovakia. during the first phase (2003-2007) EdF was also part of the Consortium. The project is funded by the Bohunice International Decommissioning Support Fund (BIDSF) administered by the RBRD. The main objective of the project is to provide the necessary engineering and resources of project management for planning, execution, management, coordination and monitoring of all tasks in support of the decommissioning. (Author)

  18. Informing the Lithuanian public about the decommissioning of Unit 1 at Ignalina NPP

    International Nuclear Information System (INIS)

    The final decision about decommissioning of Unit 1 at Ignalina NPP by 2005 was taken when the Lithuanian Parliament approved the National Energy Strategy in 1999. In 2000 the Board of the European Bank of Research and Development (EBRD) approved the establishment of the Ignalina International Decommissioning Support Fund and the International Donors' Conference took place in Vilnius. Sweden's longterm co-operation with Lithuania in the area of nuclear safety started already in 1992, soon after the country had regained its independence. SIP (Swedish International Project Nuclear Safety) administers this bilateral assistance. Public information has been included in the Swedish programme since the establishment of the Information Centre at INPP and is also a part of the bilateral decommissioning support. SIP finances a series of TV-programmes on a national channel and the local cable TV in Visaginas (the town close to Ignalina NPP) about various aspects of decommissioning. The Lithuanian regulatory authority VATESI uses its experience in public relations to inform about the situation related with decommissioning. The authority organizes 'Open Doors' days and press conferences to provide objective and trustworthy information. The reaction of the viewers to the TV-programmes were very positive and Sweden will continue the support to the information programme in Lithuania. (author)

  19. Interactive model of the steam generator blowdown system of the Kozloduy NPP units 5 and 6

    International Nuclear Information System (INIS)

    A program complex for full scale modelling of the WWER reactor dynamics 'RADUGA-EU' has been developed. The complex includes: program complex 'RADUGA - 7.3' - for non-stationary neutron-hydraulic calculations of reactors with 3-dimensional reactor core; package TPP (Thermal Power Plant) - for modeling of non-stationary and stationary processes in complicated thermal-hydraulic networks (including primary and secondary circuit of NPPs and TPPs); program 'GENERATOR' - for modeling of the electric generator; program 'MVTU (Modeling in technical devices)' - for modeling, analysis and optimisation of dynamical processes. The 'RADUGA-EhU' is used for calculations of thermal-hydraulic processes in the steam generator blowdown system of the Kozloduy NPP units 5 and 6. An interactive model of the blowdown system has been created. It is used not only for testing of technical solutions, but also as interactive environment for the development of the equipment operational regulations

  20. Preserving the life extension option for Wolsong NPP Unit 1 through plant life management program

    International Nuclear Information System (INIS)

    The first CANDU 6 plants, including Wolsong Unit 1 nuclear power plant (NPP) (which entered service in the early 1980's) are now approaching two thirds of their thirty-year design life. Korea Electric Power Research Institute (KEPRI) and Atomic Energy of Canada Limited (AECL) have worked together since 2000 to develop and implement a comprehensive and integrated CANDU Plant Lifetime Management (PLiM) program for Wolsong Unit 1 NPP. PLiM will see this plant successfully and reliably through to the design life and preserve the option for life extension. The focus of the initial phase of the program is on the major critical components and structures and any potential aging phenomena that might affect plant safety and availability. In-depth life assessments of Wolsong Unit 1 critical systems, structures, and components (CSSCs) are under going. It is recognized that effective plant practices in inspection, monitoring, maintenance, and operations are the primary means of managing aging through the design life and necessary for preserving the life extension option. Hence, the PLiM assessments identify enhancements to current plant programs to mitigate aging effects and to ensure reliable life attainment and performance. The KEPRI/AECL co-operation for the PLiM program over the last few years is providing in-depth assessments and promising life prognosis for the key CSSCs of Wolsong Unit 1. The assessments are also identifying those areas for optimized plant inspection, monitoring and maintenance programs to achieve utility targets for safety, reliability and production capacity during extended life. These outcomes are important inputs to decision makings to embark upon a detailed Wolsong Unit 1 life management program. In this paper, the PLiM program assessment methods and techniques tailored to the components, like CANDU 6 steam generators, are described. A typical proactive aging management program for steam generators, aimed to continue current excellent service for

  1. Testing manoeuvrability of WWER-1000 at 5 unit of Zaporozhe NPP

    International Nuclear Information System (INIS)

    Specific features of the WWER-1000 reactor control algorithms under maneuverable conditions during everyday load management are discussed. The results of the suggested algorithm verification at the Zaporozhe NPP fifth unit are presented. It is shown that unlike to power management under normal operation conditions involving reactor transition from one stationary state into another, in a case of the reactor power daily variations it constantly operates under transients because of the xenon oscillations. The feasibility of WWER-1000 power unit operation under daily load management schedule at the core lifetime end is proved. The reliable and high-efficient algorithm assuring control of the reactor power level and power density distribution under minor water exchange which is not higher than that under normal operation is developed. Different variants of manual and automatic reactor regulating rod groups control, as well as operating modes for reactor power and turbine regulators are tested. The conclusion is made that the calculational prediction obtained using the IR program is completely confirmed in the course of tests. The control algorithm suggested assures power daily variations at a power unit with the WWER-1000 reactor with load decreasing lower 50 % of the rated power level

  2. Methodology and measures for preventing unacceptable flow-accelerated corrosion thinning of pipelines and equipment of NPP power generating units

    Science.gov (United States)

    Tomarov, G. V.; Shipkov, A. A.; Lovchev, V. N.; Gutsev, D. F.

    2016-10-01

    Problems of metal flow-accelerated corrosion (FAC) in the pipelines and equipment of the condensate- feeding and wet-steam paths of NPP power-generating units (PGU) are examined. Goals, objectives, and main principles of the methodology for the implementation of an integrated program of AO Concern Rosenergoatom for the prevention of unacceptable FAC thinning and for increasing operational flow-accelerated corrosion resistance of NPP EaP are worded (further the Program). A role is determined and potentialities are shown for the use of Russian software packages in the evaluation and prediction of FAC rate upon solving practical problems for the timely detection of unacceptable FAC thinning in the elements of pipelines and equipment (EaP) of the secondary circuit of NPP PGU. Information is given concerning the structure, properties, and functions of the software systems for plant personnel support in the monitoring and planning of the inservice inspection of FAC thinning elements of pipelines and equipment of the secondary circuit of NPP PGUs, which are created and implemented at some Russian NPPs equipped with VVER-1000, VVER-440, and BN-600 reactors. It is noted that one of the most important practical results of software packages for supporting NPP personnel concerning the issue of flow-accelerated corrosion consists in revealing elements under a hazard of intense local FAC thinning. Examples are given for successful practice at some Russian NPP concerning the use of software systems for supporting the personnel in early detection of secondary-circuit pipeline elements with FAC thinning close to an unacceptable level. Intermediate results of working on the Program are presented and new tasks set in 2012 as a part of the updated program are denoted. The prospects of the developed methods and tools in the scope of the Program measures at the stages of design and construction of NPP PGU are discussed. The main directions of the work on solving the problems of flow

  3. Integrity Analysis of Turbine Building for the MSLB Using GOTHIC code for Wolsong NPP Unit 2

    International Nuclear Information System (INIS)

    A break in the piping between the steam generators and the turbine can lead to rapid loss of secondary circuit inventory. A break inside the turbine building leads to pressure differentials between different areas of the turbine building. In order to improve the environmental protection of various components within the turbine building, a wall has been erected which effectively separates the area in which these components are housed from the rest of the turbine building. Relief panels installed in the turbine building ensure that the pressure differential across the wall would be less than that required to jeopardize the wall integrity. The turbine building service wing is excluded from the scope of this analysis. It is further assumed that any doors in the heavy wall are as strong as the wall itself, with no gaps or leakage around the doors. For the full scope safety analysis of turbine building for Wolsong NPP unit 2, input decks for the various objectives, which can be read by GOTHIC 7.2a, are developed and tested for the steady state simulation. The input data files provide simplified representations of the geometric layout of the turbine building (volumes, dimensions, flow paths, doors, panels, etc.) and the performance characteristics of the various turbine building subsystems

  4. Mounting the large-size building blocks of the reactor room structure at the Kozloduj NPP fifth power unit (Bulgaria)

    International Nuclear Information System (INIS)

    Pecularities of the construction of Kozloduj NPP fifth power unit with a WWER-1000 reactor are described. Methods of mounting reactor well, storage pond and underwater reloading well using large-size building blocks are presented. The described methods can be applied for the construction of NPPs with WWER-1000 reactors using a high capacity crane (not less than 200 t) erected in the centre of the reactor building

  5. 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

  6. PLATON and SPV programme - means of improving reliability of cernavoda NPPs

    International Nuclear Information System (INIS)

    A data-acquisition system for plant information named PLATON is connected to the plant digital control computers and allows inspection of trends, bar charts, alarms and hard copies of main control room displays. It allows the construction of historical trends of process variables. PLATON helps plant expertise be quickly focused during plant transients and is a good tool in emergency exercises. SPV means 'Single Point of Vulnerability' project in Cernavoda NPP. The main goal of the SPV initiative is to reduce to as low a level as possible the vulnerability of the plant to events as a result of failures of equipment representing SPV. The experience gained during this initiative development will be used to improve the plant preventive maintenance programme. (author)

  7. Strategic maintenance plan for Cernavoda steam generators

    International Nuclear Information System (INIS)

    Steam generators are among the most important pieces of equipment in a nuclear power plant. They are required full time during the plant operation and obviously no redundancy exists. Past experience has shown that those utilities which implemented comprehensive steam generator inspection and maintenance programs and strict water chemistry controls, have had good steam generator performance that supports good overall plant performance. The purpose of this paper is to discuss a strategic Life Management and Operational-monitoring program for the Cernavoda steam generators. The program is first of all to develop a base of expertise for the management of the steam generator condition; and that is to be supported by a program of actions to be accomplished over time to assess their condition, to take measures to avoid degradation and to provide for inspections, cleaning and modifications as necessary. (author)

  8. The management of safety within the completion of units 3. and 4. in NPP Mochovce

    International Nuclear Information System (INIS)

    The contribution defines the way of management of safety and protection of health and protection against the fire during completion of units 3. and 4. in NPP Mochovce. The creation of the management of safety raised from the legal and other requirements applied in the civil activities and mainly from the requirements for coordination of safety on the site. The whole system is methodically managed through the 5 basic documents so-called 'Building rules': 1) Safety-technical conditions of performance in SE, Inc. Bratislava (project MO34); 2) MO34/1/MNA-003.00-02 the elaboration of the integrated safety plan; 3) MO34/1/NA-003.00-03 risks analyse; 4) PNM3460100 Integrated safety plan for completion of Units 3.and 4 in NPP Mochovce; 5) Project of construction organization. The system itself of the management of the safety prevention must by provided by the supplier in compliance with the standard OHSAS 18 001 and ISO 14001, and in compliance with the requirement of the builder applied in the technical specification for the contract. Most of necessary related documentation of Safety plan for the site is usually part of the documentation for quality management of contractor. Therefore it is necessary to put the reference in each chapter of the Safety plan for site and the standpoint how to apply it for the particular specific situation. The coordinator is mandatory to manage the prevention for the part of safety of specified site and to coordinate the activity of suppliers during the works tie in this way, that the each contractor shall meet the safety requirements given by safety plan and also to identify and to eliminate the risks menaced in the particular work places or the suppliers each other. The builder established its own control system and for this purpose he settled the data base so-called 'The system of corrective and precautionary activities'. The system registers in its data base all discrepancies determined during the regular controls of the head workers

  9. RELAP5/MOD3.2 sensitivity calculations of loss-of-feed water (LOFW) transient at Unit 6 of Kozloduy NPP

    Energy Technology Data Exchange (ETDEWEB)

    Pavlova, M.P. [Institute for Nuclear Research and Nuclear Energy, Tzarigradsko Shaussee 72, Sofia 1784 (Bulgaria)]. E-mail: pavlova@inrne.bas.bg; Groudev, P.P. [Institute for Nuclear Research and Nuclear Energy, Tzarigradsko Shaussee 72, Sofia 1784 (Bulgaria)]. E-mail: pavlinpg@inrne.bas.bg; Stefanova, A.E. [Institute for Nuclear Research and Nuclear Energy, Tzarigradsko Shaussee 72, Sofia 1784 (Bulgaria)]. E-mail: antoanet@inrne.bas.bg; Gencheva, R.V. [Institute for Nuclear Research and Nuclear Energy, Tzarigradsko Shaussee 72, Sofia 1784 (Bulgaria)]. E-mail: roseh@inrne.bas.bg

    2006-02-15

    This paper provides a comparison between the real plant data obtained by Unit 6 of Kozloduy nuclear power plant (NPP) during the loss-of-feed water (LOFW) transient and the calculation results received by RELAP5/MOD3.2 computer model of the same NPP unit. RELAP5/MOD3.2 computer model of the VVER-1000 has been developed at the Institute for Nuclear Research and Nuclear Energy-Bulgarian Academy of Sciences (INRNE-BAS) based on Unit 6 of Kozloduy NPP. This model has been used for simulation the behavior of the real VVER-1000 NPP during the LOFW transient. Several calculations have been provided to describe how the different boundary conditions reflect on the prediction of real plant parameters. This paper discusses the results of the thermal-hydraulic sensitivity calculations of loss-of-feed water transient for VVER-1000 reactor design. The report also contains a brief summary of the main NPP systems included in the RELAP5 VVER model and the LOFW transient sequences. This report was possible through the participation of leading specialists from Kozloduy NPP and with the assistance of Argonne National Laboratory (ANL) for the United States Department of Energy (US DOE), International Nuclear Safety Program (INSP)

  10. Main Results and Conclusions of Probabilistic Safety Analysis (PSA) Level 1 for Units 5 and 6 of ''Kozloduy'' NPP

    International Nuclear Information System (INIS)

    In accordance with international practice, probabilistic safety analysis (PSA) is an established tool for studying the main risk aspects of the design and operation, to explore the importance of plant modifications and evaluation of events plant experience. Different PSA applications are very useful and flexible tool in addition to deterministic analysis. PSA can be used to optimize the different plant configurations, for justification or basis for modification of limiting conditions for operation (LCO), for planning of maintenance activities, to provide engineering evaluations in decisions making process as well as to control and monitoring the safety. This paper presents the main results and conclusions from the last update of PSA level 1 for 5 and 6 units of ''Kozloduy'' NPP. This study shows the measures of ''modernization program'' 5 and 6 units of ''Kozloduy'' NPP, realized in the period 2001-2007. PSA level 1 is performed by the team of Risk Engineering. This paper shows the main contributors to the risk. The results for internal initiating events, earthquakes, internal flooding and internal fires are given.(author).

  11. Two managerial grids in NPP

    International Nuclear Information System (INIS)

    Today, the nuclear power corporation (NPC) enjoys the profit of LCEP (the low carbon economic policy). at the same time, they also enduring more and more pressure. For example, the partner competition or the NPP potential occupational risk . The efficient counterplot of risk is the self-ability cultivation. It is essential to research the NPP managerial flow. The nuclear power plant (NPP) unit is a carrier of the NPC enterprise management system, and has taken on a new look 'pull one portion then the whole moving'. The NPP has three systematical characters, the security responsibility center, the man-machine system and the input-output system. The manufacturing system and the enterprise management system are the great constituents of the NPP managerial flows. Means of systems analysis, we can find out the truth of the NPP running interface. In CHINA, there are many operating experiences near 20 years. It indicates that the NPP manufacturing system and the enterprise system are the roots of the nuclear power corporation, the core of the all NPP systems must be based on it. So the ability cultivation is the work core to NPP. It is reliably to ensure the NPP to be up against problems, for instance, the security duty, the costing control and the man-machine system running harmoniously. This paper introduces the NPP managerial flow and the present state of QNPC, also come up with a proposal to refer for the NPC development actions of collective measure, specialization, standardization, fine. (author)

  12. Maintenance optimization methods for NPP critical systems, structures and components

    International Nuclear Information System (INIS)

    Considerable progress has been made in the development and implementation of the plant life management (PLiM) program with formal processes to identify systematically and evaluate the major critical systems, structures and components (CSSCs) in the station, and a plan to ensure that the plant surveillance, operation, and maintenance programs monitor and control component degradation well within the original design specifications essential for the plant life attainment. The paper presents a brief description of most important aspects of the methods used to identify the CSSCs taking into account maintenance activities. The system structures and components (SSCs) that influence decisively the NPP reliability are considered as critical. Also, for the accident conditions, the SSCs, which have a major influence to the system availability/operability, are considered also as critical. PSA techniques serve as a basis for maintenance optimization. In the paper a case of association between operating events and CSSC is presented. The main reference was the PSA study for Cernavoda NPP, Unit 1 CPSE B+. From this study it was selected and presented: - the contribution diagram for the occurrence of one accident (small LOCA) with some severe consequence (e.g. PDS 1 - 2 - early core damage); - dominant accident sequence analyzed; - the initial event that generated the possible dominant sequence; - the most important accident events; - qualitative and quantitative results; - main CSSC identification; - results validation and proposals for system operation performance improving; - documentation of the analysis. For the critical components, if periodical maintenance operations are needed, the maintenance activities must be optimized. In order to ensure these, some sensitivity studies have to be performed. In the system probabilistic models the associated events for the critical components could be the failure events of the components and also the unavailability due to component

  13. Control of NPP aging processes

    International Nuclear Information System (INIS)

    The concept of the control program on the NPP aging processes is considered. The methodological algorithms for the working programs plotting and realization, intended for accomplishing the measures for mitigating the aging mechanisms and factors, effecting the NPP safety, are presented. The efficiency of the equipment for the aging processes control and power units systems, aimed at the control of the NPP service life, is analyzed

  14. Annex V. Project re-start management experience Mochovce unit 3 and 4 NPP, Slovak Republic

    International Nuclear Information System (INIS)

    The purpose of this report is to describe the re-starting phase of DNPP MO 34 Project, mainly focusing on management issues. The report consists of three main parts dealing with the Project management organization during the three different periods of the of DNPP re-starting process. The first part (Chapter 2) begins with the general background information about the NPP and then focuses on the pre-feasibility and feasibility study. The second part (chapter 3) deals with the current status of the plant and it stresses the main steps of the DNPP Project resuming after completion of the feasibility study. The third part (Chapter 4) outlines the main issues related to the criticality of a typical DNPP Project (e.g. preservation and maintenance of equipments, updating to technological and regulatory requirements, human resources, protection of design documentation, etc.) and the measures implemented in MO 34. The hereby presented content reflects the experience and good practices concerning the following main management issues: - project control measures; - human resources; - preservation and maintenance of site installations, structures and equipment; - updating of the whole Project to meet licensing requirements and technology upgrades; - preservation of Project documentation. (author)

  15. Preparation for Ignalina NPP decommissioning

    International Nuclear Information System (INIS)

    Latest developments of atomic energy in Lithuania, works done to prepare Ignalina NPP for final shutdown and decommissioning are described. Information on decommissioning program for Ignalina NPP unit 1, decommissioning method, stages and funding is presented. Other topics: radiation protection, radioactive waste management and disposal. Key facts related to nuclear energy in Lithuania are listed

  16. Project Management Unit for decommissioning of NPP Bohunice VI (2003-2014); Project Management Unit para el desmantelamiento de CN Bohunice V1 (2003-2014)

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Fernandez-conde, A.; Brochet, I.; Ferreira, A.

    2015-07-01

    From October 2003 until december 2014 the Consortium consisting of Iberdrola Engineering and Construction (leader). Empresarios Agrupados Internacional, and Indra Sistemas has carried out the project Project Management Unit ((PMU) for the decommissioning of Bohunice V1 NPP (units 1 and 2), type VVER-440/V-230 in Slovakia. during the first phase (2003-2007) EdF was also part of the Consortium. The project is funded by the Bohunice International Decommissioning Support Fund (BIDSF) administered by the RBRD. The main objective of the project is to provide the necessary engineering and resources of project management for planning, execution, management, coordination and monitoring of all tasks in support of the decommissioning. (Author)

  17. Change of secondary water regime of Paks NPP. Change of secondary water regime at Unit 2

    International Nuclear Information System (INIS)

    The installation of high pH water regime during the 17th cycle of Unit 2 aimed to decrease the amount of transportation inlet of erosion-corrosion products (magnitude) in feedwater to SGs. The resolution of OAH-NBI permitting the installation ordained to make an evaluation of the process. The main conclusions and results are discussed. The high pH water regime proved to be adequate in the case of Unit 2 as well, similarly to Units 3, 4 and 1. (R.P.)

  18. Fabrication and erection of special building structures at the Rovno NPP third unit

    International Nuclear Information System (INIS)

    It is described how works on fabrication and erection of special building structures in the reactor section, a special building and a stand-by diesel-generator station at the Rovno Unit-3 are organized

  19. Introduction of nitrogen blow-through in the cooling circuit of the Chernobyl NPP Unit 3 in experimental industrial use

    International Nuclear Information System (INIS)

    Analysis of nuclide composition of Chernobyl NPP releases (inert gases) showed that Ar-41 plays there the main role (84-90%). For its decrease a system for gas tank blow-through by nitrogen of high purification was proposed

  20. Safety evaluation for communication network software modifications of PCS in Ulchin NPP unit 3

    International Nuclear Information System (INIS)

    On February 2, 1999, an incident occurred at the Ulchin Nuclear Power Plant Unit 3 which resulted in the corruption of data on Perform Net of Plant Control System. This incident was caused by the ASIC (Application Specific Integrated Circuit) chip on the Rehostable Module which is a part of Network Interface Module. Regarding this incident, we required that the utility should propose new algorithms to detect the hardware failure of ASIC chip and evaluated the appropriateness of network software modifications. As a result of this evaluation process, we required that the safety related interlock signals using data communication path be hardwired to make up for the vulnerability of the system architecture. In this paper, we will discuss the system architecture of PCS and fault analysis and evaluation findings

  1. Upgrading the SPP-500-1 moisture separators-steam reheaters used in the Leningrad NPP turbine units

    Science.gov (United States)

    Legkostupova, V. V.; Sudakov, A. V.

    2015-03-01

    The specific features of existing designs of moisture separators-steam reheaters (MSRs) and experience gained with using them at nuclear power plants are considered. Main factors causing damage to and failures of MSRs are described: nonuniform distribution of wet steam flow among the separation modules, breakthrough of moisture through the separator (and sometimes also through the steam reheater), which may lead to the occurrence of additional thermal stresses and, hence, to thermal-fatigue damage to or stress corrosion cracking of metal. MSR failure results in a less efficient operation of the turbine unit as a whole and have an adverse effect on the reliability of the low-pressure cylinder's last-stage blades. By the time the design service life of the SPP-500-1 MSRs had been exhausted in power units equipped with RBMK-1000 reactors, the number of damages inflicted to both the separation part and to the pipework and heating surface tubes was so large, that a considerable drop of MSR effectiveness and turbine unit efficiency as a whole occurred. The design of the upgraded separation part used in the SPP-500-1 MSR at the Leningrad NPP is described and its effectiveness is shown, which was confirmed by tests. First, efforts taken to achieve more uniform distribution of moisture content over the perimeter and height of steam space downstream of the separation modules and to bring it to values close to the design ones were met with success. Second, no noticeable effect of the individual specific features of separation modules on the moisture content was revealed. Recommendations on elaborating advanced designs of moisture separators-steam reheaters are given: an MSR arrangement in which the separator is placed under or on the side from the steam reheater; axial admission of wet steam for ensuring its uniform distribution among the separation modules; inlet chambers with an extended preliminary separation system and devices for uniformly distributing steam flows in the

  2. Studies about level of ageing related to isolation of cables used in Cernavoda NPP

    International Nuclear Information System (INIS)

    The use of equipment and cables shown that after a period of operation in normal operational conditions, some modifications of physical, mechanical and electrical properties occur, which are caused by the materials ageing. The paper treats the cables ageing problems, and specifies some methods for observation and some evaluations techniques of 'health condition', of life time for signal and supply electrical cables, in the operating conditions specific to CANDU nuclear power plants. The paper presents the tests performed on Cross -Linked Poly Ethylene (XLPE) and Ethylene Propylene Rubber (EPR) isolation using sequential exposures to thermal stress and radiation. The influence of ageing level on elongation at break (EAB) is also presented. (authors)

  3. Tritium - intake and clearance. Verification of ICRP Model based on Cernavoda NPP individual monitoring data

    International Nuclear Information System (INIS)

    Operating experience to date of CANDU reactors has indicated that the major contributor to the internal dose is the tritium oxide. Special consideration of routine individual monitoring for internal exposure of workers to tritium oxide is necessary. Data on many humans have indicated that a single exponential essentially describes the retention of tritiated water over the first months or more following the intake. A typical value of the effective half time for tritium is 10 days. Lower tritium effective half-lives, 5.43 and 6.55 days, respectively, were observed in case of internal contamination if diuresis was accelerated. The dose factor for tritiated water incorporation was calculated as a function of the ICRP model parameters. The principal objectives of individual monitoring for intakes of radionuclides are: - to obtain an assessment of the committed effective dose; - to contribute to the control of operation and the design of the plant; - in the case of accidental exposure, to provide valuable information for the initiation and support of any appropriate health surveillance and treatment. Exposure to an atmosphere contaminated by tritiated water results in intake of that substance both by inhalation and by absorption through the intact skin, in a ratio assumed to be 2 to 1. Vapours of tritiated water are considered to be of SR-2 absorption class, that means the tritiated water is instantaneously absorbed into body fluids and uniformly distributed among all the soft tissues. Tritium (H-3) is a pure beta emitter, with an average energy of beta radiation of 0.0186 MeV. Its presence in the body can be detected by measuring the urine samples using the liquid scintillation counting and it presents no detection problems. (authors)

  4. Assessing the consequences in a nuclear accident scenario at Cernavoda NPP

    International Nuclear Information System (INIS)

    Having in view a possible nuclear incident, considerable planning is necessary to reduce at manageable levels the types of decisions leading to effective responses concerning the public protection. One of the most important parts of an emergency response plan is the computerized system which allows to predict the radiological impact of the accident and to provide information in a manageable and effective form for evaluating alternative countermeasure strategies in the various stages of the accident. In this paper the PC-COSYMA results for early containment failure of a CANDU reactor are presented. The deterministic health effects arising in nuclear accident situation are also presented. As source term we have used the core inventory obtained with ORIGEN computer code. The essential input parameters for PC-COSYMA computer code are also done. (authors)

  5. The primary circuit materials properties results analysis performed on archive material used in NPP V-1 and Kola NPP Units 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Kupca, L.; Beno, P. [Nuclear Power Plants Research Institute Inc., Trnava (Slovakia)

    1997-04-01

    A very brief summary is provided of a primary circuit piping material properties analysis. The analysis was performed for the Bohunice V-1 reactor and the Kola-1 and -2 reactors. Assessment was performed on Bohunice V-1 archive materials and primary piping material cut from the Kola units after 100,000 hours of operation. Main research program tasks included analysis of mechanical properties, corrosion stability, and microstructural properties. Analysis results are not provided.

  6. 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

  7. 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.

  8. Regulatory aspects of NPP safety

    International Nuclear Information System (INIS)

    Extensive review of the NPP Safety is presented including tasks of Ministry of Health, Ministry of Internal Affairs, Ministry of Environment and Waters, Ministry of Defense in the field of national system for monitoring the nuclear power. In the frame of national nuclear safety legislation Bulgaria is in the process of approximation of the national legislation to that of EC. Detailed analysis of the status of regulatory body, its functions, organisation structure, responsibilities and future tasks is included. Basis for establishing the system of regulatory inspections and safety enforcement as well as intensification of inspections is described. Assessment of safety modifications is concerned with complex program for reconstruction of Units 1-4 of Kozloduy NPP, as well as for modernisation of Units 5 and 6. Qualification and licensing of the NPP personnel, Year 2000 problem, priorities and the need of international assistance are mentioned

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

    International Nuclear Information System (INIS)

    In August 1991, following the SMiRT-11 Conference in Tokyo, a Technical Committee Meeting was held on the 'Seismic safety issues relating to existing NPPs'. The Proceedings of this TCM was subsequently compiled in an IAEA Working Material. One of the main recommendations of this TCM, called for the harmonization of criteria and methods used in Member States in seismic reassessment and upgrading of existing NPPs. Twenty four institutions from thirteen countries participated in the CRP named 'Benchmark study for the seismic analysis and testing of WWER type NPPs'. Two types of WWER reactors (WWER-1000 and WWER-440/213) selected for benchmarking. Kozloduy NPP Units 5/6 and Paks NPP represented these respectively as prototypes. Consistent with the recommendations of the TCM and the working paper prepared by the subsequent Consultants' Meeting, the focal activity of the CRP was the benchmarking exercises. A similar methodology was followed both for Paks NPP and Kozloduy NPP Unit 5. Firstly, the NPP (mainly the reactor building) was tested using a blast loading generated by a series of explosions from buried TNT charges. Records from this test were obtained at several free field locations (both downhole and surface), foundation mat, various elevations of structures as well as some tanks and the stack. Then the benchmark participants were provided with structural drawings, soil data and the free field record of the blast experiment. Their task was to make a blind prediction of the response at preselected locations. The analytical results from these participants were then compared with the results from the test. Although the benchmarking exercises constituted the focus of the CRP, there were many other interesting problems related to the seismic safety of WWER type NPPs which were addressed by the participants. These involved generic studies, i.e. codes and standards used in original WWER designs and their comparison with current international practice; seismic analysis

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

    International Nuclear Information System (INIS)

    In August 1991, following the SMiRT-11 Conference in Tokyo, a Technical Committee Meeting was held on the 'Seismic safety issues relating to existing NPPs'. The Proceedings of this TCM was subsequently compiled in an IAEA Working Material. One of the main recommendations of this TCM, called for the harmonization of criteria and methods used in Member States in seismic reassessment and upgrading of existing NPPs. Twenty four institutions from thirteen countries participated in the CRP named 'Benchmark study for the seismic analysis and testing of WWER type NPPs'. Two types of WWER reactors (WWER-1000 and WWER-440/213) selected for benchmarking. Kozloduy NPP Units 5/6 and Paks NPP represented these respectively as prototypes. Consistent with the recommendations of the TCM and the working paper prepared by the subsequent Consultants' Meeting, the focal activity of the CRP was the benchmarking exercises. A similar methodology was followed both for Paks NPP and Kozloduy NPP Unit 5. Firstly, the NPP (mainly the reactor building) was tested using a blast loading generated by a series of explosions from buried TNT charges. Records from this test were obtained at several free field locations (both downhole and surface), foundation mat, various elevations of structures as well as some tanks and the stack. Then the benchmark participants were provided with structural drawings, soil data and the free field record of the blast experiment. Their task was to make a blind prediction of the response at preselected locations. The analytical results from these participants were then compared with the results from the test. Although the benchmarking exercises constituted the focus of the CRP, there were many other interesting problems related to the seismic safety of WWER type NPPs which were addressed by the participants. These involved generic studies, i.e. codes and standards used in original WWER designs and their comparison with current international practice; seismic analysis

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

    International Nuclear Information System (INIS)

    In August 1991, following the SMiRT-11 Conference in Tokyo, a Technical Committee Meeting was held on the 'Seismic safety issues relating to existing NPPs'. The Proceedings of this TCM was subsequently compiled in an IAEA Working Material. One of the main recommendations of this TCM, called for the harmonization of criteria and methods used in Member States in seismic reassessment and upgrading of existing NPPs. Twenty four institutions from thirteen countries participated in the CRP named 'Benchmark study for the seismic analysis and testing of WWER type NPPs'. Two types of WWER reactors (WWER-1000 and WWER-440/213) selected for benchmarking. Kozloduy NPP Units 5/6 and Paks NPP represented these respectively as prototypes. Consistent with the recommendations of the TCM and the working paper prepared by the subsequent Consultants' Meeting, the focal activity of the CRP was the benchmarking exercises. A similar methodology was followed both for Paks NPP and Kozloduy NPP Unit 5. Firstly, the NPP (mainly the reactor building) was tested using a blast loading generated by a series of explosions from buried TNT charges. Records from this test were obtained at several free field locations (both downhole and surface), foundation mat, various elevations of structures as well as some tanks and the stack. Then the benchmark participants were provided with structural drawings, soil data and the free field record of the blast experiment. Their task was to make a blind prediction of the response at preselected locations. The analytical results from these participants were then compared with the results from the test. Although the benchmarking exercises constituted the focus of the CRP, there were many other interesting problems related to the seismic safety of WWER type NPPs which were addressed by the participants. These involved generic studies, i.e. codes and standards used in original WWER designs and their comparison with current international practice; seismic analysis

  12. Application of risk-informed approach to the in-service inspection programme of Unit 1 of Loviisa NPP

    Energy Technology Data Exchange (ETDEWEB)

    Nikula, V.; Hietanen, O. (Fortum Ltd., Espoo (Finland)); Kauppinen, P. (VTT Technical Research Centre of Finland, Espoo (Finland))

    2010-05-15

    The pre-service and in-service inspections (ISI) of the primary circuit components and piping of Loviisa NPP (VVER440) have been carried out since the start-up of the plant following the ISI-programme which is based on the requirements presented in the ASME Code Section XI. The latest 10 years' ISI programme was completed in 2007 and the preparation of the new ISI programme for following years was started in 2005. The basis for this new ISI programme is the new YVL-guideline issued in 2003 by the Finnish Radiation and Nuclear Safety Authority STUK. The guideline requires that utilities shall utilize risk-informed methodology when planning new ISI-programmes for safety class 1, 2, 3 and 4 as well as for non nuclear safety class classified piping systems. The approach applied in drafting the ISI-programme was in principle the same as in ASME XI Supplement R, Method B but the approach was applied for the whole plant. The consequence assessment was based on the results of existing extensive probabilistic safety assessment (PSA) analysis according to the values for Conditional Core Damage Probability (CCDP) and Conditional Large Early Release Probability (CLERP). The failure assessment was performed on a qualitative basis by a group of Fortum's experts familiar with Loviisa NPP associated materials integrity and in-service activities. The selection of elements for inspection was based on the risk categorization and identified degradation mechanisms of the piping section in concern. In addition plant specific failure types and experience with their locations were taken into account. The operational history of the plant since 1977 and the experience gained through in-service inspections and maintenance work during the years passed gave valuable additional information for the selection of items to be inspected. The new approach has brought several new features compared to the existing ISI programme. New systems, system portions and small diameter instrumentation

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

    International Nuclear Information System (INIS)

    In August 1991, following the SMiRT-11 Conference in Tokyo, a Technical Committee Meeting was held on the 'Seismic safety issues relating to existing NPPs'. The Proceedings of this TCM was subsequently compiled in an IAEA Working Material. One of the main recommendations of this TCM, called for the harmonization of criteria and methods used in Member States in seismic reassessment and upgrading of existing NPPs. Twenty four institutions from thirteen countries participated in the CRP named 'Benchmark study for the seismic analysis and testing of WWER type NPPs'. Two types of WWER reactors (WWER-1000 and WWER-440/213) selected for benchmarking. Kozloduy NPP Units 5/6 and Paks NPP represented these respectively as prototypes. Consistent with the recommendations of the TCM and the working paper prepared by the subsequent Consultants' Meeting, the focal activity of the CRP was the benchmarking exercises. A similar methodology was followed both for Paks NPP and Kozloduy NPP Unit 5. Firstly, the NPP (mainly the reactor building) was tested using a blast loading generated by a series of explosions from buried TNT charges. Records from this test were obtained at several free field locations (both downhole and surface), foundation mat, various elevations of structures as well as some tanks and the stack. Then the benchmark participants were provided with structural drawings, soil data and the free field record of the blast experiment. Their task was to make a blind prediction of the response at preselected locations. The analytical results from these participants were then compared with the results from the test. Although the benchmarking exercises constituted the focus of the CRP, there were many other interesting problems related to the seismic safety of WWER type NPPs which were addressed by the participants. These involved generic studies, i.e. codes and standards used in original WWER designs and their comparison with current international practice; seismic analysis

  14. Visaginas NPP Project Regional Approach: Lithuania

    International Nuclear Information System (INIS)

    Lithuania has a long standing nuclear energy history. The country is the host of the Ignalina NPP consisting of two RBMK-1500 reactors (a type of boiling water reactor developed by the Soviet Union) located in Visaginas, Lithuania. Ignalina NPP (INPP) Unit 1 came online in December 1983 and Unit 2 was completed in 1987. Lithuania agreed to close the Ignalina NPP as part of its Accession Treaty to the European Union of 2003, as the Ignalina NPP design shares similarities with the Chernobyl NPP. Unit 1 was closed in December 2004 and Unit 2 was closed on 31 December 2009. Around 80% of electricity production in Lithuania in 2009 came from Unit 2 of the INPP. However, following the closure of the Ignalina NPP, Lithuanian electricity net import was 62% of the entire electricity demand in 2010 and 59%32 in 2011. To meet its energy needs following the INPP’s closure, in the absence of a new nuclear power plant, Lithuania relies on a combination of imported electricity, predominantly from interconnections with the UPS/IPS network, and power from alternative domestic generation facilities, which are predominantly fossil plants reliant on gas or oil imports from other countries

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

    International Nuclear Information System (INIS)

    The Co-ordinated research programme on the benchmark study for the seismic analysis and testing of WWER-type nuclear power plants was initiated subsequent to the request from representatives of Member States. The conclusions adopted at the Technical Committee Meeting on Seismic Issues related to existing nuclear power plants held in Tokyo in 1991 called for the harmonization of methods and criteria used in Member States in issues related to seismic safety. The Consulltants' Meeting which followed resulted in producing a working document for CRP. It was decided that a benchmark study is the most effective way to achieve the principal objective. Two types of WWER reactors (WWER-440/213 and WWER-1000) were selected as prototypes for the benchmark exercise to be tested on a full scale using explosions and/or vibration generators. The two prototypes are Kozloduy Units 5/6 for WWER-1000 and Paks for WWER-440/213 nuclear power plants. This volume of Working material contains reports on data related to floor response spectra of Kozloduy NPP; calculational-experimental examination and ensuring of equipment and pipelines seismic resistance at starting and operating WWER-type NPPs; analysis of design floor response spectra and testing of the electrical systems; experimental investigations and seismic analysis Kozloduy NPP; testing of components on the shaking table facilities and contribution to full scale dynamic testing of Kozloduy NPP; seismic evaluation of the main steam line, piping systems, containment pre-stressing and steel ventilation chimney of Kozloduy NPP

  16. Response to water hammer of Loop No. 1, including the pressurizer cold injection piping, at the Temelin NPP, Units 1 and 2

    International Nuclear Information System (INIS)

    Within the Leak Before Break analysis of the primary circuit pipeline system, it is necessary to demonstrate the resistance of the pipe system to water hammers, i.e., various high-frequency hydrodynamic events of the type of collapse of an air or steam crack (unexpected impact shock) and of an abrupt halt of a moving liquid column or vice versa (expected impact shock). The demonstration consists in analyzing the stability of a postulated circumferential pass-through crack and its fatigue growth and comparing the results with the requirements of applicable standards. The publication describes an analysis of the primary circuit of the Temelin NPP, Units 1 and 2, Loop No. 1, i.e. the 850 mm i.d. main circulation loop along with the associated pressurizer cold injection piping. Abrupt seizure of the main circulation pump rotor caused by a seismic event was chosen as the initiating event. It is shown that the water hammer can be neglected against the seismic effect. The results are generalized for Loops No. 2 through 4. (P.A.). 9 tabs., 11 figs., 5 refs

  17. Nuclear power plant life management: strategy for long term operation of the Beznau NPP unit 1 and 2

    International Nuclear Information System (INIS)

    The strategy for attaining long-term operation (LTO) of the Beznau nuclear power plants (NPPs) (2 Units) is given. The requirements, technical evaluations for LTO, in addition to considerations for fuel, radwaste disposal, staff and materials management and economic factors, are described. It is shown that, thanks to optimum management strategies, including backfitting and operational improvements, there are no technical reasons to prevent LTO. (author)

  18. Changing NPP consumption patterns in the Holocene: from Megafauna "liberated" NPP to "ecological bankruptcy"

    Science.gov (United States)

    Doughty, C.

    2015-12-01

    There have been vast changes in how net primary production (NPP) is consumed by humans and animals during the Holocene beginning with a potential increase in availability following the Pleistocene megafauna extinctions. This was followed by the development of agriculture which began to gradually restrict availability of NPP for wild animals. Finally, humans entered the industrial era using non-plant based energies to power societies. Here I ask the following questions about these three energy transitions: 1. How much NPP energy may have become available following the megafauna extinctions? 2. When did humans, through agriculture and domestic animals, consume more NPP than wild mammals in each country? 3. When did humans and wild mammals use more energy than was available in total NPP in each country? To answer this last question I calculate NPP consumed by wild animals, crops, livestock, and energy use (all converted to units of MJ) and compare this with the total potential NPP (also in MJ) for each country. We develop the term "ecological bankruptcy" to refer to the level of consumption where not all energy needs can be met by the country's NPP. Currently, 82 countries and a net population of 5.4 billion are in the state of ecologically bankruptcy, crossing this threshold at various times over the past 40 years. By contrast, only 52 countries with a net population of 1.2 billion remain ecologically solvent. Overall, the Holocene has seen remarkable changes in consumption patterns of NPP, passing through three distinct phases. Humans began in a world where there was 1.6-4.1% unclaimed NPP to consume. From 1700-1850, humans began to consume more than wild animals (globally averaged). At present, >82% of people live in countries where not even all available plant matter could satisfy our energy demands.

  19. Integrated ageing management of Atucha NPP

    Energy Technology Data Exchange (ETDEWEB)

    Ranalli, Juan M.; Marchena, Martin H.; Zorrilla, Jorge R.; Antonaccio, Elvio E.; Brenna, Pablo; Yllanez, Daniela; Cruz, Gerardo Vera de la; Luraschi, Carlos, E-mail: ranalli@cnea.gov.ar [Gerencia Coordinacion Proyectos CNEA-NASA, Comision Nacional de Energia Atomica, Buenos Aires (Argentina); Sabransky, Mario, E-mail: msabransky@na-sa.com.ar [Departamento Gestion de Envejecimiento, Central Nuclear Atucha I-II Nucleoelectrica Argentina S.A., Provincia de Buenos Aires (Argentina)

    2013-07-01

    Atucha NPP is a two PHWR unit site located in Lima, Province of Buenos Aires, 120 km north of Buenos Aires, Argentina. Until recent, the site was split in Atucha I NPP, a 350 MW pressure vessel heavy water reactor in operation since 1974; and Atucha II, a similar design reactor, twice as big as Atucha I finishing a delayed construction. With the start-up of Atucha II and aiming to integrate the management of the plants, the Utility (Nucleolectrica Argentina Sociedad Anonima - NASA) has reorganized its operation units. Within this reorganization, an Ageing Management Department has been created to cope with all ageing issues of both Atucha I and II units. The Atomic Energy Commission of Argentina (Comision Nacional de Energia Atomica - CNEA) is a state-owned R and D organization that; among other functions such as designing and building research reactors, developing uranium mining and supplying radioisotopes to the medical market; is in charge of providing support and technological update to all Argentinean NPPs. The Ageing Management Department of Atucha NPP and the Ageing Management Division of CNEA has formed a joint working group in order to set up an Integrated Ageing Management Program for Atucha NPP following IAEA guidelines. In the present work a summary of the activities, documental structure and first outputs of the Integrated Ageing Management Program of Atucha NPP is presented. (author)

  20. Evaluation of equivalent dynamic soil properties from experimental and analytical studies of foundation model at the site of NPP Cernavoda

    International Nuclear Information System (INIS)

    The seismic response of a building of the nuclear power plant, is determined, to a great extent, by the foundation soil parameters (the dependence of the shear mode and the internal damping with shear strain as result of the loads generated by seismic wave). These dynamic soil parameters values may determine (or not) the resonating of the building with the seismic excitation typical for that site and may or may not damp the seismic energy transferred to the building. Generally the determination of the soil dynamic parameters is made by measurements, in situ, of the 'p' and 's' propagation wave velocities for very low strain cases of the foundation soil as well as by lab testing with resonant column. In order to determine the shear models variation and the internal damping variation with the strain condition, upon the undersigned proposal, a study on a cylindrical model built in a cavity made in limestone and founded on clay layer was elaborated. The model was subjected to shocks generated by land blasting and to pulling by a tractor associated with the sudden release of the load and the module was left to oscillate freely. The model was subjected also to forced oscillations generated by a vibrator installed on top of the model. In order to determine the dynamic parameters of limestone layer, the behavior of the model after its embedding into limestone layer by cyclopean concrete poring was analyzed. Following to the analysis, the variation of shear mode and soil damping, for clay layer were determined. For limestone layer it was determined that the modification of parameter reduction is maximum 15 %. (authors)

  1. Gamma irradiation tests of concrete material recommended for storage casks of spent nuclear fuel arising from Cernavoda NPP

    International Nuclear Information System (INIS)

    Considerable effort is being devoted in the Romania's Nuclear Spent Fuel and Waste Management R and D Program to develop engineered barriers for the containment of nuclear fuel waste under conditions of deep geological disposal. Engineering practice suggests that the concrete should fulfill the requirements of long term physical stability and resistance to radiation damage. With an appropriate system of metal reinforcement, it should be possible to obtain the tensile and impact strength required avoiding the risk of mechanical damage during handling and emplacement. In accordance with the concept developed by SITON-Bucharest, presently, the dry storage of spent nuclear fuel is thought by two choices: the alternative of dry storage type MMB3 and the alternative of dry storage type TRANSTOR. By using ORIGEN and PELSHIE computer codes, we evaluated the absorbed gamma radiation dose absorbed by the concrete walls of the storage vault both in MMB3 and in TRANSTOR designing choice.The irradiation tests were performed at the Gamma Irradiation Facility from the Institute for Nuclear Research. (authors)

  2. Gamma irradiation tests of concrete material recommended for storage casks of spent nuclear fuel arising from Cernavoda NPP

    International Nuclear Information System (INIS)

    Considerable effort is being devoted to the Romania's Nuclear Spent Fuel and Waste Management R and D Program to develop engineered barriers for the containment of nuclear fuel waste under conditions of deep geological disposal. Engineering practice suggests that the concrete should fulfil the requirements of long term physical stability and resistance to radiation. With an appropriate system of metal reinforcement, it should be possible to obtain the tensile and impact strength required, avoiding the risk of mechanical damage during handling and emplacement. In accordance with the concept developed by CITON-Bucharest, presently, the dry storage of spent nuclear fuel is thought by two choices: - The alternative of dry storage type MMB3; - The alternative of dry storage type TRANSTOR. By using ORIGEN and PELSHIE computer codes, we evaluated the gamma radiation dose absorbed by the concrete walls of the storage vault both in MMB3 and in TRANSTOR designing variants. The irradiation tests were performed at the Gamma Irradiation Facility of the Institute for Nuclear Research. (authors)

  3. Replacement of shutdown cooling system and repair of reactor pressure vessel nozzle welds at NPP Forsmark unit 1 and unit 2

    International Nuclear Information System (INIS)

    The Forsmark Nuclear Power Plant is located about 150 km north of Stockholm. The plant consists of three units with boiling water reactors. Unit 1 and Unit 2 were put into operation in 1981 and 1982, respectively. Both of these units are identical each having a capacity of 970 MW. Unit 3 was completed in 1985 and has a capacity of 1160 MW. In November 1998 Babcock Noell Nuclear was awarded the contract to replace the pipe-work of the two-sectioned Shutdown Cooling System 321 from the nozzles at the reactor pressure vessel to 10 meters outside the containment. Moreover, the inner and outer isolation valves including the penetrations had to be replaced. Finally, the repair of the RPV (reactor pressure vessel) connecting welds of the System 415 (Feed Water) and System 323 (Emergency Cooling) was to be performed. The work was carried out by a Babcock Noell Nuclear team integrating Swedish companies during the outages May/June 2000 in Forsmark 2 and August/September 2000 in Forsmark 1. In the Forsmark Nuclear Power Plant, Units 1 and 2, 19 RPV nozzle connections were improved successfully. All relevant start-up deadlines could be kept. All new tools and manipulators met the stringent project requirements. The mockup qualification of the equipment and the special personnel training performed in advance proved that such challenging work can be managed despite limited preparation time and planned effectively in order to recognize and avoid possible risks. (authors)

  4. Optimized planning of in-service inspections of local flow-accelerated corrosion of pipeline elements used in the secondary coolant circuit of the VVER-440-based units at the Novovoronezh NPP

    Science.gov (United States)

    Tomarov, G. V.; Povarov, V. P.; Shipkov, A. A.; Gromov, A. F.; Budanov, V. A.; Golubeva, T. N.

    2015-03-01

    Matters concerned with making efficient use of the information-analytical system on the flow-accelerated corrosion problem in setting up in-service examination of the metal of pipeline elements operating in the secondary coolant circuit of the VVER-440-based power units at the Novovoronezh NPP are considered. The principles used to select samples of pipeline elements in planning ultrasonic thickness measurements for timely revealing metal thinning due to flow-accelerated corrosion along with reducing the total amount of measurements in the condensate-feedwater path are discussed.

  5. Fuel reliability of Bohunice NPP

    International Nuclear Information System (INIS)

    Paper summarizes experience from last 15 years of operation at NPP Jaslovske Bohunice. During this period, leaking fuel assemblies have had been identified by in-core sipping method and verified by vendor specified canister sipping method. Methodology of operational and outage fuel integrity monitoring is described. Full survey of identified leaking assemblies is given. Fuel failure rates are calculated separately for V-1 (V-230 type) and V-2 (V-213 type) units. Systematic difference - significantly lower fuel failure rate at V-213 units exists for all period investigated. Analysis of potential fuel failure reasons and all related measures (planned and already implemented) are presented. Design, operation and fabrication features have been analyzed with the aim to identify dominant factors contributing to fuel failure. No unambiguous reasons have been found so far. It is believed that there is a superposition of several factors and differences causing higher failure rate at V-230 type units. (author)

  6. Foreign NPP decommissioning

    International Nuclear Information System (INIS)

    Different versions of NPP decommisioning, which worked out their life are considered. Dismantling work technology as well as devices for cutting and decontamination of equipment and concrete structures are described. Data on the quantity of shutdown and dismantled NPPs are given. It is noted that to perform successfully dismantling works it is necessary to: choose NPP decommisioning version; calculate radioactivity level; substantiate necessity of decontamination; develop the plan of removal of radioactive equipment; radioactive concrete and structures; contaminated systems; transport and bury solid, liquid and gaseous radioactive and chemical wastes; evaluate the accepted solutions of dismantling from the point of view of the effect on environment; determine costs. It is shown that optimal period of complete or partial dismantling after the NPP decommisioning is 15 years. NPPs dismantling expenditures can reach 10-15% of expenditures for their construction

  7. Project No. 10 - Partial restoration of Ignalina NPP territory

    International Nuclear Information System (INIS)

    At present Ignalina NPP territory makes a total of 2544 ha of land. Due to termination of construction activity development and due to the decision taken to shutdown unit 1 the need in such a territory fell off. For normal and safe operation of Ignalina NPP 1440 ha is enough, including 1237 ha for of Ignalina NPP administrative area and 203 ha for auxiliary objects. Ignalina NPP will have to rearrange territory, forestry that was damaged during the construction activities of the plant and to restore the damaged farmlands and to pass the rearranged forestry that belonged to the Ignalina NPP to the Ministry of Forestry. The total estimated cost of the project is about 1.042 M EURO

  8. NPP electrical price and tariff in the world

    International Nuclear Information System (INIS)

    Construction of a Nuclear Power Plant (NPP) is always become a controversial issue. Nuclear utility and other party which support the NPP present a calculation of NPP electricity cost too optimistic. However for utility and other party that contra to nuclear present a calculation of NPP electricity cost too pessimistic. This study present to reduce the controversy of nuclear cost. In this study, capital cost (Engineering Procurement Construction, EPC) was taken from Asian, America and Europe, operating and maintenance cost uses experience data of PLN, and nuclear fuel cost uses data year of 2008 with high price, low price and average price scenario. The methodological tools used to compare electricity generation cost was LEGECOST, a program developed by IAEA (International Atomic Energy Agency), while for electricity tariff- price calculation using a program developed by PLN research and development center. With the discount rate 10%, the result shows that the cheapest electricity generation cost of NPP is less than 40 mills/kWh, and average electricity tariff was 55 mills/kWh. In the Europe countries the electricity tariff more expensive than NPP in Asia. However generating cost and electricity tariff of NPP in United Stated of America (USA) less competitive because investment cost more expensive. Generating cost and electricity tariff was different at each country depend on salary, labor wage, materials price, construction specification, regulation related to NPP and environment aspect. (author)

  9. KEPIC application on Korean NPP

    International Nuclear Information System (INIS)

    In the management of nuclear power plant, the security of safety is most important and the such a safety security is closely related to the governing code requirements for nuclear facility. In the first stage of NPP construction in Korea, there was no independent Korean codes for the nuclear facility, accordingly different kind of foreign codes were applied. From the later of 1980, KHNP leads the development of KEPIC (Korea Electric Power Industry Code). The development had been being performed in the three step and finished in the end of Dec. 2000. After that, the KEPIC developed had been selectively applied for the UI-Chin 5 and 6 units construction and it is now expected that the application of KEPIC will be markably expended in the Shin-Kori 1 and 2 and Shin Wol-Sung 1 and 2 units scheduled. Thereby here I introduce the status of development and application of the KEPIC for information of persons interested

  10. Fuel handling at Cernavoda 1 N.P.S. - commissioning and training philosophy

    International Nuclear Information System (INIS)

    Efficient operation of a Candu nuclear power plant depends greatly on the reliable and safe operation of the fuel handling system. Successful commissioning of the system is obviously a key aspect of the reliability of the system and this coupled with a rigorous training programme for the fuel handling staff will ensure the system's safe operation. This paper describes the philosophy used at Cernavoda 1 N.P.S. for the commissioning of the fuel handling systems and for the training of staff for operation and maintenance of these systems. The paper also reviews the commissioning programme, describing the milestones achieved and discussing some of the more interesting technical aspects which includes some unique Romanian input. In conclusion the paper looks at the organization of the mature fuel handling department from the operations, maintenance and technical support points of view and the long term plans for the future. (author). 1 fig

  11. Influence of the crustal and subcrustal Vrancea seismic sources on Cernavoda nuclear power plant site

    International Nuclear Information System (INIS)

    The basis of the seismic hazard assessment in different geographical regions with dense-populated areas and strategic objectives (dams, nuclear power plants, etc.) is the study of seismicity of the seismogenic sources which affect these sites. The purpose of this paper is to provide a complete set of information relative to the Vrancea seismic source (in the crust and the intermediate depth domains) that is fundamental for the seismic hazard evaluation at Cernavoda nuclear power plant site. The analysis that we propose has to deal with the following items: (1) geometrical definition of the seismic sources; (2) setting the earthquake catalog associated to each seismic source; (3) estimation of the maximum possible magnitude; (4) estimation of the frequency - magnitude relationship; (5) computation of the distribution function for focal distance; (6) correlation between focal depth and magnitude; (7) attenuation law. We discuss also the implications of the model parameters on the seismic hazard level. (authors)

  12. The Terrestrial NPP Simulation in China since 6ka BP

    Institute of Scientific and Technical Information of China (English)

    HE Yong; DONG Wenjie; JI Jinjun; DAN Li

    2005-01-01

    A better understanding of the long-term global carbon cycle required estimate of the changes in terrestrial carbon storage after the last glacial period. The results of simulation at mid-Holocene (MH) from PMIP (Paleoclimate Modeling Intercomparison Project) and the modern data from CRU (Climate Research Unit,East Anglia University, UK) allow us to use the Atmosphere-Vegetation Interaction Model (AVIM) to simulate the Chinese terrestrial net primary productivity (NPP) at 6ka BP and present time. The change of NPP and total NPP in China from now to mid-Holocene are about 54 g m-2yr-1 and 0.63 Pg yr-1,respectively, mainly due to the build-up of temperate forest and tropical rainforest. Chinese terrestrial NPP variation from MH to now is closely related to the variation in intensity of Asian monsoon, which controlled the climate-vegetation pattern change.

  13. A historical survey of the Ignalina NPP

    International Nuclear Information System (INIS)

    Full text: When the boom of nuclear power industry began in the former Soviet Union, the idea of constructing the Ignalina NPP occurred to the circles in Moscow's central institutions at the turn of the 1970s. The nuclear power plant remained a facility under all-union jurisdiction supervised by the Ministries of Atomic Energy and Medium-Machine Building of the USSR from September 16, 1971, when the Central Committee of the Communist Party of the Soviet Union and the Council of Ministers of the Soviet Union adopted the resolution regarding the beginning of its construction, until Lithuania regained independence in 1990. Nuclear power is the basis of Lithuania's power industry. The Ignalina NPP is a product of the former Soviet Union. Two reactors of RBMK-1SOO type are operational at the Ignalina NPP. This is the most advanced and the most recent version of the RBMK reactor design series (only two reactors of this type have ever been built). The power plant was built as part of the Soviet Union's North-West Unified Power System rather than to meet Lithuania's needs. The first unit of Ignalina NPP was commissioned in late 1983, and the second one in August 1987. A total of four units with RBI/1K-1S00 reactors were to be built. However, due to political and safety motives the construction of the third unit was suspended as early as 1989. After Lithuania declared independence in 1990, the Ignalina NPP was still guarded by Soviet troops and KGB operatives, and remained under the jurisdiction of the Soviet Union until August 1991. Supervision was carried out by that country's regulatory authority, the State Nuclear Power Supervision Inspection (Gosatomnadzor). It was only after the political events of August 1991 in Moscow that the Ignalina NPP finally came under the authority of the Lithuanian Republic. It is now controlled administratively by the Lithuanian Ministry of Economy, and its supervision is carried out by the Lithuanian State Nuclear Power Safety Inspectorate

  14. The performance shaping factors influence analysis on the human reliability for NPP operation

    International Nuclear Information System (INIS)

    The Human Reliability Analysis (HRA) is an important step in Probabilistic Safety Assessment (PSA) studies and offers an advisability for concrete improvement of the man - machine - organization interfaces, reliability and safety. The goals of this analysis are to obtain sufficient details in order to understand and document all-important factors that affect human performance. The purpose of this paper is to estimate the human errors probabilities in view of the negative or positive effect of the human performance shaping factors (PSFs) for the mitigation of the initiating events which could occur in Nuclear Power Plant (NPP). Using THERP and SPAR-H methods, an analysis model of PSFs influence on the human reliability is performed. This model is applied to more important activities, that are necessary to mitigate 'one steam generator tube failure' event at Cernavoda NPP. The results are joint human error probabilities (JHEP) values estimated for the following situations: without regarding to PSFs influence; with PSFs in specific conditions; with PSFs which could have only positive influence and with PSFs which could have only negative influence. In addition, PSFs with negative influence were identified and using the DOE method, the necessary activities for changing negative influence were assigned. (authors)

  15. Impact of nuclear information on the public acceptance. Case study for young people in Cernavoda and Pitesti towns

    International Nuclear Information System (INIS)

    The general objective of this work was to investigate the impact of nuclear information on young people's knowledge and attitudes by using different Methods/Participatory Tools in an Educational Programme. The investigation started with a baseline survey of six groups of youngsters, three each from Pitesti and Cernavoda, which was completed early in 2005. After analysing the results an Educational Programme was proposed and developed following the FP6- COWAM2 Annual Seminar at Ljubljana. The Programme was produced by November 2005 and three methods were selected: classical methods usually used for school teaching, the discovery method, and a method involving simulation of a Local Committee. Three groups from Pitesti and four from Cernavoda attended the Programme, which was followed by a new questionnaire-based measurement (May 2006). (authors)

  16. SAT for NPP personnel training in USA

    International Nuclear Information System (INIS)

    This discussion addressed the experience with the application of SAT at USA NPPs. In particular, the transition of NPP training processes, staff composition, and reporting structure from the TMI accident to present. As well, oversight and guidance activities of the INPO and more intensive inspection by the NRC began during this period. The average NPP training staff grew to 30-40 per unit, along with a change in reporting line from plant to corporate management. With the reduction of resources occurring in the late 1980s, overall training staff size decreased, the composition changed, and reporting line reverted to plant management. The overall lessons-learned for application of the SAT consisted of the need for simplification, management involvement, and exploitation of the technology

  17. Human Resources Training Requirement on NPP Operation and Maintenance

    International Nuclear Information System (INIS)

    This paper discussed the human resources requirement on Nuclear Power Plant (NPP) operation and maintenance (O&M) phase related with the training required for O&M personnel. In addition, this paper also briefly discussed the availability of training facilities domestically include with some suggestion to develop the training facilities intended for the near future time in Indonesia. This paper was developed under the assumptions that Indonesia will build twin unit of NPP with capacity 1000 MWe for each using the turnkey contract method. The total of NPP O&M personnel were predicted about 692 peoples which consists of 42 personnel located in the head quarter and the rest 650 people work at NPP site. Up until now, Indonesia had the experience on operating and maintaining the nonnuclear power plant and several research reactors namely Kartini Reactor Yogyakarta, Triga Mark II Reactor Bandung, and GA Siwabessy Reactor Serpong. Beside that, experience on operating and maintaining the NPP in other countries would act as one of the reference to Indonesia in formulating an appropriate strategy to develop NPP human resources particularly in O&M phases. Education and training development program could be done trough the cooperation with vendor candidates. (author)

  18. NPOESS Preparatory Project (NPP) Science Overview

    Science.gov (United States)

    Butler, James J.

    2011-01-01

    NPP Instruments are: (1) well understood thanks to instrument comprehensive test, characterization and calibration programs. (2) Government team ready for October 25 launch followed by instrument activation and Intensive Calibration/Validation (ICV). NPP Data Products preliminary work includes: (1) JPSS Center for Satellite Applications and Research (STAR) team ready to support NPP ICV and operational data products. (2) NASA NPP science team ready to support NPP ICV and EOS data continuity.

  19. Suomi NPP Ground System Performance

    Science.gov (United States)

    Grant, K. D.; Bergeron, C.

    2013-12-01

    The National Oceanic and Atmospheric Administration (NOAA) and National Aeronautics and Space Administration (NASA) are jointly acquiring the next-generation civilian weather and environmental satellite system: the Joint Polar Satellite System (JPSS). JPSS will replace the afternoon orbit component and ground processing system of the current Polar-orbiting Operational Environmental Satellites (POES) managed by NOAA. The JPSS satellites will carry a suite of sensors designed to collect meteorological, oceanographic, climatological and geophysical observations of the Earth. The first satellite in the JPSS constellation, known as the Suomi National Polar-orbiting Partnership (Suomi NPP) satellite, was launched on 28 October 2011, and is currently undergoing product calibration and validation activities. As products reach a beta level of maturity, they are made available to the community through NOAA's Comprehensive Large Array-data Stewardship System (CLASS). CGS's data processing capability processes the satellite data from the Joint Polar Satellite System satellites to provide environmental data products (including Sensor Data Records (SDRs) and Environmental Data Records (EDRs)) to NOAA and Department of Defense (DoD) processing centers operated by the United States government. CGS is currently processing and delivering SDRs and EDRs for Suomi NPP and will continue through the lifetime of the Joint Polar Satellite System programs. Following the launch and sensor activation phase of the Suomi NPP mission, full volume data traffic is now flowing from the satellite through CGS's C3, data processing, and data delivery systems. Ground system performance is critical for this operational system. As part of early system checkout, Raytheon measured all aspects of data acquisition, routing, processing, and delivery to ensure operational performance requirements are met, and will continue to be met throughout the mission. Raytheon developed a tool to measure, categorize, and

  20. Psychology of NPP operation safety

    International Nuclear Information System (INIS)

    The book is devoted to psychologic investigations into different aspects of NPP operative personnel activities. The whole set of conditions on which successful and accident-free personnel operation depends, is analysed. Based on original engineering and socio-psychologic investigations complex psychologic support for NPP personnel and a system of training and upkeep of operative personnel skills are developed. The methods proposed have undergone a practical examination and proved their efficiency. 154 refs., 12 figs., 9 tabs

  1. 数字化核电厂全范围模拟机研制方案概述%The Development Scheme of Full Scope Simulator for DCS-based NPP Unit

    Institute of Scientific and Technical Information of China (English)

    陈春丽

    2014-01-01

    概述了核电厂全范围模拟机的性能和功能要求及最新应用,阐述了当今主流数字化控制核电厂全范围模拟机的总体研制方案,并着重针对数字化仪控系统的不同处理方式进行了性能和经济性的比较。最后介绍了方家山核电工程1、2号机组全范围模拟机的技术方案。%The paper summarizes the requirements for the Full Scope Simulator of current nuclear power plant , and the new application demands in V&V field as well .For DCS-based Nuclear Power Plant unit , the devel-opment scheme of its Full Scope Simulator is introduced , and different solutions to DCS implementation are compared .And the technical solution to the Full scope simulator of Fangjiashan NPP is described as an exam -ple.

  2. Temelin NPP status and challenge

    International Nuclear Information System (INIS)

    In this presentation author deals with the NPP Temelin status and challenge. It was concluded that: - Temelin NPP was modified from the every beginning in order to meat internationally acceptable safety level; - IAEA, US and Western countries safety principles, criteria and requirements are mostly applied; - Number of international safety review missions confirmed this fact; All assessments of the Temelin NPP have been positive and all recommendations were carefully considered and either implemented or other equivalent solution was found. Temelin NPP Halliburton NUS audit in 1992 stated that Temelin can be licensable, but licensibility could not be assured unless the audit team's technical and programmatic recommendations are implemented. ENCONET Consulting (Austria) in 1998 stated that: - After modifications are fully implemented, Temelin NPP will be a much safer plant than originally designed and much more safer than some of the already operating WWER 1000 plants; - The process of compatibility was specifically assured by selecting prudent practices acceptable in the Western countries. IAEA mission on Safety issues resolution (1996) stated that: - It is recognized that the Czech Electric Company (CEZ) has made a large effort to improve the design of Temelin independently of the identification of safety issues by the IAEA

  3. Demands on project management of comprehensive modernization projects in the electrical systems area. Example of modernization of electrical systems of Kozloduy NPP Unit 5 and 6

    Energy Technology Data Exchange (ETDEWEB)

    Stinshoff, Helmut; Weber, Patrick [Framatome ANP GmbH, P.O. Box 3220, Freyeslebenstrasse 1, D-91050 Erlangen (Germany)

    2006-07-01

    In nuclear power plants, station supply with electric energy must be guaranteed any time. This applies in particular also during the implementation of complex electrical systems modernization projects. Highest demands on the project management, extensive experience and system knowledge are required. In the frame of the Modernization Program for the nuclear power plant Kozloduy unit 5 and 6 in Bulgaria Framatome ANP has approved its ability to implement a large scope of modernization measures during the refueling outages of the years 2003 to 2005. The Contract of the Modernization Program for the European Consortium Kozloduy (Framatome ANP, Atomenergoexport) was signed in July 1999 and became effective in June 2001. The project will be finished by May 2006, with the approval of the Updated Final Safety Analysis Report. The scope of hardware work has been implemented within 6 plant outages during the years 2002 to 2005. The focus of the Modernization Program is mainly oriented to nuclear safety aspects, with the aim of upgrading of the Units to a high safety level in compliance with international practice. A further section of the project is dedicated to upgrading of operational equipment. Framatome ANP personnel have shown that besides the technical challenges which had to be faced, also the intercultural and language barriers were successfully overcome. The good teamwork between the partners of the Consortium ECK, its Bulgarian subcontractors and with Kozloduy plant personnel has been an important success factor. (authors)

  4. Main principles of the Chernobyl' NPP zone development

    International Nuclear Information System (INIS)

    It is suggested to divide the Chernobyl' NPP zone into two parts, which are the alienation and evacuation (buffer) zones. The alienation zone includes the areas with greatest contamination around the Chernobyl' NPP. The population residence in this zone is forbidden. The watching method of working with short-time personnel residence is suggested to be used in this zone. The buffer zone is the territory out of the alienation zone boundaries including all settlements, from which the population is evacuated. Constant residence is permitted in the buffer zone for persons 50 and more years old with introduction of restrictions for diet and residence organization. The production activity in this zone includes operation of three units of the Chernobyl' NPP, works with the Ukrytie object and researches. Operations connected with radioactive waste processing and redisposal from places of storage is not recommended to be done. It is suggested to develop methods for local radioactive waste processing

  5. Kozloduy NPP intranet portal, Bulgaria

    International Nuclear Information System (INIS)

    The Kozloduy NPP intranet portal was established in the late 1990s. The purpose of the portal was to provide access to general and frequently used information necessary for routine and daily work of the plant staff. Over the years the intranet site has been continuously improved and extended. The portal is now a standard tool for every member of plant personnel. The portal architecture has been designed on a modular basis and follows the general structure of the plant. The home page contains general, publicly accessible and frequently used information and corresponding links. Each major division maintains its own sub-portal, which services the specific needs of the division personnel. Hierarchical structure, pull down and shortcut menus facilitate navigation and provide a user friendly interface. The portal is based on FrameWork 1.1 and DotNetNuke and provides group and individual communications and data exchange. Most of the major plant databases related to documentation, plant operation, plant safety, plant systems data, training and human resources are accessible through the portal. Miscellaneous information and useful internal and external links also are available. Different types of communication services are organized through a separate server. Depending on their role and position, each staff member has been provided with an internal and/or external email address and an individually configured internet connection. For general purposes cable internet is accessible at several points, which are evenly located around the site, and there is also a secure wireless network connection. Search and retrieve functions are implemented through respective engines, which are incorporated into applications. The portal has a strongly defined access rights system. Anonymous access is prevented; page personalization is available only for limited specific cases. Figures show the home page and the path to Units 5 and 6 on-line technical parameters

  6. Corrosion of copper-alloy tubes in the NPP cooling systems

    International Nuclear Information System (INIS)

    Factors efficiency on leaks in the NPP power unit steam turbine condensers are analyzed. Causes of corrosion - erosion wear of copper-alloy tubes are considered. A model for calculation of copper and copper-nickel alloy corrosion is proposed

  7. Acceptable risk as the criteria for NPP efficiency and safety

    International Nuclear Information System (INIS)

    Four types of criteria of effective and safe operation of NPP power units are studied and formulated. Criterion types are formulated in risk terms of failure to comply problems, losses of capital outlays and territory (ecological risk), NPP personnel and population health damage. The structure of losses and profiles under conditions of the modern economic system is considered for the given types of criteria. The mathematical cost-profit model of a stochastic processes of power unit utilization is developed. The explicit functional form of the positive effect on the process trajectories for each of criterion types is constructed. The functional construction is based on the representation of a power unit as a generator of random events leading to power unit failure its damage or loss of territory, correspondingly

  8. Main public health risk factors nearby NPP construction site

    International Nuclear Information System (INIS)

    Full text:This paper discusses methods, which were developed based on original results and international recommendations, for processing and analysis of data on environmental monitoring to assess risk of adverse ecological consequences. The methods considered are also applicable for the data relevant to the territories nearby NPP construction site. Factor of both radiational and non-radiational origin, which may cause adverse health effects, were analyzed. An algorithm for assessment of environmental contamination was developed and coded in Delphi. The algorithm allows calculating integral contamination coefficient, getting information on safety state of a facility, and studying human body interaction with the environment under various conditions at work and home. Existing chemical and radiational parameters of the environment in the vicinity of the NPP construction site were considered. A potential environmental contamination form radioactive gaseous and aerosol emission during normal operation of 2 VVER-1200 units was estimated. Calculations showed that maximal soil surface contamination will not exceed 0.144 Bq/m2 (3.89·10-6 Ci/km2) during the first year of NPP operation. By the end of 60 years of NPP operation, maximal soil contamination will have increased by 1.67 Bq/m2 (4.5·10-5 Ci/km2). Fraction of soil contamination with radionuclides from NPP emission will be insignificant and will have reached 9.0·10-2 % by the end of 60 years of NPP operation. Individual annual exposure of population due to gaseous and aerosol emissions is 4.5·10-4 mSv (0.045% of the annual dose limit as recommended by radiation safety norms) in the maximal contamination spot at normal operation of 2 VVER-1200 units. Experimental measurements of pollutants' content in the atmospheric air on the territory being researched were done at Republic Center for Radiation Control and Environmental Monitoring. Experimentally obtained data on radioactive contamination of atmospheric air nearby

  9. Nuclear Oversight Function at Krsko NPP

    International Nuclear Information System (INIS)

    industry experience (events, good practice etc.) in its assessment. That becomes most important in small utilities (with one nuclear unit only) such as the Krsko NPP. Involvement in international organizations is therefore a must and not an option for such organization. The Krsko NPP is today widely involved in various international organizations. Both sides are deriving substantial benefits from such cooperation.(author).

  10. Unification as a method to increase NPP component quality

    International Nuclear Information System (INIS)

    The experience of unifjcation of standard sizes of applied materials (rolled stock, tubes) of structural elements (threads, radii, grooves), detail and equipment units in the course of reactors development is investigated. Examples of unification of the WWER-1000 reactor pipe connections, equipment units, NPP equipment unification level with WWER-440 and WWER-1000 reactors are indicated. Coefficients of equipment applicability which in author's opinion must be 30-70% are given

  11. Feed water distribution pipe replacement at Loviisa NPP

    Energy Technology Data Exchange (ETDEWEB)

    Savolainen, S.; Elsing, B. [Imatran Voima Loviisa NPP (Finland)

    1995-12-31

    Imatran Voima Oy operates two WWER-440 reactors. Unit 1 has been operating since 1977 and unit 2 since 1981. First damages of feed water distribution (FWD) pipe were observed in 1989. The FWD-pipe T-connection had suffered from severe erosion corrosion damages. Similar damages have been been found also in other WWER-440 type NPPs. In 1989 the nozzles of the steam generator YB11 were inspected. No signs of the damages or signs of erosion were detected. The first damaged nozzles were found in 1992 in steam generators of both units. In 1992 it was started studying different possibilities to either repair or replace the damaged FWD-pipes. Due to the difficult conditions for repairing the damaged nozzles it was decided to study different FWD-pipe constructions. In 1991 two new feedwater distributors had been implemented at Dukovany NPP designed by Vitckovice company. Additionally OKB Gidropress had presented their design for new collector. In spring 1994 all the six steam generators of Rovno NPP unit 1 were replaced with FWD-pipes designed by OKB Gidropress. After the implementation an experimental program with the new systems was carried out. Due to the successful experiments at Rovno NPP Unit 1 it was decided to implement `Gidropress solution` during 1994 refueling outage into the steam generator YB52 at Loviisa 2. The object of this paper is to discuss the new FWD-pipe and its effects on the plant safety during normal and accident conditions. (orig.).

  12. Risk indicators at Cofrentes NPP

    International Nuclear Information System (INIS)

    Following the tend to try to find indicators to show the excellence in the performance where Nuclear Power Plants are currently involved, Cofrentes NPP are managing several indicators related with risk. The concept of risk is classically associated with the product RISK = PROBABILITY * DAMAGE So what a risk based indicator will show is the probability of having a 'damage'. Speaking about a period of time, we will have frequencies of having 'damages'. What is call 'damage' can be differently interpreted depending of what we concern. In western NPP is very extended the concept of 'core damage', meaning the loss of fuel integrity, as a final state to avoid. This have carried in most of western NPP to develop a Probabilistic Risk Assessment (PRA/PSA), that using technical based in fault trees and event trees models, looks for the frequency to reach core damage. The PSA in Cofrentes NPP has been deeply applied to find weakness in the design and procedures, prioritizations in maintenance activities, quality assurance requirements, justifications to continued operation, and others. A Risk Monitor based in PSA models (and so monitoring the Core Damage Frequency) has been developed and is currently installed in the Control Room to help operators to control the risk associated with each configuration of availability or unavailability of equipments. This PSA Monitor is the source for some indicators that Cofrentes NPP has defined and are sharing with IAEA trying to find an standard. Maximum Core Damage Frequency reached and accumulated annual probability is calculated and compared with expected values and with predefined limits. As the PSA in Cofrentes NPP is only for at power Operations, there has been developed a methodology based on NUMARC 91-06 to measure and control the risk during shutdowns. The 'damage' here is a concept related with the safety functions. Some coefficients are applied to each configuration according with how the safety functions are fulfilled (defense

  13. Artificial intelligence and NPP safety

    International Nuclear Information System (INIS)

    The main tasks of the software for probabilistic safety analysis, thermal hydraulic analysis and probabilistic risk assessment are discussed. Their combination for direct improvement of NPP operation through information support of the staff is stressed. The general philosophy (in-depth protection) of computerized Emergency Response Guidelines (ERGs) - symptom based (safety parameters) and events-oriented (types of accident) is pointed out. The use of expert systems for proper diagnosing of the accident, its forecasting and finding the way of overcoming it is shown. Mandatory components of the modern management policy in abnormal situations are: the ERGs, the installation of Safety Parameter Display panels, the availability of an safety engineer (superviser); local, regional and national systems for monitoring of the radiation environment within and outside the NPP; local protection centres for maintenance in the case of accident. The importance of verification and validation (V and V) approach and benchmark exercise is stressed. Some peculiarities of the on-going implementation of the computerized information system for radiation control in Kozloduj NPP are discussed. 3 figs, 7 refs

  14. User experiences using the operator support systems SCORPIO and SPDS at Kola NPP

    International Nuclear Information System (INIS)

    Full text: During the years from 2000 to 2004 a Safety Parameter Display System (SPDS) and a SCORPIO-VVER system have been installed and put into operation at Kola NPP in northern Russia. The projects have been carried out in co-operation with Finnish and Russian subcontractors with IFE, Halden, as the main contractor and the project manager. Both projects have been defined within the Norwegian Assistance Programme to Nuclear Installations at the Kola Peninsula and financed by the Norwegian government. The SPDS project has also been partly financed by the Finnish government. The Kola SPDS, which is based on a system originally developed for the Loviisa Nuclear Power Plant in Finland, was installed and put into operation on Kola NPP units 1 and 2 in April 2000 and on Kola NPP units 3 and 4 in March 2004. The system has been licensed and approved by Russian authority (GAN) for use in the control room environment. The SCORPIO-VVER system is based on the SCORPIO-VVER framework developed for Dukovany NPP, Czech Republic and Bohunice NPP, Slovak Republic. Further, the experience gained with the SCORPIO framework developed for Western PWRs have been utilised. The SCORPIO-VVER system was installed and put into operation at Kola NPP Nuclear Safety Centre in December 2003 for core monitoring on units 3 and 4. The user experiences by introducing the SPDS and the SCORPIO-VVER system at Kola NPP are so far very positive. By introducing an SPDS at Kola NPP, the process safety status (single or combinations of signals) is presented for the operator in a centralized location (on one screen) in the control room and in a form that makes it easier to obtain a quick assessment of the process safety status. According to feedback from control room personnel the SPDS has enhanced the monitoring of the safety status of the plant. The reactor core is the most central component of a nuclear power plant and a comprehensive core monitoring system is very important for maintaining reactor

  15. Evaluation of radiation impacts of spent nuclear fuel storage (ISP-2) of Chernobyl NPP

    International Nuclear Information System (INIS)

    The estimation of radiation impacts during normal operation of dry spent fuel storage facility for ChNPP RBMK reactors, designed for long-term storage of spent fuel assemblies (SFA), which originated from the operation 1,2,and 3 units ChNPP was made. It is shown that the maximum concentration of radionuclides in the air near the ISF-2 well below allowable concentration for the population, and additional pollution is negligible in comparison with the existing one

  16. Lessons learnt from Ignalina NPP decommissioning project

    International Nuclear Information System (INIS)

    The Ignalina Nuclear Power Plant (INPP) is located in Lithuania, 130 km north of Vilnius, and consists of two 1500 MWe RBMK type units, commissioned respectively in December 1983 and August 1987. On the 1. of May 2004, the Republic of Lithuania became a member of the European Union. With the protocol on the Ignalina Nuclear Power in Lithuania which is annexed to the Accession Treaty, the Contracting Parties have agreed: - On Lithuanian side, to commit closure of unit 1 of INPP before 2005 and of Unit 2 by 31 December 2009; - On European Union side, to provide adequate additional Community assistance to the efforts of Lithuania to decommission INPP. The paper is divided in two parts. The first part describes how, starting from this agreement, the project was launched and organized, what is its present status and which activities are planned to reach the final ambitious objective of a green field. To give a global picture, the content of the different projects that were defined and the licensing process will also be presented. In the second part, the paper will focus on the lessons learnt. It will explain the difficulties encountered to define the decommissioning strategy, considering both immediate or differed dismantling options and why the first option was finally selected. The paper will mention other challenges and problems that the different actors of the project faced and how they were managed and solved. The paper will be written by representatives of the Ignalina NPP and of the Project Management Unit. (author)

  17. Ignalina NPP: living and working conditions

    International Nuclear Information System (INIS)

    The conference was devoted to discuss the social problems related with the operation of Ignalina NPP. The main topics are the following: analysis of public opinion of surrounding region of Ignalina NPP including neighbouring Daugavpils district in Latvia, environment impact evaluation of Daugavpils district, assessment of the influence of Ignalina NPP operation to the development of business in the region, investigation of problems of Visaginas town - residence of Ignalina NPP personnel. The specificity of Visaginas (former Sniechkus) is defined by the majority of non-native Lithuanians living there. Cultural transformation and political organization of the region were surveyed as well

  18. NPP technical and economical parameters and safety

    International Nuclear Information System (INIS)

    The problem of the ratio between technical and economic indices of NPP and its safety has been considered. It is suggested that safety indices of NPP projected should be made allowance for, when calculating net cost of electric power generated so, that NPP with higher safety indices remained competitive. The problem can be solved using a special invariance fund for compensating the costs of protection measures taken. The amount of contribution is to be the higher, the lower are safety indices of NPP. 2 refs

  19. The role of research programs and commercial contracts for increase of economic competitiveness and development at INR Pitesti

    International Nuclear Information System (INIS)

    In the period in which globalization is increasing, one of the strategic objectives of the institute is to focus on those activities which help developing of services, products and technologies, applicable in nuclear industry, environment protection and medicine. One way to sustain INR activity is the technological transfer which ensures availability of research results by carrying out of R and D contracts in priority areas and of contracts with economical agents for the supply of services, products, technologies, such as: - Materials irradiation for medicine, industry and research; - Neutron Activation Analysis (NAA) and prompt gamma spectrometry for Cernavoda NPP - Unit 1; - Control and testing: non-destructive examination, functional tests of samples and equipment from Cernavoda NPP - Unit 1; - Characterization, conditioning and treatment of radioactive wastes for NPP- Cernavoda, Unit 1, Nuclear Fuel Plant (FCN) - Pitesti; - Measurement of isotopes concentration in environmental samples; -Corrosion experiments in static autoclaves and experiments regarding microbial corrosion for NPP Cernavoda Unit 1 and FCN Pitesti; - Nuclear consultancy for Cernavoda NPP - Unit 1 and Unit 2; - Stainless steel casks for radwaste; - Containers for heavy water; - Training and practice for students at the Universities of Pitesti, Bucuresti, Brasov. The paper presents the main areas where the results obtained in R and D programs can be applied, their implementation can be done, and the status of contracts and their importance for INR Pitesti and Romanian society development, as well. (authors)

  20. Polish media and public opinion on NPP Mochovce commissioning

    International Nuclear Information System (INIS)

    The so called 'Mochovce Problem' was one of the major topics in Polish media in the period from May to July 1998. The nuclear power plant commissioning caused an unexpectedly strong reaction, especially in the newspapers, slightly less so in electronic media. Faced with clearly hostile media reaction to Mochovce NPP, the National Atomic Energy Agency representatives, together with atomic and nuclear experts, undertook to change these attitudes. In numerous interviews, letters to the editors and talks with journalists, they attempted to correct the mistakes, explain the true safety situation in the nuclear power plant, by whom it was constructed, who supervised and tested the systems and so on. The completion of Mochovce NPP construction improved significantly the electricity balance in Slovakia, thus decreasing the pressure for continuing the operation of older Bohunice V1 units beyond their design lifetime. For this reason, as well as in view of striving for improvement in environmental factors beyond Polish southern border, especially after Kyoto/97 decisions on greenhouse gases emissions, the public opinion in Poland should support the Mochovce NPP construction. In 1996 Poland has signed with Slovakia a bilateral inter-governmental agreement on the prompt notification on nuclear accidents and on the cooperation in the nuclear safety and radiological protection matters. On the basis of this agreement the experts from Polish National Atomic Energy Agency are in perpetual contact with Slovakian Nuclear Regulatory Body and in each and every moment can obtain full and comprehensive information on the plant parameters iportant for nuclear safety. The experts explanations, together with the NAEA top management visit to the plant itself, brought some results. The media became less aggressive, and Polish public and authorities - contrary to the Austrians - do not protest loudly against the commissioning of this newest European NPP. Now, in December 1998, the tune of

  1. The kinetics of aerosol particle formation and removal in NPP severe accidents

    Science.gov (United States)

    Zatevakhin, Mikhail A.; Arefiev, Valentin K.; Semashko, Sergey E.; Dolganov, Rostislav A.

    2016-06-01

    Severe Nuclear Power Plant (NPP) accidents are accompanied by release of a massive amount of energy, radioactive products and hydrogen into the atmosphere of the NPP containment. A valid estimation of consequences of such accidents can only be carried out through the use of the integrated codes comprising a description of the basic processes which determine the consequences. A brief description of a coupled aerosol and thermal-hydraulic code to be used for the calculation of the aerosol kinetics within the NPP containment in case of a severe accident is given. The code comprises a KIN aerosol unit integrated into the KUPOL-M thermal-hydraulic code. Some features of aerosol behavior in severe NPP accidents are briefly described.

  2. Emergency preparedness at Barsebaeck NPP in Sweden

    International Nuclear Information System (INIS)

    On-site emergency preparedness plan at Barsebaeck NPP is presented. In an emergency the responsibility of the NPP is to alarm the emergency organizations, spend all efforts to restore safe operation, assess the potential source term as to size and time, protect their own personnel, inform personnel and public. Detailed emergency procedures overview is provided

  3. The decommissioning NPP A-1

    International Nuclear Information System (INIS)

    Project of decommissioning NPP A-1 is split into 4 main groups of tasks. Tasks in group 1 are focused on the solution of selected problems that have immediate impact on the environment. It is mainly the solution of problems in the building of cleaning station of wastage water and in the building with underground storage tanks for wastage water and solid radwaste, including the prevention of wash-out and penetration of contaminated soil from these buildings into surface and underground waters. A part of addressing these tasks is a controlled of generated radwaste-predominatly sludge with various physical and chemical properties. Tasks in group 2- following the removal of spent fuel-are focused on the management of all radwaste in the long-term storage facility, in the short-term storage facility, equipment of transport and technology part, equipment in hot cells. Tasks in group 3 are focused on development of technology procedures for treatment and conditioning of sludge, contaminated soils and concrete crush, saturated ionexes and ash from incineration facility of the Bohunice radwaste treatment and conditioning complex. Tasks in group 4 are focused on the methodology. And technical support for particular activities applicable during decommissioning NPP

  4. Enhancing NPP Safety Through an Effective Dependability Management

    International Nuclear Information System (INIS)

    Taking into account the importance of the continuous improvement of the performance and reliability of a NPP and practical measures to strengthen nuclear safety and security, it is to be noted that a good management for a nuclear power reactor involves a ''good dependability management'' of the activities, such as: Reliability, Availability, Maintainability (RAM) and maintenance support. In order to evaluate certain safety assessment criteria intended to be applied at the level of the nuclear reactor unit management, equipment dependability indicators and their impact over the availability and reactor safety have to be evaluated. Reactor equipment dependability indicators provide a quantitative indication of equipment RAM performances (Reliability, Availability and Maintenance). One of the important benefits of maintenance and failure data gathering is that it can be used as a support of probabilistic safety assessment (PSA). Also, a good dependability management implementation may be used to complement reactor level unit performance indicators in the field of safe operation, maintenance and improving operating parameters, as well as for Strengthening Safety and Improving Reliability of a NPP. This paper underlines the importance of nuclear safety and security as prerequisites for nuclear power. In addition, it demonstrates how different technical aspects, through implementation of a good dependability management, contribute to a strengthened safety and an improvement of availability of the NPP through dependability indicators determination and evaluation. (author)

  5. Belene NPP - main approaches in the construction organisation

    International Nuclear Information System (INIS)

    Technical planning for the construction of two units at the Belene NPP is presented. Detailed scheme for the assembling of the containment is given, taking into account the capacity of cranes. For the construction of NPP Belene it is possible to use the existing on-site construction 50 tons cranes, as well as mobile crawler cranes with increased lifting capacity. A timetable for the construction is developed. A shortening of the construction time is possible with 4 months. Improvements of the construction process are suggested including use of ready pipe and equipment modules, automated welding, use of advanced technologies for isolation and concreting, organising and control of the technological processes, use of 3D and 6D modeling etc. The recommended improvements can shorten the construction period to 5-5.5 years

  6. Simulator training and human factor reliability in Kozloduy NPP, Bulgaria

    International Nuclear Information System (INIS)

    This is a PowerPoint presentation. Situated in North Bulgaria, in the vicinity of the town of Kozloduy, near the Danube River bank, there is the Bulgarian Kozloduy Nuclear Power plant operating four WWER-440 and two WWER-1000 units. Units 1 and 2 were commissioned in July, 1974 and November, 1975, respectively. These were shut down at the end of 2003. Units 3 and 4 were commissioned in December, 1980 and May, 1982. They were shut down at the end of 2006 as a precondition for Bulgaria's accession to the European Union. The 1000 MW units 5 and 6 of Kozloduy NPP were commissioned in September, 1988 and December, 1993, respectively. Large-scale modernization have been implemented and now the units meet all international safety standards. The paper describes the multifunctional simulator Kozloduy NPP for the operational staff training. The training stages are as follows: - Preparatory; -Theoretical studies; - Training at the Training Centre by means of technical devices; - Preparation and sitting for an exam before a Kozloduy NPP expert commission; - Simulator training ; - Preparation to obtain a permit for a license, corresponding to the position to begin work at the NPP; - Exams before the Nuclear Regulatory Agency (NRA) and licensing; - Shadow training at the working place; - Permission for unaided operation. The following positions are addressed by the simulator training: - Chief Plant Supervisor; - Shift Unit Supervisor; - Senior Reactor Operator; - Simulator Instructor; - Controller physicist; -Senior Turbine Operator; - Senior Operator of Turbine Feedwater Pumps of Kozloduy NPP. Improving of training method led to a reduction of number of significant events while worldwide practice proves that improvement of engineering resulted in an increase in the percentage of events, related to human factor. Analysis of human reliability in 2005 and 2006 in cooperation with representatives from Great Britain and the Technical University in Sofia were worked on the DTI NSP B

  7. NPP lifetime philosophy: the transatlantic difference

    International Nuclear Information System (INIS)

    Fundamental institutional and cultural differences in the transatlantic nuclear power industries, and in particular those between the Nordic countries and the United States, have driven divergent plant life management strategies -strategies resulting in distinctly different plant performance. Recognition of the linkage between three key components of overall Nuclear Power Plant (NPP) performance - yearly O and M costs, safety, and effective plant lifetime -is based on different institutional perspectives. In the Nordic countries, explicit recognition of this linkage has been historically translated into an integrated approach to plant performance. American NPPs, however, have been forced to focus primarily on near term O and M performance and regulatory mandated investment. While Nordic NPPs view capital investment in plant lifetime management and modernization as necessary to avoid declining plant performance and the cost of replacement power, American NPPs exhibit reluctance for such investments due to the difficulty of justifying the associated short-term costs. The diverging histories of two NPPs of the same vintage and design, one in Sweden and one in the United States, exemplify the potential ramifications of these approaches. The Swedish plant continues to operate with excellent performance indicators, while undertaking a comprehensive and long-term modernization program. The American facility is likely to be decommissioned due to unsustainable economic performance. (author)

  8. Water chemistry of secondary circuit and SG currently status NPP 'Kozloduy' 3

    International Nuclear Information System (INIS)

    The author gives a historical review of the secondary water chemistry regimes of NPP Kozloduy Unit 3. Results of eddy current inspection on the steam generator of Unit 5 and quantity of the deposits on the surfaces of steam generator during 1989-2001 inspections are given. (uke)

  9. Does climate directly influence NPP globally?

    Science.gov (United States)

    Chu, Chengjin; Bartlett, Megan; Wang, Youshi; He, Fangliang; Weiner, Jacob; Chave, Jérôme; Sack, Lawren

    2016-01-01

    The need for rigorous analyses of climate impacts has never been more crucial. Current textbooks state that climate directly influences ecosystem annual net primary productivity (NPP), emphasizing the urgent need to monitor the impacts of climate change. A recent paper challenged this consensus, arguing, based on an analysis of NPP for 1247 woody plant communities across global climate gradients, that temperature and precipitation have negligible direct effects on NPP and only perhaps have indirect effects by constraining total stand biomass (Mtot ) and stand age (a). The authors of that study concluded that the length of the growing season (lgs ) might have a minor influence on NPP, an effect they considered not to be directly related to climate. In this article, we describe flaws that affected that study's conclusions and present novel analyses to disentangle the effects of stand variables and climate in determining NPP. We re-analyzed the same database to partition the direct and indirect effects of climate on NPP, using three approaches: maximum-likelihood model selection, independent-effects analysis, and structural equation modeling. These new analyses showed that about half of the global variation in NPP could be explained by Mtot combined with climate variables and supported strong and direct influences of climate independently of Mtot , both for NPP and for net biomass change averaged across the known lifetime of the stands (ABC = average biomass change). We show that lgs is an important climate variable, intrinsically correlated with, and contributing to mean annual temperature and precipitation (Tann and Pann ), all important climatic drivers of NPP. Our analyses provide guidance for statistical and mechanistic analyses of climate drivers of ecosystem processes for predictive modeling and provide novel evidence supporting the strong, direct role of climate in determining vegetation productivity at the global scale.

  10. Krsko NPP radioactive waste characteristics

    International Nuclear Information System (INIS)

    In May 2005 Krsko NPP initiated the Radioactive Waste Characterization Project and commissioned its realization to the consulting company Enconet International, Zagreb. The Agency for Radwaste Management was invited to participate on the Project. The Project was successfully closed out in August 2006. The main Project goal consisted of systematization the existing and gathering the missing radiological, chemical, physical, mechanical, thermal and biological information and data on radioactive waste. In a general perspective, the Project may also be considered as a part of broader scope of activities to support state efforts to find a disposal solution for radioactive waste in Slovenia. The operational low and intermediate level radioactive waste has been structured into 6 waste streams that contain evaporator concentrates and tank sludges, spent ion resins, spent filters, compressible and non-compressible waste as well as specific waste. For each of mentioned waste streams, process schemes have been developed including raw waste, treatment and conditioning technologies, waste forms, containers and waste packages. In the paper the main results of the Characterization Project will be briefly described. The results will indicate that there are 17 different types of raw waste that have been processed by applying 9 treatment/conditioning technologies. By this way 18 different waste forms have been produced and stored into 3 types of containers. Within each type of container several combinations should be distinguished. Considering all of this, there are 34 different types of waste packages altogether that are currently stored in the Solid Radwaste Storage Facility at the Krsko NPP site. Because of these findings a new identification system has been recommended and consequently the improvement of the existing database on radioactive waste has been proposed. The potential areas of further in depth characterization are indicated. In the paper a brief description on the

  11. COMPARISON OF NOVORONEZH UNIT 5 NPP AND SOUTH UKRAINE UNIT 1 NPP LEVEL I PRA RESULTS.

    Energy Technology Data Exchange (ETDEWEB)

    MUSICKI,Z.; GINSBERG,T.

    2002-04-18

    This paper describes a study undertaken to explain the risk profile differences in the results of PRAs of two similar WER-1000 nuclear power plants. The risk profile differences are particularly significant in the area of small steam/feedwater line breaks, small-small LOCAs, support system initiators and containment bypass initiators. A top level (limited depth) approach was used in which we studied design differences, major assumptions, data differences, and also compared the two PRA analyses on an element-by-element basis in order to discern the major causative factors for the risk profile differences. We conclude that the major risk profile differences are due to differences in assumptions and engineering judgment (possibly combined with some design and data differences) involved in treatment of uncertain physical phenomena (primarily sump plugging in LOCAs and turbine building steaming effects in secondary system breaks). Additional major differences are attributable to support system characteristics.

  12. Reliability analysis of protection systems in NPP applying fault-tree analysis method

    International Nuclear Information System (INIS)

    This paper demonstrates the applicability and limits of dependability analysis in nuclear power plants (NPPS) based on the reactor protection refurbishment project (RRP) in NPP Paks. This paper illustrates case studies from the reliability analysis for NPP Paks. It also investigates the solutions for the connection between the data acquisition and subsystem control units (TSs) and the voter units (VTs), it analyzes the influence of the voting in the VT computer level, it studies the effects of the testing procedures to the dependability parameters. (author)

  13. Intranet portal at the Krsko NPP, Slovenia

    International Nuclear Information System (INIS)

    The intranet portal (named IntraNEK) at Krsko NPP serves as a single entry point to access the internet and various plant applications and links. The front page consists of the standard internet search bar and links to various applications that can either reside within the technological computer network (TRM) or within the plant business computer network. Access to the TRM applications is read only. Some applications on the business computer network are open to all personnel who log on to the network while some applications are restricted and secured, and require additional login entries. A selected link will open in a new window. Documents will open with the appropriate software tool depending on the document file format. Some categories of documents are available in image form only (e.g. procedures, drawings etc.), while some are available in fully searchable PDF format (e.g. technical specifications, updated safety analysis reports (USARs) etc.). Plant departments (organizational units) have their own pages accessible from the front page. Their pages contain links to their own information resources or links to other resources and applications, tailored to the department needs. During recent years a number of web based applications have been developed that are connected also with a common Oracle database. Some are designed to serve for data entry and browsing while others serve for browsing only

  14. Optimizing NPP performance and service life

    International Nuclear Information System (INIS)

    The most effective way for new power production in Ukraine is the completions of the Khmelnitskij 2 and Rovno 4 NPP project. The report presents the financing terms and conditions of the Energoatom corporate bonds issue

  15. Krsko NPP Periodic Safety Review program

    International Nuclear Information System (INIS)

    The need for conducting a Periodic Safety Review for the Krsko NPP has been clearly recognized both by the NEK and the regulator (SNSA). The PSR would be highly desirable both in the light of current trends in safety oversight practices and because of many benefits it is capable to provide. On January 11, 2001 the SNSA issued a decision requesting the Krsko NPP to prepare a program and determine a schedule for the implementation of the program for 'Periodic Safety Review of NPP Krsko'. The program, which is required to be in accordance with the IAEA safety philosophy and with the EU practice, was submitted for the approval to the SNSA by the end of March 2001. The paper summarizes Krsko NPP Periodic Safety Review Program [1] including implemented SNSA and IAEA Expert Mission comments.(author)

  16. Treatment of NPP wastes using vitrification

    International Nuclear Information System (INIS)

    Glass-based materials to immobilize various liquid and solid radioactive wastes generated at nuclear power plants (NPP) were designed. Glassy waste forms can be produced using electric melting including a cold crucible melting. Leach rate of cesium was found to be 10-5-10-6 g/(cm2 day) (IAEA technique). Volume reduction factor after vitrification reached 4-5. Various technologies for NPP waste vitrification were developed. Direct vitrification means feeding of source waste into the melter with formation of glassy waste form to be disposed. Joule heated ceramic melter, and cold crucible were tested. Process variables at treatment of Kursk, Chernobyl (RBMK), Kalinin, Novovoronezh (VVER) NPP wastes were determined. The most promising melter was found to be the cold crucible. Pilot plant based on the cold crucibles has been designed and constructed. Solid burnable NPP wastes are incinerated and slags are incorporated in glass. (author)

  17. Electrical Grid Conditioning For First NPP Integration, a Systems Engineering Approach Incorporating Quality Function Deployment

    Energy Technology Data Exchange (ETDEWEB)

    Pwani, Henry; James, J. [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-10-15

    Nuclear power plant has a high potential to cause serious harm to environment as evidenced by effects of Fukushima and Chernobyl accidents. A reliable electrical power is required for a NPP to facilitate cooling after a shutdown. Failure of electrical power supply during shutdown increases core damage probability. Research shows that a total of 39% of LOOP related events in US are electrical grid centered. In Korea, 38% and 29% of all events that led to NPP shutdown at Hanul units 3-6 and at Hanbit units 3-6 respectively were electrical related. Electric grids for both operating and new NPPs must therefore be examined and upgraded for reliability improvement in order to enhance NPP safety.

  18. Analysis on the effect of local content to the economic aspect of NPP

    International Nuclear Information System (INIS)

    Study analysis on the effect of local content to the economic aspect of NPP has already been conducted. This scope of study covers: NPP technology system analysis (OPR-1000), national industry capability to participate in NPP construction and effect analysis toward the economic. Economic analysis is conducted for 2 units NPP OPR-1000. This study concludes that: (1) The level of local content for the first 2 units NPP in Indonesia about 35.34% (pessimistic case) and 43.38% (optimistic case). (2) To reach the local content government support is needed, i.e. policy of industry, particularly the police related to technology transfer. (3) The total generation cost that could be saved per year in pessimistic case is around US$ 14.55 million - US$ 14.57 million and in optimistic case it is around US$ 22.23 million – US$ 22.26 million. (4) The local content implementation will provide decreasing of generation cost about 1.75% up to 1.76% in pessimistic case, and around 2.67% up to 2.68% in optimistic case. (author)

  19. Decommissioning Study of Oskarshamn NPP

    Energy Technology Data Exchange (ETDEWEB)

    Larsson, Helena; Anunti, Aake; Edelborg, Mathias [Westinghouse Electric Sweden AB, Vaesteraas (Sweden)

    2013-06-15

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for Oskarshamn NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding.

  20. Decommissioning study of Forsmark NPP

    Energy Technology Data Exchange (ETDEWEB)

    Anunti, Aake; Larsson, Helena; Edelborg, Mathias [Westinghouse Electric Sweden AB, Vaesteraas (Sweden)

    2013-06-15

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for the Forsmark NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding.

  1. Decommissioning study of Forsmark NPP

    International Nuclear Information System (INIS)

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for the Forsmark NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding

  2. Decommissioning Study of Oskarshamn NPP

    International Nuclear Information System (INIS)

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for Oskarshamn NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding

  3. Achievements and challenges of Paks NPP

    International Nuclear Information System (INIS)

    As the six year long safety upgrading program at Paks NPP is approaching its final stage this year, it is a good opportunity to draw the conclusion: what have been done and how have measures influenced the safety of the plant. In its first part the paper gives an overview of the program's main issues, assesses the results from the point of view of safety, reliability and cost effectiveness as well. In the second part a survey of future tasks follows: (1) Hungary is joining to the EU. The accession process so far has not revealed any major problems concerning nuclear safety which could be seen as obstacles toward the membership. However the plant should be ready to meet the increasing level of safety regulations. Further safety upgrading measures are planned, mostly in the field of severe accident management. (2) The electricity market liberalisation in Hungary will start in 2003 and being a EU member state, the full market opening will happen within a few years. The plant has to take into account the specificity of market functioning. The most important thing is to preserve the present cost advantage of nuclear electricity generation within the market conditions. The paper presents measures performed and planned to keep the unit generation cost competitive. (3) The first unit at Paks will mark its 20't'h anniversary this year. Lifetime management issues are at the centre of the engineering activities. The work already started to prepare the lifetime extension for 20 years. The program for the license renewal, which was elaborated jointly with the nuclear regulatory body will be described.(author)

  4. A risk informed safety classification for a Nordic NPP

    Energy Technology Data Exchange (ETDEWEB)

    Jaenkaelae, K. [Fortum Nuclear Services Ltd. (Finland)

    2002-01-01

    The report describes a study to develop a safety classification proposal or classi- fication recommendations based on risks for selected equipment of a nuclear power plant. The application plant in this work is Loviisa NPP unit 1. The safety classification proposals are to be considered as an exercise in this pilot study and do not necessarily represent final proposals in a real situation. Comparisons to original safety classifications and technical specifications were made. The study concludes that it is possible to change safety classes or safety signifi- cances as considered in technical specifications and in in-service-inspections into both directions without endangering the safety or even by improving the safety. (au)

  5. Status of steam generator tubing integrity at Jaslovske Bohunice NPP

    Energy Technology Data Exchange (ETDEWEB)

    Cepcek, S. [Nuclear Regulatory Authority of the Slovak Republic, Trnava (Slovakia)

    1997-02-01

    Steam generator represents one of the most important component of nuclear power plants. Especially, loss of tubing integrity of steam generators can lead to the primary coolant leak to secondary circuit and in worse cases to the unit shut down or to the PTS events occurrence. Therefore, to ensure the steam generator tubing integrity and the current knowledge about tube degradation propagation and development is of the highest importance. In this paper the present status of steam generator tubing integrity in operated NPP in Slovak Republic is presented.

  6. R and D Activities for NPP Life Management in Korea

    International Nuclear Information System (INIS)

    Many R and D activities related to PLiM have been carried out and implemented to Korean NPP for the long term operation. Those activities include ageing management study, periodic safety review, steam generator management programme, materials reliability programme, thinned pipe management programme, study on dissimilar metal welds, etc. Based on the R and D activities, long term operation of Kori Unit 1 was successfully started from January 17, 2008 for next 10 years beyond its original design life. In this paper, all the activities and their results of the R and D programmes are briefly introduced. (author)

  7. Sensitivity of Input Parameters in the PSHA for NPP Sites

    International Nuclear Information System (INIS)

    In this study, the most uncertain input parameter in the PSHA was identified for Korean NPP sites through sensitivity analysis. Shinuljin Nuclear Units 1 and 2 site was selected in this study. Expert panels developed input parameters for PSHA. Input data were analyzed, and used for sensitivity analysis to see the effects of each parameter on seismic hazard. Through sensitivity analysis, we identified the degree of uncertainty of each parameter. The CONPAS, EQHAZAS, and EQHAZAS Manager codes, which were developed by KAERI, were utilized to compute the seismic hazard. The Gutenberg-Richter parameter was identified as the most uncertain one in this study

  8. Maintenance optimization of the Ignalina NPP safety systems

    International Nuclear Information System (INIS)

    This paper represents some theses and mathematical approach to optimization of technical specification problems of the diesel generators system (DGS) at the Ignalina NPP (INPP) in Lithuania. Analysis unites three chapters, each attributed to the solving of related problems: dependency of the Core Damage Frequency (CDF) on DGS test interval (Chapter 2), analysis and comparison of two different maintenance strategies for DGS (Chapter 3), DGS test interval's optimisation (averaged loss function minimisation) taking into consideration maintenance and DGS failure's consequence costs (Chapter 4). The mathematical model was developed which lets to estimate DGS failure probability, the averaged loss function value and study the influence of different parameters into final results. (author)

  9. Emergency operating procedures knowledge management for NPP MCR operators' support

    International Nuclear Information System (INIS)

    The described research aims at computerization of handling of the knowledge gathered from emergency operating procedures, which makes it possible to reduce frequency of errors committed by NPP main control room operators when executing the procedures. The mechanism for representation of procedures' declarative knowledge has been proposed. This method is based on two level semantic network hierarchy, namely intensional and extensional levels. The method has been used for a basic development of prototype of computer based procedures intended to support of operators under accidents. The system provides automatic on-line identification of the situation, selection of relevant procedure, its representation at video display unit and tracking of correctness of the procedure execution

  10. Nuclear disasters at Chornobyl NPP, Fukushima NPP and nuclear power engineering in the 21- century

    International Nuclear Information System (INIS)

    The article presents a brief analysis of nuclear accidents at the Chornobyl NPP 91986) and Fukushima NPP (2011), discusses causes and scenarios of the accidents. The radioactive contamination of the environment resulting from the disasters is characterized, and top-priority actions for mitigation of the consequences and protection of public are discussed

  11. Regulatory aspects of NPP safety

    International Nuclear Information System (INIS)

    In beginning, a history of legislative process regulating industrial utilisation of nuclear energy is given, including detailed list of decrees issued by the first regulatory body supervising Czech nuclear installations - Czechoslovak Atomic Energy Commission (CSKAE). Current status of nuclear regulations and radiation protection, especially in connection with Atomic Act (Act No 18/1997 Coll.), is described. The Atomic Act transfers into the Czech legal system a number of obligations following from the Vienna Convention on Civil Liability for Nuclear Damage and Joint Protocol relating to the Application of the Vienna and Paris Convention, to which the Czech Republic had acceded. Actual duties and competence of current nuclear regulatory body - State Office for Nuclear Safety (SUJB) - are given in detail. Execution of the State supervision of peaceful utilisation of nuclear energy and ionising radiation is laid out in several articles of the Act, which comprises: control activities of the SUJB, remedial measures, penalties. Material and human resources are sufficient for fulfilment of the basic functions for which SUJB is authorised by the law. For 1998, the SUJB allotted staff of 149, approximately 2/3 of that number are nuclear safety and radiation protection inspectors. The SUJB budget for 1998 is approximately 180 million Czech crowns (roughly 6 million US dollars). Inspection activity of SUJB is carried out in three different ways: routine inspections, planned specialised inspections, inspections as a response to a certain situation (ad-hoc inspections). Approach to the licensing of major plant upgrades and backfittings are mainly illustrated on the Temelin NPP licensing. Regulatory position and practices concerning review activities are presented. (author)

  12. World's first NPP and its role in nuclear power development

    International Nuclear Information System (INIS)

    Full text: On 26th of June 2004, it will be 50 years anniversary of start-up of the World's First Nuclear Power Plant (FNPP). This small size nuclear power plant that was constructed on the site of Laboratory 'V' (now State Scientific Center of the Russian Federation - Institute for Physics and Power Engineering) has become a symbol of peaceful use of nuclear energy. As long ago as before the Second World War and during the War, proposals on the use of nuclear energy for peaceful purposes including electricity production, were made by Academicians V.I. Vernadsky, S.I. Vavilov and P.L. Kapitsa. Based on these proposals, a Decree was issued by the Council of Ministers of the USSR in December 1946, in which the objectives of peaceful application of nuclear energy were first stated. However, target-oriented, intensive work on the designs of power reactors began after successful nuclear weapon test in 1949. Academician I.V. Kurchatov, manager of Nuclear Project of the USSR, became scientific supervisor of this work, while L.P. Beriya, Head of Special Committee and B.L. Vannikov, Head of the First General Board were administrative leaders. In May 1950, the Governmental Decree was issued on the construction at Laboratory 'V' of 'V-10' facility including three reactor units and separate machine building with a 5000 kW turbine generator. AM facility, the first nuclear power plant, was determined as the first priority. Initial evaluation of AM reactor neutronics was performed at Laboratory 2 under the leadership of I.V. Kurchatov, reactor design was developed at the SKB-5 NIIKHIMMASH under the leadership of Professor N.A. Dollezhal, and the LPI (A.I. Gutov) was the General Architect of the Project. On the proposal of I.V. Kurchatov, in March 1951, Laboratory 'V' became the scientific supervisor of justification of the First NPP physical characteristics. The First NPP was designed and constructed in four and a half years. Under condition of permanent lack of time and hard

  13. Principles of arranging a specialized operating system for the NPP APCS

    International Nuclear Information System (INIS)

    This paper discusses problems related to the development of software for the low level computers of nuclear power plant (NPP) automated process control systems (APCS). These systems monitor and control process equipment and are connected to the NPP control panel. The authors propose concepts and principles for developing specialized system software. The NPP APCS has a two to three level structure. For the upper level it is appropriate to use more generalized software (operating systems, network support, databases, etc.), but for lower levels it is necessary to develop specialized software to meet often conflicting requirements of hardware configuration and functions. Details of developing an operating system for a OVER-500 power unit are presented. (L.L.)

  14. Forest NPP estimation based on MODIS data under cloudless condition

    Institute of Scientific and Technical Information of China (English)

    CHEN LiangFu; GAO YanHua; LI Li; LIU QinHuo; GU XingFa

    2008-01-01

    Based on light-use efficiency model, an MODIS-derived daily net primary production (NPP) model was developed. In this model, a new model for the fraction of photosynthetically active radiation absorbed by vegetation (FPAR) is developed based on leaf area index (LAI) and albedo parameters, and a photosynthetically active radiation (PAR) is calculated from the combination of Bird's model with aerosol optical thickness and water vapor derived from cloud free MODIS images. These two models are integrated into our predicted NPP model, whose most parameters are retrieved from MODIS data. In order to validate our NPP model, the observed NPP in the Qianyanzhou station and the Changbai Mountains station are used to compare with our predicted NPP, showing that they are in good agreement. The NASA NPP products also have been downloaded and compared with the measurements, which shows that the NASA NPP products underestimated NPP in the Qianyanzhou station but overestimated in the Changbai Mountains station in 2004.

  15. Lifetime evaluation of Bohunice NPP components

    International Nuclear Information System (INIS)

    The paper discuss some aspects of the main primary components lifetime evaluation program in Bohunice NPP which is performed by Nuclear Power Plant Research Institute (NPPRI) Trnava in cooperation with Bohunice and other organizations involved. Facts presented here are based on the NPPRI research report which is regularly issued after each reactor fuel campaign under conditions of project resulted from the contract between NPPRI and Bohunice NPP. For the calculations, there has been used some computer codes adapted (or made) by NPPRI and the results are just the conclusive and very brief, presented here in Tables (Figures). (authors)

  16. NPP/NPOESS Tools for Rapid Algorithm Updates

    Science.gov (United States)

    Route, G.; Grant, K. D.; Hughes, R.

    2010-12-01

    The National Oceanic and Atmospheric Administration (NOAA), Department of Defense (DoD), and National Aeronautics and Space Administration (NASA) are jointly acquiring the next-generation weather and environmental satellite system; the National Polar-orbiting Operational Environmental Satellite System (NPOESS). NPOESS replaces the current Polar-orbiting Operational Environmental Satellites (POES) managed by NOAA and the Defense Meteorological Satellite Program (DMSP) managed by the DoD. The NPOESS Preparatory Project (NPP) and NPOESS satellites will carry a suite of sensors that collect meteorological, oceanographic, climatological, and solar-geophysical observations of the earth, atmosphere, and space. The ground data processing segment for NPOESS is the Interface Data Processing Segment (IDPS), developed by Raytheon Intelligence and Information Systems. The IDPS processes both NPP and NPOESS satellite data to provide environmental data products to NOAA and DoD processing centers operated by the United States government. The Northrop Grumman Aerospace Systems (NGAS) Algorithms and Data Products (A&DP) organization is responsible for the algorithms that produce the Environmental Data Records (EDRs), including their quality aspects. As the Calibration and Validation (Cal/Val) activities move forward following both the NPP launch and subsequent NPOESS launches, rapid algorithm updates may be required. Raytheon and Northrop Grumman have developed tools and processes to enable changes to be evaluated, tested, and moved into the operational baseline in a rapid and efficient manner. This presentation will provide an overview of the tools available to the Cal/Val teams to ensure rapid and accurate assessment of algorithm changes, along with the processes in place to ensure baseline integrity.

  17. Methodical recommendations for power unit comprehensive engineering and radiation survey

    International Nuclear Information System (INIS)

    The article describes power unit radiation survey methods developed and applied during conduction of Ch NPP unit I Comprehensive Engineering Radiation Survey. Special requirements for units under decommissioning, main survey principals, criteria for definition of volume and the order of survey for various systems of a NPP Unit are included

  18. Thermohydraulic calculation of WWER-type NPP

    International Nuclear Information System (INIS)

    Technique of thermohydraulic calculation of the WWER-type NPP in unsteady processes is described. Effective algorithm for solving hydrodynamics equations without regard for acoustic effects permitting to use enough large time integration step is given. Calculation of two-dimensional temperature fields in fuel element is considered. Method for calculating a pressurizer, steam generators and pumps is described as well

  19. Safety culture development at Daya Bay NPP

    International Nuclear Information System (INIS)

    From view on Organization Behavior theory, the concept, development and affecting factors of safety culture are introduced. The focuses are on the establishment, development and management practice for safety culture at Daya Bay NPP. A strong safety culture, also demonstrated, has contributed greatly to improving performance at Daya Bay

  20. RHR system reliability analysis of Krsko NPP

    International Nuclear Information System (INIS)

    In this paper Systems reliability analysis is applied to residual heat Removal System in Krsko NPP. Fault tree method is used. Qualitative analysis of the fault tree was made using FTAP-2 computer code, and quantitative using IMPORT code. results are evaluated and their possible application is given. (author)

  1. Slovakia: Mochovce NPP. Project control. Annex 10

    International Nuclear Information System (INIS)

    This annex deals with project control. Mochovce NPP suffered considerable delay primarily due to lack of money. This situation was corrected and construction resumed in 1996. Throughout the 'dormant' period the plant received considerable support from the major contractors, who maintained skeleton staff at site. Significant safety and managerial improvements are being introduced and a strategic plan for the plant has been developed. (author)

  2. Accident management insights after the Fukushima Daiichi NPP accident

    International Nuclear Information System (INIS)

    events and accidents at NPPs, and what additional measures should be considered as an accident progresses to the severe accident stage. Insights are provided on the experiences and practices existing or being proposed in the NEA member states, as well as new findings from post-Fukushima studies. Emphasis is placed on identifying commendable practices that support enhanced and integrated on-site accident management response and decision-making by NPP operators. The report provides information (including commendable practices) useful for regulatory authorities to consider as they implement enhancements to their regulatory framework in the area of integrated accident management building on the lessons learnt from the Fukushima Daiichi NPP accident. The report's insights also should be useful to regulatory authorities, operating organisations and others in the nuclear safety community for addressing accident management issues such as procedures and guidelines, equipment, infrastructure and instrumentation, and human and organisational resources. Factors such as accidents involving spent fuel pools, multi-unit aspects of accident management, the interface between onsite and off-site organisations and resources, and degradation of the surrounding infrastructure are also discussed. (authors)

  3. Analysis list: npp-13 [Chip-atlas[Archive

    Lifescience Database Archive (English)

    Full Text Available npp-13 Embryo + ce10 http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/target/npp-13....1.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/target/npp-13.5.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/target/npp...-13.10.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/colo/npp-13.Embryo.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/colo/Embryo.gml ...

  4. Analysis list: npp-3 [Chip-atlas[Archive

    Lifescience Database Archive (English)

    Full Text Available npp-3 Embryo + ce10 http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/target/npp-3.1....tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/target/npp-3.5.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/target/npp...-3.10.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/colo/npp-3.Embryo.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/colo/Embryo.gml ...

  5. Modernization and power upgrading of the Loviisa NPP

    Energy Technology Data Exchange (ETDEWEB)

    Keskinen, A. [IVO Power Engineering Ltd., Vantaa (Finland)

    1997-12-31

    In 1995, Imatran Voima Oy (IVO) started a project for modernization and power upgrading of the Loviisa NPP. The main objectives of the project are to ensure plant safety, to increase electricity production and to improve the expertise of the IVO staff. The total electricity output of Loviisa 1 and 2 units is planned to be increased by about 100 MW. This will be achieved through renovation of the steam turbines and through gradual increase in the thermal reactor power up to 1,500 MW from the present level of 1,375 MW. The Loviisa NPP Final Safety Analysis Report has been revised to a great extent in connection with the licensing process of the reactor power upgrading. The project also includes certain improvements in the primary and safety systems to ensure plant safety. The total cost estimate of the project is around 200 million FIM. The project implementation started in 1995 and in accordance with the plans in 2000 after several phases the last measures at power plant will be completed. (orig.). 4 refs.

  6. Design and Analysis of Prevention and Mitigation Measures against Core Melting under High Pressure in RCS for CHASHMA NPP Unit 2%恰希玛核电厂2号机组高压熔堆预防和缓解措施的设计和分析

    Institute of Scientific and Technical Information of China (English)

    史国宝

    2011-01-01

    A motor operated valve (MOV) is added on the Pressurizer for CHASHMA NPP Unit 2, to implement the bleed function in Feed-Bleed cooling mode, and depressurize rapidly the RCS during high pressure core melt in severe accident. This paper analyzes the accident consequence of Station Blackout coincident with the loss of Diesel Driven Feedwater Pumps using the computer code of SCDAP/RELAP5/MOD 3.1, and the analysis results justify that the added MOV is able to depressurize the RCS effectively to mitigate the accident consequence in severe accident.%恰希玛核电厂2号机组在稳压器上增设一个电动节流阀,用于在“充水-排汽”冷却中实施排汽,以及严重事故高压熔堆下快速降压.本文采用SCDAP/RELAP5/MOD3.1程序分析了全厂断电叠加2个系列柴油机辅助给水系统失效事故,结果表明,增设的稳压器电动节流阀能有效地实施严重事故下快速降压,缓解事故后果.

  7. Experience from the Inspection of Licensees' Outage Activities, Including Fire Protection Programmes, Event Response Inspections, and the Impact of the Fukushima Daiichi NPP Accident on Inspection Programmes. Workshop Proceedings, Chattanooga, Tennessee, United States, 7-10 April 2014 - Appendix: Compilation of Survey Responses

    International Nuclear Information System (INIS)

    This appendix provides the complete compilation of responses received to the questionnaire issued in conjunction with the workshop announcements. The responses are provided as received, with changes made only to the formatting. The OECD Nuclear Energy Agency (NEA) Committee on Nuclear Regulatory Activities (CNRA) Working Group on Inspection Practices (WGIP) sponsored the 12. International Workshop on Nuclear Regulatory Inspection Activities. The workshop was hosted by the U.S. NRC, in Chattanooga, Tennessee, United States of America on 7 -10 April 2014. The three workshop topics that were addressed were as follows: - Inspection of Outage Activities Including Fire Protection Programmes. - Event Response Inspections. - The Impact of Inspection Programmes of the Fukushima Daiichi NPP Accident. Each of the respondents was given the following instructions in relation to their response: - Only one response per country is required. If more than one person from your country is participating, please co-ordinate the responses accordingly. - Please provide responses on separate sheet and clearly identify the questionnaire part and topic. For preparation of the workshop, participants are invited to supply their national inspection approaches used in inspection of events and incidents according to the surveys. Actual issues that were discussed during the workshop were generated by the topic leaders based on the responses submitted by participants with their registration forms. This formats helps to ensure that issues considered most important by the workshop participants are covered during the group discussions. (authors)

  8. NPOESS Preparatory Project (NPP) Environmental Products

    Science.gov (United States)

    Grant, K. D.; Smith, D. C.

    2011-12-01

    The National Oceanic and Atmospheric Administration (NOAA) and National Aeronautics and Space Administration (NASA) are jointly acquiring the next-generation civilian weather and environmental satellite system: the Joint Polar Satellite System (JPSS). The Joint Polar Satellite System will contribute the afternoon orbit component and ground processing system of the restructured National Polar-orbiting Operational Environmental Satellite System (NPOESS). As such, the Joint Polar Satellite System replaces the current Polar-orbiting Operational Environmental Satellites (POES) managed by NOAA and the ground processing component of both POES and the Defense Meteorological Satellite Program (DMSP) replacement, known as the Defense Weather Satellite System (DWSS), managed by the Department of Defense (DoD). The Joint Polar Satellite System satellite will carry a suite of sensors designed to collect meteorological, oceanographic, climatological, and solar-geophysical observations of the earth, atmosphere, and space. The ground processing system for the Joint Polar Satellite System is known as the Common Ground System (JPSS CGS), and consists of a Command, Control, and Communications Segment (C3S) and the Interface Data Processing Segment (IDPS). Both are developed by Raytheon Intelligence and Information Systems (IIS). The Interface Data Processing Segment will process Joint Polar Satellite System and Defense Weather Satellite System satellite data to provide environmental data products (aka, Environmental Data Records or EDRs) to the National Oceanic and Atmospheric Administration and Department of Defense processing centers operated by the United States government. The Interface Data Processing Segment will process Environmental Data Records beginning with the NPOESS Preparatory Project (NPP) and continue through the lifetime of the Joint Polar Satellite System and Defense Weather Satellite System programs. Under the National Polar-orbiting Operational Environmental

  9. Organizational development at Forsmark NPP

    International Nuclear Information System (INIS)

    Forsmark is a three unit BWR site with a total capacity of 3200 MW. Units 1 and two are identical and went into commercial operation in 1980 and 1981. Unit 3 is of a later design with an output of 1200 MW and has been operating since 1985. The average availability for the site has been over 90% for the last 10 years, and the total busbar cost has been competitive. A consistent management strategy has been used to achieve the good results. Several organizational modifications have been made during the years to adapt the organization to changing internal and external conditions. An overall goal regarding staffing has been to keep the number of employees at the same level as in 1985 when Unit 3 went into commercial operation. During the time period from 1975, when the operational organization was formed, until today, the focus for the organization has changed several times. During the commissioning period the focus was on training and establishing routines and procedures. During the first years of operation development of maintenance programs and taking over activities from the supplier dominated. Next area in focus was increasing availability and making the outages more efficient. Several minor modifications to the plant were made to support maintenance activities. More focus on cost reduction and increasing the production through technical modifications were next. After 15 years of operation the need for replacement of components to ensure reliable operation was evident. A program for major modifications was developed, aiming at 40 years lifetime. Deregulation of the Nordic Electricity Market now calls for further reductions in production costs. (author)

  10. NPP bulk equipment dismantling problems and experience

    International Nuclear Information System (INIS)

    NPP bulk equipment dismantling problems and experience are summarized. 'ECOMET-S' JSC is shown as one of the companies which are able to make NPPs industrial sites free from stored bulk equipment with its further utilization. 'ECOMET-S' JSC is the Russian Federation sole specialized metallic LLW (MLLW) treatment and utilization facility. Company's main objectives are waste predisposal volume reduction and treatment for the unrestricted release as a scrap. Leningrad NPP decommissioned main pumps and moisture separators/steam super heaters dismantling results are presented. Prospective fragmentation technologies (diamond and electro-erosive cutting) testing results are described. The electro-erosive cutting machine designed by 'ECOMET-S' JSC is presented. The fragmentation technologies implementation plans for nuclear industry are presented too. (author)

  11. Intelligent system for accident identification in NPP

    International Nuclear Information System (INIS)

    Accidental situations in NPP are great concern for operators, the facility, regulatory bodies and the environmental. This work proposes a design of intelligent system aimed to assist the operator in the process of decision making initiator events with higher relative contribution to the reactor core damage occur. The intelligent System uses the results of the pre-operational Probabilistic safety Assessment and the Thermal hydraulic Safety Analysis of the NPP Juragua as source for building its knowledge base. The nucleus of the system is presented as a design of an intelligent hybrid from the combination of the artificial intelligence techniques fuzzy logic and artificial neural networks. The system works with variables from the process of the first circuit, second circuit and the containment and it is presented as a model for the integration of safety analyses in the process of decision making by the operator when tackling with accidental situations

  12. LTO License Application Project NPP Borssele

    International Nuclear Information System (INIS)

    Borssele NPP plans to extend its operating life with 20 years until 2034. Borssele has started the project LTO 'bewijsvoering' (LTO 'Justification') in order to meet the requirements of the Dutch regulator. The outline of the project is based on IAEA safety guide 57 'Safe Long Term Operation of Nuclear Power Plants'. This paper describes the contents and coherence of the different parts in the project and how these respond to the IAEA guidelines on LTO. The goal of the project LTO 'bewijsvoering' is to ensure that safety and safety relevant systems, structures and components continue to perform their intended functions during long term operation. The outcome of the project LTO 'bewijsvoering' will be used for a license change application and this will be submitted to the Dutch regulator KFD for approval of prolonged operation of Borssele NPP after 2013. (author)

  13. NPP EQUIPMENT LIFETIME MANAGEMENT UNDER AGEING

    Directory of Open Access Journals (Sweden)

    Olga M. Gulina

    2012-01-01

    Full Text Available This paper deals with the problem of nuclear power plant (NPP equipment lifetimeprediction with the use of information about damage processes, operation conditions andpreventive actions. The developed model is based on Kalman linear stochastic filter. For steamgenerator heat-exchanged tubes we use the martingale theory for predicting the number ofsuppressed heat-exchanged tubes to the next control. Finally, we formulate the principle of SGlifetime optimal management.

  14. Engineering geological and hydrogeological invstigations for storage of medium and low-activity nuclear waste at Cernavoda, Romania. Soil stabilisation using the CONSOLID system; Ingenieurgeologische und hydrogeologische Untersuchungen zur Lagerung mittel- und schwachradioaktiver Abfaelle in Cernavoda Rumaenien. Baugrundstabilisierung mit dem CONSOLID-System

    Energy Technology Data Exchange (ETDEWEB)

    Giurgea, V.; Merkler, G.P.; Hoetzl, H.; Hannich, D. [Karlsruhe Univ. (T.H.) (Germany). Lehrstuhl fuer Angewandte Geologie

    1998-12-31

    In Cernavoda/Romania investigations and planning from a low and middle radioactive waste disposal site have been carried out. A multitude of hydrogeological, geological, engineering geological criteria`s and constructional security measures were examined with respect to the strict regulations for such a waste site. This studies and measures are shortly analyzed and discussed in this paper. In accordance with the selection criteria for such a hazardous waste site, several laboratory and `in situ` tests, soil-mechanic studies, numerical modeling and foundation tests for soil stabilization with the CONSOLID-System are presented. (orig.) [Deutsch] Zur Einhaltung der strengen Vorgaben, die bei einem Deponiestandort fuer mittel- und schwachradioaktive Abfaelle gestellt werden, sind in Cernavoda/Rumaenien eine Vielzahl von hydrogeologischen und ingenieurgeologischen Untersuchungen sowie bautechnischen Sicherungsmassnahmen vorgesehen, die im Rahmen dieser Publikation kurz analysiert und diskutiert werden. Im Zusammenhang mit den geologischen und hydrogeologischen Auswahlkriterien des Standortes werden eine Reihe von Labor- und `in situ` Untersuchungen, Modellrechnungen sowie Baugrundstabilisierungsmassnahmen mit dem CONSOLID-System vorgestellt. (orig.)

  15. The development of a living PSA for the Temelin NPP

    International Nuclear Information System (INIS)

    The general purpose of the project is to perform a systematic examination of unit 1 of the Temelin NPP for severe accident vulnerabilities by performance of a Level 1 and 2 Probabilistic Safety Assessment study. The objectives, scope of the work and project schedule are given. The analysis was focused on the occurrence of initiating events. The Event Sequence Diagram was used in accident sequence modelling. Fault trees were created using the NUPRA code. The approach used in human reliability analysis explicitly relates the operator actions to the working procedures and the success or failure of the system. A safety monitor was developed to provide an online measurement of risk based on the current plant configuration and testing status, thus enabling the plant staff to plan and perform maintenance activities meeting maximized safety and avoiding ionizer plant shutdown. (J.B.) 1 tab., 3 figs

  16. Verification of revised EOP using the CATHENA code for Wolsong NPP- Candu 6

    International Nuclear Information System (INIS)

    EOP (Emergency Operating Procedure) is the operating procedure document which describes the operator's action needed for the maintenance of nuclear power plant (NPP) safety when a certain accident takes place. EOPs of Wolsong NPP Units 2, 3, 4 (Candu 6) have been revised aiming at the optimization of procedure to recover the NPP from an accident and the minimization of human errors. The revised overall EOPs are composed of 2 EOPs describing the accident diagnosis and recovery of critical safety parameters and 13 EOPs describing the operator actions needed for the individual accidents which include LOCA and MSLB and so on. The purpose of the present study is to verify the revised EOPs if the procedures and operator actions described in each EOP are fully appropriate and effective for the safe shutdown of NPP leading to temperature low enough to start the long term cooling using the shutdown cooling system and for the maintenance of fuel and pressure boundary integrity. The verification was carried out with the deterministic safety analysis methodology using the CATHENA computer program which is a Thermalhydraulic numerical code used in the safety analysis of Candu 6 reactors. CATHENA can simulate the various thermalhydraulic behaviors which are expected to happen during each accident and by various operator actions. From the verification results it can be assured that the revised individual EOPs have the enough appropriateness with respect to the engineering aspects and effectiveness in view of fuel and pressure boundary integrity. (authors)

  17. Database of Temelin NPP Operational States and Its Use for Neutron Codes Validation

    International Nuclear Information System (INIS)

    Analogous to NPP Dukovany is made for NPP Temelin database of operational states. The database ETEBase is needed for the validation of various reactor computing codes, which will be developed during NPP Temelin life cycle and used for WWER-1000 core analyses. To obtain licenses in Czech Republic for new neutron codes programs it is needed to publish technical report about validation and evaluated precision of the computer codes. Benchmark data sets are processed from operational measurements data on Temelin WWER-1000 reactors. The input data from the NPP are verified; errors and inaccuracies are filtered out. Required data are chosen and processed, and then data are transferred to a form suitable for input data for neutron codes and for validation. Main data contained in benchmark dataset: effective time, boron concentration, thermal power, position of working group control clusters, inlet coolant temperature and flow rate of coolant water. Additional 3D-data are stored only for chosen time points (approx. 40 per cycle) - axial and radial power distribution in full and 60-degree core symmetry. Also datasets contain core description and list of outages during the cycle. At present, ETEBase contains processed data from these unit/cycles: 1-1, 1-2, 1-3 (partial of data), 2-1, 2-2 (Author)

  18. Decommissioning database of V1 NPP

    International Nuclear Information System (INIS)

    Since 2001, the preparation of V1 NPP practical decommissioning has been supported and partly financed by the Bohunice International Decommissioning Support Fund (BIDSF), under the administration of the European Bank for Reconstruction and Development. AMEC Nuclear Slovakia, together with partners STM Power and EWN GmbH, have been carrying out BIDSF B6.4 project - Decommissioning database development (June 2008 until July 2010). The main purpose of the B6.4 project is to develop a comprehensive physical and radiological inventory database to support RAW management development of the decommissioning studies and decommissioning project of Bohunice V1 NPP. AMEC Nuclear Slovakia was responsible mainly for DDB design, planning documents and physical and radiological characterization including sampling and analyses of the plant controlled area. After finalization of all activities DDB includes over 75.000 records related to individual equipment and civil structures described by almost 3.000.000 parameters. On the basis of successful completion of the original contract the amendment was signed between JAVYS and Consultant's Consortium related to experimental characterization of NPP activated components. The works within this amendment have been still running. (authors)

  19. Knowledge management in the NPP domain

    Energy Technology Data Exchange (ETDEWEB)

    Nilsen, Svein; Bisio, Rossella; Ludvigsen, Jan Tore

    2004-03-15

    This report gives an outlook on Knowledge Management (KM) activities within NPP related establishments as of today. There may be less activity in the NPP world as compared to many other industrial sectors. Still there is an awakening within the NPP industry demanding that KM should be attended to at a larger scale. The most notable reason for this is maybe an imminent increase in the number of people going into retirement. The types of establishments involved cover the major kinds such as utilities, research institutes and worldwide nuclear organizations. The report sums up a few of those efforts that are presently being implemented. Moreover the report looks at general advancements within the field of knowledge management. Simply stated the endeavours belong to either one of two classes. The first class emphasize the use of technology to solve knowledge management problems. The second class regard knowledge management as a problem pertaining to human factors and organizational issues. This report maintain that knowledge management initiatives should make due considerations to both perspectives. This report also sums up the Halden Reactor Project short term KM initiative. (Author)

  20. Tritium liquid effluents from the Krsko NPP

    International Nuclear Information System (INIS)

    In the past, 12-months' fuel cycles in the Krsko NPP had not caused any problems regarding compliance with its Technical Specifications and license limits on liquid tritium releases (20 TBq/year, 8 TBq/three months). The first 18-months' fuel cycle, which was introduced in 2004, required fuel with higher enrichment, higher boron concentration in the primary coolant and more fuel rods with burnable poisons. In 2005, the NPP operated without refueling outage for the whole year and produced the highest amount of energy so far. Due to these facts and a few unplanned shutdowns and power reductions, production of tritium and releases increased strongly in 2005. As a result, the Krsko NPP hardly succeeded to stay within regulatory limits on tritium releases. However, the three-months' limit was exceeded in the first quarter of 2006. On the basis of conclusions acquired from the SNSA's study and practice of other European countries the SNSA considerably increased the annual limit of permitted liquid tritium releases (from 20 TBq to 45 TBq) and abolished the three-months' limit. At the same time, the SNSA reduced the limit of fission and activation products by halves. (author)

  1. Knowledge management in the NPP domain

    International Nuclear Information System (INIS)

    This report gives an outlook on Knowledge Management (KM) activities within NPP related establishments as of today. There may be less activity in the NPP world as compared to many other industrial sectors. Still there is an awakening within the NPP industry demanding that KM should be attended to at a larger scale. The most notable reason for this is maybe an imminent increase in the number of people going into retirement. The types of establishments involved cover the major kinds such as utilities, research institutes and worldwide nuclear organizations. The report sums up a few of those efforts that are presently being implemented. Moreover the report looks at general advancements within the field of knowledge management. Simply stated the endeavours belong to either one of two classes. The first class emphasize the use of technology to solve knowledge management problems. The second class regard knowledge management as a problem pertaining to human factors and organizational issues. This report maintain that knowledge management initiatives should make due considerations to both perspectives. This report also sums up the Halden Reactor Project short term KM initiative. (Author)

  2. Safety Culture Survey in Krsko NPP

    International Nuclear Information System (INIS)

    The high level of nuclear safety, stability and competitiveness of electricity production, and public acceptability are the main objectives of Krsko Nuclear Power Plant. This is achievable only in environment where strong Safety Culture is taking dominant place in the way how employees communicate, perform tasks, share their ideas and attitudes, and demonstrate their concern in all aspects of work and coexistence. To achieve these objectives, behaviour of all employees as well as specific ethical values must become more transparent and that must arise from the heart of organization. Continuous ongoing and periodic self assessments of Safety Culture in Krsko NPP present major tools in implementation process of this approach. Benefits from Periodic interdisciplinary focused self assessment approach, which main intention is finding the strengths and potential areas for improvements, was used second time to assess the area of Safety Culture in Krsko NPP. Main objectives of self assessment, performed in 2006, were to increase the awareness of the present culture, to serve as a basis for improvement and to keep track of the effects of change or improvement over a longer period of time. For the purpose of effective self assessment, extensive questionnaire was used to obtain information that is representative for whole organization. Wide range of questions was chosen to cover five major characteristics of safety culture: Accountability for safety is clear, Safety is integrated into all activities, Safety culture is learning-driven, Leadership for safety is clear and Safety is a clearly recognized value. 484 Krsko NPP employees and 96 contractors were participated in survey. 70-question survey provided information that was quantified and results compared between groups. Anonymity of participant, as well as their willingness to contribute in this assessment implicates the high level of their openness in answering the questions. High number of participant made analysis of

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

    International Nuclear Information System (INIS)

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

  4. GIDROPRESS development center experience in the field of extension of the BN-600 NPP steam generator service life and steam generator development tasks for new fast reactor power units

    International Nuclear Information System (INIS)

    The article presents the work of the GIDROPRESS development center both on evaluation of residual life and lifetime extension of the BN-600 power unit PGN-200M steam generators. The strength of the steel constructions was justified; the recommendations were given on seismic resistance improvement. The imperfection of the standing regulatory base was noted, the measures to correct this situation were highlighted. The BN-600 steam generators positive operating experience as well as the examination results of the critical components condition after the steam generators long performance enables to confidently change over to the new generation of large steam generators, thus considerably improving technical and economic characteristics of prospective designs of fast reactors

  5. Monitoring of radionuclides in the atmosphere of the Czech Republic after Fukushima NPP disaster

    International Nuclear Information System (INIS)

    Monitoring system carried out under the Radiation Monitoring Network (RMS) of the Czech Republic (CR) after Fukushima NPP disaster showed that RMS is able to respond flexibly when it detects any deviation from normal operational situations and adapt monitoring circumstances. The first increased values were observed in the CR from March 23 to March 24, 2011, the highest values were measured among March 28 to April 1, 2011. The measured units were mBq/m3.

  6. Summary of the data collection and analysis process used for Temelin NPP PSA project

    International Nuclear Information System (INIS)

    The Temelin NPP is a WWER-1000/320 two unit plant under construction. This paper briefly discusses the characteristics of data sources that were used to estimate the initiating event frequencies, component reliability parameters, unavailabilities due to maintenance, common cause failure probabilities and human error probabilities in the frame of Temelin PSA Project covering Level 1 for both at power and non power modes of operation, external events and the Level 2 analysis. (authors)

  7. Management of the operational and investment risk at the National Society Nuclearelectrica S. A

    International Nuclear Information System (INIS)

    The National Society Nuclearelectrica S.A. has developed a program for the management of operational and investment risk. The paper presents the implementation of the insurance program for the Cernavoda NPP on the domestic and international insurance market. A condition for implementing the contract of constructing Cernavoda Unit 2 was that of maintaining an adequate guarantee program. At the moment of loading with nuclear fuel the Unit 2 in 2007 the guarantee program will be replaced with one similar to that which is operational with Unit 1

  8. Experience in performing the commissioning procedures for meeting the requirements of water chemistry at NPP With VVER

    International Nuclear Information System (INIS)

    The integrity of NPP Unit equipment and pipelines is assured by strict following the requirements of rules and regulations by the NPP personnel in the field of nuclear power engineering and other regulatory documents. But all efforts of NPP personnel are unavailing in case of violation of the requirements of design documentation during Unit commissioning. Here the surface cleanness of equipment and pipelines during mounting, the post-mounting cleaning and assurance of water chemistry quality figures during commissioning procedures are of importance. During commissioning activities at the Unit of NPP with VVER a number of procedures are performed and the important place belongs to the procedures on water chemistry coordination. Post-mounting washing of steam generators is intended for cleaning and washing the steam generator internal surfaces against corrosion products, corrosive impurities, preservative residue and mounting fouling. During circulation washing of the reactor plant primary circuit the final cleaning of the internal surfaces is performed as well as preparing for formation of the protective oxide film. During reactor plant «hot» running-in the homogeneous solid protective oxide film is formed during a long-term interaction of the primary circuit internal surfaces with the alkaline reducing medium created due to proportioning of hydrazine and potassium hydroxide into the primary water. The composition and structure of the protective oxide film, formed on the internal surfaces, is such that its safe keeping is assured during Unit further operation. (author)

  9. Analysis of spatio-temporal distribution characteristics of vegetation NPP in Jiangsu province%江苏省植被净初级生产力时空分布格局研究

    Institute of Scientific and Technical Information of China (English)

    王驷鹞; 刘振波

    2012-01-01

    Net Primary Productivity (NPP)is the accumulation of organic matter by green plants per unit of space and time. Using Geographic Information System and Remote Sensing spatial analysis software,this paper analyzes the spatio-temporal distribution characteristics of vegetation NPP in Jiangsu province from 2000 to 2006 based on NPP data from EOS/MOD1S. Results show a decreasing spatial trend from southeast to northwest and a temporal trend with higher NPP in 2004. The average annual NPP in Jiangsu province (569. 28 gC/(m2 ·a))was higher than the national average NPP during the same period (345. 91 gC/(m2·a))and a little lower than the average NPP in Guangdong(595. 51 gC/(m2·a)). Analyzing NPP of different city and different buffer of shoreline shows that the NPP increases firstly and then decreases with the increasing distance to shoreline. NPP of Nantong (a city in the Southeast of Jiangsu)was highest (693. 57 gC/(m2·a)),while NPP of Xuzhou (a city in the Northwest of Jiangsu)was lowest (478.72 gC/(m2·a)). NPP grows to the highest when the distance to the Ring Buffer increases to 30 km,and land cover change is an influential factor affecting changes in vegetation NPP based on Ring Buffer. Analysis of vegetation NPP shows that climate factors were the key factors controlling the NPP in Jiangsu,and the human influence is becoming more and more important.%基于MODIS植被净初级生产力(NPP)数据产品,利用ArcGIS地理信息系统软件和ENVI遥感软件空间分析工具,分析了2000-2006年间江苏省NPP的时空分布.研究结果表明:江苏省NPP值空间分布由东南部向西北部递减,在时间变化上,研究时段内2004年NPP值相对较高,2003年相对较低;通过对各个地级市及距海岸不同距离的NPP值分析,发现随着距离海岸线的距离不断加大,NPP值先增加后降低.最后对江苏省NPP时空分布影响因素做了简要分析.

  10. Maintaining staff competence-a NPP operator viewpoint

    International Nuclear Information System (INIS)

    For a nuclear power plant operator, it is crucial to guarantee the safe and economic operation of the power plant as well as to look after the general acceptability of nuclear power. As to human resources management, this requires continuous maintenance and enhancement of the performance of the individuals and organisation. To this end, several development projects have recently been implemented by Teollisuuden Voima Oy (TVO) at the Olkiluoto nuclear power plant, which consists of twin 840 MWe BWR units that commenced their operation in 1978 and 1980. Systematic initial and continuing training programmes are needed to maintain the technical and managerial skills and know-how at a high level. The present stabile state of nuclear power, i.e. operation of ageing plants with personnel ageing as well, requires a variety of actions to reinforce the training efforts. At Olkiluoto NPP, we have carried out an extensive modernization programme that allowed the personnel to strengthen their knowledge and supplement it with the most recent results of development. We have also closely monitored the NPP development projects of the vendors, which has added to the preservation of know-how and understanding of advanced nuclear power technology. We have close contacts to the research institutes and universities, and have performed R and D activities to limited extent. In addition to the projects mentioned above, a co-ordinated development programme, 'TVO 2002', was initiated last year. The main objective of this programme is to ensure the functional preconditions and the competitiveness of the company in a changing environment. The management and operational procedures will be developed in such a way that the goals set for year 2002 will be achieved. The programme is organised as ten projects, which cover a variety of development subjects. One of the focal areas includes projects that can be characterised with the words 'Survey of competencies' and 'Preservation of know

  11. Corporate portal system at PAKS NPP, Hungary

    International Nuclear Information System (INIS)

    The new Corporate Portal System (CPS) of Paks NPP was launched in November 2006. The portal is based on one of the latest technologies, Plumtree Enterprise WEB 5.0. The main purpose of the installation of the new technology was to serve the working culture change, to give a platform to access all information and applications including the integrated process model used at the NPP. The new technology also supports those goals which were defined in the organization development programme: e.g. to improve internal communication with the establishment of communities of practice. Installation of the CPS has provided a powerful tool for knowledge management; it is possible to share and find all information through a controlled access in documents from various sources, to have links to people, portlets and different communities. Document management of the Paks NPP is supported by the integration of the Document 5 application, as the new Electronic Data Management System (EDMS) and the CPS. Depending on their access rights, all users of the CPS, through Microsoft Internet Explorer, can access technical, economic and human resources documents which are stored anywhere on the internal network (file servers, EDMS, old INRANET). The CPS is also accessible from the internet through a secure connection. The main concept is the integration of all applications to one platform and to help users to find all information they need. An access control list specifies which users and groups have access to an object (and what kind of access privileges they have such as read, select, edit, admin)

  12. Mochovce NPP safety improvement and completion

    International Nuclear Information System (INIS)

    6th Nuclear society information meeting dealt with the completion of the Mochovce NPP with regard to implementation of safety measures. It was aimed to next problems: I. 'Survey' presentation on the situation of the nuclear power industry in partner countries; II. Basic technical presentations; III. Presentations of operators of the other VVER 440/213 NPPs on their activities in the field of safety improvement in relation to IAEA recommendations; IV. Technical solutions of safety improvements ranked with IAEA degree 3 (Report SC 108 VVER); V: Technical solutions of selected Safety Measures ranked with IAEA degree 2 and 1 (Report SC 108 VVER)

  13. Safe 15 Terawatt of Temelin NPP

    International Nuclear Information System (INIS)

    In this work author presents a project Safe 15 Terawatt realised on the Temelin NPP. This project is one of the eight key projects of the CEZ group, associated in the 'Programme of efficiency'. The project started in June 2007 with long-term goals for horizon of year 2012. The safety indicators will be reached of the first quarter level of world's nuclear power plant - by the end of the first decade. By the end of year 2012 we will have achieved annual production of 15 billion kWh - in the Czech Republic: 15 Terawatt.

  14. Sociological investigations on Ignalina NPP and within its surroundings

    International Nuclear Information System (INIS)

    The purpose of this study was to determine the impact of Ignalina NPP and Visaginas town on the social territorial processes in the region and to reveal the impact of Ignalina NPP on the regional economic, social, demographic, political and cultural processes in the context of ecological and psychological affect. According to the results of this research three quarters of the inhabitants and the functionaries of local administration hold an opinion that operation of Ignalina NPP posses threat for the population and environment. Meanwhile they are sure that danger of Ignalina NPP is not critical. 21 - 35 % of the local administrators speak for the closure of Ignalina NPP , whereas half of Visaginas residents and three quarters of the local administrators indicate that operation of reactors is expedient. Over 90% of the population do not have sufficient information on the operation of Ignalina NPP. In the opinion of the rest Lithuanian people Ignalina NPP zone is related with the physical danger and the image of Visaginas residents as the 'others', 'strangers'. More than 90% of Ignalina NPP employees are Russian speaking, not native Lithuanians. The social relations of Visaginas with the environment are poor as a result of the situation of the town, lack of communications and cultural self isolation. (author)

  15. Trends and Variability of AVHRR-Derived NPP in India

    Directory of Open Access Journals (Sweden)

    Hirofumi Hashimoto

    2013-02-01

    Full Text Available In this paper, we estimate the trends and variability in Advanced Very High Resolution Radiometer (AVHRR-derived terrestrial net primary productivity (NPP over India for the period 1982–2006. We find an increasing trend of 3.9% per decade (r = 0.78, R2 = 0.61 during the analysis period. A multivariate linear regression of NPP with temperature, precipitation, atmospheric CO2 concentration, soil water and surface solar radiation (r = 0.80, R2 = 0.65 indicates that the increasing trend is partly driven by increasing atmospheric CO2 concentration and the consequent CO2 fertilization of the ecosystems. However, human interventions may have also played a key role in the NPP increase: non-forest NPP growth is largely driven by increases in irrigated area and fertilizer use, while forest NPP is influenced by plantation and forest conservation programs. A similar multivariate regression of interannual NPP anomalies with temperature, precipitation, soil water, solar radiation and CO2 anomalies suggests that the interannual variability in NPP is primarily driven by precipitation and temperature variability. Mean seasonal NPP is largest during post-monsoon and lowest during the pre-monsoon period, thereby indicating the importance of soil moisture for vegetation productivity.

  16. Forest NPP estimation based on MODIS data under cloudless condition

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    Based on light-use efficiency model, an MODIS-derived daily net primary production (NPP) model was developed. In this model, a new model for the fraction of photosynthetically active radiation absorbed by vegetation (FPAR) is developed based on leaf area index (LAI) and albedo parameters, and a pho- tosynthetically active radiation (PAR) is calculated from the combination of Bird’s model with aerosol optical thickness and water vapor derived from cloud free MODIS images. These two models are inte- grated into our predicted NPP model, whose most parameters are retrieved from MODIS data. In order to validate our NPP model, the observed NPP in the Qianyanzhou station and the Changbai Mountains station are used to compare with our predicted NPP, showing that they are in good agreement. The NASA NPP products also have been downloaded and compared with the measurements, which shows that the NASA NPP products underestimated NPP in the Qianyanzhou station but overestimated in the Changbai Mountains station in 2004.

  17. RCM at NPP Dukovany, Czech Republic

    International Nuclear Information System (INIS)

    The Project components are: RCM course for beneficiaries of the Project; software - EPRI RCM Workstation 2.5; pilot RCM projects at NPP Dukovany and NPP Bohunice. For the pilot project at Dukovany Failure Modes and Effects Analysis (FMEA) is performed. As a result a proposal of the current PM programme revision was worked up in a form of a comparison between the recent PM tasks and the RCM recommendations. The plant maintenance history electronic databases are found to be comprehensive, but not ready for the reliability determination. The maintenance history doesn't contain an identification of specific failure modes. Therefore, generic reliability data were used at FMEA (Failure Modes: Component Type, Failure Mode ID, Failure Mode Description, Probability Value, and Probability Type). In some important cases, when the RCM recommendation was to change a current task interval, the RCM proposed task frequencies were calculated from real plant data which were verified and consulted. Further, condensate pumps maintenance strategy and failure rate review is made. RCM analysis and recommendations for the pump maintenance are presented. The RCM application to selected electric systems is also discussed. Based on the calculations, maintenance programme was modified

  18. Utilization of NPP Krsko plant specific simulator

    International Nuclear Information System (INIS)

    NPP Krsko started with licensed operator training using its own plant-specific full scope simulator in April 2000. Today, two years after simulator was completed, the benefits of simulator use are visible in various fields. The simulator was effectively used to conduct licensed operator continuing training and practical examinations. Two-year continuous training program was designed to help maintain and improve operator performance. The simulator was also used to provide just-in-time training prior to plant evolutions. Together with licensed operators the non-licensed operators are also included into simulator training to provide affective team training opportunity and to foster good communication and increase scenario realism. Now, the first group of initial licensed operator training using plant-specific simulator is also almost completed. It is the first time that NPP Krsko training department conducted complete initial training and this will represent the great experience for future training. Besides training, the simulator was also utilized for procedure development and validation, operating standards development, testing of plant modifications and other activities, like emergency preparedness procedures validation and training exercises.(author)

  19. Brazilian system for NPP personnel training

    International Nuclear Information System (INIS)

    Brazil has two nuclear power plants in operation (Westinghouse design 657 MW PWR-type Angra-1 NPP, in commercial operation since 1985), (Siemens/KWU-design 1300 MW PWR-type Angra-2 NPP in commercial operation since 2000) and a third for which about 80% of components are already stored on site, awaiting for construction (Siemens/KWU-design 1300 MW PWR-type Angra-3 NPP). The training center is operated by ELETRONUCLEAR at Angra site. It is divided in main training center, simulator training center and maintenance training center. All training activities for Angra-1 and 2 operation personnel are performed in the training center, with exception of simulator training for licensed control room operators of Angra 1, which is performed at training centers in the U.S. and Spain. International cooperation and assistance have been extensively used during last years . All training modules are developed and updated by utility staff. Most of Instructors come from the Operations staff. Training methodology is characterized by modules which follow international practices. The simulator training center was built in 1985 and houses a full-scope training simulator used as design reference is the one used for Angra-2 NPP. Since 1985 an extensive scope of courses for operators, managers and other specialists from a total of eleven NPPs and other organizations in Germany, Spain, Argentina and Switzerland is being provided by ELETRONUCLEAR with utilization of the simulator and Angra-2 training center staff. Provision of such courses for NPP operators from other countries results in acquisition, by ELETRONUCLEAR instructors, of considerable experience in the field of training of NPP operation personnel. This experience is extremely useful for qualification of Angra-2 operators. Maintenance training center started its activities in July 1996. It presently consists of classrooms, meeting rooms and offices for staff. A maintenance workshop is currently under construction and is going to be

  20. Using lessons learned to improve the NPP license renewal process

    International Nuclear Information System (INIS)

    There are 103 licensed, operating commercial nuclear power plant reactors in the United States today. Based on the Atomic Energy Act of 1954, the United States (U.S.) Nuclear Regulatory Commission (NRC) issues licenses for commercial nuclear power plants (NPP) to operate for up to 40 years and allows these licenses to be renewed. The NRC has established a license renewal process that establishes guidelines for renewal of operating power plant licenses for an additional 20 years of plant life and that can be completed in a reasonable period of time. The NRC has developed internationally available license renewal guidance documents to describe the interrelated aspects of preparing and reviewing license renewal applications. The objective of this presentation is to provide background information on the development of these documents and to briefly explain the intended use of the guidance documents singularly and in combination-to facilitate the renewal process starting from the application development by the plant to the regulatory staff review including audits and inspections of on-site supporting technical documentation. (authors)

  1. Nuclearelectrica - a player on the Romanian energy market

    International Nuclear Information System (INIS)

    Nuclearelectrica operates at Cernavoda NPP a CANDU 6 unit. The production performances and some technical indicators are presented. The paper introduces the players of the new-born Romanian energy market, where Nuclearelectrica acts as a significant producer, and. gives a short description of the current market mechanisms. The specific features of a producer operating a single nuclear unit, related to both technical and economical terms, are itemized; they are considered in the market rules issued by the Romanian Electricity Regulatory Authority - ANRE. Following these rules, Nuclearelectrica concluded with Electrica, the main energy supplier to final consumers, a long-term energy wholesale contract for all the generated by Cernavoda 1 electricity, based on the so-called Power Purchase Agreement model, where a large part of the risk related to the power sales is borne by the buyer. On the same time, the existing conditions on the Romanian market proved the competitiveness of Cernavoda unit as an energy producer; hence, the above-mentioned contract provides a futile over-protection to the NPP facing the market risks. The paper presents also the critical issue of the collection of revenues for the sold electricity and the company's approach in allotting this limited revenues. In light of the completion of Unit 2 of the Cernavoda NPP, the company's strategy considers new possible contracts, with eligible customers and energy exports.(author)

  2. ATUCHA I NPP - Emergency drill practice

    International Nuclear Information System (INIS)

    Full text: Atucha I NPP performs an Emergency Drill Practice once a year. Its main goals are: -) Fulfill the requirements of the Argentine Nuclear Regulatory Authority (ARN) regarding Atucha I NPP's Operating License; -) Fulfill the commitment with the community regarding the safe and reliable operation Atucha I NPP; -) Verify the response of the Civil Organizations, Security Forces, and Armed Forces, as well as the correct application of the Emergency Plan; -) Perform the 'General Alarm Drill' periodic control; -) Perform a re-training of the members of the Security Advisor Internal Committee (CIAS) on the Internal and External Aspects of the Emergency Plan and on the related procedures; -) Test the Emergency Communications System. New goals are added every year, considering the Drill's scope. This drill comprises two different kinds of practices: Internal practices (practices in the station, with our personnel) and external practices (practices outside the station with governmental organizations). Internal practices comprise: -) Internal and external communications practices; -) Acoustic alarms; -) Personnel gathering in the Meeting Points; -) Safety of selected Meeting Points; -) Personnel count, selective evacuation; -) Iodide Potassium pills distribution; -) CICE (Internal Group for Emergency Control) Coordination. External practices comprise: -) Nuclear Regulatory Authority; -) Argentine Navy, Comando Area Naval Fluvial, Base Naval Zarate; -) Lima firemen; -) Zarate firemen; -) Municipal Civil Defense (Zarate and Lima); -) National Guard, Escuadron Atucha; -) Zarate Regional Hospital; -) Lima Police Department; -) Zarate Police Department; -) Argentine Coast Guard, Zarate; -) Local radios: Radio FM Libre, FM El Sitio; -) First Aid clinic. The following activities are performed together with the aforementioned organizations: -) Formation of an 'Operative committee'; -) Evacuation of citizens in a 3 km radio; -) Control of every access to Lima; -) Control of

  3. Project equipment HVAC chilled with R22 in the NPP Asco; Proyecto de sustitucion de equipos HVAC refrigerados con R22 en la C.N. Asco

    Energy Technology Data Exchange (ETDEWEB)

    Jaimot Jimenez, J. J.; Imbert, J. J.

    2013-07-01

    This paper describes the project of changing units of air conditioning in the Asco NPP currently used R22 as coolant. The project has a powerful, affecting 37 units, of which more than half are Clase1E. The document describes the process of sizing, scope of change and solutions adopted for this change of design.

  4. Unusual occurrences during the whole operation of BN-250 NPP

    International Nuclear Information System (INIS)

    Unusual occurrences during the whole operation BN-350 NPP. 1. Oil ingress in high pressure receiver for the not reveled reason, 12.05.1994. 2. lncrease of water radioactivity of circulating water supply system due to heat exchanger leak of spent fuel assembly washing out system, 17.09.1993. 3. Lack of passableness of sodium drain header of primary circuit reveled during inspection on scheduled preventative maintenance, 28.11.1996. 4. Destruction of the blow-off line of MCP-6 due to corrosion damage of the pipeline while unit was being operated at rated power, 23.04.1993. 5. Lack of passableness of blow-down pipeline connecting reactor gas cover with gas-type pressurizer while unit was being operated at rated power, 17.11.1994. 6. Sodium ingress in blow-down pipeline of loop-5 intermediate heat exchanger while loop-5 was being fed of sodium during scheduled preventative maintenance, 27.06.1994. 7. Resistance deterioration of electro heating zones of loop-4 due to heat exchanger leak and water ingress in air-pipeline of primary circuit boxes recirculating air system, 02.05.1997. 8. Resistance deterioration of electro heating zones of sodium drain header of secondary circuit was sopped in the water for the extinguishing the fire of blowing ventilation oil-strainer, 23.12.1994. 9. Sodium ingress in gas-type pressurizer through pipeline of primary sodium cleanup system and blow-down pipeline of failed MCP-2 while primary sodium cleanup system was being connected to the primary circuit, 17.08.1976. As a rule, the main reactor systems are scrutinized more carefully than the auxiliary reactor systems and the order actions are existed for eliminating and mitigating of consequences of main reactor system fails. Therefore the auxiliary reactor system fails may impact on the main reactor systems through places of its contact in significant measure. The influence of auxiliary reactor system fails on main reactor systems and its possible consequences for behavior of the main

  5. Proceedings of the joint WANO/OECD-NEA workshop on pre-stress loss in NPP containments

    International Nuclear Information System (INIS)

    This joint WANO/OECD-NEA workshop on pre-stress loss in NPP containments started with Opening Remarks (by OECD and EDF) and two presentations on 'Creep and Shrinkage of Concrete: Physical Origins, Practical Measurements', and 'Past, Present and Future Techniques for Predicting Creep and Shrinkage of Concrete'. It was then followed by papers and presentations from 12 countries, which titles are: Assessment of Creep Methodologies for Predicting Prestressing Forces Losses in Nuclear Power Plant Containments; Prestress Behaviour in Belgian NPP Containments; Presentation of Gentilly 2 NPP Containment (abstract only); Containment Structure Monitoring and Prestress Losses; Experience from Daya Bay Nuclear Power Plant (China); Prestress losses in NPP containments - the EDF experience; Prestress Force Monitoring on the THTR Prestressed Concrete Reactor Vessel During 19 Years; NPP Containment Design: Evolution and Indian Experience; In-Service Inspections and R and D of PCCVs in Japan; Comparison of Grouted and Un-grouted Tendons in NPP Containments; Prestress Losses in Containment of VVER 1000 Units; Prestressing in Nuclear Power Plants; Anchor Lift-off Measuring System for 37 T 15 Tendons; Monitoring of Stressed-Strained State and Forces in Reinforcing Cables of Prestressed Containment Shells of Nuclear Power Plants; Long-Term In-Service Monitoring of Pre-stressing in Magnox Pre-stressed Concrete Pressure Vessels; The Measurement of Un-bonded Tendon Loads in PCPV and Primary Containment Buildings; The Long Term In-service Performance of Corrosion Protection to Prestressing Tendons in AGR Prestressed Concrete Pressure Vessels; Prestress Force Losses in Containments of U.S. Nuclear Power Plants. Discussions and a synthesis are also presented

  6. Industry Operating Experience Process at Krsko NPP

    International Nuclear Information System (INIS)

    Experience has shown that number of minor events and near misses, usually without immediate or significant impact to plant safety and reliability, are precursors of significant or severe events due to the same or similar root or apparent cause(s). It is therefore desirable to identify and analyze weaknesses of the precursor problems (events) in order to prevent occurrence of significant events. Theoretically, significant events could be prevented from occurring if the root cause(s) of these precursor problems could be identified and eliminated. The Operating Experience Program identifies such event precursors and by reporting them to the industry, plant specific corrective actions can be taken to prevent events at other operational plants. The intent of the Operating Experience Program is therefore to improve nuclear power plant safety and reliability of the operating nuclear power plants. Each plant develops its own Operating Experience Program in order to learn from the in-house operating experience as well as from the world community of nuclear plants. The effective use of operating experience includes analyzing both plant and industry events in order to identify fundamental weaknesses and then determining appropriate plant-specific actions that will minimize the likelihood of similar events. Learning and applying the lessons from operating experience is an integral part of station safety culture and is encouraged by managers throughout the top plant administrative programs and procedures. Krsko NPP is developed it own Operating Experience Program by using the most relevant INPO/WANO/IAEA guidelines as well as its own knowledge, skills an operating practice. The Operating Experience Program is a part of the Corrective Action Program, which is among top management programs, thus program is strongly encouraged by top management. The purpose of Operating Experience Program is to provide guidance for using, sharing, and evaluating operating experience information

  7. Students education and training for Slovak NPP

    International Nuclear Information System (INIS)

    Slovak University of Technology is the largest and also the oldest university of technology in Slovakia. It is certain that more than 50% of the highly-educated technicians who are currently working in the nuclear industry have graduated from this university. The Department of Nuclear Physics and Technology of the Faculty of Electrical Engineering and Information Technology as one of the seven faculties of this University feels the responsibility to impart proper engineering education and training for Slovak NPP operating staff. The education process is realised via undergraduate (BSc), graduate (MSc) and postgraduate (PhD) study as well as via specialised training courses within the framework of a continuous education system. (author)

  8. N-16 monitors: Almaraz NPP experience

    Energy Technology Data Exchange (ETDEWEB)

    Adrada, J. [Almaraz NPP, Madrid (Spain)

    1997-02-01

    Almaraz Nuclear Power Plant has installed N-16 monitors - one per steam generator - to control the leakage rate through the steam generator tubes after the application of leak before break (LBB) criteria for the top tube sheet (TTS). After several years of operation with the N-16 monitors, Almaraz NPP experience may be summarized as follows: N-16 monitors are very useful to follow the steam generator leak rate trend and to detect an incipient tube rupture; but they do not provide an exact absolute leak rate value, mainly when there are small leaks. The evolution of the measured N-16 leak rates varies along the fuel cycle, with the same trend for the 3 steam generators. This behaviour is associated with the primary water chemistry evolution along the cycle.

  9. Trust in the government, gender, and technical knowledge in college students as correlate of the three dimensions of attitude towards NPP establishment in Thailand

    International Nuclear Information System (INIS)

    The correlation comparative study aimed at investigating the relationships among trust in the government, gender, knowledge on NPP, and attitude toward NPP establishment. Attitude towards NPP establishment, as three dependent variables, were measured in terms of three dimensions: cognitive, affective, and intention to act. Trust in the government referred to one's beliefs and emotional disposition that the government will do its best, less corruption, and display more integrity on NPP construction and management. Knowledge on NPP consisted of 3 dimensions: safety, advanced technology, and social aspects. Measures mostly were in the form of summated ratings with 6 unit-Likert scales. Reliability if these measures ranged between 0.6518 to 0.9267. The sample in this study, obtained by stratified quota random sampling method, consisted of 817 Thai undergraduate students, with the average age of 21.41 years, average GPA of 2.66. Three hundred and fifty three students were science majors (43.2%), and the rest (464 students, 56.8%) were social science majors. It was found that trust in the government, as well as, knowledge on NPP were positively and significantly related to all three dimensions of attitudes toward the NPP establishment. Results from three way ANOVA revealed that males reported more favorable to NPP establishment in terms of affective and intention to act that females. The findings also revealed that males with high trust in the government and more knowledge on NPP got the highest score on cognitive dimension. This result was found in the total sample and, especially in social science students. These results supported the three hypotheses in this study. Path Analysis indicated that trust in the government and knowledge on NPP directly affects cognitive aspect, and affective aspect, while theses two aspects directly affected intention to act. Comparisons were made with the results from studies of online tax, and mobile banking adoptions concerning the

  10. Use of interview and inquiry procedures in design process for NPP control room upgrade

    International Nuclear Information System (INIS)

    Major part of design activities for upgrade of NPP control rooms is using NPP personnel operating experience and participation of NPP personnel in detecting and solving the human factor problems. The ways of such participation include application of various human factors engineering and psychological techniques, for example interviews, inquiries (filling in questionnaire), operator activity observations. The present paper deals with activation of NPP personnel role in the design of control room upgrade, in particular, in creation of operator support systems. NPP personnel selection for incorporation in NPP upgrade group and initial training design skills are considered. NPP personnel responsibilities during particular stages of control room designing are specified. (author). 1 ref

  11. A Matric System Combining NPP facilities information and decommissioning activity information

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hee Seong; Park, Seung Kook; Song, Chan Ho; Moon, Jei kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    D-D (Decontamination and Decommissioning) research divisions have experience in dismantling the uranium conversion plant and KRR-2 (Korean Research Reactor 2, TRIGA Mark type III) of 1998-2009. Using data obtained through the dismantled KRR-2, the divisions have studied how to dismantle a commercial nuclear power plant. There are lots of problems to apply directly dismantled data of the research reactor into the dismantling of a commercial reactor. The paper introduces a matrix system to manage a decommissioning project in preparing the dismantling of nuclear power plants as the first phase of solving the problems. The matrix, which is a system that combines the WBS code and the facility code of the nuclear power plant to be dismantled, has the decommissioning information of dismantling of the NPP. The matrix system has an important role in the evaluation of the amount of dismantling waste and decommissioning schedule and cost in conjunction with a database system that has been developed. To apply the information obtained from the dismantling of the KRR-2 into NPP dismantling, a matrix system has been devised. The matrix system is configured with data related to the dismantling of the ISDC information and WBS used during the dismantling of KRR-2 and the facilities information of the NPP. The code in the matrix system has all specifications of the facility and information about the device, as well as the unit operation obtained from the research reactors.

  12. WWER-1000/V-428 type fuel operational experience at the Tianwan NPP

    International Nuclear Information System (INIS)

    The commercial operation of Unit 1 of Tianwan NPP was started on May 17, 2007. Nuclear fuel assemblies of WWER-1000/V-428 type for the initial core loading were supplied by JSC TVEL and manufactured by JSC Novosibirsk Chemical Concentrates Plant. This paper introduces the superficial and preliminary operational experience of the nuclear fuel in the Unit 1 of Tianwan NPP. Since the nuclear fuel was loaded into the reactor core of Unit 1 of TNPP, the work on fuel cladding gas tightness monitoring was commenced. The database on fuel performance and behaviour is established and running normally at TNPP. The total iodine radio-nuclide specific activity Σ(131I-135I) was stabilized and kept on the 105Bq/kg level since the Unit 1 was put into operation. On the basis of information and analysis to the radio-nuclides in the primary coolant during power operation of reactor, up to now the preliminary decision was drawn that there were probably one or more fuel rods with the gas-leakiness defect in the reactor core and fuel failure detection (FFD) inspection plan was made for the coming outage of Unit 1 of TNPP by the end of year 2007. (author)

  13. NPP safety in Slovakia according to stress tests after accident in Fukushimi

    OpenAIRE

    Králik, Juraj

    2013-01-01

    This paper presents the new requirements to test of the safety and reliability of the NPP structures due to the last nuclear accidents in the world. The accidents of the NPP in Chernobyl and Fukushima give us the new inspiration to verify the safety level of the NPP structures. The probabilistic assessment of NPP structures for PSA level 2 of VVER 440 in the case of LOCA accident is presented. The results of the probabilistic nonlinear analysis of the NPP structures are present...

  14. Hydrodynamic model of Fukushima-Daiichi NPP Industrial site flooding

    CERN Document Server

    Vaschenko, V N; Gerasimenko, T V; Vachev, B

    2014-01-01

    While the Fukushima-Daiichi was designed and constructed the maximal tsunami height estimate was about 3 m based on analysis of statistical data including Chile earthquake in 1960. The NPP project industrial site height was 10 m. The further deterministic estimates TPCO-JSCE confirmed the impossibility of the industrial site flooding by a tsunami and therefore confirmed ecological safety of the NPP. However, as a result of beyond design earthquake of 11 March 2011 the tsunami height at the shore near the Fukushima-Daiichi NPP reached 15 m. This led to flooding and severe emergencies having catastrophic environmental consequences. This paper proposes hydrodynamic model of tsunami emerging and traveling based on conservative assumptions. The possibility of a tsunami wave reaching 15 m height at the Fukushima-Daiichi NPP shore was confirmed for deduced hydrodynamic resistance coefficient of 1.8. According to the model developed a possibility of flooding is determined not only by the industrial site height, magni...

  15. The Regulatory System for the First NPP in Indonesia

    International Nuclear Information System (INIS)

    The first Nuclear Power Energy Resources (NPP) will operate in 2016 in order to fulfill the needs of national electrical energy especially in Java, Madura and Bali (JAMALI), It was stated in the blue print in National Energy Management 2005 - 2025. The regulatory aspects of the use of nuclear energy in accordance with the role and functions of BAPETEN (Nuclear Energy Regulatory Agency) are to prepare and develop rules and regulations, licensing system, inspection system, as well as human resources. The road map in the regulation of the first NPP has been in place since 2004. According to the challenges in the Strategic Plan of BAPETEN, BAPETEN carries out the regulatory program for the first NPP, for the ageing management of research reactors, as well as for nuclear security. In this paper, I will present the preparation of the regulatory aspects of NPP according to the role and functions of BAPETEN, i.e. to prepare and develop rules and regulations, licensing system, inspection system, as well as human resources. Rules and regulations on NPP has been enacted and some are still being prepared and developed. Government Regulation No. 43 of 2006 regulates the licensing of nuclear installations, including site license, construction license, operation license, commissioning license and decommissioning license. Government Regulation that is being drafted is on Nuclear Safety and Security. Presidential Regulation on Nuclear Liability is expected to be enacted by the end of this year. The licensing system prepared in facing the operation of the first NPP in Indonesia should begin with the preparation of the process and procedures for obtaining NPP licenses. The review and assessment procedures in every stage of NPP licenses (site, construction, commissioning, operation and decommissioning) should be prepared in line with the existing regulations. The inspection and enforcement procedures in the construction and operation of NPP are prepared based on the applicable rules

  16. Morbidity with temporary disability in Kozloduy NPP workers

    International Nuclear Information System (INIS)

    Changes with time in indicators of disease incidence with temporary disability in Kozloduy NPP personnel have been studied for the period 1974-1991. The data were compared with those for 'Sofia-Iztok' TPP. The causes contributing to formation of the indicators of frequency, severity, and average duration were examined. No temporary disability because of radiation exposure has been recorded. As a whole, less temporary disability has been found at NPP than at TPP. (author)

  17. Students education and training for Slovak NPP

    International Nuclear Information System (INIS)

    elaboration of diploma thesis. In addition to regular academic education we perform post-gradual courses: 'Safety aspects of NPP operation'. The main goal is to increase safety culture of NPP operation and target groups are operation staff of NPP, NRA officers, nuclear safety specialists - all graduated from technical universities with at least two years practice in nuclear industry. On international level we organised the 4 weeks 'IAEA Regional Training Course on Safety, Management and Utilization of Research Reactors' which was held in Bratislava (Slovakia) and Vienna (Austria) during March 05-30th 2001. IAEA in co-operation with the Department of Nuclear Physics and Technology of the Slovak University of Technology and the Atominstitut of Austrian Universities Vienna prepared and realized this training course with the aim to train junior staff from research reactors in various aspects of safety, management and utilization of research reactors. All participants had to have at least 4 years experiences in operation, management, utilization or regulation of research reactors. Lectures covered the topics in nuclear design and operation, neutron physics, reactor physics, health physics, dosimetry, reactor instrumentation, fuel management decontamination procedures, preparation of experiments at research reactors and others. Beside theoretical part of the course, the practical exercises at TRIGA II reactor in Vienna constituted an important part of training. The course was held in English for participants from 6 countries (Slovakia, Russia, Romania, Hungary, Ukraine, Turkey) and thank support of IAEA was fully provided with textbooks and laboratory guides. This year we take part via students and 2 professors the second run of the Eugene Wiegner course establishing in frame of ENEN project. According to international experiences obtained during the last 3 years, we created The Slovak Nuclear Education Network (SNEN) which is supervised at our Department. Coordination of nuclear

  18. EPC projects for EPR Flamanville 3 NPP

    Energy Technology Data Exchange (ETDEWEB)

    Diaz, J.I.; Polo, J.; Aymerich, E.; Cubian, B. [Nuclear Generation Department, Iberdrola Ingenieria y Construccion, Avda. Manoteras 20, 28050 Madrid (Spain)

    2010-07-01

    IBERDROLA Ingenieria y Construccion is carrying out a handful of activities in the EPR Flamanville 3 -FA3 NPP- context since 2007 matching oriented to position the company in the emerging marketplace of new nuclear power plants Generation III+, whose expectation for the next years is highly promising. IBERDROLA Ingenieria y Construccion leads 5 EPC -Engineering, Procurement and Commissioning- projects for FA3 NPP from the Nuclear Island till Sea Water Pumping Station as follows: - Design, procurement. fabrication, installation and testing of 21 shell and tubes heat-exchangers for the nuclear island. 12 out of these 17 HXs are conventional and will be designed according to ASME BPV code Section VIII and have to comply with PED 97/23/CE and ESPN. The remaining 5 HXs are nuclear and will be designed according to ASME BPV code Section III and have also to comply with PED and ESPN. - Design, procurement, fabrication and assembly of 9 demineralizers for different plant systems. Three of these Important To Safety (IPS) equipments have been manufactured according with ASME VIII codes and six of them with EN 13445 code plus additional requirements to comply with PED and final client requirements for nuclear island. - Design, fabrication and installation of qualified travelling water screening filters. The equipments furnished will be two nuclear safety qualified filters and associated equipment (cleaning water system and control system). Additionally some auxiliary devices such as grids, automatic trash rakes and stop gates are included in the contract. - Engineering, procurement, fabrication, erection and commissioning for the condensate treatment plant. This system includes a demineralizer tank, 5 filters, reactive injection mixer, pneumatic and manual valves, piping and instrumentation and control systems. - Engineering, procurement erection and commissioning for the electro-chlorination plant to protect the IPS piping for Condensate Water System for FA3. This system

  19. CFD analysis of the temperature field in emergency pump room in Loviisa NPP

    International Nuclear Information System (INIS)

    Highlights: • Laser scanned room geometry from Loviisa NPP was utilized for CFD simulation. • Uncertainty of CFD simulation was estimated using the Grid Convergence Index. • Measured temperature field of pump room was reproduced with CFD simulation. - Abstract: In the Loviisa Nuclear Power Plant (NPP) six emergency pumps belonging to the same redundancy are located in the same room. During a postulated accident the cooling of the room is needed as the engines of the emergency pumps generate heat. Cooling is performed with fans blowing air to the upper part of the room. Temperature limits have been given to the operating conditions of the main components in order to ensure their reliable operation. Therefore the temperature field of the room is important to know. Temperature measurements were made close to the most important components of the pump room to get a better understanding of the temperature field. For these measurements emergency pumps and cooling fan units were activated. To simulate conditions during a postulated accident additional warm-air heaters were used. Computational fluid dynamic (CFD) simulations were made to support plant measurements. For the CFD study one of the pump rooms of Loviisa NPP was scanned with a laser and this data converted to detailed 3-D geometry. Tetrahedral computation grid was created inside the geometry. Grid sensitivity studies were made, and the model was then validated against the power plant tests. With CFD the detailed temperature and flow fields of the whole room were produced. The used CFD model was able to reproduce the temperature field of the measurements. Two postulated accident cases were simulated. In the cases the operating cooling units were varied. The temperature profile of the room changes significantly depending on which units are cooling and which only circulating the air. The room average temperature stays approximately the same. The simulation results were used to ensure the acceptable operating

  20. CFD analysis of the temperature field in emergency pump room in Loviisa NPP

    Energy Technology Data Exchange (ETDEWEB)

    Rämä, Tommi, E-mail: tommi.rama@fortum.com [Fortum Power and Heat, P.O.B. 100, FI-00048 Fortum (Finland); Toppila, Timo, E-mail: timo.toppila@fortum.com [Fortum Power and Heat, P.O.B. 100, FI-00048 Fortum (Finland); Kelavirta, Teemu, E-mail: teemu.kelavirta@fortum.com [Fortum Power and Heat, Loviisa Power Plant, P.O.B. 23, FI-07901 Loviisa (Finland); Martin, Pasi, E-mail: pasi.martin@fortum.com [Fortum Power and Heat, Loviisa Power Plant, P.O.B. 23, FI-07901 Loviisa (Finland)

    2014-11-15

    Highlights: • Laser scanned room geometry from Loviisa NPP was utilized for CFD simulation. • Uncertainty of CFD simulation was estimated using the Grid Convergence Index. • Measured temperature field of pump room was reproduced with CFD simulation. - Abstract: In the Loviisa Nuclear Power Plant (NPP) six emergency pumps belonging to the same redundancy are located in the same room. During a postulated accident the cooling of the room is needed as the engines of the emergency pumps generate heat. Cooling is performed with fans blowing air to the upper part of the room. Temperature limits have been given to the operating conditions of the main components in order to ensure their reliable operation. Therefore the temperature field of the room is important to know. Temperature measurements were made close to the most important components of the pump room to get a better understanding of the temperature field. For these measurements emergency pumps and cooling fan units were activated. To simulate conditions during a postulated accident additional warm-air heaters were used. Computational fluid dynamic (CFD) simulations were made to support plant measurements. For the CFD study one of the pump rooms of Loviisa NPP was scanned with a laser and this data converted to detailed 3-D geometry. Tetrahedral computation grid was created inside the geometry. Grid sensitivity studies were made, and the model was then validated against the power plant tests. With CFD the detailed temperature and flow fields of the whole room were produced. The used CFD model was able to reproduce the temperature field of the measurements. Two postulated accident cases were simulated. In the cases the operating cooling units were varied. The temperature profile of the room changes significantly depending on which units are cooling and which only circulating the air. The room average temperature stays approximately the same. The simulation results were used to ensure the acceptable operating

  1. Regulation and license for NPP in Indonesia

    International Nuclear Information System (INIS)

    Any activity relating to nuclear energy shall maintain safety, security, safeguards, health worker and public as well as environmental protection, according to article 16(1) act No. 10 year 1997 on Nuclear Energy. The act No. 10 year 1997 on Nuclear Energy stipulated independent government agency as nuclear energy regulatory called BAPETEN (Nuclear Energy Regulatory Agency). BAPETEN has task to make regulation, licensing process and inspection. Bapeten shall have a licensing and inspection system in fulfilling his function to issued licensing according to Nuclear Energy Act. In Article 17 stipulated that any nuclear energy utilization or construction and operation of nuclear reactor and other nuclear installation as well as decommissioning of nuclear reactor shall have license. Requirements and process to issue license for nuclear reactor stipulated further in Government Regulation no. 43 year 2006. The purpose of the Government Regulation No. 43 is to stipulate licensing of nuclear reactor in order to assure the health of worker and public, environment protection and security of nuclear material and nuclear facility. Requirement and guidance in licensing NPP mandated by Government Regulation or Presidential Decree stipulated in Bapeten Chairman Regulation

  2. SAT for NPP personnel training in Spain

    International Nuclear Information System (INIS)

    The SAT process objectives as applied to Spanish NPPs are: Perform JTA for selected job positions at the NPPs; develop the associated training plans; develop training support media; prepare training instructors as teachers and as task analysts; develop a SAT database. A lesson-learned from the task assessments conducted at Spanish NPPs is that the final task list should be obtained with full participation of workers so that they feel the final training plan has been developed taking into account their own opinion and experience. The breakdown of the tasks into its elements and the concordant job performance measure was presented. The process of determining knowledge and skills associated with the task elements and the structure and use of the taxonomy codes (for component, system, and academic skills and knowledge) was shown and explained. Based on the Spanish experience, the average time devoted to analyze a complete task is 5.33 person-hours per task. This data has permitted training and plant management to allocate the NPP human resources to support the analysis phase of SAT (which can be very time-consuming)

  3. Thermal performance monitoring in Dukovany NPP

    Energy Technology Data Exchange (ETDEWEB)

    Pliska, J.; Machat, Z.; Horky, V.; Sury, P.; Havlat, L. [I and C Energo plc., Prazska 684, 674 01 Trebic (Czech Republic)

    2010-07-01

    The paper presents a practical application of the thermal performance monitoring on Dukovany NPP related to the performance of the balance of plant. The system described is focused on the health of the process and on the health major equipment involved in the process. The system provides information on actual and expected or desirable (should-be) values of thermal performance indicators for performance engineers, maintenance planners and control room operators. The system is designed to monitor steady states. The system contains two main functions: Data validation and Process simulation. Data validation provides a solid base for detection, identification and elimination of process data corrupted by gross errors and for monitoring and evaluation of measurement degradation. Process simulation is performed with steady state mathematical model of power plant components configured into secondary side. Major purpose of Process simulation is calculation of performance data for an expected state of the plant equipment and the actual mode of operation. Control room operators (in near-real time) and performance engineers then can evaluate and diagnose the health of the equipments and the adjustment of the process parameters by comparing an actual and expected state of the performance data. The system also allows 'what-if' analysis and efficiency optimization based on varying user selected parameters of the plant components, process parameters and flow-sheet structure changes. (authors)

  4. Economic aspects of Dukovany NPP fuel cycle

    International Nuclear Information System (INIS)

    The paper discusses some aspects of high burnup program implementation at Dukovany NPP and its influence on the fuel cycle costs. Dukovany internal fuel cycle is originally designed as a three years cycle of the Out-In-In fuel reloading patterns. These reloads are not only uneconomical but they additionally increased the radiation load of the reactor pressure vessel due to high neutron leakage typical for Out-In-In loading pattern. To avoid the high neutron leakage from the core a transition to 4-year fuel cycle is started in 1987. The neutron leakage from the core is sequentially decreased by insertion of older fuel assemblies at the core periphery. Other developments in fuel cycle are: 1) increasing of enrichment in control assemblies (3.6% of U-235); 2) improvement in fuel assembly design (reduce the assembly shroud thickness from 2.1 to 1.6 mm); 3) introduction of Zr spacer grid instead of stainless steel; 4) introduction of new type of assembly with profiled enrichment with average value of 3.82%. Due to increased reactivity of the new assemblies the transition to the partial 5-year fuel cycle is required. Typical fuel loading pattern for 3, 3.5, 4 and 5-year cycles are shown in the presented paper. An evaluation of fuel cost is also discussed by using comparative analysis of different fuel cycle options. The analysis shows that introduction of the high burnup program has decrease relative fuel cycle costs

  5. PSA analysis focused on Mochovce NPP safety measures evaluation from operational safety point of view

    International Nuclear Information System (INIS)

    Mochovce NPP consists of four reactor units of WWER 440/V213 type and it is located in the south-middle part of Slovakia. At present two units are operated and another two are under the construction. As these units represent second generation of WWER reactor design, the additional safety measures (SM) were implemented to enhance operational and nuclear safety according to the recommendations of performed international audits and operational experience based on the exploitation of similar units. These requirements result into a number of SMs grouped according to their purpose to reach recent international requirements on nuclear and operational safety. The paper presents the bases used for SMs establishing including their grouping covering different areas of safety goals and results of SM contributions to the total core damage frequency based on FPSA analysis. (author)

  6. Criticality safety analysis of spent fuel storage for NPP Mochovce using MCNP5

    International Nuclear Information System (INIS)

    The paper presents results of nuclear criticality safety analysis of spent fuel storage for the first and second unit of NPP Mochovce. The spent fuel storage pool (compact and reserve grid) was modeled using the Monte Carlo code MCNP5. Conservative approach was applied and calculation of keff values was performed for normal and various postulated emergency conditions in order to evaluate the final maximal keff values. The requirement of current safety regulations to ensure 5% subcriticality was met except one especially conservative case. (Authors)

  7. Support of the Ukrainian supervisory authority in establishing a modern nuclear power plant monitoring for NPP Rovno and Saparoshje

    International Nuclear Information System (INIS)

    A system to improve the operational monitoring for the 3rd unit of the Rovno NPP - VVER-1000/V-320 - was put up by analogy with the six units of the same type of the Zaporoshye NPP. For that 57 current and relevant to safety parameters are available to the Supervisory Authority on-site and in Kiev for collection and assessment. These parameters are transferred on-line by modern technical facilities once a minute. The developed evaluation software enables the visualisation of the monitoring results in the form of diagrams, charts and graphs. By means of an archive modus the trends of all parameters can be analysed. Additionally, the efficiency and the reliability of the whole remote monitoring system was increased. Thus, the monitoring of more than 60% of the total Ukrainian nuclear power by the Supervisory Authority has been significantly improved up to now. (orig.)

  8. Decommissioning of the A-1 NPP heavy water evaporator facility - 59225

    International Nuclear Information System (INIS)

    The paper deals with experience and techniques in the application of remotely controlled robotic devices for the dismantling of the A-1 NPP technological equipment during undergoing decommissioning process of the A-1 NPP, which is characterized by high level of radioactivity and contamination. For liquidation of the heavy water evaporator has been applied a mobile robotic system MT 80, which had been developed, designed and constructed as a general-purpose decommissioning equipment. The heavy water evaporator as a part of the NPP heavy water system is located inside the main production unit building in Room No. 220 where the inner surface contamination is from 101 Bq/cm2 to the level of 103 Bq/cm2, dose rate up to 1.5 mGy/h and the feeding pipeline contained LRAW with high tritium content. The first step was the development of a work procedure with special focus on the elimination of activity and aerosols leaking into the environment. Special tooling was developed for application with the robot, such as hydraulic shears, circular saw, reciprocating saw, circular pipe cutter and a system for quick tool-change without direct intervention of the operators. Then, civil engineering modifications were made to the workplace and new technology was installed, including an efficient exhaust system. After draining-off the remains of LRAW and rinsing the pipeline, fragmentation of the pieces of equipment was started. The fragments are being deposited into drums which are transported in shielded containers to the decontamination facility, where their activity is reduced prior to their storage or further use. All operations are remotely controlled on basis of visual information from four cameras, with consistent radiation protection of the operators. This experience will be exploited in the continuation of work in Room No. 219, where the second identical heavy water evaporator is located. Nuclear Power Plant A-1 is situated in the locality of Jaslovske Bohunice. The A-1 NPP

  9. RISKAUDIT Report no. 7, Vol. 1: Safety evaluation of VVER 440/213 and VVER 1000/320 reactors in Rovno NPP Units 1, 2 and 3. Final Report by AIB-Vincotte Nuclear, CIEMAT, ANPA, GRS, IPSN, AEA-T

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-07-15

    The Riskaudit 7 report has been made by a group of independent experts from Western European countries representing technical organizations specialized in the support of regulatory bodies of those countries. It represents a preliminary estimation of the Ukrainian WWER B 213 and B 320 reactors, based on the example of Rovno NPP, analysed with a Western practice. The first part of the document covers the following aspects of the report: core design and fuel management; pressurized components; electrical supply; instrumentation and control; containment; internal events; site conditions and external events.

  10. RISKAUDIT Report no. 7, Vol. 2: Safety evaluation of VVER 440/213 and VVER 1000/320 reactors in Rovno NPP Units 1, 2 and 3. Final Report by AIB-Vincotte Nuclear, CIEMAT, ANPA, GRS, IPSN, AEA-T

    International Nuclear Information System (INIS)

    The Riskaudit 7 report has been made by a group of independent experts from Western European countries representing technical organizations specialized in the support of regulatory bodies of those countries. It represents a preliminary estimation of the Ukrainian WWER B 213 and B 320 reactors, based on the example of Rovno NPP, analysed with a Western practice. The second part of the document covers the following aspects of the report: accident analysis; systems analysis; plant operation; operating experience feedback; radio protection and health; probabilistic safety assessment; summary and future plans

  11. RISKAUDIT Report no. 7, Vol. 1: Safety evaluation of VVER 440/213 and VVER 1000/320 reactors in Rovno NPP Units 1, 2 and 3. Final Report by AIB-Vincotte Nuclear, CIEMAT, ANPA, GRS, IPSN, AEA-T

    International Nuclear Information System (INIS)

    The Riskaudit 7 report has been made by a group of independent experts from Western European countries representing technical organizations specialized in the support of regulatory bodies of those countries. It represents a preliminary estimation of the Ukrainian WWER B 213 and B 320 reactors, based on the example of Rovno NPP, analysed with a Western practice. The first part of the document covers the following aspects of the report: core design and fuel management; pressurized components; electrical supply; instrumentation and control; containment; internal events; site conditions and external events

  12. RISKAUDIT Report no. 7, Vol. 2: Safety evaluation of VVER 440/213 and VVER 1000/320 reactors in Rovno NPP Units 1, 2 and 3. Final Report by AIB-Vincotte Nuclear, CIEMAT, ANPA, GRS, IPSN, AEA-T

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-07-15

    The Riskaudit 7 report has been made by a group of independent experts from Western European countries representing technical organizations specialized in the support of regulatory bodies of those countries. It represents a preliminary estimation of the Ukrainian WWER B 213 and B 320 reactors, based on the example of Rovno NPP, analysed with a Western practice. The second part of the document covers the following aspects of the report: accident analysis; systems analysis; plant operation; operating experience feedback; radio protection and health; probabilistic safety assessment; summary and future plans.

  13. Researches of a thermodynamic behaviour of bubbling vacuum system bubble condenser NPP 'Mochovce'

    International Nuclear Information System (INIS)

    During joint development and designing of the bubbling vacuum system (BVS) equipment for localization of under-loss of coolant accident (LOCA) consequences on NPPs with WWER 440/213, a large volume of experimental and calculational activities have been performed by VTI and SverdNIIchimmash for the substantiation of functionality of this system, and in particular, for bubbler-condenser (BC) design, as a part of BVS. However, not looking on broad introduction of BVS on 16-th NPP units with WWER 440/213, its functionality was subjected to a doubt from experts of different countries. Sequentially, that promoted issue of the IAEA, document and OECD document. Therefore, before commissioning of the NPP 'Mochovce' unit 1 it was decided to execute additional experimental and computational researches for Safety Analysis Report preparation. Within the framework of these BVS thermodynamic behavior researches, in particular the following problems were chosen: (1) The check of a capability of valves DN 250 blocking in an opened position, as a result of return pressure differential on BC, during vent clearing process of the hydro-lock, that can sequentially result in an a drop of efficiency of stem condensation in BC pool; (2) To provide by direct measurements the absence of pressure oscillations dangerous for strength of a BC design in different modes of steam condensation in BC and to execute computational researches of instability of steam condensation processes (for such mode as 'chugging'); (3) Study influences of pool swell and water carry over through check valves DN 500 in the air traps on a BVS functionality; (4) To determine by a computational way the maximum pressure in NPP premises during LOCA, with taking into consideration additional failures of the BC equipment: absence of a water on two and more BC plates and DN 250 valves have blocked in an opened position (conservative conditions). (authors)

  14. Presentation of Gentilly 2 NPP containment

    International Nuclear Information System (INIS)

    The paper (abstract only) describes the plant significant features and the concrete containment life management including ageing related problems and remedies applied. Gentilly 2 NPP is a PHWR CANDU 6 nuclear power plant with a net 600 MW capacity, located in Quebec (Canada). During 15 years operations, the plant was shutdown every year for maintenance and repairs including the periodic reactor building leak rate test. The containment is a 35 Mpa concrete cylinder with a dome roof, resting on a concrete base slab. It is reinforced and pre-stressed structure with an inside diameter of 41.4 meters and a wall thickness 1070 mm for the cylinder wall and 610 mm for the dome. BBR was selected as pre-stressing system, with independent cables in the containment base slab, cylinder and dome. Strain gauges were embedded in the concrete with readings in 2 directions at each location, and can provide an insight into the concrete ageing process at each subsequent high pressure leak rate test. The variation of the leak rate, a sign of ageing, is discussed in this paper, as well as the remedies applied to reduced it. The non-conformances during construction and which had an impact on the containment ageing process are also discussed. Finally the ageing management program is described, including inspection and testing. Under testing are presented the results of the periodic high pressure leak rate tests performed and the low pressure test performed at full power, of the lift-off and of the test beams tests, as part of monitoring of the ageing of the concrete and pre-stressing cables respectively. Where remedial actions were applied, the method used and results obtained are described

  15. Spent fuel management of Jose Cabrera NPP

    Energy Technology Data Exchange (ETDEWEB)

    Blanco Zurro, J.E.; Garcia Costilla, M. [Area de Generacion - Unidad Nuclear, Gas Natural Fenosa, Avda. de San Luis, 77, 28033 Madrid (Spain); Lavara Sanz, A. [Division Nuclear, SOCOIN, P. del Club Deportivo, 1 - Edificio 5, 28223 Pozuelo de Alarcon, Madrid (Spain); Martinez Abad, J.E. [Departamento de Residuos de Alta Actividad, ENRESA, C/ Emilio Vargas, 7, 28043 Madrid (Spain)

    2010-07-01

    The definitive shutdown of Jose Cabrera Nuclear Power Plant took place on 30. of April 2006. From this moment, cooperation agreements between ENRESA and GAS NATURAL FENOSA were established to reach, among others objectives, its decommissioning, 3 years after the shutdown of the reactor. In order to accomplish the Spanish nuclear regulation, a spent fuel management plan was developed. This plan determined that the fuel assemblies placed in the spent fuel pool would be managed by means of their storage in an interim installation. For this reason, an Independent Spent Fuel Storage Installation (ISFSI) was built at plant site, pioneer in Spain by its characteristics of design. Different administrative authorizations from the point of view of nuclear safety as well as from the environmental were required for ISFSI licensing process. The transference and storage of spent fuel was carried out using the HI-STORM 100Z Dry Storage System, developed by HOLTEC INTERNATIONAL. This system, designed for the spent fuel storage in casks, supports abnormal and very hard accident conditions. The system has three main components: Storage Cask (HI-STORM), Transfer Cask (HI-TRAC) and Multipurpose Canister (MPC). In addition to this, the system has a specific Transport Cask (HI-STAR) for the future transport out of the Plant. More than 30 Design Modifications to the system and plant were implemented to solve structural problems and to include safety and ALARA improvements. The transfer of the spent fuel and its emplacement in the ISFSI began on January 2009 and finished on September of that year allowing starting the decommissioning process, three years and a half after Jose Cabrera NPP shutdown. (authors)

  16. The terrestrial NPP simulations in China since Last Glacial Maximum

    Institute of Scientific and Technical Information of China (English)

    HE Yong; DAN Li; DONG Wenjie; JI Jinjun; QIN Dahe

    2005-01-01

    Based on Atmosphere-Vegetation Interaction Model (AVIM), the magnitude and spatial distribution of terrestrial net primary productivity (NPP) in China is simulated during three different geological eras, Last Glacial Maximum (LGM), Mid-Holocene (MH) and the present. The simulation shows that the glacial-interglacial variation of East Asian summer monsoon in China is the key factor affecting the NPP change. During the three eras, mean NPPs are 208 g/m2·a, 409 g/m2·a, and 355 g/m2·a. The total NPPs are 2.05 Pg/a, 3.89 Pg/a and 3.33 Pg/a, respectively. The terrestrial NPP in China during warm-humid climate is larger than that during cold-arid eras, and the correlation analysis between NPP and climate factors suggests that temperature is the primary factor affecting the terrestrial NPP during 21 kaBP (LGM), and for 6 kaBP (MH) and the present the primary factor is precipitation.

  17. Modification of the Decontamination Facility at the Kruemmel NPP - 13451

    Energy Technology Data Exchange (ETDEWEB)

    Klute, Stefan; Kupke, Peter [Siempelkamp Nukleartechnik GmbH Am Taubenfeld 25/1, 69123 Heidelberg (Germany)

    2013-07-01

    In February 2009, Siempelkamp Nukleartechnik GmbH was awarded the contract for the design, manufacture, delivery and construction of a new Decontamination Facility in the controlled area for Kruemmel NPP. The new decontamination equipment has been installed according to the state of art of Kruemmel NPP. The existing space required the following modification, retrofitting and reconstruction works: - Demounting of the existing installation: to create space for the new facility it was necessary to dismantle the old facility. The concrete walls and ceilings were cut into sizes of no more than 400 kg for ease of handling. This enabled decontamination so largest possible amount could be released for recycling. All steel parts were cut into sizes fitting for iron-barred boxes, respecting the requirement to render the parts decontaminable and releasable. - Reconstructing a decontamination facility: Reconstruction of a decontamination box with separate air lock as access area for the decontamination of components and assemblies was conducted using pressurized air with abrasives (glass beads or steel shots). The walls were equipped with sound protection, the inner walls were welded gap-free to prevent the emergence of interstices and were equipped with changeable wear and tear curtains. Abrasive processing unit positioned underneath the dry blasting box adjacent to the two discharge hoppers. A switch has been installed for the separation of the glass beads and the steel shot. The glass beads are directed into a 200 l drum for the disposal. The steel shot was cleaned using a separator. The cleaned steel shot was routed via transportation devices to the storage container, making it available for further blasting operations. A decontamination box with separate air lock as access area for the decontamination of components and assemblies using high pressure water technology was provided by new construction. Water pressures between 160 bar and 800 bar can be selected. The inner

  18. Modification of the Decontamination Facility at the Kruemmel NPP - 13451

    International Nuclear Information System (INIS)

    In February 2009, Siempelkamp Nukleartechnik GmbH was awarded the contract for the design, manufacture, delivery and construction of a new Decontamination Facility in the controlled area for Kruemmel NPP. The new decontamination equipment has been installed according to the state of art of Kruemmel NPP. The existing space required the following modification, retrofitting and reconstruction works: - Demounting of the existing installation: to create space for the new facility it was necessary to dismantle the old facility. The concrete walls and ceilings were cut into sizes of no more than 400 kg for ease of handling. This enabled decontamination so largest possible amount could be released for recycling. All steel parts were cut into sizes fitting for iron-barred boxes, respecting the requirement to render the parts decontaminable and releasable. - Reconstructing a decontamination facility: Reconstruction of a decontamination box with separate air lock as access area for the decontamination of components and assemblies was conducted using pressurized air with abrasives (glass beads or steel shots). The walls were equipped with sound protection, the inner walls were welded gap-free to prevent the emergence of interstices and were equipped with changeable wear and tear curtains. Abrasive processing unit positioned underneath the dry blasting box adjacent to the two discharge hoppers. A switch has been installed for the separation of the glass beads and the steel shot. The glass beads are directed into a 200 l drum for the disposal. The steel shot was cleaned using a separator. The cleaned steel shot was routed via transportation devices to the storage container, making it available for further blasting operations. A decontamination box with separate air lock as access area for the decontamination of components and assemblies using high pressure water technology was provided by new construction. Water pressures between 160 bar and 800 bar can be selected. The inner

  19. Investigation of thermohydraulic parameter variations in operating conditions of Bilibino NPP CPS cooling circuit

    International Nuclear Information System (INIS)

    In consequence of activities on uncovering the reasons for through faults formation in cooling tubes of reactor control and protection system (CPS) channels of Bilibino-2 reactor the conclusion is made that corrosion failure development takes place against the backdrop of periodic increase of total moisture in reactor space at transient and standby modes at top of cooling tubes of CPS channels. Formation of corrosion defects in cooling tubes of four CPS channels of unit 2 in 2011-2012 is specific factor for this plant unit and do not effect on operation of other plant units. It is pointed out that ingress of moisture into gas system of the reactor is the critical factor providing integrity of structure elements of EhPG-6 reactor core cooling system. This fact agrees nicely with the results obtained during operation AM reactor of the First NPP

  20. Validation of MCNP NPP Activation Simulations for Decommissioning Studies by Analysis of NPP Neutron Activation Foil Measurement Campaigns

    Science.gov (United States)

    Volmert, Ben; Pantelias, Manuel; Mutnuru, R. K.; Neukaeter, Erwin; Bitterli, Beat

    2016-02-01

    In this paper, an overview of the Swiss Nuclear Power Plant (NPP) activation methodology is presented and the work towards its validation by in-situ NPP foil irradiation campaigns is outlined. Nuclear Research and consultancy Group (NRG) in The Netherlands has been given the task of performing the corresponding neutron metrology. For this purpose, small Aluminium boxes containing a set of circular-shaped neutron activation foils have been prepared. After being irradiated for one complete reactor cycle, the sets have been successfully retrieved, followed by gamma-spectrometric measurements of the individual foils at NRG. Along with the individual activities of the foils, the reaction rates and thermal, intermediate and fast neutron fluence rates at the foil locations have been determined. These determinations include appropriate corrections for gamma self-absorption and neutron self-shielding as well as corresponding measurement uncertainties. The comparison of the NPP Monte Carlo calculations with the results of the foil measurements is done by using an individual generic MCNP model functioning as an interface and allowing the simulation of individual foil activation by predetermined neutron spectra. To summarize, the comparison between calculation and measurement serve as a sound validation of the Swiss NPP activation methodology by demonstrating a satisfying agreement between measurement and calculation. Finally, the validation offers a chance for further improvements of the existing NPP models by ensuing calibration and/or modelling optimizations for key components and structures.

  1. Validation of MCNP NPP Activation Simulations for Decommissioning Studies by Analysis of NPP Neutron Activation Foil Measurement Campaigns

    Directory of Open Access Journals (Sweden)

    Volmert Ben

    2016-01-01

    Full Text Available In this paper, an overview of the Swiss Nuclear Power Plant (NPP activation methodology is presented and the work towards its validation by in-situ NPP foil irradiation campaigns is outlined. Nuclear Research and consultancy Group (NRG in The Netherlands has been given the task of performing the corresponding neutron metrology. For this purpose, small Aluminium boxes containing a set of circular-shaped neutron activation foils have been prepared. After being irradiated for one complete reactor cycle, the sets have been successfully retrieved, followed by gamma-spectrometric measurements of the individual foils at NRG. Along with the individual activities of the foils, the reaction rates and thermal, intermediate and fast neutron fluence rates at the foil locations have been determined. These determinations include appropriate corrections for gamma self-absorption and neutron self-shielding as well as corresponding measurement uncertainties. The comparison of the NPP Monte Carlo calculations with the results of the foil measurements is done by using an individual generic MCNP model functioning as an interface and allowing the simulation of individual foil activation by predetermined neutron spectra. To summarize, the comparison between calculation and measurement serve as a sound validation of the Swiss NPP activation methodology by demonstrating a satisfying agreement between measurement and calculation. Finally, the validation offers a chance for further improvements of the existing NPP models by ensuing calibration and/or modelling optimizations for key components and structures.

  2. Use of control room simulators for training of NPP personnel

    International Nuclear Information System (INIS)

    The objective of this report is to provide NPP managers, training center managers and personnel involved with control room simulator training with practical information they can use to improve the performance of their personnel. While the emphasis in this report is on simulator training of control room personnel using full scope simulators, information is also provided on how organizations have effectively used control room simulators for training of other NPP Personnel, Vienna (AT) including simulators other than full-scope simulators. The documents includes: the main body with current practices and recommendations; selected examples from countries; a CD ROM with all examples (different languages). The document will be available on the IAEA web site. The topics describes are: trends in simulators training; designing and developing training involving room simulators; implementation of simulator training; evaluating the effectiveness of simulator training; simulator instructor competence; application of different types of simulators in the training of NPP personnel (other than full scope simulators

  3. Comprehensive radiation survey and public health assessment in the vicinity of NPP

    Directory of Open Access Journals (Sweden)

    Samoilov A.S.

    2015-12-01

    health indicators of the public living around the NPP, general state of the adult and children public is healthy. There is no impact of the NPP on negative trends in some changing indicators of the adult and children public health.

  4. Evaluation of NPP-VIIRS Nighttime Light Data for Mapping Global Fossil Fuel Combustion CO2 Emissions: A Comparison with DMSP-OLS Nighttime Light Data.

    Directory of Open Access Journals (Sweden)

    Jinpei Ou

    Full Text Available Recently, the stable light products and radiance calibrated products from Defense Meteorological Satellite Program's (DMSP Operational Linescan System (OLS have been useful for mapping global fossil fuel carbon dioxide (CO2 emissions at fine spatial resolution. However, few studies on this subject were conducted with the new-generation nighttime light data from the Visible Infrared Imaging Radiometer Suite (VIIRS sensor on the Suomi National Polar-orbiting Partnership (NPP Satellite, which has a higher spatial resolution and a wider radiometric detection range than the traditional DMSP-OLS nighttime light data. Therefore, this study performed the first evaluation of the potential of NPP-VIIRS data in estimating the spatial distributions of global CO2 emissions (excluding power plant emissions. Through a disaggregating model, three global emission maps were then derived from population counts and three different types of nighttime lights data (NPP-VIIRS, the stable light data and radiance calibrated data of DMSP-OLS for a comparative analysis. The results compared with the reference data of land cover in Beijing, Shanghai and Guangzhou show that the emission areas of map from NPP-VIIRS data have higher spatial consistency of the artificial surfaces and exhibit a more reasonable distribution of CO2 emission than those of other two maps from DMSP-OLS data. Besides, in contrast to two maps from DMSP-OLS data, the emission map from NPP-VIIRS data is closer to the Vulcan inventory and exhibits a better agreement with the actual statistical data of CO2 emissions at the level of sub-administrative units of the United States. This study demonstrates that the NPP-VIIRS data can be a powerful tool for studying the spatial distributions of CO2 emissions, as well as the socioeconomic indicators at multiple scales.

  5. NPP capital equipment life control facilities and tools

    International Nuclear Information System (INIS)

    Algorithms and simulation package for calculation of eigen modes of coolant pressure oscillations in equipment of primary coolant circuit of WWER-1000 NPP, tuned-circuit Q-factor of an oscillating contour of the coolant, fluctuation frequencies pass band and attenuation factors of were developed. Calculation results for cases of presence and absence of gaseous state radiolysis products in the coolant were obtained. Results analysis makes it possible to disclose operating conditions which result in raised vibrations, and to develop control response in NPP industrial control system for their prevention

  6. Management of Damaged SNF Handling Operations At Paks NPP

    International Nuclear Information System (INIS)

    The issue of handling leaky fuel is one of the crucial issues of nuclear energy. It is directly connected with transportation of leaky spent nuclear fuel (SNF) that is mostly stored in the station's cooling pools. At present damaged spent nuclear fuel (SNF) of thirty VVER-440 spent fuel assemblies (SFA) is loaded into the ventilated canisters of types 28 and 29 and temporary stored in the cooling pool of Paks NPP. The report presents the milestones of preparation and safety justification of the technology for preparing canisters with damaged SNF of Paks NPP for transport to FSUE “PA “Mayak” (Russia) for reprocessing. (author)

  7. Experimental Studies for the VVER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213

    Directory of Open Access Journals (Sweden)

    Vladimir N. Blinkov

    2012-01-01

    Full Text Available In the frame of Tacis Project R2.01/99, which was running from 2003 to 2005, the bubble condenser system of Kola NPP (unit 3 was qualified at the integral test facility BC V-213. Three LB LOCA tests, two MSLB tests, and one SB LOCA test were performed. The appropriate test scenarios for BC V-213 test facility, modeling accidents in the Kola NPP unit 3, were determined with pretest calculations. Analysis of test results has shown that calculated initial conditions and test scenarios were properly reproduced in the tests. The detailed posttest analysis of the tests performed at BC V-213 test facility was aimed to validate the COCOSYS code for the calculation of thermohydraulic processes in the hermetic compartments and bubble condenser. After that the validated COCOSYS code was applied to NPP calculations for Kola NPP (unit 3. Results of Tacis R2.01/99 Project confirmed the bubble condenser functionality during large and small break LOCAs and MSLB accidents. Maximum loads were reached in the LB LOCA case. No condensation oscillations were observed.

  8. A study on the applicability for primary system decontamination through analysis on NPP decommission technology and international experience

    Energy Technology Data Exchange (ETDEWEB)

    Song, Jong Soon; Jung, Min Young; Lee, Sang Heon [Chosun University, Gwangju (Korea, Republic of)

    2016-03-15

    Decontamination is one of the most important technologies for the decommissioning of NPP. The purpose of decontamination is to reduce the Risk of exposure of the decommissioning workers, and to recycle parts of the plant components. Currently, there is a lack of data on the efficiency of the decontamination technologies for decommissioning. In most cases, the local radiation level can be lowered below a regulatory limitation by decontamination. Therefore, more efficient decontamination technology must be continuously developed. This work describes the practical experiences in the United States and the European countries for NPP decommissioning using these decontamination technologies. When the decommissioning of domestic nuclear power plant is planned and implemented, this work will be helpful as a reference of previous cases.

  9. Development of technical risk communication guideline in Nuclear Power Plant (NPP)

    International Nuclear Information System (INIS)

    The way Risk Communication in technological field like NPP should be outlined and executed according to basic principles has not been well described. Therefore a Technical Risk Communication (TRC) guideline was developed to provide directions about key issues of communication between the technical personnel and PSA experts. Applying TRC in NPP can have several benefits like enhancing safety culture in NPP. (author)

  10. Multi-scale evaluation of ISIMIP biome models against NDVI and MODIS NPP data

    Science.gov (United States)

    Rafique, Rashad; Zhao, Fang; Zeng, Ning; Asrar, Ghassem; Reyer, Christopher; Ostberg, Sebastian; Francois, Louis; Tian, Hanqin; Chnag, Jinfeng; Nishina, Kazuya

    2016-04-01

    The net primary productivity (NPP) is commonly used for understanding the dynamics of terrestrial ecosystems and their role in carbon cycle. The global NPP, highly variable over space and time, cannot be directly observed, therefore, satellite based observations of Normalized Difference Vegetation Index (NDVI) are used as a proxy to understand and monitor the NPP dynamics. In this study, we used a combination of most recent NDVI and modeled NPP data for the period 1982-2012, to study the role of terrestrial ecosystems in carbon cycle under the prevailing climate conditions. We found that in general there is good agreement between the spatial patterns and global seasonal cycles between observed NDVI and modeled NPP values. Simulated NPP values also generally agree with MODIS NPP spatially, and temporally, MODIS NPP falls within the model spread of NPP values. Despite of the general agreement in the trends of global total NDVI, MODIS NPP and modeled NPP, considerable spatial differences are found, and the ensemble mean of the models often agrees better with the spatial patterns of observed NDVI and MODIS NPP than individual models.

  11. Arrangement and statistics of storage containers of spent fuel for assemblies of the SFP of NPP-L V, Unit 1; Arreglo y estadistica de contenedores de almacenamiento de combustible gastado para los ensambles de la ACG de la Unidad 1 de la Central Nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Mijangos D, Z. E.; Vargas A, A. F.; Amador C, C., E-mail: zoedelfin@gmail.com [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Km 44.5 Carretera Cardel-Nautla, 91476 Laguna Verde, Alto Lucero, Veracruz (Mexico)

    2014-10-15

    This work presents the determination of assemblies of the spent fuel pool (SFP) of the nuclear power plant of Laguna Verde (NPP-L V) which are candidates to be assigned to storage containers of independent spent fuel, with the objective of liberating decay heat and to have more space in the SFP, for the store of retired assemblies of the reactors in future reloads of NPP-L V, besides that the removed assemblies of the SFP should be stored in specific containers to guarantee the physical safety of them, as well as the radiological protection to the population and the environment. The design of the containers considered in this work is to store a maximum of 69 assemblies; it has a thermal capacity of 26 kilowatts and allows storing assemblies with a minimum of 5 years of have been extracted of the reactor core. Is considered that in 2016 start the storage of the spent assemblies on the containers, the candidates assemblies to store cover from the first reload in 1991, until the assemblies deposited in the SFP in the 14 reload in 2010; therefore in 2016, such assemblies will have fulfilled with the criteria of 5 years of have been removed of the Reactor, also the 69 assemblies assigned to each container will have a resulting decay heat that does not exceed the thermal capacity of the container, but that in great percentage approximates to the same one, and this way to take full advantage of their storage capacity and thermal capacity for each container. This work also contains the arrangement to accommodate the assemblies in the containers; such arrangement is constituted by areas according to the decay heat of each assembly. (Author)

  12. Study of Degradation Processes in Dielectric Materials Used in Electronic Control Equipment Operated in ``Kozloduy'' NPP

    Science.gov (United States)

    Naydenov, Nayden; Popov, Angel

    2007-04-01

    The electronic equipment for control of different systems of Units 5 and 6 is studied for presence of degradation processes occurring in result of continuous usage in conditions of controlled radiation background in compliance with ``Kozloduy'' NPP safety codes. Systems, operated in a continuous mode in the course of about 10 years were chosen - separate units containing different dielectric materials (varnish coating, circuit board bases, cable insulations, electro protective elements, etc.) were extrapolated. Series of test samples were prepared which were connected with flat or coaxial condensers and their characteristic parameters were measured: tgδ, ɛ, low voltage conductivity and leak currents at voltages that exceed the working ones several times. When comparing the obtained data with the reference ones, a conclusion is made about the effectiveness of electric ageing during operation in the course of time.

  13. Selection of suitable sites for NPP in Slovenia (stage 3)

    International Nuclear Information System (INIS)

    Selection of suitable sites for nuclear power plants in Slovenia is considered. This includes the studies of available data on regional and local characteristics specified in general site suitability criteria for NPP. The most suitable selected sites will be included into land use urbanistic planning of Slovenia

  14. Software to Compare NPP HDF5 Data Files

    Science.gov (United States)

    Wiegand, Chiu P.; LeMoigne-Stewart, Jacqueline; Ruley, LaMont T.

    2013-01-01

    This software was developed for the NPOESS (National Polar-orbiting Operational Environmental Satellite System) Preparatory Project (NPP) Science Data Segment. The purpose of this software is to compare HDF5 (Hierarchical Data Format) files specific to NPP and report whether the HDF5 files are identical. If the HDF5 files are different, users have the option of printing out the list of differences in the HDF5 data files. The user provides paths to two directories containing a list of HDF5 files to compare. The tool would select matching HDF5 file names from the two directories and run the comparison on each file. The user can also select from three levels of detail. Level 0 is the basic level, which simply states whether the files match or not. Level 1 is the intermediate level, which lists the differences between the files. Level 2 lists all the details regarding the comparison, such as which objects were compared, and how and where they are different. The HDF5 tool is written specifically for the NPP project. As such, it ignores certain attributes (such as creation_date, creation_ time, etc.) in the HDF5 files. This is because even though two HDF5 files could represent exactly the same granule, if they are created at different times, the creation date and time would be different. This tool is smart enough to ignore differences that are not relevant to NPP users.

  15. NPP safety and personnel training. XII International conference. Abstracts

    International Nuclear Information System (INIS)

    The 12th International conference NPP Safety and Personnel Training took place in Obninsk, October 4-7, 2011. The issues of nuclear technologies safety are considered.The problems of life-cycle management of nuclear facilities are discussed. The criteria of assessment of physical protection systems of nuclear facilities are presented

  16. NPP Krsko core calculations to improve operational safety

    International Nuclear Information System (INIS)

    Calculation tools and methodology used to perform independent calculations of cumulative influence of different changes related to fuel and core operation of NPP Krsko were described. Some examples of steady state and transient results are used to illustrate potential improvements to understanding and reviewing plant safety. (author)

  17. Improvement of organization and payment on NPP construction

    International Nuclear Information System (INIS)

    Effect of introducing advanced methods and organization forms of work on increase of labour productivity during the NPP construction is shown. Role of progressive forms of payment for work in reducing terms and improving the quality of works performed is examined

  18. Reactor Dosimetry Aspects of the Service Life Extension of the Hungarian Paks NPP

    Science.gov (United States)

    Zsolnay, Eva M.; Czifrus, Szabolcs; Fehér, Sándor; Hordósy, Gábor; Keresztúri, András; Kresz, Norbert; Oszvald, Ferenc

    2016-02-01

    The service life of the Hungarian Paks Nuclear Power Plant (NPP) will be extended from the originally planned 30 years to 50 years. To improve the reliability of the results obtained in frame of the old reactor pressure vessel (RPV) surveillance programme, new methods have been developed, and based on them, the old exposition data have been re-evaluated for all the four reactor units. At the same time, a new RPV surveillance programme has been developed and introduced, and long term irradiations have been performed to determine the radiation damage of the surveillance specimens due to the high fast neutron exposition. Neutron transport calculations have been performed with a validated neutron transport code system to determine the fast neutron exposition of the RPVs during the extended service life. The cavity dosimetry is in the introductory phase. This paper presents the new developments in the field of the RPV surveillance dosimetry and summarises the results obtained. According to the results the service life of the NPP can safely be extended for the planned 50 years.

  19. Reactor Dosimetry Aspects of the Service Life Extension of the Hungarian Paks NPP

    Directory of Open Access Journals (Sweden)

    Zsolnay Eva M.

    2016-01-01

    Full Text Available The service life of the Hungarian Paks Nuclear Power Plant (NPP will be extended from the originally planned 30 years to 50 years. To improve the reliability of the results obtained in frame of the old reactor pressure vessel (RPV surveillance programme, new methods have been developed, and based on them, the old exposition data have been re-evaluated for all the four reactor units. At the same time, a new RPV surveillance programme has been developed and introduced, and long term irradiations have been performed to determine the radiation damage of the surveillance specimens due to the high fast neutron exposition. Neutron transport calculations have been performed with a validated neutron transport code system to determine the fast neutron exposition of the RPVs during the extended service life. The cavity dosimetry is in the introductory phase. This paper presents the new developments in the field of the RPV surveillance dosimetry and summarises the results obtained. According to the results the service life of the NPP can safely be extended for the planned 50 years.

  20. A Radiological Survey Approach to Use Prior to Decommissioning: Results from a Technology Scanning and Assessment Project Focused on the Chernobyl NPP

    International Nuclear Information System (INIS)

    The primary objectives of this project are to learn how to plan and execute the Technology Scanning and Assessment (TSA) approach by conducting a project and to be able to provide the approach as a capability to the Chernobyl Nuclear Power Plant (ChNPP) and potentially elsewhere. A secondary objective is to learn specifics about decommissioning and in particular about radiological surveying to be performed prior to decommissioning to help ChNPP decision makers. TSA is a multi-faceted capability that monitors and analyzes scientific, technical, regulatory, and business factors and trends for decision makers and company leaders. It is a management tool where information is systematically gathered, analyzed, and used in business planning and decision making. It helps managers by organizing the flow of critical information and provides managers with information they can act upon. The focus of this TSA project is on radiological surveying with the target being ChNPP's Unit 1. This reactor was stopped on November 30, 1996. At this time, Ukraine failed to have a regulatory basis to provide guidelines for nuclear site decommissioning. This situation has not changed as of today. A number of documents have been prepared to become a basis for a combined study of the ChNPP Unit 1 from the engineering and radiological perspectives. The results of such a study are expected to be used when a detailed decommissioning plan is created

  1. A Radiological Survey Approach to Use Prior to Decommissioning: Results from a Technology Scanning and Assessment Project Focused on the Chornobyl NPP

    Energy Technology Data Exchange (ETDEWEB)

    Milchikov, A.; Hund, G.; Davidko, M.

    1999-10-20

    The primary objectives of this project are to learn how to plan and execute the Technology Scanning and Assessment (TSA) approach by conducting a project and to be able to provide the approach as a capability to the Chernobyl Nuclear Power Plant (ChNPP) and potentially elsewhere. A secondary objective is to learn specifics about decommissioning and in particular about radiological surveying to be performed prior to decommissioning to help ChNPP decision makers. TSA is a multi-faceted capability that monitors and analyzes scientific, technical, regulatory, and business factors and trends for decision makers and company leaders. It is a management tool where information is systematically gathered, analyzed, and used in business planning and decision making. It helps managers by organizing the flow of critical information and provides managers with information they can act upon. The focus of this TSA project is on radiological surveying with the target being ChNPP's Unit 1. This reactor was stopped on November 30, 1996. At this time, Ukraine failed to have a regulatory basis to provide guidelines for nuclear site decommissioning. This situation has not changed as of today. A number of documents have been prepared to become a basis for a combined study of the ChNPP Unit 1 from the engineering and radiological perspectives. The results of such a study are expected to be used when a detailed decommissioning plan is created.

  2. 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)

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

    International Nuclear Information System (INIS)

    In August 1991, following the SMiRT-11 Conference in Tokyo, a Technical Committee Meeting was held on the 'Seismic safety issues relating to existing NPPs'. The Proceedings of this TCM was subsequently compiled in an IAEA Working Material. One of the main recommendations of this TCM, called for the harmonization of criteria and methods used in Member States in seismic reassessment and upgrading of existing NPPs. Twenty four institutions from thirteen countries participated in the CRP named 'Benchmark study for the seismic analysis and testing of WWER type NPPs'. Two types of WWER reactors (WWER-1000 and WWER-440/213) selected for benchmarking. Kozloduy NPP Units 5/6 and Paks NPP represented these respectively as prototypes. Consistent with the recommendations of the TCM and the working paper prepared by the subsequent Consultants' Meeting, the focal activity of the CRP was the benchmarking exercises. A similar methodology was followed both for Paks NPP and Kozloduy NPP Unit 5. Firstly, the NPP (mainly the reactor building) was tested using a blast loading generated by a series of explosions from buried TNT charges. Records from this test were obtained at several free field locations (both downhole and surface), foundation mat, various elevations of structures as well as some tanks and the stack. Then the benchmark participants were provided with structural drawings, soil data and the free field record of the blast experiment. Their task was to make a blind prediction of the response at preselected locations. The analytical results from these participants were then compared with the results from the test. Although the benchmarking exercises constituted the focus of the CRP, there were many other interesting problems related to the seismic safety of WWER type NPPs which were addressed by the participants. These involved generic studies, i.e. codes and standards used in original WWER designs and their comparison with current international practice; seismic analysis

  4. Observation and modeling of NPP for Pinus elliottii plantation in subtropical China

    Institute of Scientific and Technical Information of China (English)

    MA ZeQing; LIU QiJing; WANG HuiMin; LI XuanRan; ZENG HuiQing; XU WenJia

    2008-01-01

    Based on the stem analysis of 59 individuals of Pinus elliottii in combination with tree biomass models,we calculated annual biomass increment of forest plots at Qianyanzhou Ecological Station,Chinese Academy of Sciences in subtropical China. In addition,canopy layer and community NPP were calculated based on 12 years' litter fall data. NPP of the 21-year-old forest was estimated by using the BIOME BGC model; and both measured NPP and estimated NPP were compared with flux data. Community lation between annual litter fall and annual biomass increment; and the litter fall was 1.19 times the biomass increment of living trees. From 1985 to 2005,average NPP and GPP values based on BGC simulated tree layer NPP values. NPP accounted for 30.2% (25.6%-32.9%) of GPP,while NEP accounted for 57.5% (48.1%-66.5%) of tree-layer NPP and 41.74% (37%-52%) of stand NPP. Soil respiration accounted for 77.0% of measured tree NPP and 55.9% of the measured stand NPP. NEE based on eddy covariance method was 12.97% higher than the observed NEP.

  5. Trillo NPP full scope replica simulator project: The last great NPP simulation challenge in Spain

    International Nuclear Information System (INIS)

    In the year 2000, Trillo NPP (Spanish PWR-KWU design nuclear power plant) and Tecnatom came to the agreement of developing a Trillo plant specific simulator, having as scope all the plant systems operated either from the main control room or from the emergency panels. The simulator operation should be carried out both through a control room replica and graphical user interface, this latter based on plant schematics and softpanels concept. Trillo simulator is to be primarily utilized as a pedagogical tool for the Trillo operational staff training. Because the engineering grade of the mathematical models, it will also have additional uses, such as: - Operation engineering (POE's validation, New Computerized Operator Support Systems Validation, etc).; - Emergency drills; -Plant design modifications assessment. This project has become the largest simulation task Tecnatom has ever undertaken, being structured in three different subprojects, namely: - Simulator manufacture, Simulator acceptance and Training material production. Most relevant technological innovations the project brings are: Highest accuracy in the Nuclear Island models, Advanced Configuration Management System, Open Software architecture, Human machine interface new design, Latest design I/O system and an Instructor Station with extended functionality. The Trillo simulator 'Ready for Training' event is due on September 2003, having started the Factory Acceptance Tests in Autumn 2002. (author)

  6. Utilization of other quality assurance standards than CSA CAN3.Z299/NRAC AQ-04 for the procurement of CANDU NPP items and services

    International Nuclear Information System (INIS)

    The Romanian prescription which establishes the specific Quality Assurance requirements for items and services for nuclear facilities and installations is NRAC AQ-04/1983. This prescription is equivalent to the CSA CAN3.Z299 series of standards. The most important problem in procurement activities for Cernavoda Unit 1 and 2 is at present the large utilization of other manufacturing Quality Program Standards (especially the ISO 9000 standards) by the potential suppliers of items. The design were procurement documents may call up CSA CAN3.Z299/NRAC AQ-04 standards, but the supplier has established a program to an other standard. For such cases, it is necessary to know how to obtain an equivalence. The paper suggests the methods for obtaining this equivalence of the CSA CAN3.Z299/NRAC AQ-04 standards to the other widely-used international standards in the Procurement Quality Assurance field. It defines the supplementary requirements that must be imposed in conjunction with the international standards to achieve equivalence CSA CAN3.Z299/NRAC AQ-04 standards

  7. Ageing management of french NPP civil work structures

    Directory of Open Access Journals (Sweden)

    Dauffer D.

    2011-04-01

    Full Text Available This paper presents EDF practice about concrete structure ageing management, from the mechanisms analysis to the formal procedure which allows the French company to increase 900 MWe NPP lifetime until 40 years; it will also introduce its action plan for 60 years lifetime extension. This practice is based on a methodology which identifies every ageing mechanism; both plants feedback and state of the art are screened and conclusions are drawn up into an “ageing analysis data sheet”. That leads at first to a collection of 57 data sheets which give the mechanism identification, the components that are concerned and an analysis grid which is designed to assess the safety risk. This analysis screens the reference documents describing the mechanism, the design lifetime hypotheses, the associated regulation or codification, the feedback experiences, the accessibility, the maintenance actions, the repair possibility and so one. This analysis has to lead to a conclusion about the risk taking into account monitoring and maintenance. If the data sheet conclusion is not clear enough, then a more detailed report is launched. The technical document which is needed, is a formal detailed report which summarizes every theoretical knowledge and monitoring data: its objective is to propose a solution for ageing management: this solution can include more inspections or specific research development, or additional maintenance. After a first stage on the 900 MWe units, only two generic ageing management detailed reports have been needed for the civil engineering part: one about reactor building containment, and one about other structures which focuses on concrete inflating reactions. The second stage consists on deriving this generic analysis (ageing mechanism and detailed reports to every plant where a complete ageing report is required (one report for all equipments and structures of the plant, but specific for each reactor. This ageing management is a

  8. Operational diagnostics of thermal state and efficiency of steam turbines of TPP and NPP

    Science.gov (United States)

    Bozhko, V. V.; Kovalenko, A. N.; Lyapunov, V. M.; Khomenok, L. A.

    2016-05-01

    Various ways for solving complex problems of the strength and operating life of steam turbines of TPP and NPP are studied. Diagnostic characters and technical possibilities for their control during the steam turbine operation are determined. It is shown that the effect of various factors on the reliability, maneuverability, and service life of power installations of TPP and NPP is generally determined by the thermal state of steam-electric generating sets. Leading foreign and domestic manufacturers give major attention to the organization of the control of the thermal state of facilities and the development of systems for accounting ("counter") the service life depletion. Zones of high-temperature sites of shafts and disks with maximum parameters of operating environment are determined. A model for on-line computation of thermal stresses with the diagnostic evaluation of the service life depletion (fatigue accumulation) and forecasting of optimum heating conditions for thermostressed turbine units is briefly stated. An example of a program for diagnostics of the quality of the facility operation is given. The program provides the operative control of thermal stresses and the service life depletion in main units of the turbine under various operation conditions, operates in the real-time mode, calculates and represents currents values of thermal stresses in turbine units, and forms and transmits into the industrial control signals on the occurrence of restrictions with respect to thermal stresses and prohibition of an increase or decrease in the vapor temperature and the load in the case of approaching pressures to maximum permissible ones. In the case of stationary operation conditions, the program computed the current efficiency in high (HPC) and mean (MPC) pressure cylinders.

  9. NPP Krsko Lifetime Extension - Business Impact for Hrvatska Elektroprivreda

    International Nuclear Information System (INIS)

    This paper deals with the analysis of possible business impacts for HEP in the case of NPP Krsko life extension. Due to numerous reasons nuclear power plant life extension of ten to twenty years is a common procedure abroad. Having this practise in mind as well as other circumstances in Croatian and Slovenian electric power system, the extension of NPP Krsko lifetime is considered to be a possible scenario. Foreseeable impacts of this decision are evaluated primarily with consideration of its effect on HEPs projected cash flows, though other aspects will be addressed as well. Preserving a well maintained production facility with an extraordinary operational record and stable, or possibly falling overall production costs seems as a very rational choice. This is particularly true having in mind expected rise of electricity demand and energy prices in the region. Having NPP Krsko in operation beyond 2023 implies that no replacement source for NPP Krsko capacity needs to be built. This means avoiding all costs connected with the construction and operation of the replacement plant, assuming it will be fossil fuelled. Due to the high uncertainty of the future fossil fuel prices, the avoidance of replacement plant operational cost is likely to prove as highly rewarding. It should be kept in mind that avoided costs also include the replacement plant greenhouse gases emission costs, thus further enlarging the list of value adding impacts. The latter is valid anticipating the ratification of the Kyoto protocol and joining the European emission trading scheme. In addition to that, the extension of NPP Krsko lifetime would mean that the majority of costs connected with the decommissioning and final waste disposal can be postponed further down the time line. This will have very positive financial and possibly technological impact. Other value creating effects for HEP that are foreseeable as a consequence of the plant lifetime extension include: maintaining the knowledge of

  10. Mapping and analysing cropland use intensity from a NPP perspective

    Science.gov (United States)

    Niedertscheider, Maria; Kastner, Thomas; Fetzel, Tamara; Haberl, Helmut; Kroisleitner, Christine; Plutzar, Christoph; Erb, Karl-Heinz

    2016-01-01

    Meeting expected surges in global biomass demand while protecting pristine ecosystems likely requires intensification of current croplands. Yet many uncertainties relate to the potentials for cropland intensification, mainly because conceptualizing and measuring land use intensity is intricate, particularly at the global scale. We present a spatially explicit analysis of global cropland use intensity, following an ecological energy flow perspective. We analyze (a) changes of net primary production (NPP) from the potential system (i.e. assuming undisturbed vegetation) to croplands around 2000 and relate these changes to (b) inputs of (N) fertilizer and irrigation and (c) to biomass outputs, allowing for a three dimensional focus on intensification. Globally the actual NPP of croplands, expressed as per cent of their potential NPP (NPPact%), amounts to 77%. A mix of socio-economic and natural factors explains the high spatial variation which ranges from 22.6% to 416.0% within the inner 95 percentiles. NPPact% is well below NPPpot in many developing, (Sub-) Tropical regions, while it massively surpasses NPPpot on irrigated drylands and in many industrialized temperate regions. The interrelations of NPP losses (i.e. the difference between NPPact and NPPpot), agricultural inputs and biomass harvest differ substantially between biogeographical regions. Maintaining NPPpot was particularly N-intensive in forest biomes, as compared to cropland in natural grassland biomes. However, much higher levels of biomass harvest occur in forest biomes. We show that fertilization loads correlate with NPPact% linearly, but the relation gets increasingly blurred beyond a level of 125 kgN ha-1. Thus, large potentials exist to improve N-efficiency at the global scale, as only 10% of global croplands are above this level. Reallocating surplus N could substantially reduce NPP losses by up to 80% below current levels and at the same time increase biomass harvest by almost 30%. However, we

  11. Investigation of primary to secondary leakage at low power during 'Hydro-test' for VVER440/V230 at Kozloduy NPP

    Energy Technology Data Exchange (ETDEWEB)

    Groudev, P., E-mail: pavlinpg@inrne.bas.bg [Institute for Nuclear Research and Nuclear Energy, Tzarigradsko Shaussee 72, Sofia 1784 (Bulgaria); Stefanova, A., E-mail: antoanet@inrne.bas.bg [Institute for Nuclear Research and Nuclear Energy, Tzarigradsko Shaussee 72, Sofia 1784 (Bulgaria); Manolov, M., E-mail: m_manolov@npp.bg [Kozloduy NPP Plc, Kozloduy 3320 (Bulgaria)

    2011-02-15

    This paper presents the thermal-hydraulic investigation 'Primary to secondary leakage at low power' for analytical validation of Symptom Based Emergency Operating Procedures (SBEOPs) at low power for VVER440/V230 units 3 and 4 at Kozloduy NPP. The main purpose of this analysis is to provide the response of monitored plant parameters to identify symptoms available to the operators and define timing for reaching the following stages during the development of processes in the reactor system, after primary to secondary leakage: {center_dot}Reaching the saturated temperature at the outlet of the assembly. {center_dot}Beginning of reactor core uncovery. {center_dot}Define the time for reaching maximum level in the damaged SG. {center_dot}Termination of natural circulation after decreasing of water level in reactor vessel below the hot nozzles. {center_dot}Defining the time for opening SVs of damaged SG. {center_dot}Define the CSF status and the time of loss of Critical Safety Functions. The thermal-hydraulic analysis for analytical validation of Symptom Based Emergency Operating Procedures (SBEOPs) at low power of reactor for VVER440/V230 units 3 and 4 at Kozloduy NPP is performed with RELAP5/MOD3.2 computer code. The RELAP5/MOD3.2 model of Kozloduy NPP VVER-1000 for investigation of operational occurrences, abnormal events, and design basis scenarios have been developed and validated in the Institute for Nuclear Research and Nuclear Energy - Bulgarian Academy of Sciences (INRNE-BAS) Sofia, and Kozloduy NPP. The model provides a significant analytical capability for the specialists working in the field of NPP safety.

  12. Incorporation of the new safety technology in NPP design

    International Nuclear Information System (INIS)

    A permanent target of nuclear energy development is to optimize the quality of the NPP and the performance of the nuclear energy generation, but at the same time a remarkable effort was devoted to protect the public and the environment by means of the improvement of Nuclear safety principles. The incorporation of new technologies, safety criteria and Norms, analysis methods and concepts to enhance the design's safety of NPP as a result in some cases, of the interaction between operation and design work is a complex task in the case of NPPs in operation or under construction while the elaboration of advanced reactor concepts allows the simultaneous introduction of new safety features and modern technology. The purpose of this work is to summarize the Argentine experience in the field of nuclear safety improvement in our NPPs in operation/construction and in the new advanced reactor design. (author)

  13. The intelligent system for accident identification in NPP

    International Nuclear Information System (INIS)

    Accidental situations in NPP are of greet concern for operators, the facility, regulatory bodies and the environment. This work proposes a design of intelligent system aimed to assist the operator in the process of decision making when initiator events with higher relative contribution to the reactor core damage occur. The intelligent System uses the results of the pre operational Probabilistic Safety Assessment and the Thermal hydraulic Safety Analyses of the NPP Juragua as source for building its knowledge base. The nucleus of the system is presented as a design of an intelligent hybrid system from the combination of the artificial intelligence techniques: fussy logic and artificial neural networks. The system works with variables from the process of the firsts circuit, second circuit and the containment and it is presented as a model for the integration of safety analyses in the process of decision making by the operator when tackling with accidental situations

  14. Social problems and territorial experiences from closing down Tihange NPP

    International Nuclear Information System (INIS)

    The town of Huy, better known by the name of the NPP Tihange, which is the nearby village, accounts to 50,000 inhabitants including the surrounding region. An Advisory Committee at a community level was set up concerned with the emergency services and the NPP related problems. One of the outstanding problems is the planned interim storage for radioactive waste. The unsolved question of long term storage in Belgium resulted in the fact that general situation is not promising for launching the debate on the future of nuclear energy. The mission of the delegation from Huy visited Tokaimura with the aim to measure the scale of real responsibilities and the concern against nuclear power that the accident created in the population

  15. Appendix XXI: Workforce planning applications at the Paks NPP Ltd

    International Nuclear Information System (INIS)

    Paks Nuclear Power Plant Ltd., Hungary,is a state owned Public Stakeholders' Corporation with one nuclear site with four reactors in operation. The process describes the long term workforce planning policy at the Paks NPP Ltd. The objective of the human resource policy at the Paks NPP Ltd. is to make available personnel in optimal quantity, either employed or contracted, that are properly selected, trained and equipped with all knowledge, skills and attitudes required for the long term safe, competitive and reliable operation of the plant. Accordingly the primary goal achievable by the plant is job positions (requiring managerial, professional or special expertise) be filled in by staff members performing at the highest possible level of professionalism and the most efficient manner

  16. Geological-Hydrological Site Evaluation for NPP Planning

    Energy Technology Data Exchange (ETDEWEB)

    Faust, Brigitte; Mini, Paolo [Nordostsschweizerische Kraftwerke AG NOK, Parkstrasse 23, 5401 Baden (Switzerland)

    2008-07-01

    NOK is investigating the potential replacement of the current NPP in Beznau. In order to meet the requirements with respect to a general licence application, geological, seismological, and geotechnical engineering, but also hydrological boundary conditions have been defined. These conditions define the nature of necessary investigations to obtain the geological, seismic, geotechnical and hydrological data themselves forming the basis to determine the site suitability. Viability has to be provided that a NPP can be built and operated at the proposed site without compromising public health, safety and environment. The collected data are also the basis for the design of all safety relevant structures, systems, and components. For example, the latter have to withstand the effects of natural phenomena such as earthquakes and human induced impact such as airplane crash without loosing their capability to perform the assigned safety functions. (authors)

  17. Equipment performance monitoring in NPP Krsko (Summarized system health report)

    International Nuclear Information System (INIS)

    Management common goal is safe, reliable, effective, acceptable to public and conservative/cautious operation of NPP Krsko. A set of programs, including Corrective Action Program, Performance Indicators, Operating Experience, Self Assessment and System Health Report, is developed to assist NPP Krsko management in fulfilling those goals. System Health Report is a tool that management can use to quickly assess how selected systems are performing, to determine where additional management attention is required and to determine if appropriate corrective actions have been established. Summarized System Health Report is developed for management's quick overview of systems status, important system malfunctions and problems as well as major changes from previous assessment period. Summarized Report contains nine sections: status difference including brief explanation, selected performance indicators, new equipment problems, functional failures, important problem analyses, action plan for systems with Potential Danger (RED) status, maintenance rule status overview and systems availability (planned and unplanned).(author)

  18. Exposure management in emergency preparedness and planning at Mochovce NPP

    International Nuclear Information System (INIS)

    The legal requirements on emergency preparedness come from Acts of Slovak republic as the Act on State Safety Supervision of Nuclear Facilities, The Act on Civil Protection of population and the Act on Protection of Public Health. The operating organization, regulatory bodies and public authorities shall cooperate to prepare emergency plans according to these Acts in which the contents and conditions of the emergency planning are specified, exercises and reviews are demanded. On-site emergency plan with Emergency Plan Implementing procedures are the basic documents for emergency planning on NPP Management of response to emergency including exposure management shall be handled by Emergency Response Organization. There are the centers at which management is present during the emergency at NPP Mochovce: - Main Control Room; - Emergency Control Room; -Emergency Control Center; - Operational Support Center; - Technical Support Center; - Information Center; - Off-site Assessment Centre. NPP Mochovce owns facilities and equipment for the permanent environment monitoring at site and within the 20 km emergency planning zones. The major tasks of the Emergency Response Organization, which are carried out in compliance with defined procedures after an extraordinary event, are as follows: - assessment of extraordinary events; - warning and notification of the plant personal and population in the surroundings; - analysis and evaluation of on-site radiation situation; - exposure management; - taking measures for protection of the workforce (turn-back dose); - coordination of the activities of monitoring teams in environment; - coordination of the rescue teams (turn-back dose); - recommendations for public protection; - implementation of activities to remove the extraordinary event and to return to a safe state. Events are ranked in the Emergency Plan in compliance with their radiological consequences as follows: - 1. Degree - 'the alert state'; - 2.Degree; - 'On-site Emergency

  19. Application of reliability centered maintenance to Embalse NPP

    International Nuclear Information System (INIS)

    One of the most recent applications of Probabilistic Safety Analysis to Embalse NPP is the Safety Oriented Maintenance Program developed through the Reliability Centered Maintenance (RCM) methodology. Such an application was carried out by a cooperated effort between the staff of nuclear safety department of NPP and experts from Instituto Superior de Tecnologias y Ciencias Aplicadas of Cuba. So far 6 technological systems have been analyzed with important results regarding the optimization of preventive and predictive maintenance program of those systems. Any tasks of RCM were automated via MOSEG code. The results of this study were focused on the elaboration and modification of the Preventive Program, prioritization of stocks, reorientation of predictive techniques and modification in the time parameters of maintenance. (author)

  20. Seismic qualification tests of fans of the NPP of Laguna Verde U-1 and U-2; Pruebas de calificacion sismica de ventiladores de la Central Laguna Verde U1 and U2

    Energy Technology Data Exchange (ETDEWEB)

    Jarvio C, G.; Garcia H, E. E.; Arguelles F, R.; Vela H, A. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Naranjo U, J. L., E-mail: gilberto.jarvio@inin.gob.mx [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km 7.5, Dos Bocas, Veracruz (Mexico)

    2013-10-15

    This work presents the results of the seismic qualification tests applied to the fans that will be installed in the control panels of the three divisions of the diesel generators of the nuclear power plant (NPP) of Laguna Verde, Unit-1 and Unit-2. This seismic qualification process of the fans was carried out using two specimens that were tested in the seismic table (vibrating) of the Engineering Institute of Universidad Nacional Autonoma de Mexico (UNAM), in accordance with the requirements of the standard IEEE 344-1975, to satisfy the established requirements of seismic qualification in the technical specifications and normative documents required by the nuclear standards, in order to demonstrate its application in the diesel generators Divisions I, II and III of the NPP. The seismic qualification tests were developed on specimens that were retired of the NPP of Laguna Verde recently with a service life of 7.75 years. (Author)

  1. Advanced simulation strategies of dynamic regimes in nuclear plants in order to increase the nuclear safety

    International Nuclear Information System (INIS)

    Since the design period of Cernavoda NPP, Unit 2, performing thermal hydraulic analysis for nuclear power plants of Romania has become a priority for Romanian research and design institutes. As a result a number of 26 thermal-hydraulic analyses was achieved to support systems responsible for nuclear safety. This constituted a first step in investigating the complex field of thermo-hydraulic analysis. In this paper I will briefly present some of the results obtained and the proposed changes to Unit 2 at Cernavoda NPP in effecting the following analyses. The paper will present also some conclusions from the analysis on several systems from the secondary circuit, namely Feedwater System, Main Steam System and Main Condensate System. In these analyses we have been studied all the operating modes given by the system design manuals. The paper is limited to analysis of regimes involving changes in safety philosophy of the plant or plant operating procedures. By making these thermo-hydraulic analyses for Cernavoda NPP it was proven the Romanian design capability of making complete and consistent safety analyses for nuclear power plants as a first step towards independence from foreign support in implementing all necessary thermal-hydraulic analyses for future units that will be designed and made in Romania. (author)

  2. Surface Passivation Studies on n+pp+ Bifacial Solar Cell

    OpenAIRE

    Suhaila Sepeai; M. Y. Sulaiman; Kamaruzzaman Sopian; Saleem H. Zaidi

    2012-01-01

    Bifacial solar cell is a specially designed solar cell for the production of electricity from both sides of the solar cell. It is an active field of research to make photovoltaics (PV) more competitive by increasing its efficiency and lowering its costs. We developed an n+pp+ structure for the bifacial solar cell. The fabrication used phosphorus-oxy-trichloride (POCl3) diffusion to form the emitter and Al diffusion using conventional screen printing to produce the back surface field (BSF). Th...

  3. Corrosion deposits removal from Kozloduy NPP VVER-440 steam generator tubing by chemical cleaning

    International Nuclear Information System (INIS)

    A strict control of primary and secondary circuits metal equipment corrosion of VVER-440 Kozloduy NPP units has been performed for the whole period of operation. This is carried out following a specific program including visual inspection and chemical analysis of equipment corrosion deposits. During their migration, the corrosion products deposit on the metal surface in the so-called standstill zones. One of these is the steam generator. The process results in: deterioration of thermal exchange; deterioration of corrosion conditions under deposits corrosion, pitting corrosion, etc. Using quantity deposits data and deposits chemical consistence, chemical cleaning of steam generator surfaces is performed. Decision for such chemical treatment of secondary circuit equipment is taken when the amount of deposits on the steam generator tubing is greater than 150 g/m2. This limit is based on operational experience and manufacturer requirements. (R.P.)

  4. Integrated tool for NPP lifetime management in Spain

    Energy Technology Data Exchange (ETDEWEB)

    Francia, L. [UNESA, Madrid (Spain); Lopez de Santa Maria, J. [ASCO-Vandellos 2 NPPs l' Hospitalet de l' Infant, Tarragona (Spain); Cardoso, A. [Tecnatom SA, Madrid (Spain)

    2001-07-01

    The project for the Integrated Nuclear Power Plant Lifetime Management System SIGEVI (Sistema Integrado de GEstion de VIda de Centrales Nucleares) was initiated in April 1998 and finalized in December 2000, the main objective of the project being to develop a computer application facilitating the assessment of the condition and lifetime of nuclear power plant components. This constituted the second phase of a further-reaching project on NPP Lifetime Management. During the first phase of this project, carried out between 1992 and 1995, the methodology and strategy for the lifetime management of the Spanish NPP's were developed. Among others, degradation phenomena were assessed and the most adequate methods for their monitoring were defined. The SIGEVI Project has been performed under the management of UNESA (Spanish Electricity Association) and with the collaboration of different engineering firms and research institutes (Tecnatom, Empresarios Agrupados, Ufisa, Initec and IIT), with Vandellos II as the pilot plant. The rest of the Spanish NPP's have also actively participated through the Project Steering Committee. The following sections describe the scope, the structure and the main functionalities of the system SIGEVI. (authors)

  5. NPP Temelin safety analysis reports and PSA status

    International Nuclear Information System (INIS)

    To enhance the safety level of Temelin NPP, recommendations of the international reviews were implemented into the design as well as into organization of the plant construction and preparation for operation. The safety assessment of these design changes has been integrated and reflected in the Safety Analysis Reports, which follow the internationally accepted guidelines. All safety analyses within Safety Analysis Reports were repeated carefully considering technical improvements and replacements to complement preliminary safety documentation. These analyses were performed by advanced western computer codes to the depth and in the structure required by western standards. The Temelin NPP followed a systematic approach in the functional design of the Reactor Protection System and related safety analyses. Modifications of reactor protection system increase defense in depth and facilitate demonstrating that LOCA and radiological limits are met for non-LOCA events. The rigorous safety analysis methodology provides assurance that LOCA and radiological limits are met. Established and accepted safety analysis methodology and accepted criteria were applied to Temelin NPP meeting US NRC and Czech Republic requirements. IAEA guidelines and recommendations

  6. Robot dispatching Scenario for Accident Condition Monitoring of NPP

    International Nuclear Information System (INIS)

    In March of 2011, unanticipated big size of tsunami attacks Fukushima NPP, this accident results in explosion of containment building. Tokyo electric power of Japan couldn't dispatch a robot for monitoring of containment inside. USA Packbot robot used for desert war in Iraq was supplied to Fukushima NPP for monitoring of high radiation area. Packbot also couldn't reach deep inside of Fukushima NPP due to short length of power cable. Japanese robot 'Queens' also failed to complete a mission due to communication problem between robot and operator. I think major reason of these robot failures is absence of robot dispatching scenario. If there was a scenario and a rehearsal for monitoring during or after accident, these unanticipated obstacles could be overcome. Robot dispatching scenario studied for accident of nuclear power plant was described herein. Study on scenario of robot dispatching is performed. Flying robot is regarded as good choice for accident monitoring. Walking robot with arm equipped is good for emergency valve close. Short time work and shift work by several robots can be a solution for high radiation area. Thin and soft cable with rolling reel can be a good solution for long time work and good communication

  7. Technical and economical problems of decommissioning nuclear power plants (NPP) in Russia

    International Nuclear Information System (INIS)

    The introduction per new century has brought to atomic Engineering many new problems. One of them, which has got a serious urgency, we now shall consider. It is a problem of decommissioning NPP in Russia. By 2014 all maintained nowadays NPP in Russian Federation will develop the regular service life. And all of them on idea should be removed from operation. But, as we understand, in today's difficult economic conditions, to it NPP the procedure of prolongation of service life will be applied, and where it is impossible by virtue of the various reasons, the procedure of translation NPP in nuclear - safe condition and in a mode of a long storage under supervision, before acceptance of the decision about a method and way of financing of a decommissioning will be applied. Possible the following variants will be: use platforms of the old NPP for construction new NPP, or using as burial place NPP. The variant of a decommissioning up to a condition 'green grass' is represented unprofitable because of its dearness. The similar decommissioning was carried out in Japan. Was removed from operation research reactor of a type WWR. The expenses for this method of a decommissioning considerably surpass expenses for a method of a burial place NPP basically because of high cost of dismantle and transportation in long-term storehouses of the 1 contour equipment. The most urgent problem of decommissioning NPP, which developed their regular service life - is financing this final stage of a exploitation cycle of the block. I shall remind, that the financing is carried out from uniform fund of decommissioning. The formation of this fund occurs by deduction 1.3 % of cost of the put electric power to the consumers by all maintained NPP of Russia. The expenditure of this fund is carried on time on some tens years. They are spent for 3 basic stages: preparation to decommissioning NPP, long endurance under supervision, dismantle and burial the NPP equipment. Nowadays on faculty NPP MPEI

  8. DCVD Measurements at the Laguna Verde NPP

    Energy Technology Data Exchange (ETDEWEB)

    Chen, J.D.; Gerwing, A.F. [Channel Systems Inc., Pinawa MA (Canada); Kosierb, R. [Canadian Nuclear Safety Commission, Ottawa, ON (Canada); Vones, J.; Broodryck, A. [International Atomic Energy Agency, Vienna (Austria)

    2006-12-30

    A new digital Cerenkov viewing device (DCVD) with high ultraviolet light sensitivity has been developed. Field measurements on BWR spent fuel at Laguna Verde Nuclear Power Plant Unit 2 resulted in new Cerenkov information on GE9 and GE12 spent fuel assemblies. Off-alignment measurements show: quantitative differences in the degree of light collimation from between the fuel rods; lack of light collimation from water rods; and decreased light collimation from partial length rod positions. Hidden rods could also be detected in off-angle views. The results indicate that it may be possible to detect missing partial-length fuel rods in GE12 fuel assemblies. The new DCVD was able to verify low burnup, long-cooled, natural uranium GE6 fuel assemblies.

  9. Leningrad NPP full scope simulator upgrade for PPC HMI improvement and operator support systems development and testing

    International Nuclear Information System (INIS)

    The Project Objective was further development of Training Support Center (TSC) created at the Leningrad NPP (LNPP, Sosnovy Bor, Russia) which incorporates full-scope and analytical simulators to provide plant's DCS HMI and OSS improvement. The Project also gave possibilities of development, adjusting and testing of any new or up-graded Operators' Support System before its installation at the reference unit. Upgraded Simulators ensure the modeling of a wide range of accidents and transients and provide with special software and ETHERNET data process communications with the Operator Support Systems prototypes. RRC 'Kurchatov Institute' and LNPP team has implemented the Project jointly

  10. A new earthquake catalogue for seismic hazard assessment of the NPP (Nuclear Power Plant) Jaslovske Bohunice, Slovakia, site

    Science.gov (United States)

    Kysel, Robert; Kristek, Jozef; Moczo, Peter; Csicsay, Kristian; Cipciar, Andrej; Srbecky, Miroslav

    2014-05-01

    According to the IAEA (International Atomic Energy Agency) Safety Guide No. SSG-9, an earthquake catalogue should comprise all information on pre-historical, historical and seismometrically recorded earthquakes in the region which should cover geographic area not smaller than a circle with radius of 300 km around the site. Jaslovske Bohunice is an important economic site. Several nuclear facilities are located in Jaslovske Bohunice - either in operation (NPP V2, national radioactive waste repository) or in decommissioning (NPP A1, NPP V1). Moreover, a new reactor unit is being planned for the site. Jaslovske Bohunice site is not far from the Dobra Voda seismic source zone which has been the most active seismic zone at territory of Slovakia since the beginning of 20th century. Relatively small distances to Austria, Hungary, Czech Republic and Slovak capital Bratislava make the site a prominent priority in terms of seismic hazard assessment. We compiled a new earthquake catalogue for the NPP Jaslovske Bohunice region following the recommendations of the IAEA Safety Guide. The region includes parts of the territories of Slovakia, Hungary, Austria, the Czech Republic and Poland, and it partly extends up to Germany, Slovenia, Croatia and Serbia. The catalogue is based on data from six national earthquake catalogues, two regional earthquake catalogues (ACORN, CENEC) and a catalogue from the local NPP network. The primarily compiled catalogue for the time period 350 - 2011 consists of 9 142 events. We then homogenized and declustered the catalogue. Eventually we checked the catalogue for time completeness. For homogenization, we divided the catalogue into preseismometric (350 - 1900) and seismometric (1901-2011) periods. For earthquakes characterized by the epicentral intensity and local magnitude we adopted relations proposed for homogenization of the CENEC catalogue (Grünthal et al. 2009). Instead of assuming the equivalency between local magnitudes reported by the

  11. Programmes design for Bohunice NPP personnel other than control room operators

    International Nuclear Information System (INIS)

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

  12. Probabilistic safety assessment activities at Ignalina NPP

    International Nuclear Information System (INIS)

    The Barselina Project was initiated in the summer 1991. The project was a multilateral co-operation between Lithuania, Russia and Sweden up until phase 3, and phase 4 has been performed as a bilateral between Lithuania and Sweden. The long-range objective is to establish common perspectives and unified bases for assessment of severe accident risks and needs for remedial measures for the RBMK reactors. During phase 3, from 1993 to 1994, a full scope Probabilistic Safety Analysis (PSA) model of the Ignalina Nuclear Power Plant unit 2 was developed to identify possible safety improvement of risk importance. The probabilistic methodology was applied on a plant specific basis for a channel type reactor of RBMK design. During phase 4, from 1994 to 1996, the PSA was further developed, taking into account plant changes, improved modelling methods and extended plant information concerning dependencies (area events, dynamic effects, electrical and signal dependencies). The model reflected the plant status before the outage 1996. During phase 4+, 1998 to 1999 the PSA model was upgraded taking into account the newest plant modifications. The new PSA model of CPS/AZRT was developed. Modelling was based on the Single Failure Analysis

  13. PSA analysis focused on Mochovce NPP safety measures evaluation from operational safety point of view

    International Nuclear Information System (INIS)

    Mochovce NPP consists of four reactor units of WWER 440/V213 type and it is located in the south-middle part of Slovakia. At present first unit operated and the second one under the construction finishing. As these units represent second generation of WWER reactor design, the additional safety measures (SM) were implemented to enhance operational and nuclear safety according to the recommendations of performed international audits and operational experience based on exploitation of other similar units (as Dukovany and J. Bohunice NPPs). These requirements result into a number of SMs grouped according to their purpose to reach recent international requirements on nuclear and operational safety. The paper presents the bases used for safety measures establishing including their grouping into the comprehensive tasks covering different areas of safety goals as well as structural organization of a project management of including participating companies and work performance. More, results are given regarding contribution of selected SMs to the total core damage frequency decreasing.(author)

  14. Comparing global models of terrestrial net primary productivity (NPP): Global pattern and differentiation by major biomes

    Science.gov (United States)

    Kicklighter, D.W.; Bondeau, A.; Schloss, A.L.; Kaduk, J.; McGuire, A.D.

    1999-01-01

    Annual and seasonal net primary productivity estimates (NPP) of 15 global models across latitudinal zones and biomes are compared. The models simulated NPP for contemporary climate using common, spatially explicit data sets for climate, soil texture, and normalized difference vegetation index (NDVI). Differences among NPP estimates varied over space and time. The largest differences occur during the summer months in boreal forests (50??to 60??N) and during the dry seasons of tropical evergreen forests. Differences in NPP estimates are related to model assumptions about vegetation structure, model parameterizations, and input data sets.

  15. Attitude of the population and students to further construction of NPP

    International Nuclear Information System (INIS)

    This presentation shows the public opinion poll young people on NPP in the Slovakia i.e. comparative research results on Attitude of the Slovak population (1991 - a sample 1104 respondents, and Slovak students 1992 - a sample 291 respondents) to the nuclear energy and NPP; Source of information about NE and NPP, motivation of apprehensions of young people concerning NE; what meaning for young people have the arguments FOR and AGAINST construction of NPP in Slovakia; whom students from Bratislava believe during discussions about NE

  16. Total Spent Nuclear Fuel Back-End Costs For Ignalina NPP

    International Nuclear Information System (INIS)

    Discussions are going on different acceptable scenarios for Ignalina NPP decommissioning. To choose the optimum alternative it is necessary to know the spent nuclear fuel back-end costs for Ignalina NPP. This paper deals with an analysis of such results for different decommissioning scenarios. The costs are estimated for the main three components: NPP decommissioning and short-lived waste treatment costs, spent nuclear fuel (SNF) and long-lived waste (LLW) storage costs, SNF and LLW disposal costs. Also, the annual flow of these costs is shown The estimated data are compared with the available data on Ignalina NPP and Sweden. (author)

  17. Life Assurance Strategy for CANDU NPP

    International Nuclear Information System (INIS)

    include design provisions to replace fuel channels and steam generators. Difficult to replace components such as reactor building structures and calandria/shield tank assembly are designed for much beyond 40 years. Given the performance of CND's to date and the successfully completed rehabilitations and the lessons learned from older plants, a newly committed CANDU will have an economic service life significantly longer than 40 years. The CANDU design life was initially set at thirty years. The key components of a CANDU nuclear steam plant are the calandria vessel, the fuel channels, the reactivity control mechanisms, and the primary heat transport components including piping and steam generators. The calandria vessel, a large stainless steel tank, experiences conditions of relatively low temperature and pressure and is designed for a very long life. Experience to date shows that of the remaining components, fuel channels and reactivity control mechanisms are replaceable. Given that other refurbishments and/or replacements can be done to existing plants, a minimum of 40 year operating life can be achieved. Large scale fuel channel replacement was dictated by Station Life Assurance rather than Life Extension considerations. This major rehabilitation program has been successfully implemented for three of the Pickering A reactors to achieve a minimum 40 year operating life. In this program steady flow of successful design and process improvements have contributed to the knowledge base and know how of the CANDU industry. Over the next few years, retuning of the fourth Pickering A unit and the first of the Bruce A units will be undertaken providing the opportunity for Life extension of these units. Steam Generators in most CANDU plants continue to perform, with relatively low tube failures and plugging rates. Remedial measures are being taken, with solutions being evaluated by Ontario Hydro to address current degradation problems due to tube fouling and sludge deposition. R

  18. Planning for environmental restoration of the contaminated banks near NPP Bohunice

    International Nuclear Information System (INIS)

    The 18 km long banks of the Bohunice NPP waste water recipient are contaminated by cesium-137 as a result of two accidents on the CO2 cooled NPP A1 unit in 1976 and 1977. Since 1992, all he contaminated waste waters dumping from NPP Bohunice has been carried out directly to the Vah River through a specially constructed 15 km long pipeline. The final extent of contamination in the Bohunice site is represented. The overall contaminated area in this site with cesium-137 activity above 1 Bq/g of soil is about 67000 m2 and thus, the corresponding volume of top 20 cm thick soil layer is about 13000 m3. For optimizing less costly remedial measures (warning signs...) an agreed scenario with a pre-estimated factor factor collective dose 2.10-7 man.Sv.y-1/(m2.Bq137Cs.g-1) was applied. Limitation of individual effective doses according to a site specific stay scenario was also considered for this purposes with a limiting value of 0.25 mSv/y. Cost analysis of available remedial techniques were carried out, too. Two techniques have been selected for the contaminated banks restoration project: 1) removing/disposal of 20 cm soil top layer from steep and unengineered banks, and 2) mechanical dilution/fixation of contamination by clean 15 cm soil cover for the contaminated flat areas. Two-fold reduction of anticipated potential radiation risk were accepted, maximally, for the lastly mentioned technique, however cost saving is considerable (about 10-time lower the cost comparing to removing/disposal technique one). The basic acceptance limits AL for 137Cs in soil and criteria size of continuously contaminated bank areas were derived as: AL200 = 6.0 Bq/g and 800 m2 (300 m) or AL50 8.0 Bq/g and 200 m2 (80 m) for removing/disposal of the soil on steep unengineered banks. For clean soil covering technique the resulting limits are in an interval AL50C = 8 up to 16 Bq/g. According to the criteria developed, it is necessary to subject to restoration about 11000 m2 of contaminated area on

  19. Gaining public acceptance for Temelin NPP

    International Nuclear Information System (INIS)

    The construction of the Temelin nuclear power plant, which initially was planned to consist of 4 units with the Russian WWER-1000 reactors, later reduced to 2 began in 1986. There were no public opinion problems, because then, in the communist Czechoslovakia, public opinion was no issue of major importance. The first problems emerged after 1989 when Czechoslovakia began to seek it place among democratic countries. Then it turned out that the nuclear power plant had its opponents, that it aroused fright among the uninformed people and could become a tool for political manipulation. Generally, public opinion was in favour of nuclear power but the voice of the opponents had to be taken seriously. It was not later than 1989, during the political changes, that the first germs of Public Relations departments began to form at Czechoslovak nuclear power plants. The technicians and economists, however, were to say the crucial words. For the CEZ utility, with its Temelin under construction, to become a credible partner for the public in Czechoslovakia and abroad, efforts had to be made for the plant to be completed so that it should meet safety requirements which are conventional in Western Europe and in the United States. There came IAEA missions and international audits, which confirmed that the power plant would be able to meet international safety standards provided that some upgrading and changes in the Russian design are implemented, in particular, the instrumentation and control. We foster and expand personal contacts with media and make efforts to keep them informed. We arrange events through which they can get familiar with nuclear power problems abroad. The Temelin newspaper is a monthly through which we inform the population within 20 km from the power plant about all important events. We have expanded the Information Center which, following the model of the French EDF, employs external female guide staff. Over 13 thousand people visit the Center every year. So

  20. A Study of the Impacts of Npp-Desalination Development in Madura on Sectoral Regional Economy

    International Nuclear Information System (INIS)

    This study aims to assess the economic impact of construction and early operation of the nuclear power plant (NPP)-desalination project in the island of Mad Lira until the year 2018. Long-term projection on economic output (X) of Madura uses Leo ntiefdynamic 1-0 (input-output) model, and for GRDP- final demand (Y) uses time series model with random growth adjustment based on autoregressive model. Since the Madura 1-0 Table is not available, then it is necessary to construct it for 2000 using RAS method and some modifications. The NPP project will use SMART technology with 2 units of power generators (100 MWe capacity per unit, total output 200 MWe), but to be built sequentially with one year lag. As for the desalination will use 4 units MED with each unit capacity of 10.000 m'/day. The construction stage will take 5 years to be completed (2014-2018), preceded by the pre-project stage along 2010-2013. Total investment requirements of the project is amounted to US$ 357,87 million (in 2002). At the time when the contract (turn key contract) is signed in 2009, the value will become US$ 397.18 million, and in 2014 (early construction) will be US$ 427.87 million. At the end of the project (2018), total investment requirements will amount to US$ 440.79 million. To include land make up payment and licenses costs the project will be worth US$ 476. In the pre-project stage (2010-2013), cumulatively, land make up payment and licenses management activities as much as Rp 114.11 billion (US$ 10.69 million) has indirect effect--transmiUed through private and government consumption -- onto Madura economy. Dynamic 1-0 simulation results (2000 Madura 1-0 Table, 1Ox10) show that the rise in consumption generate increases in output, GRDP and employment respectively in cumulative as much as Rp 146.39 billion, Rp79.20 billion, and 7,428 men. In overall, project activities in construction stage (2014-2017) estimated to Rp 231.37 billion (US$19.36 million) which has direct effect on

  1. Investigation of dry out of SFP for VVER440/V230 at Kozloduy NPP

    Energy Technology Data Exchange (ETDEWEB)

    Groudev, P., E-mail: pavlinpg@inrne.bas.bg [Institute for Nuclear Research and Nuclear Energy, Tzarigradsko Shaussee 72, Sofia 1784 (Bulgaria); Stefanova, A., E-mail: antoanet@inrne.bas.bg [Institute for Nuclear Research and Nuclear Energy, Tzarigradsko Shaussee 72, Sofia 1784 (Bulgaria); Manolov, M., E-mail: m_manolov@npp.bg [NPP Plc, Kozloduy 3320 (Bulgaria)

    2013-09-15

    This paper presents the thermal-hydraulic investigation of spent fuel behavior during its transferring from reactor vessel through refueling cavity (RC) to spent fuel pool (SFP) in case of dry out for VVER440/V230 units 3 and 4 at Kozloduy NPP. The fuel transfer canal connects the refueling cavity and spent fuel pool and this way set up a command pool. The presented analysis has been performed up to the moment of fuel heat up in case of spent fuel pool (SFP) dry out during the first stage of refueling activities. The main feature during this stage is: the maximum decay power of “new” spent fuel; the “new” spent fuel is still in the reactor vessel; the fuel transfer canal connects the refueling cavity and spent fuel pool. In this way the coolant have maximum volume and the spent fuel with maximum decay power is still in the reactor vessel. The “old” spent fuel in SFP has significantly low decay power. The main purpose of this analysis is to estimate the time for dry out of SFP, heat up of spent fuel and time for recovery actions from the operators. In the performed analysis are defined the following stages during the accident. ∘Termination of natural circulation after decreasing of water level in reactor vessel below the hot nozzles. ∘Beginning of coolant heat up in the reactor core. ∘Reaching the temperature of saturation at the outlet of the assembly. ∘Startup of the reactor core uncover. ∘Loss of critical safety functions. The analysis has been performed with the thermal-hydraulic computer code RELAP5/MOD3.2. The RELAP5/MOD3.2 model for Kozloduy NPP VVER-440 have been developed and validated at the Institute for Nuclear Research and Nuclear Energy – Bulgarian Academy of Sciences (INRNE-BAS) Sofia.

  2. Retrieving Atmospheric Temperature and Moisture Profiles from NPP CRIS/ATMS Sensors Using Crimss EDR Algorithm

    Science.gov (United States)

    Liu, X.; Kizer, S.; Barnet, C.; Dvakarla, M.; Zhou, D. K.; Larar, A. M.

    2012-01-01

    The Joint Polar Satellite System (JPSS) is a U.S. National Oceanic and Atmospheric Administration (NOAA) mission in collaboration with the U.S. National Aeronautical Space Administration (NASA) and international partners. The NPP Cross-track Infrared Microwave Sounding Suite (CrIMSS) consists of the infrared (IR) Crosstrack Infrared Sounder (CrIS) and the microwave (MW) Advanced Technology Microwave Sounder (ATMS). The CrIS instrument is hyperspectral interferometer, which measures high spectral and spatial resolution upwelling infrared radiances. The ATMS is a 22-channel radiometer similar to Advanced Microwave Sounding Units (AMSU) A and B. It measures top of atmosphere MW upwelling radiation and provides capability of sounding below clouds. The CrIMSS Environmental Data Record (EDR) algorithm provides three EDRs, namely the atmospheric vertical temperature, moisture and pressure profiles (AVTP, AVMP and AVPP, respectively), with the lower tropospheric AVTP and the AVMP being JPSS Key Performance Parameters (KPPs). The operational CrIMSS EDR an algorithm was originally designed to run on large IBM computers with dedicated data management subsystem (DMS). We have ported the operational code to simple Linux systems by replacing DMS with appropriate interfaces. We also changed the interface of the operational code so that we can read data from both the CrIMSS science code and the operational code and be able to compare lookup tables, parameter files, and output results. The detail of the CrIMSS EDR algorithm is described in reference [1]. We will present results of testing the CrIMSS EDR operational algorithm using proxy data generated from the Infrared Atmospheric Sounding Interferometer (IASI) satellite data and from the NPP CrIS/ATMS data.

  3. Application of Mössbauer spectroscopy on corrosion products of NPP

    Science.gov (United States)

    Dekan, J.; Lipka, J.; Slugeň, V.

    2013-04-01

    Steam generator (SG) is generally one of the most important components at all nuclear power plants (NPP) with close impact to safe and long-term operation. Material degradation and corrosion/erosion processes are serious risks for long-term reliable operation. Steam generators of four VVER-440 units at nuclear power plants V-1 and V-2 in Jaslovske Bohunice (Slovakia) were gradually changed by new original "Bohunice" design in period 1994-1998, in order to improve corrosion resistance of SGs. Corrosion processes before and after these design and material changes in Bohunice secondary circuit were studied using Mössbauer spectroscopy during last 25 years. Innovations in the feed water pipeline design as well as material composition improvements were evaluated positively. Mössbauer spectroscopy studies of phase composition of corrosion products were performed on real specimens scrapped from water pipelines or in form of filters deposits. Newest results in our long-term corrosion study confirm good operational experiences and suitable chemical regimes (reduction environment) which results mostly in creation of magnetite (on the level 70 % or higher) and small portions of hematite, goethite or hydrooxides. Regular observation of corrosion/erosion processes is essential for keeping NPP operation on high safety level. The output from performed material analyses influences the optimisation of operating chemical regimes and it can be used in optimisation of regimes at decontamination and passivation of pipelines or secondary circuit components. It can be concluded that a longer passivation time leads more to magnetite fraction in the corrosion products composition.

  4. Public acceptance of nuclear energy in Indonesia. A traditional puppet show for NPP in Java

    International Nuclear Information System (INIS)

    In Indonesia, activities on public relation have been carried out since the establishment of the agency responsible for research and development of atomic energy in 1958 (which later in the year 1964 became Batan, National Atomic Energy Agency), wile activities on public acceptance started 'at the end of 1985. After the Government indicated that it has to look seriously into the construction of the NPP, as from 1990, the public acceptance (PA) activities have been intensified in anticipation of the construction of the first NPP. An important part of the preparatory activities for the construction of the NPP is preparing the people, particularly those who live near the NPP site, to accept and to support the NPP program. The interdepartmental team has bee established in August 1990 consisting of representatives of several institutions, namely, Ministry of Information, Ministry of Domestic Affairs, Ministry of Defense, Land Utilization Agency, State Electricity Corporation, Office of the Minister for Population and Environment, and Batan. This team, called the 'Team on Public Acceptance of NPP', has the main task providing extensive information to the public concerning the government plan to construct nuclear power plants in Indonesia. From 1990 through the middle of 1994 the activity of the Team on Public Acceptance of NPP was focused on providing information on te NPP program to the local community leaders and the public, particularly in the districts of the NPP site in the Muria Peninsula region. Its main purpose was to precondition the people who live near the NPP site to accept the NPP in their neighbourhood without fear

  5. Training in fundamentals of radiological coverage in Laguna Verde NPP

    International Nuclear Information System (INIS)

    In 2010, the Institute of Nuclear Power Operations (INPO) celebrates the Knowledge Transfer and Retention Workshop, an event where nuclear regulators and operators presented the strategies that various NPP to worldwide were implemented to mitigate the consequences of this generational change and take advantage of it, the trend in the presented works was the same: the generational change occurs in a faster way that the transfer of knowledge, the future was already here and many NPP had not been adequately prepared to train its nuclear technicians and engineers in the tasks demanded by the industry of them, so in addition to preparing these workers to forced marches was necessary to establish strategies to retain at more experienced staff in the industry. The Laguna Verde NPP has not been exempt to this process; the preparation of personnel squares to replace those that reaching retirement age in the Comision Federal de Electricidad (CFE) has become extensive in the last five years, sometimes leading to have personnel covering functions without an alternate to the next lower position, the cause? Not enough staff. In the specific case of radiation protection (Rp) the time required for obtaining the status of Rp technician according to the ANSI/ANS 3.1 standard is 2 years, one of the tasks that most occupies part of these two years is training in radiological coverage, this training requires a mix of knowledge and experience, recently one of the concepts used for training in Rp is the evaluation and management of the radiological risk, topic that is considered in this technical work. (Author)

  6. NPP accident analysis for spray safety system operation

    International Nuclear Information System (INIS)

    Different methods for calculating the NPP containment spray system are considered in brief. The spray system consists of three manifolds mounted in the upper part of the containment. Indicated are formulas for calculating the degree of the liquid jet warm-up+ comparison of theoretical and experimental valwes of temperature and pressure in transients, dependence of pressure decrease rate on cooling water initial temperature, heat removal intensity curves at different cooling water temperatures and pressure decrease curves at various estimations of the degree of liquid jet warm-up

  7. About works perspectives in the ChNPP exception Zone

    International Nuclear Information System (INIS)

    The analysis of the situation that turned out by now in the 30-km exception zone of ChNPP has been carried out. The accumulation of the negative processes connected with the radionuclides transition to the soluble mobile forms are noted. The influence at least of three potentially dangerous high active sources on the increase of the subsoil water radioactive contamination level is determined. Recommendations concerning the organization of the reliable monitoring in the exception zone are given. The problems of the points of the radioactive waste provisional localization and collection are discussed. The top priority tasks connected with the management in the exception zone are defined

  8. Characterization of neutron field in a NPP workplace.

    Science.gov (United States)

    Breznik, B; Pochat, J L; Muller, H; Asselineau, B; Pavlin, M

    2007-01-01

    At the Krsko Nuclear Power Plant (NPP), albedo dosimeters are used for personal neutron dosimetry. Spectrometric measurements allow determination of reference dosimetric values of realistic neutron fields to be used for calibration of albedo dosimeters. The Laboratory for Neutron Metrology and Dosimetry from the Institute for Radiological Protection and Nuclear Safety (IRSN) was in charge of characterising neutron fields in the plant at two representative points with high neutron and gamma dose rate. Calibration of the dosimeters in the workplace used to be performed only by a spherical survey meter. Based on the reference dosimetric values, the Plant Dosimetry Laboratory has verified the response of albedo dosimeters.

  9. Vibrational fatigue analysis for main steam pipelines on a NPP

    International Nuclear Information System (INIS)

    The vibration and noise of pipings adjacent to isolation valves of main steam pipelines in a NPP were excessive during operation. To assess the safety in operation of main steam pipelines, both stress and fatigue analysis were performed using ANSYS program, and evaluation was performed according to ASME code. The main steam pipeline considered in this report, includes the main steam piping, safety valves, main steam isolation valve and other branch pipings between the containment penetration and the first transverse direction limit stop downstream of the isolation valve

  10. Application of ant colony optimization in NPP classification fault location

    International Nuclear Information System (INIS)

    Nuclear Power Plant is a highly complex structural system with high safety requirements. Fault location appears to be particularly important to enhance its safety. Ant Colony Optimization is a new type of optimization algorithm, which is used in the fault location and classification of nuclear power plants in this paper. Taking the main coolant system of the first loop as the study object, using VB6.0 programming technology, the NPP fault location system is designed, and is tested against the related data in the literature. Test results show that the ant colony optimization can be used in the accurate classification fault location in the nuclear power plants. (authors)

  11. Appendix XXVII: Succession planning applications at the Paks NPP Ltd

    International Nuclear Information System (INIS)

    Paks Nuclear Power Plant Ltd, Hungar, is a state owned Public Stakeholders' Corporation with one nuclear site with four reactors in operation. The process describes the complex career and succession planning policy at the Paks NPP Ltd. Making the competent labor force available is the responsibility of the corporate integrated HR system. A key item of this is operating the complex career and succession planning system, which covers the following prominent employee categories: - managerial posts; - non-managerial posts requiring higher academic education; - posts, that require medium level academic education and extensive professional experiences; - Posts of the operative scheme

  12. Comparison of the Uniform Hazard Spectra for Korean NPP Sites

    International Nuclear Information System (INIS)

    A site-specific median spectrum has been generally used for a seismic fragility analysis of structures and equipment in Korean nuclear power plants. The site-specific response spectrum, however, does not represent the same probability of an exceedance over the entire frequency range of interest. The uniform hazard spectrum is more appropriate to use in a seismic probabilistic risk assessment than the site-specific spectrum. In this study, the uniform hazard spectra were developed using the available seismic hazard data for Korean NPP sites

  13. Application of Robotic System for Emergency Response in NPP

    International Nuclear Information System (INIS)

    Increasing energy demand and concerns over climate change make increasing use of nuclear power plant in worldwide. Even though the probability of accident is greatly reduced, safety is the highest priority issue in the nuclear energy industry. Applying highly reliable and conservative 'defense in depth' concepts with the design and construction of NPP, there are very little possibilities with which accidents are occur and radioactive materials are released to environments in NPP. But NPP have prepared with the emergency response procedures and conduct exercises for post-accident circumstance according to the procedures. The application of robots for emergency response task for post-accident in nuclear facilities is not a new concept. Robots have been sent to recover the damaged reactor at Chernobyl where human workers could receive a lifetime dose of radiation in minutes. Based on NRC's TMI-2 Cleanup Program, several robots were built in the 1980s to help gather information and remove debris from a reactor at the Three Mile Island nuclear power plant that partially melted down in 1979. The first robot was lowered into the basement through a hatch and human operators monitoring in a control room drove it through mud, water and debris, capturing the initial post-accident images of the reactor's basement. It was used for several years equipped with various tools allowing it to scour surfaces, scoop samples and vacuum sludge. A second version carried a core sampler to determine the intensity and depth of the radiation that had permeated into the walls. To perform cleanup tasks, they built Workhorse that featured system redundancy and had a boom extendable to reach high places, but it was never used because it had too many complexities and to clean and fix. While remote robotics technology has proven to remove the human from the radioactive environment, it is also difficult to make it useful because it may requires skill about remote control and obtaining remote

  14. Appendix VIII: Knowledge management applications at the Paks NPP Ltd

    International Nuclear Information System (INIS)

    The process describes the knowledge management policy at the Paks NPP Ltd established to make available personnel in optimal quantity, properly selected, trained and equipped with all knowledge, skills and attitudes required for the long term safe, competitive and reliable operation of the plant with focus on the plant's service time extension recently approved. For this end - using knowledge related to the corporate recruitment needs and the job-specific requirements/expectations - personnel are selected from internal or external resources to become prepared through expedient, targeted development programmes to succeed in specific positions

  15. Problem of the NPP liquid radioactive wastes processing and disposal

    International Nuclear Information System (INIS)

    Modern methods of NPP radioactive waste processing and disposal are briefly presented, bituminization with the following disposal in the clayey soil in particular. Soviet installations of liquid waste bituminization and results of proving ground preservation of bituminic blocks are briefly described. These results indicate a possibility of bituminic material disposal with specific activity of 1 Ci/l directly in the soil without waterproofing. High safety and effectivity of waste bituminization is shown in comparison with preservation variant of liquid radioactive concentrates in capacities

  16. Waste management concept during dismantling of KKS NPP in Germany

    International Nuclear Information System (INIS)

    Full text: This paper gives an overview on the waste management of NPP Stade during dismantling. The general idea is to reduce the radioactive waste to about three percentage of the complete dismantling mass. The NPP Stade in Germany was shut down in November 2003. After a transient phase the license for dismantling was given in 2005. In the following 8 years about 20.000 tones of steel and 120.000 tones of concrete will be put out by the dismantling. The yearly output of steel will by about 100 times higher than during the running time of the NNP. For this a new processes for waste management had to be installed. The waste management during dismantling focus on free release (about 97%). Beside some minor exception, the rest is deemed to be radioactive waste. This will be collected in 1000 packages, which are ready to be sent to a final storage. As until now in Germany no final storage is open (and sending of radioactive waste to another country is forbidden), the NNP Stade build an intermediate storage, where the packages may by saved for longest 40 years. The clearance procedure in Germany is regulated in the radiation protection ordinances. It is based on a nuclide specific set of clearance levels. To fulfil these demands the NNP Stade chose a semi automated system for characterization and documentation, which we develop in accordance to our release license. It guaranties a most accurate determination of the relevant nuclides for a set of dismantling material (some 10 to 100 tones). After the characterization only the gamma-activity of the material is measured in boxes of about 500 kg. A short comparison of the chosen procedure with other options, possible in Germany will be given and the decision from the collaboration with the NPP in Barsebaeck, Sweden, will be withdrawn. Beside the free release different options are used for waste management, like incineration, sending to landfill or reuse in nuclear industry. The waste management of the NNP Stade take

  17. Ecological and environmental education in the region of Ignalina NPP

    International Nuclear Information System (INIS)

    During three last years the groups involving pupils, students and teachers take part in the educational sessions. They are organized in Drukshiai Ecological Station . The work of Ignalina NPP, its influence on the nature as well as methods and results of scientific investigation and assessment of the influence are discussed. To direct environmental research activity of scholars the special 3-8 days programs made up by researchers are used. They include theoretical and practical studies. Educational - research activity performed in the Drukshiai Ecological Station could be an example of ecological schooling center related to environmental protection. (author). 2 refs

  18. Characterization of neutron field in a NPP workplace

    International Nuclear Information System (INIS)

    At the Krsko Nuclear Power Plant (NPP), albedo dosimeters are used for personal neutron dosimetry. Spectrometric measurements allow determination of reference dosimetric values of realistic neutron fields to be used for calibration of albedo dosimeters. The Laboratory for Neutron Metrology and Dosimetry from the Inst. for Radiological Protection and Nuclear Safety (IRSN) was in charge of characterising neutron fields in the plant at two representative points with high neutron and gamma dose rate. Calibration of the dosimeters in the workplace used to be performed only by a spherical survey meter. Based on the reference dosimetric values, the Plant Dosimetry Laboratory has verified the response of albedo dosimeters. (authors)

  19. IAEA activities on safety aspects of NPP ageing

    International Nuclear Information System (INIS)

    A review of IAEA activities concerned with safety aspects of nuclear power plants ageing is given for the period from 1995 to 1998 with the prospects till year 2000. Coordinated Research programs were conducted on Management Ageing of Concrete Containment Buildings; Management of Ageing of In-Containment I and C cables. TECDOCs were published on Assessment and Management of Ageing of Major NPP Components Important for Safety of CANDU, PWR and BWR NPPs. Technical Committee Meetings and Interregional training courses concerned with the same subjects were held

  20. XIV International conference NPP safety and personnel training. Abstracts

    International Nuclear Information System (INIS)

    This volume presents papers of the participants of XIV International conference “NPP Safety and Training” held 25-27 November 2015 in Obninsk. Collection is prepared by teachers, research staff and students of NRNU MEPhI, INPE NRNU MEPhI, scientists and specialists of institutions of the State Corporation Rosatom, academic, scientific and industrial organizations in Russia and abroad. They reflect the level of researches in nuclear physics and energetics, nuclear medicine, electronics and automation, as well as advances in improving the efficiency and safety of nuclear power installations, environmental protection and training for the nuclear power industry

  1. Survey of Water Chemistry and Corrosion of NPP

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Ki Sok; Hong, Bong Geon

    2008-06-15

    Status of water chemistry of nuclear power plant and materials corrosion has been surveyed. For PWR, system chemistry of primary coolant and secondary coolant as well as the related corrosion of materials was surveyed. For BWR, system chemistry as whole has been surveyed with its accompanying corrosion problems. Radiolysis of coolant water and activation of corrosion products also was surveyed. Future NPP such as supercritical water cooled reactor and fusion reactor has also been surveyed for their water chemistry and corrosion problems. As a result, proposal for some research items has been suggested. Some related corrosion research techniques and electrochemical fundamentals are also presented.

  2. Dynamical study of the main building of the Paks NPP

    International Nuclear Information System (INIS)

    Explosion tests were carried out for determining the dynamical characteristics of the main building of the Paks NPP. The objectives of this work were on one hand the verification of the computations performed and, on the other hand we attempted measuring the damping value and evaluating the soil-structure interaction. The first series of explosions consisted of short-distance blows using 5- 40 kg of explosive, the second and third series were performed at longer distances with 50 - 500 kg loads. Explosions were performed by the Hungarian State geophysical Institute

  3. VVER reactor pressure vessels dosimetry for NPP lifetime management

    International Nuclear Information System (INIS)

    Assessment of the current state and lifetime of the Kozloduy NPP VVER-type reactors has been carried out by monitoring the irradiation exposure of reactor vessels and metal surveillance specimens. The neutron fluence determination is based on three-dimensional neutron transport calculation by the TORT code using the problem-oriented neutron cross-section library BGL, and by the MCNP code using the continuous energy dependence library DLC200. The fluence data are validated by measurements of the induced activity of threshold foil detectors. Reactor core loading patterns are determined to achieve minimal reactor vessel neutron exposure. (author)

  4. Characterization of neutron field in a NPP workplace.

    Science.gov (United States)

    Breznik, B; Pochat, J L; Muller, H; Asselineau, B; Pavlin, M

    2007-01-01

    At the Krsko Nuclear Power Plant (NPP), albedo dosimeters are used for personal neutron dosimetry. Spectrometric measurements allow determination of reference dosimetric values of realistic neutron fields to be used for calibration of albedo dosimeters. The Laboratory for Neutron Metrology and Dosimetry from the Institute for Radiological Protection and Nuclear Safety (IRSN) was in charge of characterising neutron fields in the plant at two representative points with high neutron and gamma dose rate. Calibration of the dosimeters in the workplace used to be performed only by a spherical survey meter. Based on the reference dosimetric values, the Plant Dosimetry Laboratory has verified the response of albedo dosimeters. PMID:17416593

  5. New approaches for seismic design standardization and retrofitting of NPP

    International Nuclear Information System (INIS)

    All the important structures, equipment piping of a nuclear power plant need to be safeguarded against natural disaster such as earthquake. The most effective way of reducing the earthquake loads in NPP structures is to isolate the structure using base isolators. Laminated rubber bearing, which is most commonly used as a isolation system for structures is discussed in the present paper. Passive energy dissipating devices called dampers are used for controlling the seismic loads in piping systems. Some of such dampers, lead extrusion dampers, friction dampers and elastoplastic dampers, are discussed in the present paper. (author)

  6. The practice of safety, quality, schedule, cost management of Sanmen NPP phase I

    International Nuclear Information System (INIS)

    Sanmen NPP Phase I is the first AP1000 project in the world, and the target construction period of the first unit is 56 months. All these pose great challenge to owner namely Sanmen Nuclear Power Company, Ltd. (ab. SMNPC). After exploration and practice for years, SMNPC has set up a project-oriented management system. With regard to safety management, a systematic safety management mechanism has been implemented innovatively. With regard to quality management, the safety grade and QA grade of non-safety related but contributing greatly to Plant safetyand new requirement of reliability assurance programhas been proposed. With regard to schedule control, a coordination, management and control mechanism by different levels has been established based on the design and modularization construction features of the first AP1000 unit; A method which correlate payment with key schedule control item and integrate bill of quantity statistics and schedule has been proposed. With regard to cost control, a four-level control system has been implemented; a complete work procedure has been established in areas as planning and Budget account Request, contract budget and settlement, fund collecting and risk management. Earned Value Management approach has been applied in the first time to integrate cost management and schedule management. SMNPC, with endeavors of all parties, will make the first AP1000 Unit a successful paragon. (authors)

  7. Nonvascular contribution to ecosystem NPP in a subarctic heath during early and late growing season

    DEFF Research Database (Denmark)

    Campioli, Matteo; Samson, Roeland; Michelsen, Anders;

    2009-01-01

    Bryophytes and lichens abound in many arctic ecosystems and can contribute substantially to the ecosystem net primary production (NPP). Because of their growth seasonality and their potential for growth out of the growing season peak, bryophyte and lichen contribution to NPP may be particularly...

  8. Dose expenditure minimization during the NPP equipment and systems maintenance and repair

    International Nuclear Information System (INIS)

    Dose expenditure change depending on NPP operation term was estimated as well as maintenance and repair contribution to the collective dose depending on the reactor type. The ways to decrease the staff irradiation during the NPP maintenance were analyzed. The optimization relevance when radioactive protection choosing was shown

  9. REGULATORY FRAMEWORK AND EVALUATION OF HUMAN-MACHINE INTERFACES IMS NPP SAFETY CASE BASED METHODOLOGY

    OpenAIRE

    Харченко, В'ячеслав Сергійович; "Національний аерокосмічний університет ім.М.Є.Жуковського "ХАІ""; Орехова, Анастасія Олександрівна; "Національний аерокосмічний університет ім.М.Є.Жуковського "ХАІ""

    2012-01-01

    The problems associated with safety of human-machine interfaces, information and control systems in NPP are analyzed.. An approach to assess the safety HMI I&C system NPP, based on Safety Case methodology is proposed. The profile of standards for HMI quality requirements is presented. An example of HMI quality assessment is described.

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

    International Nuclear Information System (INIS)

    In August 1991, following the SMiRT-11 Conference in Tokyo, a Technical Committee Meeting was held on the 'Seismic safety issues relating to existing NPPs'. The Proceedings of this TCM was subsequently compiled in an IAEA Working Material. One of the main recommendations of this TCM, called for the harmonization of criteria and methods used in Member States in seismic reassessment and upgrading of existing NPPs. Twenty four institutions from thirteen countries participated in the CRP named 'Benchmark study for the seismic analysis and testing of WWER type NPPs'. Two types of WWER reactors (WWER-1000 and WWER-440/213) selected for benchmarking. Kozloduy NPP Units 5/6 and Paks NPP represented these respectively as prototypes. Consistent with the recommendations of the TCM and the working paper prepared by the subsequent Consultants' Meeting, the focal activity of the CRP was the benchmarking exercises. A similar methodology was followed both for Paks NPP and Kozloduy NPP Unit 5. Firstly, the NPP (mainly the reactor building) was tested using a blast loading generated by a series of explosions from buried TNT charges. Records from this test were obtained at several free field locations (both downhole and surface), foundation mat, various elevations of structures as well as some tanks and the stack. Then the benchmark participants were provided with structural drawings, soil data and the free field record of the blast experiment. Their task was to make a blind prediction of the response at preselected locations. The analytical results from these participants were then compared with the results from the test. Although the benchmarking exercises constituted the focus of the CRP, there were many other interesting problems related to the seismic safety of WWER type NPPs which were addressed by the participants. These involved generic studies, i.e. codes and standards used in original WWER designs and their comparison with current international practice; seismic analysis

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

    International Nuclear Information System (INIS)

    In August 1991, following the SMiRT-11 Conference in Tokyo, a Technical Committee Meeting was held on the 'Seismic safety issues relating to existing NPPs'. The Proceedings of this TCM was subsequently compiled in an IAEA Working Material. One of the main recommendations of this TCM, called for the harmonization of criteria and methods used in Member States in seismic reassessment and upgrading of existing NPPs. Twenty four institutions from thirteen countries participated in the CRP named 'Benchmark study for the seismic analysis and testing of WWER type NPPs'. Two types of WWER reactors (WWER-1000 and WWER-440/213) selected for benchmarking. Kozloduy NPP Units 5/6 and Paks NPP represented these respectively as prototypes. Consistent with the recommendations of the TCM and the working paper prepared by the subsequent Consultants' Meeting, the focal activity of the CRP was the benchmarking exercises. A similar methodology was followed both for Paks NPP and Kozloduy NPP Unit 5. Firstly, the NPP (mainly the reactor building) was tested using a blast loading generated by a series of explosions from buried TNT charges. Records from this test were obtained at several free field locations (both downhole and surface), foundation mat, various elevations of structures as well as some tanks and the stack. Then the benchmark participants were provided with structural drawings, soil data and the free field record of the blast experiment. Their task was to make a blind prediction of the response at preselected locations. The analytical results from these participants were then compared with the results from the test. Although the benchmarking exercises constituted the focus of the CRP, there were many other interesting problems related to the seismic safety of WWER type NPPs which were addressed by the participants. These involved generic studies, i.e. codes and standards used in original WWER designs and their comparison with current international practice; seismic analysis

  12. Highly Reliable NPP Instrumentation Using Constant Voltage Feedback Circuits

    International Nuclear Information System (INIS)

    A highly reliable nuclear power plant (NPP) instrumentation using constant voltage feedback circuits is proposed. Contrary to conventional NPP instrumentation, two operational amplifiers are used at auxiliary building to supply constant DC voltage across the potentiometer or wheatstone bridge type sensors, such as resistance temperature detectors (RTD) and strain gauges. The proposed constant voltage feedback circuits maintain its output voltage as constant regardless of the length of lead wire from the auxiliary building to the sensors. A detail analysis of the proposed feedback circuits and design procedures including the internal resistance and parasitic LC components of lead wire are presented. A prototype with lumped RLC values for modeling lead wires is fabricated and experimentally verified to supply constant 10V up to 200m distance under 0.8% error. Due to its versatile characteristics with cost effective structure, the proposed scheme can be generally extended to pressure meters and water-level recorders to guarantee robust measurements without conventional current transducers under severe accidents

  13. Performance indicator system with application to NPP management

    Energy Technology Data Exchange (ETDEWEB)

    Gomez, J. [Iberdrola S.A., Madrid (Spain); Roldan, J. [Cofrentes NPP, Madrid (Spain)

    2001-07-01

    The objective of the paper is to present the work that is being conducted in the scope of a research project between Cofrentes NPP and the polytechnic university of Valencia aimed to the development and implementation of a performance indicators system to support plant management. In developing this system, attention is being paid to the areas of safety, production and dependability. The first step in the project was the development of the performance indicator system (PIS), in order to help in assessing the effectiveness of the different activities in plant (i.e. maintenance, inspections, tests, etc.). It is suggested establishing the operational indicators set in 3 levels. The lowest level concerns indicators monitoring performance and maintenance characteristics of components. The next one involves a subset of indicators placed at system level with a similar goal. And finally, the highest level summarizes the impact of the global policy in the whole plant from safety and performance point of view. The definition of an indicator should comprise, at least, the following items: indicator's name, performance area, definition and data needed. A strategy should define what, when and how indicators have to be evaluated, analyzed and reported. This article gives an example application of the methodology at the Cofrentes NPP, collective dose as safety indicator, power production as production indicator and the number of work orders as maintenance indicator are considered and their time evolution is given. (A.C.)

  14. Suomi NPP VIIRS Reflective Solar Bands Operational Calibration Reprocessing

    Directory of Open Access Journals (Sweden)

    Slawomir Blonski

    2015-12-01

    Full Text Available Radiometric calibration coefficients for the VIIRS (Visible Infrared Imaging Radiometer Suite reflective solar bands have been reprocessed from the beginning of the Suomi NPP (National Polar-orbiting Partnership mission until present. An automated calibration procedure, implemented in the NOAA (National Oceanic and Atmospheric Administration JPSS (Joint Polar Satellite System operational data production system, was applied to reprocess onboard solar calibration data and solar diffuser degradation measurements. The latest processing parameters from the operational system were used to include corrected solar vectors, optimized directional dependence of attenuation screens transmittance and solar diffuser reflectance, updated prelaunch calibration coefficients without an offset term, and optimized Robust Holt-Winters filter parameters. The parameters were consistently used to generate a complete set of the radiometric calibration coefficients for the entire duration of the Suomi NPP mission. The reprocessing has demonstrated that the automated calibration procedure can be successfully applied to all solar measurements acquired from the beginning of the mission until the full deployment of the automated procedure in the operational processing system. The reprocessed calibration coefficients can be further used to reprocess VIIRS SDR (Sensor Data Record and other data products. The reprocessing has also demonstrated how the automated calibration procedure can be used during activation of the VIIRS instruments on the future JPSS satellites.

  15. Development of NPP Monitoring and Operation Support Technology

    International Nuclear Information System (INIS)

    During the first stage (2001.7.1-2004.6.30), we developed general human factors design guidelines VDU-based workstations, PMAS alarm display design guidelines, PMAS SPADES display design guidelines, and the revision of KHNP HFE guidelines (HF-010), which have been applied to domestic NPP designs. We also supported other KNICS projects by performing RPS COM design reviews, development of RPS COM Style Guide, and a review of CEDMCS cabinet operator module display design. We developed the ADIOS prototype, NPP performance analysis systems for YGN No.1, 2 plants and Kori No. 2 plant, alarm cause tracking systems for Kori No. 2 plant and OPR1000, and signal fault detection and diagnosis methods for deaerators and steam generators. During the second stage(2004.7.1-2008.4.30), we supported other KNICS projects by reviewing RPS COM display designs three times, developing ESF-CCS COM style guides and reviewing ESF-CCS COM display design, reviewing CRCS LOM and PCS MTP display designs, and developing requirements for DCS GUI components. We also developed integrated style guide for I and C cabinet operator module display designs. In cooperative research with KOPEC-AE, we developed basic technologies for advanced HSI design including task analysis methods, an information and control requirements database, display design criteria, a HSI prototype with its evaluation, and methods for human factors engineering verification and validation

  16. Development of NPP Monitoring and Operation Support Technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung Woon; Park, Jae Chang; Lee, Yong Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)] (and others)

    2008-04-15

    During the first stage (2001.7.1-2004.6.30), we developed general human factors design guidelines VDU-based workstations, PMAS alarm display design guidelines, PMAS SPADES display design guidelines, and the revision of KHNP HFE guidelines (HF-010), which have been applied to domestic NPP designs. We also supported other KNICS projects by performing RPS COM design reviews, development of RPS COM Style Guide, and a review of CEDMCS cabinet operator module display design. We developed the ADIOS prototype, NPP performance analysis systems for YGN No.1, 2 plants and Kori No. 2 plant, alarm cause tracking systems for Kori No. 2 plant and OPR1000, and signal fault detection and diagnosis methods for deaerators and steam generators. During the second stage(2004.7.1-2008.4.30), we supported other KNICS projects by reviewing RPS COM display designs three times, developing ESF-CCS COM style guides and reviewing ESF-CCS COM display design, reviewing CRCS LOM and PCS MTP display designs, and developing requirements for DCS GUI components. We also developed integrated style guide for I and C cabinet operator module display designs. In cooperative research with KOPEC-AE, we developed basic technologies for advanced HSI design including task analysis methods, an information and control requirements database, display design criteria, a HSI prototype with its evaluation, and methods for human factors engineering verification and validation.

  17. Review experience on overturning prevention of NPP buildings in Switzerland

    International Nuclear Information System (INIS)

    Buildings with high ratios of the building height to the width of their foundations show a great potential for overturning. This problem occurs under large horizontal actions like Safe Shutdown Earthquake (SSE) or Aircraft Impact (AI). There are different concepts to prevent overturning under these actions. During the design process one concept has to be chosen and investigated. Therefore, calculations need to be done, which can be static or dynamic and linear or non-linear. In most concepts the resistance and the activation potential of the foundation soil are important for the overturning stability. Therefore, the definition of nominal values and design values of the soil has to be done carefully. In most of the cases field testing is required due to non-existing data of the soil. Namely the transmission of tensile forces to the underlying soil or rock has to be supported by experimental verification of the system's behaviour. This paper shows in the first place different possibilities of overturning prevention, which were used at NPP buildings in Switzerland. In the second place a case study of a recently investigated NPP site is presented. Thereby, the potentials and the limitations of static and linear dynamic analysis are discussed and special experiences with non-linear dynamic analysis for earthquake and aircraft scenarios are presented. (authors)

  18. Improvements of Calculating of NPP Aging Management Program Costs

    International Nuclear Information System (INIS)

    NPP(nuclear power plant) AMP(aging management program) involves various costs to carry out plant refurbishments. PLiM(plant lifetime management) consists of many areas including economic evaluation of lifetime extension. In PLiM Phase 1 research project, with PLiMEE(Plant Lifetime Economic Evaluation) computer code we calculated and compared the costs of two cases which have the same assumption that they are providing the same output power for the electric grid. In addition to this assumption, we assumed that the preparation period for plant lie extension is 5 years and beside regular over haul days additional 20 days will be used in the plant refurbishment for that period each year. However, in phase 2, we are going to evaluate the residual life of SSCs(system, structure, components) and AMP will be recommended. In this situation, economic part of project should calculate AMP cost and benefit for plant life extension. In this paper, EPRI and Palisade economic computer codes are reviewed for this purpose, and the algorithms for calculating of NPP AMP costs are found out

  19. Possible satellite oceanography on coastal waters during the NPP stage

    Science.gov (United States)

    Zhu, J.; Asanuma, I.; Zhao, C.; Huang, B.

    2007-09-01

    Ocean color monitoring on the coastal water is still under study because of an incomplete atmospheric correction over the turbid water like over the coastal water along the China main land. Currently available sensors for science as MODIS on Terra or Aqua will terminate their service in the near future and the NPOESS Preparatory Project (NPP) will be the next satellite to support the satellite oceanography on the coastal water. The Tokyo University of Information Sciences (TUIS) has updated the MODIS receiving system to capture and ingest the Visible/Infrared Imager/Radiometer Suite (VIIRS) data from NPP, which will be launched in 2008. Data processing software from the Direct Readout Laboratory (DRL), such as the Real-time Software Telemetry Processing (RT-STPS), Simulcast, and DB algorithms, will be core programs in our system. VIIRS has seven bands in VIS&NIR, which are for ocean color research. The spatial resolution is 0.742×0.259 meters at nadir. While the MODIS spatial resolution of the nine ocean color bands is 1000m. The higher spatial resolution MODIS data (250 meters) is used to illustrate the advantage of the higher spatial resolution remote sensing data, such as data from VIIRS. In this study, we propose to combine the higher spatial resolution data with the traditional products of chlorophyll-a and sea surface temperature in the low resolution so as to extract further information on the coastal ocean.

  20. Status of Chinese NPP Industry and Nuclear Fuel Cycle Policy

    International Nuclear Information System (INIS)

    China still extended their experiences to both domestic and overseas so far. Chinese State Council approved its 'Medium and Long-term Nuclear Power Development Plan' in November 2007, indicating further definition for nuclear energy as indispensable energy option and future self-reliance development of nuclear industry. China intends to become self-sufficient not only in NPPs capacity, but also in the fuel production for all those plants. There are currently 17 NPPs in operation, and 28 NPPs under construction. However, domestic uranium mining supplying is currently less than a quarter of nuclear fuel demands. This paper investigated and summarized the updated status of NPP industry in China and Nuclear Fuel Cycle(NFC) policy. There still remain a number of technical innovation and comprehensive challenges for this nuclear developing country in the long-term, but its large ambitions and dramatic improvements toward future should not be ignored. As shown in this paper, the most suitable approach for China to achieve both environmentally-friendly power supplying and increasing energy demands meeting simultaneously must be considered. Nuclear energy now was recognized as the most potential and optimal way of energy supply system. In addition, to accommodate such a high-speed NPP construction in China, it should also focus on when and how spent nuclear fuel should be reprocessed. Finally, the nuclear back-end fuel cycle policy should be established, taking into accounts of all costs, uranium resource security, spent fuel management, proliferation resistance and environmental impact

  1. Dynamic analysis and safety measures of VVER-440 NPP Paks 1 to 4 due to seismic and operational loading conditions

    International Nuclear Information System (INIS)

    In the course of the gradual safety upgrading of the VVER-440 NPP Paks, the loading capacity of the civil structures due to earthquake loading superposed by operational conditions was analyzed. Based on a three-dimensional detailed finite-element model, several dynamic analyses were performed in the frequency domain for the main building complex of each of the four nuclear units. At first, the bearing capacity of the as-built structure was evaluated, followed by additional calculations considering required and optimized upgrading measures. An additional requirement was that implementation of the upgrading steel elements had to be executed during operation. The effectiveness of different upgrading options for the structures and systems, as well as the implementation feasibility of the upgrading measures and seismic safety, were investigated. For the essential retrofit concept, the mathematical model was updated and the final dynamic response and bearing capacity calculations performed. The excitation was defined by a site-specific design spectrum, with a maximum acceleration of 0.25 g for the horizontal and 0.23 g for the vertical direction. Furthermore, a wide range of soil parameters and the liquefaction effect was considered. The maximum forces and stresses were calculated for the load cases, dead weight, snow loads (NOL), and seismic excitation. In accordance to the specified criteria made for NPP PAKS, the extraordinary loading of earthquake was super-positioned with the other load cases in a realistic manner. The stress results were evaluated by the specific acceptance criteria defined for the seismic requalification of the Paks NPP. As a result of the analysis and the provided upgrading measures, the civil structure is now capable to withstand a horizontal and vertical seismic loading equivalent to the above excitation level. (authors)

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

    International Nuclear Information System (INIS)

    Romania started the nuclear power program about 20 years ago, by a high level Government decision. After 1989 the former Ministry of Electrical Power was transformed into a state owned company, RENEL, in which nuclear activities were also included. RENEL was a monopoly system responsible for production, transport and distribution of electricity in Romania. The deregulation process in the power sector was many times asked by the World Bank and International Monetary Fund, to split this monopoly system in separately activities: Production, Transport and Distribution. The first step occurred in July 1998, when the nuclear activities were externalized from RENEL. In nuclear sector two new entities were created: SN 'Nuclearelectrica' SA, a state own company that includes three branches: - Nuclear Power Production - Cernavoda NPP Unit 1; - Nuclear Fuel Plant-Pitesti; - Project Development Branch - Cernavoda Units 2-5. The second entity is the so-called Romanian Authority (Autonomous Reggie) for Nuclear Activities (RAAN), including as branches the heavy water fabrication plant 'ROMAG PROD', the Nuclear Research Institute (ICN) Pitesti and the Nuclear Engineering and Design Institute (CITON) Bucharest. The rest of conventional power sector was renamed, namely, CONEL. The organization process continued and in August 2000, by a Government Ordinance the CONEL was split into the following companies: - one for hydropower production 'HIDROELECTRICA'; - one for thermal power production 'TERMOELECTRICA'; - one for transport 'TRANSELECTRICA'; - one for distribution 'ELECTRICA'. The goal of a third step of restructuring process is the privatization in the power field. The steps of Romanian Power Sector Restructuring are presented. Since 1991 a Public Information program has been established. Depending on the evolution of the construction of the first Romanian nuclear power station, during the years, the messages changed. Everybody working in the nuclear field knows how difficult is

  3. Selection Methodology Approach to Preferable and Alternative Sites for the First NPP Project in Yemen

    Energy Technology Data Exchange (ETDEWEB)

    Kassim, Moath [Kyunghe Univ., Yongin (Korea, Republic of); Kessel, David S. [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2015-05-15

    The purpose of this paper is to briefly present the methodology and results of the first siting study for the first nuclear power plant (NPP) in Yemen. In this study it has been demonstrated that there are suitable sites for specific unit/units power of 1000 MWt (about 300 MWe) nuclear power plant. To perform the site selection, a systematic selection method was developed. The method uses site-specific data gathered by literature review and expert judgement to identify the most important site selection criteria. A two-step site selection process was used. Candidate sites were chosen that meet a subset of the selection criteria that form the most important system constraints. These candidate sites were then evaluated against the full set of selection criteria using the Analytical Hierarchy Process Method (AHP). Candidate sites underwent a set of more specific siting criteria weighted by expert judgment to select preferable sites and alternatives using AHP method again. Expert Judgment method was used to rank and weight the importance of each criteria, then AHP method used to evaluate and weight the relation between criterion to criterion and between all criteria against the global weight. Then logical decision software was used to rank sites upon their weighting value.

  4. Primary water chemistry for NPP with VVER-TOI

    International Nuclear Information System (INIS)

    Nowadays within the framework of development of the nuclear power industry in Russia the VVER-TOI reactor is under designing (Standard optimized design). The given design provides for improvement of operation safety level, of technical-economic, operational and load-follow characteristics, and for the raise of competitive capacity of reactor plant and NPP as a whole. In VVER-TOI reactor plant design the primary water chemistry has been improved considering operation experience of VVER reactor plants and a possibility of RP operation under load-follow modes from the viewpoint of meeting the following requirements: - suppression of generation of oxidizing radiolytic products under power operation; - assurance of corrosion resistance of structural materials of equipment and pipelines throughout the NPP design service life; - minimization of deposits on surfaces of the reactor core fuel rods and on heat exchange surface of steam generators; - minimization of accumulation of activated corrosion products; - minimization of the amount of radioactive processing waste. In meeting these requirements an important role is devoted to suppression of generation of oxidizing radiolytic products owing to accumulation of hydrogen in the primary coolant. At NPP with VVER-1000 reactor the ammonia-potassium water chemistry is used wherein the hydrogen accumulation is provided at the expense of ammonia proportioning. Usage of ammonia leads to generation of additional amount of radioactive processing waste and to increased irregularity of maintaining the water chemistry under the daily load-follow modes. In VVER TOI design the primary water chemistry is improved by replacing the proportioning of ammonia with the proportioning of gaseous hydrogen. Different process schemes were considered that provide for a possibility of hydrogen accumulation and maintaining owing to direct proportioning of gaseous hydrogen. The obtained results showed that transition to the potassium water chemistry

  5. Structural Integrity Evaluation of Kori-1 NPP Steel Containment for the Replacement of Steam Generator

    International Nuclear Information System (INIS)

    In order to replace the steam generator at Kori unit 1 NPP, in 1998, a comprehensive program for the structural safety evaluation of steel containment was performed. Based on the replacement process, the check list for inspection was made to do the replacement work efficiently and prevent any mistakes. Overall replacement process was appropriately formulated based on regulatory requirements related to nuclear design and repair. As a result of inspection according to the check list, several problems were found such as adhesive defect at interface between old and fresh concrete and appropriately corrected. FEM analysis in order to determine the ultimate load of cylindrical steel shell with opening was performed using ABAQUS. Stress concentration and second order deformation due to crane load was investigated through FEM analysis considering inelastic large deformation. It was verified that the current approximation analysis using combined elastic buckling criteria gives conservative results. The analytical result has shown that the structure follows elastic load-deflection behavior under the given crane load condition with safety factor of 10.3. The result of this study will give useful information to the replacement of the steam generator of a nuclear power plant. In order to replace the steam generator at Kori unit 1 NPP, in 1998, a comprehensive program for the structural safety evaluation of steel containment was performed. Based on the replacement process, the check list for inspection was made to do the replacement work efficiently and prevent any mistakes. Overall replacement process was appropriately formulated based on regulatory requirements related to nuclear design and repair. As a result of inspection according to the check list, several problems were found such as adhesive defect at interface between old and fresh concrete and appropriately corrected. It was recognized that the direct application of the buckling criteria for the Kori-1 SGR seems to be

  6. Role of the Property Engineering in the units' construction of the Cernavoda nuclear power plant; Papel de la ingenieria de la propiedad en la construccion de las nuevas unidades 3 y 4 de la C.N. de Cernavoda (Rumania)

    Energy Technology Data Exchange (ETDEWEB)

    Esteban-Zazo Gomez, J. A.; Varas Suarez, M. I.; Dehalu, J. M.; Giura, A.

    2010-07-01

    The engineering of the property acts as owner's representative to ensure that the technical execution of the work is done according to the specifications. Normally, his paper complements the role of project management often tends to be more focused on the monitoring and supervision of commercial and financial aspects of it.

  7. Interactive analysis of human error factors in NPP operation events

    International Nuclear Information System (INIS)

    Interactive of human error factors in NPP operation events were introduced, and 645 WANO operation event reports from 1999 to 2008 were analyzed, among which 432 were found relative to human errors. After classifying these errors with the Root Causes or Causal Factors, and then applying SPSS for correlation analysis,we concluded: (1) Personnel work practices are restricted by many factors. Forming a good personnel work practices is a systematic work which need supports in many aspects. (2)Verbal communications,personnel work practices, man-machine interface and written procedures and documents play great roles. They are four interaction factors which often come in bundle. If some improvements need to be made on one of them,synchronous measures are also necessary for the others.(3) Management direction and decision process, which are related to management,have a significant interaction with personnel factors. (authors)

  8. Dynamic analysis of the NPP pressure sensor system

    International Nuclear Information System (INIS)

    The aim of the work was to develop on-line methods of control and diagnostic of pressure sensors at a NPP. The analysis was carried out along two lines: i) The detection system including the sensor itself was modeled theoretically to obtain and study its transfer function, and to establish correspondence between the spectral characteristics of the pressure signal. ii) The numerical processing of the signal using the AR technique to reconstruct the transfer function and evaluate the system's response, to a step impulse, as well as the spectral analysis. The hydraulic model presented indicate that the spectral lines observed at ∼ 10 Hz are due to longitudinal oscillations of water in the system branches, while the response time of the detection system is effectively the time of signal retardation in the porous ceramic diaphragms of the δ-cell of the sensor itself. (author)

  9. Safe management of NPP ageing in the European Union

    International Nuclear Information System (INIS)

    The objectives of the study covered by this report consist of providing recommendations for the development of a methodology to monitor, control and anticipate the ageing of Nuclear Islands, in order to maintain their level of safety during the whole NPP life cycle. This is obtained through a synthesis of the potential ageing mechanisms, their potential effects and the available identification and mitigation methods, and an evaluation of the existing ageing management practices in Belgium, France and Spain, using international recommendations as guidance documents. The aspects covered include, in particular, classification of component priorities, identification of degradation phenomena, surveillance methods and preventive maintenance and repair / replacement programs. This synthesis comparison work is the basis for the recommendations issued at the end of the study. (author)

  10. Near Real Time Processing Chain for Suomi NPP Satellite Data

    Science.gov (United States)

    Monsorno, Roberto; Cuozzo, Giovanni; Costa, Armin; Mateescu, Gabriel; Ventura, Bartolomeo; Zebisch, Marc

    2014-05-01

    Since 2009, the EURAC satellite receiving station, located at Corno del Renon, in a free obstacle site at 2260 m a.s.l., has been acquiring data from Aqua and Terra NASA satellites equipped with Moderate Resolution Imaging Spectroradiometer (MODIS) sensors. The experience gained with this local ground segmenthas given the opportunity of adapting and modifying the processing chain for MODIS data to the Suomi NPP, the natural successor to Terra and Aqua satellites. The processing chain, initially implemented by mean of a proprietary system supplied by Seaspace and Advanced Computer System, was further developed by EURAC's Institute for Applied Remote Sensing engineers. Several algorithms have been developed using MODIS and Visible Infrared Imaging Radiometer Suite (VIIRS) data to produce Snow Cover, Particulate Matter estimation and Meteo maps. These products are implemented on a common processor structure based on the use of configuration files and a generic processor. Data and products have then automatically delivered to the customers such as the Autonomous Province of Bolzano-Civil Protection office. For the processing phase we defined two goals: i) the adaptation and implementation of the products already available for MODIS (and possibly new ones) to VIIRS, that is one of the sensors onboard Suomi NPP; ii) the use of an open source processing chain in order to process NPP data in Near Real Time, exploiting the knowledge we acquired on parallel computing. In order to achieve the second goal, the S-NPP data received and ingested are sent as input to RT-STPS (Real-time Software Telemetry Processing System) software developed by the NASA Direct Readout Laboratory 1 (DRL) that gives as output RDR files (Raw Data Record) for VIIRS, ATMS (Advanced Technology Micorwave Sounder) and CrIS (Cross-track Infrared Sounder)sensors. RDR are then transferred to a server equipped with CSPP2 (Community Satellite Processing Package) software developed by the University of

  11. Development of NPP personnel training system in Ukraine

    International Nuclear Information System (INIS)

    Modern personnel training and retraining system is a guarantee of NPPs safe reliable operation. Since the time when independence of Ukraine was proclaimed personnel training system was created directly at NPPs. This system is based on the latest legislation framework, developed subject to IAEA recommendations, gained international experience in the field of personnel training in view of increased demands to personnel qualification. Training Centers, formed at each plant, form one of the main components of NPP personnel training. Personnel training at Training Centers is performed in accordance with standard programmes. Simulator training base was created by joint efforts of specialists from the USA, Russia and Ukraine. Establishing manager training system and replacement reserves for National Nuclear Energy Generating Company 'ENERGOATOM' (NNEGC 'ENERGOATOM') managerial personnel, including training programme and training materials development, teacher selection and training, is under way. (author)

  12. MORE: Management of Requirements in NPP Modernisation Projects, final report

    Energy Technology Data Exchange (ETDEWEB)

    Fredriksen, R.; Katta, V.; Raspotnig, C. (Inst. for energiteknikk (IFE) (Norway)); Valkonen, J. (Technical Research Centre of Finland (VTT) (Finland))

    2008-09-15

    This report documents the work and related activities of the MORE (Management of Requirements in NPP Modernisation Projects) (NKS-R project number NKS-R-2005-47) project. This report also provides a summary of the project activities and deliverables, and discusses possible application areas. The project has aimed at the industrial utilisation of the results from the TACO: (Traceability and Communication of Requirements in Digital I and C Systems Development) (NKS-R project number NKS-R-2002-16, completed June, 2005) project, and practical application of improved approaches and methods for requirements engineering and change management. Finally, the report provides a brief description of the extended industrial network and disseminations of the results in Nordic and NKS related events such as seminars and workshops. (author)

  13. Neutron diffraction measurements of residual stresses in NPP construction materials

    International Nuclear Information System (INIS)

    Neutron diffraction is one of the most powerful methods for condensed matter studies. This method is used for non-destructive determination of residual stresses in material. The fundamental aspects of neutron diffraction are discussed, together with a brief description of the experimental facility. The principal advantage of using neutrons rather than the more conventional X-rays is the fact that neutron can penetrate deeply (2-4 cm for steel and more than 10 cm for aluminium) into metals to determine internal parameters within the bulk of materials. We present results of measurements residual stresses in NPP construction material - austenitic stainless steel (Cr-18%, Ni-10%, Ti-1%) coated with high-nickel alloy. (authors)

  14. Safe management of NPP ageing in European union

    International Nuclear Information System (INIS)

    The paper presents the results of a study conducted by Framatome, EDF, Belgatom, Unesa and IPSN, with the support of the European Commission in order to evaluate the practices and provide recommendations for the development of a methodology to monitor, control and anticipate the ageing of Nuclear Islands, in order to maintain their level of safety during the whole NPP life cycle. The study includes a synthesis of available European and International reports, the identification of potential ageing mechanisms, their effects and the available identification and mitigation methods, and an evaluation of the existing ageing management practices in Belgium, France and Spain, using international recommendations as guidance documents. Recommendations are proposed on regulatory aspects, management, prediction, detection, follow, mitigation of physical ageing, human management and adaptation of safety culture and procedures. (author)

  15. Degradation and Failure Characteristics of NPP Containment Protective Coating Systems

    Energy Technology Data Exchange (ETDEWEB)

    Sindelar, R.L.

    2001-02-22

    A research program to investigate the performance and potential for debris formation of Service Level I coating systems used in nuclear power plant containment is being performed at the Savannah River Technology Center. The research activities are aligned to address phenomena important to cause coating disbondment as identified by the Industry Coatings Expert Panel. The period of interest for performance covers the time from application of the coating through 40 years of service, followed by a medium-to-large break loss-of-coolant accident scenario, which is a design basis accident (DBA) scenario. The interactive program elements are described in this report and the application of these elements to evaluate the performance of the specific coating system of Phenoline 305 epoxy-phenolic topcoat over Carbozinc 11 primer on a steel substrate. This system is one of the predominant coating systems present on steel substrates in NPP containment.

  16. Determination of source term for Krsko NPP extended fuel cycle

    International Nuclear Information System (INIS)

    The activity and composition of the potential radioactive releases (source term) is important in the decision making about off-site emergency measures in case of a release into environment. Power uprate of Krsko NPP during modernization in 2000 as well as changing of the fuel type and the core design have influenced the source term value. In 2003 a project of 'Jozef Stefan' Institute and Slovenian nuclear safety administration determined a plantspecific source term for new conditions of fuel type and burnup for extended fuel cycle. Calculations of activity and isotopic composition of the core have been performed with ORIGEN-ARP program. Results showed that the core activity for extended 15 months fuel cycle is slightly lower than for the 12 months cycles, mainly due to larger share of fresh fuel. (author)

  17. Far-field hydrogeological model of Paks NPP

    International Nuclear Information System (INIS)

    Complete text of publication follows. The settlements in the vicinity of Paks NPP gain the drinking water from the lower Pannonian aquifers. Uncontrolled releases from the NPP enter into the shallow ground-water and they are transported to the Danube in the Quaternary alluvial sandy gravel layer. The hydraulic potential in the area increases with the depth, so leakage from the upper gravel layer to the lower aquifer is not possible in undisturbed circumstances. The question is that an overexploitation of drinking water can change the pressure conditions so that the contaminated water can enter from the upper gravel layer into the lower aquifer. To answer this question the Visual MODFLOW program was used to simulate the groundwater w, providing quantitative estimates of w rates, w paths and travel times. The simulation was designed to represent average steady-state w conditions. A mathematical model is a representation of a real system or process. The subsurface environment constitutes a complex, three-dimensional, heterogeneous hydrogeologic setting, which strongly influences groundwater flow and transport, and it can be described through careful hydrogeologic practice in the field. The conceptual model of the hydrogeological system in the surroundings of Paks NPP was constructed from the available geologic, hydrogeological, geographical and meteorological data. To obtain a unique solution of a generic model corresponding to a given area, additional information about the physical state of the system is required (boundary and initial conditions). The model was constructed on a 20km x 22km area, its eastern boundary is Danube, the others are defined as no w boundaries. The model consists of 5 main layers: upper sequences of Pleistocene alluvial sediments (sandy layer, Kx,y = 10-4m/s); lower sequences of Pleistocene alluvial sediments (gravel, Kx,y = 10-3m/s); upper Pannonian sediments of restricted transmissivity (Kx,y = 5 x 10-6m/s); Pannonian aquifer (Kx,y = 10-4m

  18. Provisions of communication between NPP operational personnel: drifts of development

    International Nuclear Information System (INIS)

    Approaches to the creation of control room systems (CRS) in foreign countries are based on support of operator actions. The basis is the provision of compressed information about safety and technological processes with performance on screens of monitors and by paying special attention to human factors. In contrast to the traditional, the . advantage of such boards consists in granting to the operator a flexible format with the integrated information, with graphic, generalized, etc., representation of the data. When organizing information concerning the: operative personnel, the following principles are fixed: (a) Hierarchical performance of the information about NPP technological process and safety. (b) Provision of fast access to a required format or automatic performance of 8 required format in emergencies. (c) Hierarchical organization of the signal system; a uniform format of display organization. (d) Information support of the operative personnel at normal operation and in accident conditions. (authors)

  19. Use of PSA to prioritize NPP walk down activities

    International Nuclear Information System (INIS)

    Full text of publication follows: an international team of experts, organized by the Institute of Risk Research of the Academic Senate of the University of Vienna, conducted a walk down assessment of the Mochovce Nuclear Power Plant (NPP) in May 1998. The Mochovce NPP is a VVER-440/213 station which has been in final construction and implementation of a safety improvement program since 1996. In preparation for the walk down, available plant design information was organized into a probabilistic safety assessment (PSA) format in order to assist in prioritizing walk down activities. The PSA was also used to understand the likely impact on core damage frequency (CDF) resulting from implementation of the safety improvement program. The PSA employed event trees from the Dukovany PSA, modified to represent the system designs at Mochovce, to assess internal hazards. External hazards were assessed based on an evaluation performed in 1995, with consideration given to upgrades planned to be implemented up to 1998. Failure events were identified directly based on the Dukovany PSA and other sources, and quantified using data from the Dukovany PSA, other non-Mochovce PSAs, and generic data. The PSA was used to identify a suite of dominant accident sequences from internal and external causes. The impact of safety improvements on these sequences was then assessed. The 'pre-fix' and 'post-fix' cases were compared to identify the change in risk due to implementation of the safety improvement program. Following the walk down, the 'post-fix' case was updated based on insights gained from the walk down. This revised case was used to aid in understanding the risk significance of issues identified during the walk down. (author)

  20. Standard protocol for evaluation of environmental transfer factors around NPP sites

    International Nuclear Information System (INIS)

    This document presents the standard procedures for evaluation of site specific environmental transfer factors around NPP sites. The scope of this document is to provide standard protocol to be followed for evaluation of environmental transfer factors around NPP sites. The studies on transfer factors are being carried out at various NPP sites under DAE-BRNS projects for evaluation of site specific transfer factors for radionuclides released from power plants. This document contains a common methodology in terms of sampling, processing, measurements and analysis of elemental/radionuclides, while keeping the site specific requirements also in place. (author)

  1. IJS collaboration within the testing sequence for the NPP Krsko startup program

    International Nuclear Information System (INIS)

    Paper gives a description of work of a group of eight IJS members which have been working as NPP Krsko startup team under a contract between the NPP Krsko and IJS. Our work comprised activities during the core load in May 1981, hot functional testing, initial criticality, low power physical testing, initial synchronisation and 30%, 50%, 75% and 90% test sequences. Our collaboration in full power test sequence is planned for April. After this the testing program will be concluded and NPP Krsko should begin commercial operation. (author)

  2. Evaluation of Armenian NPP main structures dynamic characteristics according to experimental data

    International Nuclear Information System (INIS)

    It was envisaged and performed a complex observations for determination of main structures dynamic characteristics and assessment of ground-structure interaction while dynamic influences (explosions, micro oscillations), within the project of Seismic Conditions Additional Studies or Armenian NPP, in connection with NPP recommissioning Experimental factual materials obtained make a basis for coming to several interesting conclusions on dynamic characteristics of NPP main building and of turbo generators foundations, as well as on interaction level of ground-structure system. (author). 1 ref., 2 figs., 1 tab

  3. Evaluation of Armenian NPP main structures dynamic characteristics according to experimental data

    Energy Technology Data Exchange (ETDEWEB)

    Arakelian, F.; Pogosian, H.; Pirouzian, S. [Armenergyseismicprojects Inst., Yerevan (Armenia)

    1995-12-31

    It was envisaged and performed a complex observations for determination of main structures dynamic characteristics and assessment of ground-structure interaction while dynamic influences (explosions, micro oscillations), within the project of Seismic Conditions Additional Studies or Armenian NPP, in connection with NPP recommissioning Experimental factual materials obtained make a basis for coming to several interesting conclusions on dynamic characteristics of NPP main building and of turbo generators foundations, as well as on interaction level of ground-structure system. (author). 1 ref., 2 figs., 1 tab.

  4. Qualitative and quantitative methods for human factor analysis and assessment in NPP. Investigations and results

    International Nuclear Information System (INIS)

    A description of the most frequently used approaches for human reliability assesment is given. The relation between different human factor causes for human induced events in Kozloduy NPP during the period 2000 - 2003 is discussed. A comparison between the contribution of the casual factors for events occurrences in Kozloduy NPP and an Japanese NPP is presented. It can be concluded that for both NPPs the most important casual factors are: 1) written procedures and documents; 2) man-machine interface; 3) environmental working conditions; 4) working practice; 5) training and qualification; 6) supervising methods

  5. Role and responsibilities of management in NPP personnel training and competence. Working material

    International Nuclear Information System (INIS)

    The main aim and result of this seminar was imparting knowledge to various levels of Paks NPP management on their special tasks and responsibilities to achieve personnel competence, which include: meeting relevant regulatory and other requirements; defining the qualifications for NPP personnel jobs; training using systematic approach to training to attain the required level of qualification and competence of all NPP personnel, which includes management, operations, maintenance and technical support personnel and others; recruiting and retaining qualified personnel, including career development; supporting the training of all personnel on their responsibilities for introducing, maintaining and improving safety. Refs, figs and tabs

  6. Maintenance centered on reliability applied to a NPP auxiliary feedwater system

    International Nuclear Information System (INIS)

    The main objective of maintenance in a NPP is to assure that structures, systems and components will perform their design functions with reliability and/or availability in order to allow a safe and economic electric power generation. Reliability-Centered Maintenance (RCM) is a method of systematic review to either develop or optimize Preventive Maintenance Programs. This paper presents the objectives, concepts, organization and methods used in the application of RCM to NPP. Some application examples are include in this paper, considering some components of the Auxiliary Feedwater System of a generic Westinghouse designed two-loop PWR NPP. (author). 4 refs., 3 figs

  7. Porcine ecto-nucleotide pyrophosphatase/phosphodiesterase 1 (NPP1/CD203a)

    DEFF Research Database (Denmark)

    Petersen, Cathrine Bie; Hillig, Ann-Britt Nygaard; Viuff, Birgitte;

    2007-01-01

    /phosphodiesterase 1 (NPP1/CD203a). The porcine NPP1/CD203a encoding gene was mapped to chromosome 1 using a radiation hybrid panel, and transcription was investigated by RT-PCR analysis of several tissues. The cDNA was cloned and introduced into COS7 cells resulting in expression of functionally active enzyme...... and verification of the specificity of an SWC9 reacting monoclonal antibody. The antibody was used for immunohistochemical examination of various porcine tissues. Most prominent expression of NPP1/CD203a was found in lung macrophages and liver sinusoids....

  8. Comparing cropland net primary production estimates from inventory, a satellite-based model, and a process-based model in the Midwest of the United States

    Energy Technology Data Exchange (ETDEWEB)

    Li, Zhengpeng; Liu, Shuguang; Tan, Zhengxi; Bliss, N.; Young, Claudia J.; West, Tristram O.; Ogle, Stephen

    2014-05-06

    Accurately quantifying the spatial and temporal variability of net primary production (NPP) for croplands is essential to understand regional cropland carbon dynamics. We compared three NPP estimates for croplands in the Midwestern United States: inventory-based estimates using crop yield data from the U.S. Department of Agriculture (USDA) National Agricultural Statistics Service (NASS); estimates from the satellite-based Moderate Resolution Imaging Spectroradiometer (MODIS) NPP product; and estimates from the General Ensemble biogeochemical Modeling System (GEMS) process-based model. The three methods estimated mean NPP in the range of 469–687 g C m-2 yr-1 and total NPP in the range of 318–490 Tg C yr-1 for croplands in the Midwest in 2007 and 2008. The NPP estimates from crop yield data and the GEMS model showed the mean NPP for croplands was over 650 g C m-2 yr-1 while the MODIS NPP product estimated the mean NPP was less than 500 g C m-2 yr-1. MODIS NPP also showed very different spatial variability of the cropland NPP from the other two methods. We found these differences were mainly caused by the difference in the land cover data and the crop specific information used in the methods. Our study demonstrated that the detailed mapping of the temporal and spatial change of crop species is critical for estimating the spatial and temporal variability of cropland NPP. Finally, we suggest that high resolution land cover data with species–specific crop information should be used in satellite-based and process-based models to improve carbon estimates for croplands.

  9. Atucha II NPP full scope simulator modelling with the thermal hydraulic code TRACRT

    International Nuclear Information System (INIS)

    In February 2010 NA-SA (Nucleoelectrica Argentina S.A.) awarded Tecnatom the Atucha II full scope simulator project. NA-SA is a public company owner of the Argentinean nuclear power plants. Atucha II is due to enter in operation shortly. Atucha II NPP is a PHWR type plant cooled by the water of the Parana River and has the same design as the Atucha I unit, doubling its power capacity. Atucha II will produce 745 MWe utilizing heavy water as coolant and moderator, and natural uranium as fuel. A plant singular feature is the permanent core refueling. TRACRT is the first real time thermal hydraulic six-equations code used in the training simulation industry for NSSS modeling. It is the result from adapting to real time the best estimate code TRACG. TRACRT is based on first principle conservation equations for mass, energy and momentum for liquid and steam phases, with two phase flows under non homogeneous and non equilibrium conditions. At present, it has been successfully implemented in twelve full scope replica simulators in different training centers throughout the world. To ease the modeling task, TRACRT includes a graphical pre-processing tool designed to optimize this process and alleviate the burden of entering alpha numerical data in an input file. (author)

  10. On the problem of utilization of NPP low-temperature heat

    International Nuclear Information System (INIS)

    Results of evaluating utilization of NPP low-temperature heat for cultivating bioproducts in heat-exchanger hot-houses are given. The calculations are conducted as applied to the K-750-65/3000 turbine. The temperature of cooling water at the condenser outlet is taken to be equal to 60 deg C. The pressure in the condenser at that increases from 3.9 kPa up to 22 kPa, the electric plant output decreases by 85 MW (11%), the electric efficiency decreases from 33.6% down to 29.8%, the specific steam volume at the turbine outlet decreases from 31 down to 6.9 m3/kg. It results in a decrease in the number of low-pressure cylinders, which leads to a reduction in the turbine length from 41.4 down to 16-20 m. The heat from the K-750 turbine will enable to warm up 300 ha if heat consumption per unit of usable area equals (6-8)x106 kJ, . which can provide 7500 t of dry protein mass per year. The detailed analysis shows that losses due to electric energy deficit will be compensated under the given conditions

  11. Progress in Low and Intermediate Level Operational Waste Characterization and Preparation for Disposal at Ignalina NPP

    International Nuclear Information System (INIS)

    In Lithuania about 70-80% of all electricity is generated at a single power station, Ignalina NPP, which has two RBMK-1500 type reactors. Units 1 and 2 will be closed by 2005 and 2010, respectively, taking into account the conditions of the long-term substantial financial assistance rendered by the European Union, G-7 countries and other states as well as international institutions. The Government approved the Strategy on Radioactive Waste Management. Objectives of this strategy are to develop the radioactive waste management infrastructure based on modern technologies and provide for the set of practical actions that shall bring management of radioactive waste in Lithuania in compliance with radioactive waste management principles of IAEA and with good practices in force in European Union Member States. SKB-SWECO International-Westinghouse Atom Joint Venture with participation of Lithuanian Energy Institute has prepared a reference design of a near surface repository for short-lived low and intermediate level waste. This reference design is applicable to the needs in Lithuania, considering its hydro-geological, climatic and other environmental conditions and is able to cover the expected needs in Lithuania for at least thirty years ahead. Development of waste acceptance criteria is in practice an iterative process concerning characterization of existing waste, repository development, safety and environmental impact assessment etc. This paper describes the position in Lithuania with regard to the long-term management of low and intermediate level waste in the absence of finalized waste acceptance criteria and a near surface repository

  12. Seismic site evaluation practice and seismic design guide for NPP in Continent of China

    Energy Technology Data Exchange (ETDEWEB)

    Hu Yuxian [State Seismological Bureau, Beijing, BJ (China). Inst. of Geophysics

    1997-03-01

    Energy resources, seismicity, NPP and related regulations of the Continent of China are briefly introduced in the beginning and two codes related to the seismic design of NPP, one on siting and another on design, are discussed in some detail. The one on siting is an official code of the State Seismological Bureau, which specifies the seismic safety evaluation requirements of various kinds of structures, from the most critic and important structures such as NPP to ordinary buildings, and including also engineering works in big cities. The one on seismic design of NPP is a draft subjected to publication now, which will be an official national code. The first one is somewhat unique but the second one is quite similar to those in the world. (author)

  13. Joint probability safety assessment for NPP defense infrastructure against extreme external natural hazards

    Energy Technology Data Exchange (ETDEWEB)

    Guilin, L. [College of Engineering, Ocean Univ. ot China, Yushan Road No. 5, Qingdao 266003 (China); Defu, L. [Disaster Prevention Research Inst., Ocean Univ. ot China, Yushan Road No. 5, Qingdao 266003 (China); Huajun, L. [College of Engineering, Ocean Univ. ot China, Yushan Road No. 5, Qingdao 266003 (China); Fengqing, W. [Disaster Prevention Research Inst., Ocean Univ. of China, Songling Road No.238, Qingdao 266100 (China); Tao, Z. [College of Engineering, Ocean Univ. of China, Songling Road No.238, Qingdao 266100 (China)

    2012-07-01

    With the increasing tendency of natural hazards, the typhoon, hurricane and tropical Cyclone induced surge, wave, precipitation, flood and wind as extreme external loads menacing Nuclear Power Plants (NPP) in coastal and inland provinces of China. For all of planned, designed And constructed NPP the National Nuclear Safety Administration of China and IAEA recommended Probable Maximum Hurricane /Typhoon/(PMH/T), Probable Maximum Storm Surge (PMSS), Probable Maximum Flood (PMF), Design Basis Flood (DBF) as safety regulations for NPP defense infrastructures. This paper discusses the joint probability analysis of simultaneous occurrence typhoon induced extreme external hazards and compare with IAEA 2006-2009 recommended safety regulation design criteria for some NPP defense infrastructures along China coast. (authors)

  14. Safety improvement and results of commissioning of Mochovce NPP WWER 440/213

    International Nuclear Information System (INIS)

    Mochovce NPP is the last one of this kind and compared to its predecessors, it is characterized by several modifications which contribute to the improvement of the safety level. In addition based on Nuclear Regulatory Authority requirements and based on documents: - IAEA - Safety Issues and their ranking for NPP WWER 440/213, - IAEA - Safety Improvement of Mochovce NPP Project Review Mission, - Riskaudit - Evaluation of the Mochovce NPP Safety Improvements. Additional safety measures have been implemented before commissioning. The consortium EUCOM (FRAMATOME - SIEMENS), SKODA Praha, ENERGOPROJEKT Praha, Russian organizations and VUJE Trnava Nuclear Power Plants research institute were selected for design and implementation of the safety measures. The papers summarized, safety requirements, safety measures implemented, results of commissioning and results of safety analysis report evaluation. (author)

  15. Planning and management support for NPP personnel SAT-based training programmes

    International Nuclear Information System (INIS)

    Planning and management support for NPP personnel SAT-based training programmes is described for the following job positions: reactor operator; turbine operator; reactor maintenance worker; pump maintenance worker; chemistry foreman; health physics foreman; electric maintenance worker

  16. VIIRS Climate Raw Data Record (C-RDR) from Suomi NPP, Version 1

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Suomi NPP Climate Raw Data Record (C-RDR) developed at the NOAA NCDC is an intermediate product processing level (NOAA Level 1b) between a Raw Data Record (RDR)...

  17. On geological and geophysical safety of the new state confinement for ChNPP-4

    International Nuclear Information System (INIS)

    The paper considers evidences and mechanisms of potential impact of local depression (microgeodynamic) zones on NPP safety. The depression forms were revealed within the Chornobyl NPP site, including location of the new safe confinement. Nature of zones and character of their influence is determined by fault structures and conjugated deep degassing processes, which cannot be detected and studied by traditional methods of engineering and exploration works during NPP siting. The assumption was made that significant and still unexplored risks for nuclear facilities are related to probable release of deep hydrogen through the bottom of depressions along sub-bottom channels. The approaches were proposed to studying the system of 'depression with its sub-bottom channel' within the sites of Chornobyl NPP and other nuclear power plants

  18. Information on current status of equipment and activities for extension of NPP Kozloduy life time

    International Nuclear Information System (INIS)

    The NPP Kozloduy personnel activities are described directed to undertake measures to overcome the difficulties entailed by equipment failures and human errors in order to avoid recurrent emergency events and to reduce their total numbers. 12 figs, 2 tabs

  19. Joint probability safety assessment for NPP defense infrastructure against extreme external natural hazards

    International Nuclear Information System (INIS)

    With the increasing tendency of natural hazards, the typhoon, hurricane and tropical Cyclone induced surge, wave, precipitation, flood and wind as extreme external loads menacing Nuclear Power Plants (NPP) in coastal and inland provinces of China. For all of planned, designed And constructed NPP the National Nuclear Safety Administration of China and IAEA recommended Probable Maximum Hurricane /Typhoon/(PMH/T), Probable Maximum Storm Surge (PMSS), Probable Maximum Flood (PMF), Design Basis Flood (DBF) as safety regulations for NPP defense infrastructures. This paper discusses the joint probability analysis of simultaneous occurrence typhoon induced extreme external hazards and compare with IAEA 2006-2009 recommended safety regulation design criteria for some NPP defense infrastructures along China coast. (authors)

  20. Regression tree modeling of forest NPP using site conditions and climate variables across eastern USA

    Science.gov (United States)

    Kwon, Y.

    2013-12-01

    , Forest Service) data set for the 31 eastern most United States. Second, 8-day composite of MODIS Land Cover, FPAR, LAI and GPP/NPP data were obtained from Jan 2001 to Dec 2004 (total 182 composite) and each product were filtered by pixel-level quality assurance data to select best quality pixels. Third, 30-year averaged climate data were collected from National Oceanic and Atmospheric Administration (NOAA) and five climatic variables were obtained: Monthly temperature, precipitation, annual heating and cooling days, and annual frost-free days. Forth, topographic data were obtained from digital elevation model (1km by 1km). This research will provide a better understanding of large-scale forest responses to environmental factors that will be beneficial for the development of important forest management applications.

  1. Mochovce Unit 3 and 4 Completion

    International Nuclear Information System (INIS)

    Purpose of the Feasibility Study was to define in detail all technical, economic, financial, legal and authorization aspects of Mochovce NPP Unit 3 and 4 completion in order to provide Slovenske Elektrarne, a. s. (SE) and ENEL Top Management with all the necessary information for a final decision on Mochovce Unit 3 and 4. Feasibility study has started in January 2006. SE had the commitment to complete the Feasibility Study within 12 months from Closing of SE acquisition (April 2007). In order not to delay completion of Mochovce Unit 3 and 4, SE has decided to perform, in parallel to the Feasibility study, also all design and permitting activities which are required for the completion of Plant. This has involved anticipation of expenses for approximately 700 MSKK (or approx. 20 MEuro). SE was able to announce the positive decision about completion on Mochovce NPP Unit 3 and 4, two months in advance of the deadline.

  2. Observation and modeling of NPP for Pinus elliottii plantation in subtropical China

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    Based on the stem analysis of 59 individuals of Pinus elliottii in combination with tree biomass models, we calculated annual biomass increment of forest plots at Qianyanzhou Ecological Station, Chinese Academy of Sciences in subtropical China. In addition, canopy layer and community NPP were calcu- lated based on 12 years’ litter fall data. NPP of the 21-year-old forest was estimated by using the BIOME BGC model; and both measured NPP and estimated NPP were compared with flux data. Community biomass was 10574 g·m-2; its distribution patterns in tree layer, shrub layer, herbaceous layer, tree root, herbaceous and shrub roots and fine roots were 7542, 480, 239, 1810, 230, 274 and 239 g·m-2, respectively. From 1999 to 2004, the average annual growth rate and litter fall were 741 g·m-2·a-1 (381.31 gC·m-2·a-1) and 849 g·m?2·a?1 (463 gC·m-2·a-1), respectively. There was a significant corre- lation between annual litter fall and annual biomass increment; and the litter fall was 1.19 times the biomass increment of living trees. From 1985 to 2005, average NPP and GPP values based on BGC modeling were 630.88 (343.31 - 906.42 gC·m-2·a-1) and 1 800 gC·m-2·a-1 (1351.62 - 2318.26 gC·m-2·a-1). Regression analysis showed a linear relationship (R2=0.48) between the measured and simulated tree layer NPP values. NPP accounted for 30.2% (25.6%-32.9%) of GPP, while NEP ac- counted for 57.5% (48.1%-66.5%) of tree-layer NPP and 41.74% (37%-52%) of stand NPP. Soil respi- ration accounted for 77.0% of measured tree NPP and 55.9% of the measured stand NPP. NEE based on eddy covariance method was 12.97% higher than the observed NEP.

  3. Towards the Seismic Hazard Reassessment of Paks NPP (Hungary) Site: Seismicity and Sensitivity Studies

    Science.gov (United States)

    Toth, Laszlo; Monus, Peter; Gyori, Erzsebet; Grenerczy, Gyula; Janos Katona, Tamas; Kiszely, Marta

    2015-04-01

    In context of extension of Paks Nuclear Power Plant by new units, a comprehensive site seismic hazard evaluation program has been developed that is already approved by the Hungarian Authorities. This includes a 3D seismic survey, drilling of several deep boreholes, extensive geological mapping, and geophysical investigations at the site and its vicinity, as well as on near regional, and regional scale. Furthermore, all relevant techniques of modern space geodesy (GPS, PSInSAR) will be also utilized to construct a new seismotectonic model. The implementation of the project is still in progress. In the presentation, some important elements of the new seismic hazard assessment are highlighted, and some results obtained in the preliminary phase of the program are presented and discussed. The first and most important component of the program is the compilation of the seismological database that is developed on different time scale zooming on different event recurrence rates such as paleo-earthquakes (10-1/a). In 1995, Paks NPP installed and started to operate a sensitive microseismic monitoring network capable for locating earthquakes as small as magnitude 2.0 within about 100 km of the NPP site. During the two decades of operation, the microseismic monitoring network located some 2,000 earthquakes within the region of latitude 45.5 - 49 N and longitude 16 - 23 E. Out of the total number of events, 130 earthquakes were reported as 'felt events'. The largest earthquake was an event of ML 4.8, causing significant damage in the epicenter area. The results of microseismic monitoring provide valuable data for seismotectonic modelling and results in more accurate earthquake recurrence equations. The first modern PSHA of Paks NPP site was carried out in 1995. Complex site characterization project was implemented and hazard curves had been evaluated for 10-3 - 10-5 annual frequency. As a follow-up, PSHA results have been reviewed and updated in the frame of periodic safety

  4. The impact of the Ignalina NPP and Visaginas town on the economy of the region

    International Nuclear Information System (INIS)

    The present article is devoted to the influence of Visaginas town and Ignalina NPP on economy in the surrounding region. Preliminary the region includes the Ignalina and Zarasai administrative districts. However, these boundaries are relative. The analysis of the influence of Visaginas town and Ignalina NPP on the economy in the region revealed that such an influence exists, however, it is not as distinct as could have been expected from the town of such size. The influence on economy of the region includes influence on markets of economic resources (labour force and real estate markets were analyzed), influence on consumption market, influence on industries and services (the appearance of new manufacturing enterprises in the town itself, where, excluding the NPP, the economic sector is rather poorly developed, and the impact of the town on the enterprises of considered region were analyzed) and the influence on conditions for investment in the region. After the building Ignalina NPP and Visaginas the distribution of surrounding forests into protective categories has changed. The Ignalina NPP and Visaginas directly posses 1250 ha of forests. The influence of the town and Ignalina NPP on the enterprises of industry of considered region is important because Visaginas serving as a good market for various manufacturing enterprises makes it possible for them to maintain a certain economic level and have better profits. This aspect is extremely important for food and light industries. The extraction and building industry as well as many other branches of industries were most highly influenced during the building works of NPP. At present the building works meet only the current requirements of NPP and so they are not very intensive. The influence on consumption markets is more noticeable. With the building of Visaginas town consumption market of the region increased more than three times. The demand in the region increased as well as supply. The incomes of people in the

  5. Virtual reality in design, planning, operation and training related to the decommissioning of the Chernobyl NPP

    International Nuclear Information System (INIS)

    Virtual Reality in refueling operation and maintenance training at Leningrad NPP has been recognized by Chernobyl NPP. Institute for Energy Technology's is establishing now the Chernobyl Decommissioning Visualization Centre to be used for planning and training the dismantling procedures in addition to presenting it to the authorities and the public. It will be ready in 2007. The first scenario will be the dismantling of the refueling machines

  6. Ageing management and Long-term operation of NPP structures and components

    International Nuclear Information System (INIS)

    The paper presents methodological aspects for ageing management and long-term operation of NPP structures and components considering experience accumulated in nuclear area of Ukraine and IAEA recommendations. The research shows the role of ageing management for lifetime extension and justification of long-term operation of NPP structures and components. The given information is recommended to be used during development of regulatory and technical documents on ageing management and long-term operation

  7. Underground NPP of mean and low power on the basis of ship nuclear technologies

    International Nuclear Information System (INIS)

    The principles of creating underground NPPs, melting higher requirements of nuclear and radiation safety, are described. The proposed NPP with the Pb-Bi-cooled fast neutron reactor is characterized by inherent self-protection, excluding origination of radiation-hazardous incidents. The experience of creation and operation of the reactors with the Pb-Bi coolant, accumulated by their application on submarines, may be used by developing such a NPP

  8. Analysis of quality control efficiency for NPP pipeline welded joints using nondestructive methods

    International Nuclear Information System (INIS)

    The problems of improving the quality of nondestructive examination for welded joints of NPP cooling system pipelines are considered. The data of ultrasonic testing and radiography of the welded joints of pipelines 800 mm in-diameter at the Smolensk and Kursk NPPs are analyzed. The conclusion on the necessity of accurate fulfilment of the existing PN AEh G-7-010-89 Rules of testing during NPP contruction and operation is made

  9. The principles, terms and responsibilities contained in the Romanian legislation related to coverage of risk in nuclear activities developed by Societatea Nationala Nuclearelectrica SA

    International Nuclear Information System (INIS)

    Societatea Nationala ''NUCLEARELECTRICA'' (SNN) SA, a Romanian state owned stock company, established in July 1998, following the restructuring of RENEL, the former centralized Romanian Utility is the Owner of the Cernavoda Nuclear Power Plant and has three main branches: ''CNE Prod'', operating Unit 1 Cernavoda NPP; 'CNE Invest'', including Units no.2 to 5, actually in charge with the completion of Unit 2; ''FCN - Pitesti'', the nuclear fuel factory. Cernavoda NPP project is based technology transfer process from Canada, Italy and United States for CANDU 6 reactor type. The transfer of technology covers mainly nuclear island, secondary cycle and turbo - generator. Romania has a well developed nuclear infrastructure. Heavy water plant (ROMAG). Fuel fabrication facility (FCN). Technically qualified CANDU experienced staff. Nuclear R and D program. This places Romania in an excellent position to optimize their resources and nuclear infrastructure with the construction and the operation of Cernavoda 2 and 3. Romania is part of Non Proliferation Treaty, Third Part Liability Convention, Nuclear Safety Convention, etc.. The Romanian nuclear regulations are in line with the European Community legislation. In accordance with general international practices of Nuclear Operators and with the International and National specific Legislation regulating the nuclear activities in Romania, Nuclear All Risk - Material Damage and Nuclear Liability insurance policies and placed by SOCIETATEA NATIONALA NUCLEARELECTRICA to the international nuclear ''pools'' from February 1995. Regarding the environmental protection, each unit of Cernavoda NPP can accommodate spent fuel for ten years of full operation. Furthermore, Romania is developing radioactive waste management programs and adopting concepts recognized worldwide (interim dry storage, near surface repository for low and medium level waste). The final repository of the nuclear spent fuel is subject to future decision. Based on the

  10. Radionuclides contamination of fungi after accident on the Chernobyl NPP

    Energy Technology Data Exchange (ETDEWEB)

    Zarubina, Nataliia E.; Zarubin, Oleg L. [Institute for Nuclear Research of National Academy of Sciense, 03680, pr-t Nauki, 47, Kiev (Ukraine)

    2014-07-01

    Accumulation of radionuclides by the higher fungi (macromycetes) after the accident on the Chernobyl atomic power plant in 1986 has been studied. Researches were spent in territory of the Chernobyl alienation zone and the Kiev region. Our research has shown that macromycetes accumulate almost all types of radionuclides originating from the accident ({sup 131}I, {sup 140}Ba /{sup 140}La, {sup 103}Ru, {sup 106}Ru, {sup 141}Ce, {sup 144}Ce, {sup 95}Nb, {sup 95}Zr, {sup 137}Cs and {sup 134}Cs). They accumulate the long-living {sup 90}Sr in much smaller (to 3 - 4 orders) quantities than {sup 137}Cs. We have established existence of two stages in accumulation of {sup 137}Cs by higher fungi after the accident on the Chernobyl NPP: the first stage resides in the growth of the concentration, the second - in gradual decrease of levels of specific activity of this radionuclide. Despite reduction of {sup 137}Cs specific activity level, the content of this radionuclide at testing areas of the 5-km zone around the Chernobyl NPP reaches 1,100,000 Bq/kg of fresh weight in 2013. We investigated dynamics of accumulation of Cs-137 in higher fungi of different ecological groups. One of the major factors that influence levels of accumulation of {sup 137}Cs by fungi is their nutritional type (ecological group). Fungi that belong to ecological groups of saprotrophes and xylotrophes accumulate this radionuclide in much smaller quantities than symbio-trophic fungi. As a result of the conducted research it has been established that symbio-trophic fungi store more {sup 137}Cs than any other biological objects in forest ecosystems. Among the symbio-trophic fungi species, species showing the highest level of {sup 137}Cs contamination vary in different periods of time after the deposition. It is connected with variability of quantities of these radio nuclides accessible for absorption at the depth of localization of the main part of mycelium of each species in a soil profile. Soil contamination

  11. A1 NPP Decommissioning, Slovakia. Annex A.I-6

    International Nuclear Information System (INIS)

    The first pilot NPP in the former Czechoslovakia was A1, which was built at Jaslovske Bohunice near the town of Trnava. An NPP with a capacity of 143 MW(e), it was commissioned in 1972 and operated with interruptions until 1977. A KS-150 reactor with natural uranium as fuel, D2O as moderator and gaseous CO2 as coolant was installed in the plant. The first serious accident associated with refuelling occurred in 1976, when a locking mechanism at a fuel assembly failed. The core was not damaged during that accident and after reconstruction of the damaged technology channel, the plant resumed operation. The second serious accident (level 4 according to the International Nuclear Event Scale) occurred in 1977, when a fuel assembly overheated, causing release of D2O into the gas cooling circuit. This accident was attributed to human error during replacement of a fuel assembly. Subsequent rapid humidity increase in the primary system resulted in damage to fuel elements in the core, and the primary system was contaminated by fission products. Internal reactor structures were also damaged. Radioactive contaminants penetrated into parts of the secondary system by leaking through steam generators. The radiation impact on and around the plant site was below specified limits for both events. Based on a technical and economic study of the difficult equipment repairs needed to restore plant operation, and also due to the policy decision to discontinue further construction of gas cooled reactors in the former Czechoslovakia, a decision was made in 1977 to terminate plant operation. The decision to proceed with the A1 plant decommissioning was issued in 1979. Beginning in 1981, decommissioning proceeded with disassembly of equipment from the secondary system (process equipment in the machine hall, turbines with auxiliaries, feed water tanks, diesel generator station, pumps, cooling towers, electric equipment). At the same time, other systems were disassembled, which included turbine

  12. Assessing deposition levels of {sup 55}Fe, {sup 60}Co and {sup 63}Ni in the Ignalina NPP environment

    Energy Technology Data Exchange (ETDEWEB)

    Gudelis, A., E-mail: gudelis@ktl.mii.l [Nuclear and Environmental Radioactivity Research Laboratory, Institute of Physics, Savanoriu Avenue, 231, LT-02300 Vilnius (Lithuania); Druteikiene, R.; Luksiene, B.; Gvozdaite, R. [Nuclear and Environmental Radioactivity Research Laboratory, Institute of Physics, Savanoriu Avenue, 231, LT-02300 Vilnius (Lithuania); Nielsen, S.P.; Hou, X. [Riso National Laboratory for Sustainable Energy, Technical University of Denmark, P.O. Box 49, DK-4000, Roskilde (Denmark); Mazeika, J.; Petrosius, R. [Radioisotope Laboratory, Institute of Geology and Geography, Sevcenkos Street, 13, LT-03223 Vilnius (Lithuania)

    2010-06-15

    Two RBMK-1500 reactor units operated in Lithuania in the 1987-2004 period (one of them was stopped for decommissioning in 2004). This study presents a preliminary investigation of surface deposition density levels of {sup 55}Fe and {sup 63}Ni in moss samples collected in the close vicinity of the Ignalina NPP. Non-destructive analysis by the HPGe gamma-spectrometry was followed by radiochemical separation. Radiochemical analysis was based on anion-exchange and extraction chromatography. {sup 55}Fe and {sup 63}Ni activities were measured by liquid scintillation counting (LSC). The results indicate that the deposition values of {sup 55}Fe are generally higher than those of {sup 60}Co and {sup 63}Ni.

  13. Leningrad NPP full scope and analytical simulators as tools for MMI improvement and operator support systems development and testing

    International Nuclear Information System (INIS)

    Training Support Center (TSC) created at the Leningrad NPP (LNPP), Sosnovy Bor, Russia, incorporates full-scope and analytical simulators working in parallel with the prototypes of the expert and interactive systems to provide a new scope of R and D MMI improvement work as for the developer as well as for the user. Possibilities of development, adjusting and testing of any new or up-graded Operators' Support System before its installation at the reference unit's Control Room are described in the paper. These Simulators ensure the modeling of a wide range of accidents and transients and provide with special software and ETHERNET data process communications with the Operators' Support systems' prototypes. The development and adjustment of two state-of-the-art Operators' Support Systems of interest with using of Simulators are described in the paper as an example. These systems have been developed jointly by RRC KI and LNPP team. (author)

  14. Prioritization of Delay Factors for NPP Construction Risk in International Project by Using AHP Methodology

    Energy Technology Data Exchange (ETDEWEB)

    Hossen, Muhammed Mufazzal; Kang, Sunkoo; Kim, Jonghyun [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-10-15

    It is crucial for the nuclear power plant project decision makers and management personnel to identify the actual factors of construction delay and their ranking in order to take preventive actions. NPP project is complex in nature and the construction phase is one of the most key phase which is subject to many factors result from many sources. From experience, nuclear projects have faced challenges similar to other complex mega projects with additional nuclear specific issues and life time cost of nuclear reactor is concentrated upfront as capital cost, and therefore delays in construction may become intolerable in terms of both lost revenues and interest on the capital. Budget over-runs and delays on next generation new build nuclear projects in recent years clearly demonstrate that the nuclear industry continues to repeat its failed management and project control processes of the past. Similar to major infra-structure projects, actual completion times can vary substantially from initial estimates but this uncertainty is too crucial to the nuclear industry due to high levels of capital at risk, for every year a project is delayed the levelized cost of electricity increases by approximately 8-10%. causes of delay, to develop a generalized AHP model for delay factors, and to prioritize the risk in different factors in various levels of construction phase in international turnkey NPP project. This paper describes and prioritizes Nuclear Power Plant (NPP) construction schedule delay factor for turnkey international project. This study also determines the different party's importance in percentage behind the construction schedule delay of NPP which constitutes main contractor (28.4%), regulatory authority (27.3%), financial and country factor (23.5%), and utility (20.8%). Decision makers of nuclear industry can understand the significance of different factors on NPP construction phase and they can apply risk informed decision making to avoid unexpected

  15. NPP simulator NSSS model validation the Krsko example

    International Nuclear Information System (INIS)

    NPP Krsko has obtained, as part of the plant modernization, a plant-specific full scope simulator with the capability to support in real-time, training for the complete range of operations which can be performed from the main control room and from other selected plant areas (remote shutdown panels, etc). Due to the requested approach the simulator was developed and validated in two distinct steps. First, it was validated for plant conditions in effect before SG replacement and power uprate (Cycle 15 and before); then a second step of validation was performed before and after initial startup in Cycle 17 (after SG replacement and power uprate). This approach gave NEK and CAE the opportunity to test extensively and validate the simulator based on real plant data as well as on the results of design basis accidents, i.e. transients. In this paper we focus on the validation of the NSSS model, based on real plant transients only. For comparison we also provide results obtained using more sophisticated thermohydraulic analysis tools, such as RELAP 5/mod2. (author)

  16. Derived Land Surface Emissivity From Suomi NPP CrIS

    Science.gov (United States)

    Zhou, Daniel K.; Larar, Allen M.; Liu, Xu

    2012-01-01

    Presented here is the land surface IR spectral emissivity retrieved from the Cross-track Infrared Sounder (CrIS) measurements. The CrIS is aboard the Suomi National Polar-orbiting Partnership (NPP) satellite launched on October 28, 2011. We describe the retrieval algorithm, demonstrate the surface emissivity retrieved with CrIS measurements, and inter-comparison with the Infrared Atmospheric Sounding Interferometer (IASI) emissivity. We also demonstrate that surface emissivity from satellite measurements can be used in assistance of monitoring global surface climate change, as a long-term measurement of IASI and CrIS will be provided by the series of EUMETSAT MetOp and US Joint Polar Satellite System (JPSS) satellites. Monthly mean surface properties are produced using last 5-year IASI measurements. A temporal variation indicates seasonal diversity and El Nino/La Nina effects not only shown on the water but also on the land. Surface spectral emissivity and skin temperature from current and future operational satellites can be utilized as a means of long-term monitoring of the Earth's environment. CrIS spectral emissivity are retrieved and compared with IASI. The difference is small and could be within expected retrieval error; however it is under investigation.

  17. Analysis of seismic isolation problems of NPP buildings

    International Nuclear Information System (INIS)

    Conventional seismic design of earthquake-resistant structures is based on the philosophy conditions that the structural safety must be assured in extreme earthquake and the possible damage, if any, should be minimized or avoided in moderate earthquake ones. In the recent years the technique of seismic isolation appeared suitable to provide protection of buildings against seismic loadings introducing isolation devices (i.e. isolators) between the building itself and the foundation that may be adequate to shift the structures fundamental frequency outside the seismic characteristic range. The aim of this paper is to evaluate the influence of high damping rubber bearings, like the lead rubber ones, in the propagation of dynamic loading along NPP buildings. To this purpose a numerical approach was applied setting up suitable finite element models of the possible Generation III+ or IV NPPs. The influence of the isolator characteristics on the response of structures is analysed considering the variation of important parameters like the superstructure flexibility, isolation time period, etc. Several seismic analyses were therefore performed assuming as input different real earthquake ground motions as available in literature and in the relevant rules. The obtained results were herein presented and discussed in order to highlight the isolation technique effectiveness. (authors)

  18. Analysis of Steam Generators Corrosion Products from Slovak NPP Bohunice

    Directory of Open Access Journals (Sweden)

    Jarmila Degmová

    2012-01-01

    Full Text Available One of the main goals of the nuclear industry is to increase the nuclear safety and reliability of nuclear power plants (NPPs. As the steam generator (SG is the most corrosion sensitive component of NPPs, it is important to analyze the corrosion process and optimize its construction materials to avoid damages like corrosion cracking. For this purpose two different kinds of SGs and its feed water distributing systems from the NPP Jaslovske Bohunice were studied by nondestructive Mössbauer spectroscopy. The samples were scraped from the surface and analyzed in transmission geometry. Magnetite and hematite were found to be the main components in the corrosion layers of both SGs. Dependant of the material the SG consisted of, and the location in the system where the samples were taken, the ratios between magnetite and hematite and the paramagnetic components were different. The obtained results can be used to improve corrosion safety of the VVER-440 secondary circuit as well as to optimize its water chemistry regime.

  19. Safety analyses of the electrical systems on VVER NPP

    International Nuclear Information System (INIS)

    Energoprojekt Praha has been the main entity responsible for the section on 'Electrical Systems' in the safety reports of the Temelin, Dukovany and Mochovce nuclear power plants. The section comprises 2 main chapters, viz. Offsite Power System (issues of electrical energy production in main generators and the link to the offsite transmission grid) and Onsite Power Systems (AC and DC auxiliary system, both normal and safety related). In the chapter on the off-site system, attention is paid to the analysis of transmission capacity of the 400 kV lines, analysis of transient stability, multiple fault analyses, and probabilistic analyses of the grid and NPP power system reliability. In the chapter on the on-site system, attention is paid to the power balances of the electrical sources and switchboards set for various operational and accident modes, checks of loading and function of service and backup sources, short circuit current calculations, analyses of electrical protections, and analyses of the function and sizing of emergency sources (DG sets and UPS systems). (P.A.)

  20. Suomi NPP VIIRS Striping Analysis using Radiative Transfer Model Calculations

    Science.gov (United States)

    Wang, Z.; Cao, C.

    2015-12-01

    Modern satellite radiometers such as VIIRS have many detectors with slightly different relative spectral response (RSR). These differences can introduce artifacts such as striping in the imagery. In recent studies we have analyzed the striping pattern related to the detector level RSR difference in VIIRS Thermal Emissive Bands (TEB) M15 and M16, which includes line-by-line radiative transfer model (LBLRTM) detector level response study and onboard detector stability evaluation using the solar diffuser. Now we extend these analysis to the Reflective Solar Bands (RSB) using MODTRAN atmospheric radiative transfer model (RTM) for detector level radiance simulation. Previous studies analyzed the striping pattern in the images of VIIRS ocean color and reflectance in RSB, further studies about the root cause for striping are still needed. In this study, we will use the MODTRAN model at spectral resolution of 1 cm^-1 under different atmospheric conditions for VIIRS RSB, for example band M1 centered at 410nm which is used for Ocean Color product retrieval. The impact of detector level RSR difference, atmospheric dependency, and solar geometry on the striping in VIIRS SDR imagery will be investigated. The cumulative histogram method used successfully for the TEB striping analysis will be used to quantify the striping. These analysis help S-NPP and J1 to better understand the root cause for VIIRS image artifacts and reduce the uncertainties in geophysical retrievals to meet the user needs.

  1. Peculiarities of soil mycobiota composition in Chernobyl NPP

    International Nuclear Information System (INIS)

    Soil mycobiota in zones of strong radiation control (Lyutizh region), nine stationaries in 30 km Chernobyl NPP zone and one in the vicinity of Kiev has been investigated. 180 species of 70 genera of micromycetes has been isolated and identified. The species of genera Penicillium, Mortierella, Trichoderma, Cladosporium dominated in all soils studied, and the species of genera Acremonium, Paecilomyces, Oidiodendron etc. were frequent. The comparison of the generic composition of micromycetes in localities studied has revealed their similarity. The characteristic feature for the mycobiota was regular revealing and specific variability of melanin-containing fungi. Many of them compose the reserve group of micromycetes. There was found new and rare species Acrodontium crateriforme (v.Beyma) de Hoog, Botryosporium longibrachiatum Oud., Chuppia sarcinifera Deighton, Harzia acremonioides Harz etc., with were not registered in these soils before the accident. The structure of the micromycete complexes presented as a correlation Pleiades has been established. Discovered Pleiades were formed mainly by melanin-containing fungi. According to the preliminary results the micro-mycetes complexes, taking into account their occurrence, can be used as indicators of unfavourable ecological soil state. To our mind, a search for such complexes may be conducted among of melanin-containing species as well as numerous species of genus Penecillium and related Paecilomyces

  2. Assessment of radiation impact on biota as a result of hypothetical accidents at small NPP

    International Nuclear Information System (INIS)

    Document available in abstract form only. Full text of publication follows: Breakthrough in the development of science and technology, caused by the creation of nuclear weapons, allowed expanding the scope of application of the energy of nuclear fission. Nuclear power plants, nuclear power installations for submarines and ships were created. The main factor of the competitiveness of nuclear energy is its success in areas of its industrial, scientific, technical application. Nuclear energy, as well as any other modern sophisticated technology used by people, is associated with a particular risk for the individuals, society and the environment. According to the classification adopted by the IAEA, small reactors are reactors with an equivalent electric power of <300 MW(e) and medium-sized reactors are reactors with an equivalent electric power of 300-700 MW(e). Russia has a unique experience in the creation and operation of reactor systems with lead-bismuth coolant for nuclear-powered submarines. Such is single unit nuclear power station with an experiment industrial power reactor installation with lead-bismuth coolant with an electric capacity of 100 MW (SVBR-100). The launch of the first power unit with the SVBR-100 is going to start up after 2017 in the city of Dimitrovgrad, Russia. After the Chernobyl and Fukushima accidents, the world community makes high demands to operation safety during running of NPPs. Due to this, the analysis of the consequences of non-routine and accidental events is the essential point of rationale for innovative nuclear technologies. In this regard, the evolution of modern radiation protection system considering the radiation protection of not only the population, but also non-human biota, cannot be disregarded. The aim of the current research was the assessment of radiological impact on biota caused by hypothetical accidents at NPP with lead-bismuth cooled small fast reactor SVBR-100. (authors)

  3. Environmental qualification design for NPP refurbishment to comply with revised licensing requirements

    Energy Technology Data Exchange (ETDEWEB)

    MacBeth, M. J.; Hemmings, R. L. [Canatom-NPM, Ontario (Canada)

    2002-04-15

    Recent Canadian Nuclear Regulatory decisions have imposed Environmental Qualification (EQ) requirements for twenty-four Reactor Building (RB) airlocks at the four-unit Pickering Nuclear Generating Station-B (PNGS-B) facility. This paper describes the EQ modification design work completed by CANATOM-NPM for the problematic aspects for such projects. The airlocks allow RB access while providing a containment boundary and are designed to prevent a potential breach of containment for all analysed station conditions. Each PNGS-B unit has three large equipment airlocks and three smaller personnel airlocks. The airlocks must function under postulated worst-case design basis accident(DBA) conditions for assigned mission durations. The design must ensure that accident conditions cannot spuriously initiate an un-requested door opening. CANATOM-NPM reviewed site data to specify the necessary EQ modifications required to satisfy licensing requirements while providing a correct and complete as-found record of the existing airlock installation. The design team assessed the installed airlocks configuration against environmental qualification requirements to finalize the list of necessary modifications. A comprehensive, cross-discipline review of proposed design changes was completed to identify any further changes required to satisfy the final EQ licensing goal. The design team also conducted a design review of the EQ modification installation strategy to integrate the design deliverables with the installation team requirements while attempting to minimize necessary outage time for EQ modification installations. This project was completed on schedule and within the cost limitations required by the client with comprehensive, high quality final design packages. Overall improvements were realized for OPG system drawings and the electronic documentation of design data. The EQ modifications designed by CANATOM-NPM will ensure the continued operation of the PNGS-B NPP past December 31

  4. Planning and management support for NPP personnel SAT-based training programmes. IAEA regional workshop. Working material

    International Nuclear Information System (INIS)

    Within the European regional TC Project a workshop on Planning and Management Support for NPP Personnel SAT Based Training programmes was held at the Paks NPP Maintenance Training Centre in June 1998. It was organized jointly by IAEA and the Paks NPP. The objective of the workshop was to present the important experience gained by successful implementation of the IAEA Model Project on Strengthening Training for Safe Operation at Paks NPP as well as international experience in developing and carrying out the projects to upgrade NPP personnel training in particular maintenance training, and competence based Systematic Approach to Training (SAT). Twenty five participants from Armenia, Bulgaria, China, Czech republic, Hungary, Romania, Russia, Slovak Republic and Ukraine attended the workshop presenting and exchanging experiences in implementing NPP SAT-based training programmes

  5. Risk Informed Support of Decision Making in Nuclear Power Plant Emergency Zoning - Generic Framework towards Harmonising NPP Emergency Planning Practices

    OpenAIRE

    KUBANYI JOZEF; BOLADO LAVIN RICARDO; SERBANESCU DAN; TOTH BELA; WILKENING HEINZ

    2008-01-01

    The report provides a systematic overview of the essential aspects of risk informed support of decision making (RIDM) in nuclear power plant (NPP) emergency zoning (EZ) as a contribution to harmonising strategic practices in the area. Owing to the state-of-the-art understanding and increased characterisation of NPP severe accidents, overall management of them should be analysed as an integrated complex process. The interrelationship of NPP emergency operating procedures, safety and risk asses...

  6. On the foundation of new ''Hygienic guidlines on NPP design and operation'' (SP-AEhS-615/9-79)

    International Nuclear Information System (INIS)

    New ''Sanitary guidlines for NPP design and operation'' written considering requirements of RPG - 76 and Main sanitary guidlines-72 are discussed. The following chapters are characterized in detail namely, requirements for dose for personnel and population inhabitating the NPP vicinity; population doses at maximum design accident; estimated effluents corresponding to accidental radiation doses, gaseous aerosol effluents during NPP normal operation reguirements for liquid and solid radioactive waste disposal. Tabular data are presented

  7. Modeling of temporal and spatial coherency of net primary production (MODIS NPP) in the mountain forests of South Siberia

    Science.gov (United States)

    Ivanova, Yulia; Soukhovolsky, Vlad

    Net primary production (NPP) of mountain forest is very variable and depends on a variety of external modifying factors such as intensity and spectrum of solar radiation, climatic conditions in the area. Less studied are features of long-term NPP dynamics associated with self-regulation processes of tree growth in a forest. Mountain forests are a convenient object for analysis and modeling of long-term NPP changes that do not depend on climatic factors, since in mountain forests climatic conditions are uniquely determined by altitude Temporal and spatial coherence of mean annual NPP time series (Yrs. 2000 - 2012) was studied according to data from satellite observations of MODIS/TERRA. Mean annual NPP estimates' series were examined for different altitudinal zones in the Sayan Mountains (South of Central Siberia). Altitudes ranged from 600 to 1.800 meters above sea level. This area is lengthful vertically and has well-marked mountain-belt vegetation complexes, where mixed forests, fir and pine coniferous forests, alpine meadows and alpine tundra successively come one after another. Spatial and temporal coherence of NPP time series for different habitats is analyzed. The analysis showed that variations in annual NPP values of the fir (Abies sibirica) at different altitudes (450-1700 m) are synchronized. These variations in NPP values are described by the AR(2) model. Such behavior of studied NPP time series suggests a lag in growth of woody plants. In this case, the current NPP is influenced by the NPP values of the two previous years. At higher altitudes, where the density of the trees decreases and herbaceous plants become dominant, the range and synchronization of NPP variations decrease.

  8. Impact of climate aggregation over different scales on regional NPP modelling

    Science.gov (United States)

    Kuhnert, Matthias

    2016-04-01

    Model input data aggregation methods and data aggregation across spatial scales affect various model outputs, e.g. Net Primary Productivity (NPP). The scale at which data is collected is of great importance. In ecosystem modelling studies we often see soil and climate data collected at coarse scale being used in models to predict ecosystem responses e.g. NPP in dependency of these parameters at finer scale. Outputs of these models are impacted by the way the data is aggregated or dis-aggregated to the spatial scale. Up to know there are very few studies which quantified the impact of scaling on the simulation results. In this study, we quantify the impact of climate data aggregation using five different resolutions, to simulate NPP by 11 different crop and biogeochemical models for the same study area. The aggregation effect is investigated for wheat and maize cropping systems in the state of North Rhine-Westphalia, Germany. The simulation results are analysed for NPP averaged over growing seasons of a 30 year period at different spatial resolutions as well as for annual NPP during growing season. While there is only a minor impact of input data aggregation on NPP on 30 year averages, the annual data show differences in NPP up to 9.4 % and 13.6 % between the different resolutions for wheat and maize, respectively. The scale effect differ between the models and shows higher impacts for extreme years. This is tested by selecting years with extreme dry conditions based on a drought index, which showed stronger scale effects of up to 12.8 % and 15.5 % for wheat and maize, respectively.

  9. Managing RTP Console Upgrading Project: Best Practice for Nuclear Malaysia as TSO in Supporting NPP Development

    International Nuclear Information System (INIS)

    Human Resource Development (HRD) is required for Nuclear Power Programme (NPP). To be a Technical Support Organisation (TSO) for NPP, Nuclear Malaysia should be ready to take the responsibility in supporting Nuclear Regulatory Agency (NRA) and NPP Operators. In nurturing Nuclear Malaysia as TSO, the prime important and focus of HRD for the NPP is the reactor engineering technology. Nuclear Malaysia gives various phases of supports needed to build NPP such as during siting, design, planning, licensing, construction, commissioning, operation and maintenance in its own way and capability. The current Nuclear Malaysia unique approach is the TRIGA PUSPATI reactor (RTP) upgrading project. Research reactor plays an important role in Research and Developpement organization as a nuclear facility to assist the development of NPP. Therefore, upgrading the research reactor is needed to build the skills and gain knowledge of workers to work safely. After 29 years of operation, the RTP system is facing aging problems due to many components in the reactor are outdated. Therefore, immediate action should be carried out to mitigate the aging factor of the reactor to prevent the worsening of the aging problem, and to prevent untoward incident from happening. Action should also cover short and long term planning to prevent current situation from recurring. Currently, RTP is upgrading its console from analog to digital system. One of the achievements in this console upgrading project is the development and implementation of project management. This paper comprises the overview on the RTP console upgrading project, the project management and how this project can lead Nuclear Malaysia to be a good TSO for the development of NPP. (author)

  10. Validation of S-NPP VIIRS Sea Surface Temperature Retrieved from NAVO

    Directory of Open Access Journals (Sweden)

    Qianguang Tu

    2015-12-01

    Full Text Available The validation of sea surface temperature (SST retrieved from the new sensor Visible Infrared Imaging Radiometer Suite (VIIRS onboard the Suomi National Polar-Orbiting Partnership (S-NPP Satellite is essential for the interpretation, use, and improvement of the new generation SST product. In this study, the magnitude and characteristics of uncertainties in S-NPP VIIRS SST produced by the Naval Oceanographic Office (NAVO are investigated. The NAVO S-NPP VIIRS SST and eight types of quality-controlled in situ SST from the National Oceanic and Atmospheric Administration in situ Quality Monitor (iQuam are condensed into a Taylor diagram. Considering these comparisons and their spatial coverage, the NAVO S-NPP VIIRS SST is then validated using collocated drifters measured SST via a three-way error analysis which also includes SST derived from Moderate Resolution Imaging Spectro-radiometer (MODIS onboard AQUA. The analysis shows that the NAVO S-NPP VIIRS SST is of high accuracy, which lies between the drifters measured SST and AQUA MODIS SST. The histogram of NAVO S-NPP VIIRS SST root-mean-square error (RMSE shows normality in the range of 0–0.6 °C with a median of ~0.31 °C. Global distribution of NAVO VIIRS SST shows pronounced warm biases up to 0.5 °C in the Southern Hemisphere at high latitudes with respect to the drifters measured SST, while near-zero biases are observed in AQUA MODIS. It means that these biases may be caused by the NAVO S-NPP VIIRS SST retrieval algorithm rather than the nature of the SST. The reasons and correction for this bias need to be further studied.

  11. Variations and trends of terrestrial NPP and its relation to climate change in the 10 CMIP5 models

    Indian Academy of Sciences (India)

    Suosuo Li; Shihua Lü; Yuanpu Liu; Yanhong Gao; Yinhuan Ao

    2015-03-01

    Using global terrestrial ecosystem net primary productivity (NPP) data, we validated the simulated multi-model ensemble (MME) NPP, analyzed the spatial distribution of global NPP and explored the relationship between NPP and climate variations in historical scenarios of 10 CMIP5 models. The results show that the global spatial pattern of simulated terrestrial ecosystem NPP, is consistent with IGBP NPP, but the values have some differences and there is a huge uncertainty. Considering global climate change, near surface temperature is the major factor affecting the terrestrial ecosystem, followed by the precipitation. This means terrestrial ecosystem NPP is more closely related to near surface temperature than precipitation. Between 1976 and 2005, NPP shows an obvious increasing temporal trend, indicating the terrestrial ecosystem has had a positive response to climate change. MME NPP has increased 3.647PgC during historical period, which shows an increasing temporal trend of 3.9 gCm−2∙100 yr−2 in the past 150 years, also indicating that the terrestrial ecosystem has shown a positive response to climate change in past 150 years.

  12. Knowledge management at Kozloduy NPP - challenges and solutions

    International Nuclear Information System (INIS)

    Like any highly technical endeavor, the use of nuclear technology relies heavily on a vast accumulation of knowledge - volume upon volume of scientific research, engineering analysis, design documentation, operational data, maintenance records, regulatory reviews and countless other pieces of technical information, combined with complex reservoir of scientists, engineers, technicians and managers with relevant background and expertise. The effective management of nuclear knowledge includes systematic and organized application of accumulated specific knowledge as well as ensuring the sustainable availability of qualified personnel. This means that: 1) The know-how should be properly identified, captured and classified; 2) Adequate tools for support, access and transfer of data should be available; 3) Renewing of workforce without loss of institutional memory should be guaranteed. During the centuries this process has been applied spontaneously and there are a lot of examples that the world use to be workable earlier too. However nowadays this type of spontaneous knowledge management is ineffective. Information volume and the communication efficiency have increased so much that new tools have to be created to handle the knowledge being communicated trough numerous sources. Besides information space is strongly polluted. The information channels provide unnecessary redundant information. Target oriented searching and delivering of useful information is difficult and requires significant resources. What value this know-how represent, how can it be maintained for and passed to the next generation, what are the problems of aging and renewing of workforce, what measures have been taken by Kozloduy NPP and what are the challenges to be faced yet - these are the issues to be addressed in this paper. (authors)

  13. Radioecological evaluations of Ignalina NPP Lithuania Normal operating

    International Nuclear Information System (INIS)

    The Ignalina NPP (INPP) with two RBMK-1500 reactors is constructed in north-eastern part of Lithuania, close to its borders with Latvia and Belarus. The natural Lake Drukshiai serves as a cooling basin for INPP. Environmental monitoring in INPP region is conducted since 1979. It was extended since 1993 due to implementation of State Scientific Research Programme INPP and Environment. Radionuclides transport in both aquatic and terrestrial ecosystems in this time was studied especially comprehensively. Accumulation of artificial radionuclides in lake is governed by biogeochemical transport of radionuclides from three sources, i.e. of global ones, emitted after Chernobyl accident and released from INPP. Radioactive releases from INPP into lake formed small activity fraction of different radionuclides in water, bottom sediments as well as in biota. Radionuclides activity in water varied from 1.4 to 7 for 137 Cs, from 0.5 to 1.7 for 60 Co, from 25 to 60 Bq/m 3 for 90 Sr, and were not detected for 134 Cs and 54 Mn. Considering terrestrial ecosystem areal distribution of radionuclides in soil and biota were evaluated. Artificial radionuclides from three mentioned above sources are distributed in ecosystem which can be treated as little contaminated (mean 137 Cs activity reaches 1000 Bq/m 2 ). Local anomalies close to INPP are related to releases from water communications of INPP. Using site specific data nuclide specific dose factors for both atmospheric and aquatic pathways and individual effective doses to members of critical groups were calculated. Doses caused by radioactive releases into water and into air during 1997 are equal 0.01 mSv/a and 0.001 mSv/a, respectively

  14. Simulator experiments: effects of NPP operator experience on performance

    Energy Technology Data Exchange (ETDEWEB)

    Beare, A.N.; Gray, L.H.

    1984-01-01

    During the FY83 research, a simulator experiment was conducted at the control room simulator for a GE Boiling Water Reactor (BWR) NPP. The research subjects were licensed operators undergoing requalification training and shift technical advisors (STAs). This experiment was designed to investigate the effects of senior reactor operator (SRO) experience, operating crew augmentation with an STA and practice, as a crew, upon crew and individual operator performance, in response to anticipated plant transients. Sixteen two-man crews of licensed operators were employed in a 2 x 2 factorial design. The SROs leading the crews were split into high and low experience groups on the basis of their years of experience as an SRO. One half of the high- and low-SRO experience groups were assisted by an STA. The crews responded to four simulated plant casualties. A five-variable set of content-referenced performance measures was derived from task analyses of the procedurally correct responses to the four casualties. System parameters and control manipulations were recorded by the computer controlling the simulator. Data on communications and procedure use were obtained from analysis of videotapes of the exercises. Questionnaires were used to collect subject biographical information and data on subjective workload during each simulated casualty. For four of the five performance measures, no significant differences were found between groups led by high (25 to 114 months) and low (1 to 17 months as an SRO) experience SROs. However, crews led by low experience SROs tended to have significantly shorter task performance times than crews led by high experience SROs. The presence of the STA had no significant effect on overall team performance in responding to the four simulated casualties. The FY84 experiments are a partial replication and extension of the FY83 experiment, but with PWR operators and simulator.

  15. Development of Information Datasheets of Nuclear Power Plant (NPP) Equipment using cfiXLM schema

    International Nuclear Information System (INIS)

    In 2009, EPRI (Electrical Power Research Institute) published a new NPP information handover guide to provide NPP owners and operators with data handover templates in consistent format for effective delivery of information during all stages of the handover process. Another difficult concern for NPP data information management is to exchange the data information among many organizations such as NPP owners, operators, engineering companies, suppliers, and vendors. As a matter of fact, the improperly formatted handover of information sometimes occurs due to the discrepancy of data format (e. g., data description language type). This improper delivery can make negative effects on NPP integrity and safety. Thus, the lack of proper exchange for different data information systems of organizations should be resolved by using an international standard data format. The standard data format can reduce the cost and time for data exchange in each phase for design, procurement, delivery, installation, operation and maintenance of equipment. The AEX(automating equipment information exchange) pilot implementation project team under EPRI advanced nuclear technology (ANT) program has been conducted a research for the use of XML equipment schemas for electronic data exchange(EDE). They applied XML equipment schema for the design, selection, quotation, purchase and mock install of a safety injection centrifugal pump using EDE standard HI(hydraulic institute) 50.7. For data exchange, FIATECH, an industry consortium, has equally developed library of templates and reference data for ISO-15926, which is an international standard capable of reducing data-error and delivery time for exchanging data among different organizations. KHNP as an only owner/operator company has not experienced much difficulty in data interoperability with other organizations, but continued its unremitting exertions to develop a robust system capable of managing data information generated in all the stages of NPP

  16. A GeoServices Infrastructure for Near-Real-Time Access to Suomi NPP Satellite Data

    Science.gov (United States)

    Evans, J. D.; Valente, E. G.; Hao, W.; Chettri, S.

    2012-12-01

    The new Suomi National Polar-orbiting Partnership (NPP) satellite extends NASA's moderate-resolution, multispectral observations with a suite of powerful imagers and sounders to support a broad array of research and applications. However, NPP data products consist of a complex set of data and metadata files in highly specialized formats; which NPP's operational ground segment delivers to users only with several hours' delay. This severely limits their use in critical applications such as weather forecasting, emergency / disaster response, search and rescue, and other activities that require near-real-time access to satellite observations. Alternative approaches, based on distributed Direct Broadcast facilities, can reduce the delay in NPP data delivery from hours to minutes, and can make products more directly usable by practitioners in the field. To assess and fulfill this potential, we are developing a suite of software that couples Direct Broadcast data feeds with a streamlined, scalable processing chain and geospatial Web services, so as to permit many more time-sensitive applications to use NPP data. The resulting geoservices infrastructure links a variety of end-user tools and applications to NPP data from different sources, and to other rapidly-changing geospatial data. By using well-known, standard software interfaces (such as OGC Web Services or OPeNDAP), this infrastructure serves a variety of end-user analysis and visualization tools, giving them access into datasets of arbitrary size and resolution and allowing them to request and receive tailored products on demand. The standards-based approach may also streamline data sharing among independent satellite receiving facilities, thus helping them to interoperate in providing frequent, composite views of continent-scale or global regions. To enable others to build similar or derived systems, the service components we are developing (based in part on the Community Satellite Processing Package (CSPP) from

  17. Development of Information Datasheets of Nuclear Power Plant (NPP) Equipment using cfiXLM schema

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jaiho; Song, Eunhye [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    In 2009, EPRI (Electrical Power Research Institute) published a new NPP information handover guide to provide NPP owners and operators with data handover templates in consistent format for effective delivery of information during all stages of the handover process. Another difficult concern for NPP data information management is to exchange the data information among many organizations such as NPP owners, operators, engineering companies, suppliers, and vendors. As a matter of fact, the improperly formatted handover of information sometimes occurs due to the discrepancy of data format (e. g., data description language type). This improper delivery can make negative effects on NPP integrity and safety. Thus, the lack of proper exchange for different data information systems of organizations should be resolved by using an international standard data format. The standard data format can reduce the cost and time for data exchange in each phase for design, procurement, delivery, installation, operation and maintenance of equipment. The AEX(automating equipment information exchange) pilot implementation project team under EPRI advanced nuclear technology (ANT) program has been conducted a research for the use of XML equipment schemas for electronic data exchange(EDE). They applied XML equipment schema for the design, selection, quotation, purchase and mock install of a safety injection centrifugal pump using EDE standard HI(hydraulic institute) 50.7. For data exchange, FIATECH, an industry consortium, has equally developed library of templates and reference data for ISO-15926, which is an international standard capable of reducing data-error and delivery time for exchanging data among different organizations. KHNP as an only owner/operator company has not experienced much difficulty in data interoperability with other organizations, but continued its unremitting exertions to develop a robust system capable of managing data information generated in all the stages of NPP

  18. The development of stochastic process modeling through risk analysis derived from scheduling of NPP project

    International Nuclear Information System (INIS)

    There are so many different factors to consider when constructing a nuclear power plant successfully from planning to decommissioning. According to PMBOK, all projects have nine domains from a holistic project management perspective. They are equally important to all projects, however, this study focuses mostly on the processes required to manage timely completion of the project and conduct risk management. The overall objective of this study is to let you know what the risk analysis derived from scheduling of NPP project is, and understand how to implement the stochastic process modeling through risk management. Building the Nuclear Power Plant is required a great deal of time and fundamental knowledge related to all engineering. That means that integrated project scheduling management with so many activities is necessary and very important. Simulation techniques for scheduling of NPP project using Open Plan program, Crystal Ball program, and Minitab program can be useful tools for designing optimal schedule planning. Thus far, Open Plan and Monte Carlo programs have been used to calculate the critical path for scheduling network analysis. And also, Minitab program has been applied to monitor the scheduling risk. This approach to stochastic modeling through risk analysis of project activities is very useful for optimizing the schedules of activities using Critical Path Method and managing the scheduling control of NPP project. This study has shown new approach to optimal scheduling of NPP project, however, this does not consider the characteristic of activities according to the NPP site conditions. Hence, this study needs more research considering those factors

  19. The development of stochastic process modeling through risk analysis derived from scheduling of NPP project

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kwang Ho; Roh, Myung Sub [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-10-15

    There are so many different factors to consider when constructing a nuclear power plant successfully from planning to decommissioning. According to PMBOK, all projects have nine domains from a holistic project management perspective. They are equally important to all projects, however, this study focuses mostly on the processes required to manage timely completion of the project and conduct risk management. The overall objective of this study is to let you know what the risk analysis derived from scheduling of NPP project is, and understand how to implement the stochastic process modeling through risk management. Building the Nuclear Power Plant is required a great deal of time and fundamental knowledge related to all engineering. That means that integrated project scheduling management with so many activities is necessary and very important. Simulation techniques for scheduling of NPP project using Open Plan program, Crystal Ball program, and Minitab program can be useful tools for designing optimal schedule planning. Thus far, Open Plan and Monte Carlo programs have been used to calculate the critical path for scheduling network analysis. And also, Minitab program has been applied to monitor the scheduling risk. This approach to stochastic modeling through risk analysis of project activities is very useful for optimizing the schedules of activities using Critical Path Method and managing the scheduling control of NPP project. This study has shown new approach to optimal scheduling of NPP project, however, this does not consider the characteristic of activities according to the NPP site conditions. Hence, this study needs more research considering those factors.

  20. Calculation of economic and financing of NPP and conventional power plant using spreadsheet innovation

    International Nuclear Information System (INIS)

    The study for calculating the economic and financing of Nuclear Power Plant (NPP) and conventional power plant using spreadsheet Innovation has been done. As case study, the NPP of PWR type of class 1050 MWe is represented by OPR-1000 (Optimized Power Reactor, 1000 MWe) and the conventional plant of class 600 MWe, is coal power plant (Coal PP). The purpose of the study is to assess the economic and financial feasibility level of OPR-1000 and Coal PP. The study result concludes that economically, OPR-1000 is more feasible compared to Coal PP because its generation cost is cheaper. Whereas financially, OPR-1000 is more beneficial compared to Coal PP because the higher benefit at the end of economic lifetime (NPV) and the higher ratio of benefit and cost (B/C Ratio). For NPP and Coal PP, the higher Discount Rate (%) is not beneficial. NPP is more sensitive to the change of discount rate compared to coal PP, whereas Coal PP is more sensitive to the change of power purchasing price than NPP. (author)

  1. Studies of the landscape and its components of the Ignalina NPP region

    International Nuclear Information System (INIS)

    The causes of landscape degradation in Lake Drukshiai basin are the following: building and operation of Ignalina NPP and Visaginas town with the service infrastructure. Landscape degradation map was compiled showing the areas effected by degradation, intensity of degradation and resistance of landscape against this process. It was determined that the highly de gradated landscape in the lake basin covers the area of 395.3 ha (1.43% without the lake). The landscape resistance to the processes of degradation depends on the migration fluxes of erosion products. The investigation revealed that erosion products in Lake Drukshiai basin are the least stable in the landscape with fluvioglacial sand and gravel deposits. The land flora in Ignalina NPP region is being represented by 617 plant species belonging to 81 family. Temperature, chemical and physical changes which occurred in the lake - cooler after the Ignalina NPP was put in operation were primarily evident in the structure and abundance of by-shore complexes of micro arthropods and insects.During the first five years of operation of Ignalina NPP the abundance and diversity of species at the shores of the lake increased 2.5 - 3.5 times. The genotoxic al impact of Ignalina NPP environment on local animal populations during 184 - 1996 period was slight and did not change significantly. (author)

  2. Analysis of an NPP Structure subjected to Vibrations Induced from Airplane Crashes

    International Nuclear Information System (INIS)

    After the terrorists' attacks with civilian airplanes on September 11, 2001, special attention has been paid to the potential for an airplane crash into a Nuclear Power Plant (NPP) as a man-made hazard. An airplane crash (APC) into an NPP has the potential to damage the roofs and walls of these structures, as well as other systems and components such as pipelines, electric motors, power supplies, power cables of electricity transmission that are important for safety. Therefore, an evaluation of the structural response to an APC is important for the safety of NPPs to be confirmed. A structural integrity analysis was carried out focusing on the vibration effects of an APC on an NPP structure. The NPP structure under consideration has been conceptually redesigned based on APR1400 to have double containments for the purpose of a feasibility study to meet European requirements. The finite element method was used for the structural analysis of the NPP, and the computer code ABAQUS was employed for this analysis

  3. TRAC Real Time: A high fidelity solution for NSSS modelling. Application to Lungmen and Grafenrheinfeld NPP simulators

    International Nuclear Information System (INIS)

    Nuclear Island (NSSS) modelling represents an essential part of a simulator software, as the accuracy and scope used is essential when representing appropriately the systems behaviour in operational transients, where the transitions of phase water-vapour are dominant such as: ATWS, LOCA, Feed and Bleed, Mid Loop Operation, etc. Tecnatom has been using, since the early 90's, its real-time simulation technology, the binomial TRAC-RT and NEMO, a 6-equations thermalhydraulic code and three-dimensional neutronic code for high fidelity modelling of the Primary System of several full scope simulators. Two latest projects which have been faced are the object of this paper. The first of them refers to Lungmen NPP Full scope simulator, an ABWR type being built by GE for Taiwan Power Company. The NSSS generated model is connected with the rest of BOP conventional simulation. The validation process has been carried out according to the methodology defined in ANSI 3.5 standard, taking like reference the engineering model that GE possesses for this Power Station. The second project describes the NSSS upgrading of D3 simulator, owned by KSG, having Grafenrheinfeld (KKG), a German PWRKWU NPP as reference unit. The development platform is Digital UNIX, connected by reflective memory (RMS) to the existing ENCORE simulator platform. Real-time requirements being fulfilled. In both projects, the model generated with TRAC-RT and NEMO represents, not only the primary circuit, but also the steam lines, given their complexity and importance. Once more, these two project show the trend of training simulators in incorporating more and more accurate models, using engineering grade models

  4. Introduction of reliability, safety and risk monitoring technology in BN-600 power unit

    International Nuclear Information System (INIS)

    Rosenergoatom Concern OJSC Operating Entity set the task to introduce risk monitoring technology for continuous estimate and control of nuclear units quantitative safety measures change. JSC “Afrikantov OKBM” and “Beloyarsk NPP” developed risk monitor system “RIM” which is introducing now at Beloyarsk NPP BN-600 unit 3. To estimate quantitative safety measures Level 1 PSA for internal initiating events for full power operating conditions model of Beloyarsk NPP BN-600 unit 3 is used. PSA model was developed using national certified PSA software CRISS. To ensure NPP reliability and safety, implementation of comprehensive systematic study (monitoring) of NPP operating experience is of fundamental value. To solve this problem, JSC “Afrikantov OKBM” and “Beloyarsk NPP” developed and introduced the system for analytical reliability and safety monitoring of BN-600 power unit based on information retrieval system (IRS) “Istochnik-BN”. The paper describes system objectives, main characteristics and results of reliability, safety and risk monitoring technology introducing at Beloyarsk NPP BN-600 unit 3. (author)

  5. Temporal variability of the NPP-GPP ratio at seasonal and interannual time scales in a temperate beech forest

    Directory of Open Access Journals (Sweden)

    M. Campioli

    2011-09-01

    Full Text Available The allocation of carbon (C taken up by the tree canopy for respiration and production of tree organs with different construction and maintenance costs, life span and decomposition rate, crucially affects the residence time of C in forests and their C cycling rate. The carbon-use efficiency, or ratio between net primary production (NPP and gross primary production (GPP, represents a convenient way to analyse the C allocation at the stand level. In this study, we extend the current knowledge on the NPP-GPP ratio in forests by assessing the temporal variability of the NPP-GPP ratio at interannual (for 8 years and seasonal (for 1 year scales for a young temperate beech stand, reporting dynamics for both leaves and woody organs, in particular stems. NPP was determined with biometric methods/litter traps, whereas the GPP was estimated via the eddy covariance micrometeorological technique.

    The interannual variability of the proportion of C allocated to leaf NPP, wood NPP and leaf plus wood NPP (on average 11% yr−1, 29% yr−1 and 39% yr−1, respectively was significant among years with up to 12% yr−1 variation in NPP-GPP ratio. Studies focusing on the comparison of NPP-GPP ratio among forests and models using fixed allocation schemes should take into account the possibility of such relevant interannual variability. Multiple linear regressions indicated that the NPP-GPP ratio of leaves and wood significantly correlated with environmental conditions. Previous year drought and air temperature explained about half of the NPP-GPP variability of leaves and wood, respectively, whereas the NPP-GPP ratio was not decreased by severe drought, with large NPP-GPP ratio on 2003 due mainly to low GPP. During the period between early May and mid June, the majority of GPP was allocated to leaf and stem NPP, whereas these sinks were of little importance later on. Improved estimation of seasonal GPP and of the

  6. Temporal variability of the NPP-GPP ratio at seasonal and interannual time scales in a temperate beech forest

    Science.gov (United States)

    Campioli, M.; Gielen, B.; Göckede, M.; Papale, D.; Bouriaud, O.; Granier, A.

    2011-09-01

    The allocation of carbon (C) taken up by the tree canopy for respiration and production of tree organs with different construction and maintenance costs, life span and decomposition rate, crucially affects the residence time of C in forests and their C cycling rate. The carbon-use efficiency, or ratio between net primary production (NPP) and gross primary production (GPP), represents a convenient way to analyse the C allocation at the stand level. In this study, we extend the current knowledge on the NPP-GPP ratio in forests by assessing the temporal variability of the NPP-GPP ratio at interannual (for 8 years) and seasonal (for 1 year) scales for a young temperate beech stand, reporting dynamics for both leaves and woody organs, in particular stems. NPP was determined with biometric methods/litter traps, whereas the GPP was estimated via the eddy covariance micrometeorological technique. The interannual variability of the proportion of C allocated to leaf NPP, wood NPP and leaf plus wood NPP (on average 11% yr-1, 29% yr-1 and 39% yr-1, respectively) was significant among years with up to 12% yr-1 variation in NPP-GPP ratio. Studies focusing on the comparison of NPP-GPP ratio among forests and models using fixed allocation schemes should take into account the possibility of such relevant interannual variability. Multiple linear regressions indicated that the NPP-GPP ratio of leaves and wood significantly correlated with environmental conditions. Previous year drought and air temperature explained about half of the NPP-GPP variability of leaves and wood, respectively, whereas the NPP-GPP ratio was not decreased by severe drought, with large NPP-GPP ratio on 2003 due mainly to low GPP. During the period between early May and mid June, the majority of GPP was allocated to leaf and stem NPP, whereas these sinks were of little importance later on. Improved estimation of seasonal GPP and of the contribution of previous-year reserves to stem growth, as well as reduction

  7. Risk Management and Nuclear Insurance Program within Societatea Nationala Nuclearelectrica S.A

    International Nuclear Information System (INIS)

    This paper shall present the Risk Management and associated nuclear insurance program developed within Societatea Nationala 'Nuclearelectrica' S.A, owner and operator of Units 1 and 2 Cernavoda NPP, the Nuclear Fuel Plant and in charge with commissioning of Units 3 and 4. From the risk management perspective, the main aspects that energy industry has to face due to global economic changes within a dynamic business environment are highlighted. In order to mitigate the operational and investment associated risks, Societatea Nationala 'Nuclearelectrica' S.A. successfully developed, implemented and maintained a coherent insurance program both on local and international insurance market. (authors)

  8. Development of regulatory guide for review of aging management of the operating NPP

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Tae Myung; Lee, Jae Kyung [Cheongju Univ., Cheongju (Korea, Republic of); Kim, Young Ryul [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    2001-03-15

    This is the final report of the second year study. Based on the first year study, proposal of revised guidelines, analysis of revised or newly issued IAEA safety guides and reference guidelines of developed countries, and proposal of detailed guidelines of aging management in PSR have been performed in the second year study. The summary of results in the study so far can be summarized as below, overall view on PSR and idea of effective domestic application were leaded through additional investigation and comparison of legal basis, experiences and current status of PSR implementation among the countries having operating NPPs including Korea. Strategies of adequate application of PSR are roughly reevaluated and totally reestablished in summary from the analysis in factor by factor basis of PSR implementation experience in foreign countries and background of IAEA guidelines. Models and draft framework of PSR report in the first year study were summarized and reevaluated, and structure and outline options of PSR guidelines for judging the PSR report are newly proposed with comparison of their strengths and weaknesses based on the first year study. Among the opt ions, guidelines framework equivalent to the PSR report was picked up as the best. For the judgement of aging management, the most appropriate one was chosen for the detailed judgement of aging management review in our PSR being based on the Standard Review Plan for License Renewal (SRP-LR) in United States considering potential future usage in the judgement for continued operation of old NPP at the time of expiration of its design life. A draft PSR guidelines is prepared and attached by revision of basic guidelines issued in 2000, considering the issues discussed for the draft revision of IAEA PSR guide, the draft IAEA document about 'experience of PSR implementation of member states', and the characteristics of Hungarian PSR Guidelines.

  9. Modeling the transport of nitrogen in an NPP-2006 reactor circuit

    Science.gov (United States)

    Stepanov, O. E.; Galkin, I. Yu.; Sledkov, R. M.; Melekh, S. S.; Strebnev, N. A.

    2016-07-01

    Efficient radiation protection of the public and personnel requires detecting an accident-initiating event quickly. Specifically, if a heat-exchange tube in a steam generator is ruptured, the 16N radioactive nitrogen isotope, which contributes to a sharp increase in the steam activity before the turbine, may serve as the signaling component. This isotope is produced in the core coolant and is transported along the circulation circuit. The aim of the present study was to model the transport of 16N in the primary and the secondary circuits of a VVER-1000 reactor facility (RF) under nominal operation conditions. KORSAR/GP and RELAP5/Mod.3.2 codes were used to perform the calculations. Computational models incorporating the major components of the primary and the secondary circuits of an NPP-2006 RF were constructed. These computational models were subjected to cross-verification, and the calculation results were compared to the experimental data on the distribution of the void fraction over the steam generator height. The models were proven to be valid. It was found that the time of nitrogen transport from the core to the heat-exchange tube leak was no longer than 1 s under RF operation at a power level of 100% N nom with all primary circuit pumps activated. The time of nitrogen transport from the leak to the γ-radiation detection unit under the same operating conditions was no longer than 9 s, and the nitrogen concentration in steam was no less than 1.4% (by mass) of its concentration at the reactor outlet. These values were obtained using conservative approaches to estimating the leak flow and the transport time, but the radioactive decay of nitrogen was not taken into account. Further research concerned with the calculation of thermohydraulic processes should be focused on modeling the transport of nitrogen under RF operation with some primary circuit pumps deactivated.

  10. Issues on safe radioactive waste management at ChNPP site in International Shelter Implementation Plan

    International Nuclear Information System (INIS)

    The International Shelter Implementation Plan (SIP) [1], is aimed to convert the ChNPP unit 4, destroyed by a beyond-design accident in 1986, into an environmentally safe facility by means of large-scale projects such as stabilization of the existing Sarcophagus (Shelter), construction of a New Safe Confinement (NSC), and installation of engineering and monitoring systems. This report presents some important safety issues concerning radioactive waste (RAW) management at the Shelter. One of the main problems of RAW management is to dispose of large volumes of RAW generated during ground preparation work. It is necessary that RAW be sorted carefully to separate low-active radioactive waste (LLW), which will be the majority, from high-level waste. Considering the fact that the Shelter is in the exclusion zone, the interim storage of LLW in this zone is possible, but a set of safety measures is required, e.g. prevention of dust generation or spreading of radioactivity with water. Another problem is high level RAW management. Highly radioactive fragments of the core, including fuel were ejected during the accident and are now buried under the man-made layer around the Shelter. Unanticipated disclosure of such fragments may happen during any ground preparation work as well as during clearing of premises inside the damaged buildings. Therefore, permanent radiation monitoring is required to prevent any intolerable exposure of workers. Unanticipated disclosure of high-active radioactive waste (HLW) could lead to considerable delay of any work. Since it is particularly difficult to remove HLW from those locations, which can not be easily accessed with removal equipment, such waste needs to be confined and properly shielded at in situ. Due to absence of a permanent HLW storage, an interim storage needs to be provided for in the territory of the Sarcophagus. (author)

  11. Development of DUPIC fuel cycle technology - Assessment of Wolsong NPP fuel handling system for DUPIC fuel

    Energy Technology Data Exchange (ETDEWEB)

    Na, Bok Gyun; Nam, Gung Ihn [Korea Power Engineering Company, Taejon (Korea)

    2000-04-01

    The DUPIC fuel loading and discharge path of Wolsong NPP is studied assuming that DUPIC fuel is used at Wolsong NPP. Spent DUPIC fuel discharge path is irrelevant, since it uses the same spent fuel discharge path. Number of factors such as safety, economics of design change, radiation exposure to operators, easy of operation and maintenance, etc, are considered in the evaluation of path. A more detailed analysis of cost estimation of the selected path is also carried out. The study shows that DUPIC fuel loading path following through Spent Fuel Storage Bay and Spent Fuel Discharge Port in reverse direction will minimize the design change and additional equipment and radiation exposure to operators. The estimated total cost of using DUPIC fuel in Wolsong NPP based on price index of year 2000 is around 4.5 billion won. 4 refs., 30 figs., 13 tabs. (Author)

  12. Checking of seismic and tsunami hazard for coastal NPP of Chinese continent after Fukushima nuclear accident

    Institute of Scientific and Technical Information of China (English)

    Chang Xiangdong; Zhou Bengang; Zhao Lianda

    2013-01-01

    A checking on seismic and tsunami hazard for coastal nuclear power plant (NPP) of Chinese continent has been made after Japanese Fukushima nuclear accident caused by earthquake tsunami.The results of the checking are introduced briefly in this paper,including the evaluations of seismic and tsunami hazard in NPP siting period,checking results on seismic and tsunami hazard.Because Chinese coastal area belongs to the continental shelf and far from the boundary of plate collision,the tsunami hazard is not significant for coastal area of Chinese continent.However,the effect from tsunami still can' t be excluded absolutely since calculated result of Manila trench tsunami source although the tsunami wave is lower than water level from storm surge.The research about earthquake tsunami will continue in future.The tsunami warning system and emergency program of NPP will be established based on principle of defense in depth in China.

  13. Probabilistic assessment of the Juragua NPP response under Station Blackout conditions

    International Nuclear Information System (INIS)

    Assessment of the NPP response under SBO (station Blackout) conditions is a current safety issue of special interest, In the case of Juragua NPP, the safety assessment related to this topic is very important, taking into account the peculiarities of the Cuban Electro energetic System: small and long island, without possibilities of conexion beyond its borders and under the incidence of tropical phenomena In this papers a preliminary evaluation is presented of the potential incidence of Station Blackout conditions for Juragua NPP. the importance of this sort of events for the safety of the plant is evaluated, the factors which condition it are identified and measures for its prevention or recovering the normal situation if such an event takes place are proposed

  14. Dynamics and stability of turbine-pumping system for gas coolant supply in a NPP

    International Nuclear Information System (INIS)

    A simplified mathematical model of turbine-pumping assembly (TPA) dynamics is developed. TPA is used for gas coolant supply in a coolant circuit of NPP with HTR reactor. Stability of the stationary solution of mathematical model equations has been investigated; transients under the most characteristic accident conditions have been calculated. The mathematical model of TPA dynamics is a system of non-linear differential and algebraic equations. Some other stationary solutions may exist in such a nonlinear system besides the solution corresponding to the nominal mode of operation at the same parameter values. The presence of only one stable state of equilibrium is detected by special investigation of equations considered with parameters corresponding to the 200 MW NPP and to TPA with capacity of 2500 HP and the rotor rotational speed of 7x104 rev/min order. The conclusion that the TPA is stable and well regulated assembly introducing no anomalies in NPP dynamics, is made

  15. Nuclear power plant maintenance personnel reliability prediction (NPP/MPRP) effort at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Human errors committed during maintenance activities are potentially a major contribution to the overall risk associated with the operation of a nuclear power plant (NPP). An NRC-sponsored program at Oak Ridge National Laboratory is attempting to develop a quantitative predictive technique to evaluate the contribution of maintenance errors to the overall NPP risk. The current work includes a survey of the requirements of potential users to ascertain the need for and content of the proposed quantitative model, plus an initial job/task analysis to determine the scope and applicability of various maintenance tasks. In addition, existing human reliability prediction models are being reviewed and assessed with respect to their applicability to NPP maintenance tasks. This paper discusses the status of the program and summarizes the results to date

  16. Review of the main issues connected with the Belene NPP project

    International Nuclear Information System (INIS)

    The basic seismic studies connected with the construction of the second NPP in Bulgaria are outlined. The site selected for this plant is located on the right bank of the Donau River, near the Belene town. The seismicity of the site is investigated by the Bulgarian Academy of Sciences (BAS) and Energoproject Ltd., Sofia, and assessed by IAEA, Siemens, EQE and Westinghouse experts. The suggested coefficient for maximum seismic acceleration of 0.24 g takes into account the safety of the site, structures and equipment of the NPP. The conclusion made is that from seismic point of view the site is not hazardous. Construction works started in 1987 and were stopped in 1990 due to financial and socio-ecological reasons. The author's opinion is that the construction of the Belene NPP has no alternative and should be completed providing higher safety and reliability of the plant operation

  17. Corrosion Product Measurements to ensure integrity of the Steam Generators in Beznau NPP

    International Nuclear Information System (INIS)

    The Nuclear Power Plant Beznau comprises two identical 380 MWe PWR units with two loops each, commissioned in 1969 and 1971. Westinghouse was responsible for the primary part of the plant and BBC/ABB for the secondary circuit. The original materials used in the secondary systems were made of several copper-based alloys, such as for the Condensers, the Low Pressure Pre-heaters and the Moisture Separator Re-heater. The original Steam Generator Tubes were made of Inconel 600 MA. Regarding its age, the NPP Beznau has to be qualified as an old plant. However, in fact particularly in the last 20 years the plant has undergone an extensive modernisation programme in which about 1.5 billion Swiss Francs have been invested. Important measures were the replacements of the Steam Generators with tubes comprising Inconel 690 TT which was realized at unit 1 in 1993 and at unit 2 in 1999. Copper was completely banished from the secondary system and replaced by stainless and chromium steel. The Condensers were fitted with titanium tubes. The secondary water chemistry had to be changed by these replacements and moved step by step from Low-AVT with a pH of about 9.3 to High-AVT with a pH of 9.8 to 9.9, currently. To ensure the integrity of the new Steam Generators as well as of the whole Secondary System a corrosion product programme was introduced at the end of the Nineties. Several investigations which are performed periodically are represented by analyses of corrosion products, measurements of sludge mass and composition in the Steam Generators, Hide-Out-Return- and mass balance measurements of corrosion products in the whole circuit. Objectives of these investigations are assessments of the efficiency of the water chemistry and trend considerations regarding to the transport of corrosion products and pollutants into the Steam Generator, as well as of the potential danger of deposits and stored or absorbed pollutants. The main target of all measures is to avoid any chemical

  18. Counter-regulatory phosphatases TNAP and NPP1 temporally regulate tooth root cementogenesis

    Institute of Scientific and Technical Information of China (English)

    Laura E Zweifler; Mudita K Patel; Francisco H Nociti Jr; Helen F Wimer; Jose L Milla n; Martha J Somerman; Brian L Foster

    2015-01-01

    Cementum is critical for anchoring the insertion of periodontal ligament fibers to the tooth root. Several aspects of cementogenesis remain unclear, including differences between acellular cementum and cellular cementum, and between cementum and bone. Biomineralization is regulated by the ratio of inorganic phosphate (Pi) to mineral inhibitor pyrophosphate (PPi), where local Pi and PPi concentrations are controlled by phosphatases including tissue-nonspecific alkaline phosphatase (TNAP) and ectonucleotide pyrophosphatase/phosphodiesterase 1 (NPP1). The focus of this study was to define the roles of these phosphatases in cementogenesis. TNAP was associated with earliest cementoblasts near forming acellular and cellular cementum. With loss of TNAP in the Alpl null mouse, acellular cementum was inhibited, while cellular cementum production increased, albeit as hypomineralized cementoid. In contrast, NPP1 was detected in cementoblasts after acellular cementum formation, and at low levels around cellular cementum. Loss of NPP1 in the Enpp1 null mouse increased acellular cementum, with little effect on cellular cementum. Developmental patterns were recapitulated in a mouse model for acellular cementum regeneration, with early TNAP expression and later NPP1 expression. In vitro, cementoblasts expressed Alpl gene/protein early, whereas Enpp1 gene/protein expression was significantly induced only under mineralization conditions. These patterns were confirmed in human teeth, including widespread TNAP, and NPP1 restricted to cementoblasts lining acellular cementum. These studies suggest that early TNAP expression creates a low PPi environment promoting acellular cementum initiation, while later NPP1 expression increases PPi, restricting acellular cementum apposition. Alterations in PPi have little effect on cellular cementum formation, though matrix mineralization is affected.

  19. Knowledge Management Applications at the Paks NPP Ltd

    International Nuclear Information System (INIS)

    The objective of the human resource policy at the Paks NPP Ltd. is to make available personnel in optimal quantity, either employed or contracted, that are properly selected, trained and equipped with all knowledge, skills and attitudes required for the long term safe, competitive and reliable operation of the plant. The plant's service time extension has been approved as a consequence of which significant efforts must be turned to ensure properly prepared labor force for the long term plant operation. This is only achievable if - using knowledge related to the corporate recruitment needs and the job-specific requirements/expectations - personnel are selected from internal or external resources that can be prepared through expedient, targeted development programs to fill in positions specified as necessary for plant operations. A decisive factor of the achievements of the plant is the staff properly prepared and performing jobs with professionalism. The accumulated collective knowledge and experience of the long years are assets which, - when the future of the plant is planned - can and must be used as a firm foundation. What value does this knowledge represent, how can it be preserved and transferred to the next generation and what steps have been taken already by the plant to achieve this goal? - these are the questions that the paper is to provide a concise response for. The concise program has set the ultimate goal of - while keeping the best of traditional tools such as the spontaneous knowledge management - evolving to address KM in a planned, conscious manner, making use of the achievements of dedicated projects already terminated or on-going (like the Safety Upgrading Program, the Training Reconstruction Project or the Final Safety Report) and introducing a complex, needs-driven career and succession planning system. Planned to run on three main tracks: the selection and development of leaders in frame of the Management Pool of Talents; the selection and

  20. Current status and plans for development of NPP with BREST reactors

    International Nuclear Information System (INIS)

    This paper summarizes detailed design documentation for the nuclear power plant with a pilot demonstration fast reactor with lead coolant of 300 MW(e) output (BREST-OD-300) and on-site fuel cycle at Beloyarsk NPP site, and commencement of R and D activities to justify the design. The purpose of the work is to demonstrate feasibility of designing NPP such as to meet the following main requirements: avoidance of severe accidents at the reactor facility and nuclear fuel cycle facilities associated with radiological hazard for public; radiation-equivalent disposal of radioactive waste and their temporary storage in the region; technological support of non-proliferation regime; competitiveness

  1. Financial and economical aspects for decommissioning of NPP in Germany

    Energy Technology Data Exchange (ETDEWEB)

    Schroeder, A.; Schlingensiepen, D. [RWE Power AG, Corporate Communications, Stuettgenweg 2, 50935 Cologne (Germany)

    2003-07-01

    enclosure (2). Of RWE Power's reactors, two of them are currently decommissioned, one is in safe enclosure and for one reactor the application to decommission has been filed. The choice whether to file the application to the regulatory authorities to decommission the plant immediately after the termination of power production or to create a plant status of safe enclosure for a longer time (e.g. 30 years) and subsequently remove the plant afterwards is to the operator. The decisive factor is the operator's appraisal of the relevant technical and economical influencing factors. Experience shows that this evaluation has to be operator- and plant-specific. Either methodology implies benefits and disadvantages which have to be considered. Furthermore the operator has to decide whether the decommissioning project will be managed and executed with its own personnel or by an external contractor. The long established German legal framework obliges the operators of NPPs to ensure the safe decommissioning of the NPP and the safe and orderly disposal of all originating wastes. This obligation creates a legally defined liability of the NPP operator to decommission the nuclear installation. To ensure that the means to fulfill the obligation are available, the operator has to provide for the necessary provisions for nuclear liabilities in the balance sheet. Thus these provisions are accumulated internally. The calculation of these provisions takes into account the costs for idle operation after termination of power production, the costs for actual removal of the plant and the costs of final disposal of all wastes. Currently the European Commission is discussing proposals to establish a system of guaranteed external funds to cover the expected expenses for nuclear decommissioning. A uniform funds-concept on EU-level would discriminate against the German nuclear utilities in relation to their competitors. The different degree of liberalization established in the European countries

  2. Basic requirements for ensuring the safety of NPP extended operations (How best to achieve and ensure the safety of extended operations)

    International Nuclear Information System (INIS)

    The report contains basic requirements for prolongation of NPP extended operations. The main requirements concern obligation of operating organization for providing complex inspection, developing program for preparation NPP extended operations and justification safety. The report contains also requirements for documentation packages, submitted for obtaining license for NPP extended operations. (author)

  3. Vegetation NPP Distribution Based on MODIS Data and CASA Model——A Case Study of Northern Hebei Province

    Institute of Scientific and Technical Information of China (English)

    YUAN Jinguo; NIU Zheng; WANG Chenli

    2006-01-01

    Net Primary Productivity (NPP) is one of the important biophysical variables of vegetation activity, and it plays an important role in studying global carbon cycle, carbon source and sink of ecosystem, and spatial and temporal distribution of CO2. Remote sensing can provide broad view quickly, timely and multi-temporally, which makes it an attractive and powerful tool for studying ecosystem primary productivity, at scales ranging from local to global. This paper aims to use Moderate Resolution Imaging Spectroradiometer (MODIS) data to estimate and analyze spatial and temporal distribution of NPP of the northern Hebei Province in 2001 based on Carnegie-Ames-Stanford Approach (CASA) model.The spatial distribution of Absorbed Photosynthetically Active Radiation (APAR) of vegetation and light use efficiency in three geographical subregions, that is, Bashang Plateau Region, Basin Region in the northwestern Hebei Province and Yanshan Mountainous Region in the Northern Hebei Province were analyzed, and total NPP spatial distribution of the study area in 2001 was discussed. Based on 16-day MODIS Fraction of Photosynthetically Active Radiation absorbed by vegetation (FPAR) product, 16-day composite NPP dynamics were calculated using CASA model; the seasonal dyamics of vegetation NPP in three subregions were also analyzed. Result reveals that the total NPP of the study area in 2001 was 25.1877×106 gC/(m2·a), and NPP in 2001 ranged from 2 to 608 gC/(m2·a), with an average of 337.516 gC/(m2·a). NPP of the study area in 2001 accumulated mainly from May to September (DOY 129-272), high NPP values appeared from June to August (DOY 177-204), and the maximum NPP appeared from late July to mid-August (DOY 209-224).

  4. XIII International conference NPP safety and personnel training. Collection of works

    International Nuclear Information System (INIS)

    In the book there are the materials of the XIII International conference NPP safety and personnel training (Obninsk, October 1-5, 2013). The materials represent the level of investigations in nuclear physics and nuclear power, nuclear medicine, electronic and automatics, as well as the progress in the field of upgrading of nuclear power facilities efficiency and safety, environmental protection and personnel training

  5. Modern approach to power supply of systems important to NPP safety under in-house blackout

    International Nuclear Information System (INIS)

    The paper considers preconditions to revise a strategy of Ukrainian NPP in-house power supply and new approaches to arrangement of power supply of safety system loads from on-site power sources and mobile diesel generators. In addition, the paper shows a new scheme of power supply to safety system loads in case of blackout.

  6. Study complex of properties of the adsorbent for renewal filters of ventilation systems NPP

    International Nuclear Information System (INIS)

    Using standard and developed at NSC KIPT techniques it was carried out a comprehensive research of working characteristics (aerodynamic resistance in conditions modeling work adsorber AU-1500; mechanical strength abrasion; adsorption capacity for iodine and methyl iodide) of activated coals from different manufacturers, intended for use in rehabilitation and reconstruction of the adsorption filter ventilation system at NPP

  7. High energy pipe break analysis for a Main Steam Line of a WWER NPP

    Energy Technology Data Exchange (ETDEWEB)

    Zaccari, N., E-mail: nicola.zaccari@enel.com; Caria, S., E-mail: sara.caria@enel.com; Rubeo, G., E-mail: giampiero.rubeo@enel.com

    2014-01-15

    Highlights: • Detailed methodological approach on the High Energy Pipe Break (HEPB) analysis for NPP. • HEPB level 3 analysis on the Main Steam Line of MO3 NPP was provided. • Reducing the construction or modification cost on the NPP due to a less conservative approach as a level 1 or 2 analysis. • Innovative LBB approach to treat the through-wall crack on the piping system. -- Abstract: The aim of this study is to show the application of the High Energy Pipe Break (HEPB) methodology to a level 3 analysis, applied to the study of the Main Steam Line (MSL) of a Mochovce (MO) NPP. The analysis highlighted the significant advantage, as compared to a standard level 1 analysis, in the minimization of extra supports and restraints. In the first part of the paper an introduction on the NUREG Standard Review Plan (STRP) and on the ANSI/ANS 58.2 used as a reference in this kind of analysis is provided. In the second part a description of the analyses (coupled mechanical and fluido-dynamic) used to analyze the HEPB is described. Finally an original approach developed at ENEL is presented for an improved evaluation of the leakage cracking by following a non standard procedure related to the LBB approach, coupled with the above-mentioned HEPB.

  8. Activity level of gross α and gross β in airborne aerosol samples around the Qinshan NPP

    Institute of Scientific and Technical Information of China (English)

    CHEN Bin; YE Jida; CHEN Qianyuan; WU Xiaofei; SONG Weili; WANG Hongfeng

    2007-01-01

    The monitoring results of gross α and gross β activity from 2001 to 2005 for environmental airborne aerosol samples around the Qinshan NPP base are presented in this paper. A total of 170 aerosol samples were collected from monitoring sites of Caichenmen village, Qinlian village, Xiajiawan village and Yangliucun village around the Qinshan NPP base. The measured specific activity of gross α and gross β are in the range of 0.02 ~ 0.38 mBq/m3 and 0.10 ~ 1.81 mBq/m3, respectively, with an average of 0.11 mBq/m3 and 0.45mBq/m3, respectively. They are lower than the average of 0.15 mBq/m3 and 0.52mBq/m3, of reference site at Hangzhou City. It is indicated that the specific activity of gross α and gross β for environmental aerosol samples around the Qinshan NPP base had not been increased in normal operating conditions of the NPP.

  9. Replacement of battery in Asco NPP Chargers; Sustitucion de cargadores de baterias en C. N. Asco

    Energy Technology Data Exchange (ETDEWEB)

    Montero Lansanc, J.

    2013-07-01

    The purpose of this paper is to present the project to replace battery chargers at NPP Asco. It describes the reasons for the replacement, the project approach, the development to date and current status of the project, the economics, and some lessons learned during the process.

  10. Filtration Algorithms of Untrustworthy Analogous Information in APCS at TPP and NPP

    Directory of Open Access Journals (Sweden)

    V. Nazarov

    2012-01-01

    Full Text Available The paper considers filtration algorithms of untrustworthy analogous information in APCS at TTP and NPP that make it possible to identify credibility of information transmitted through communication channels in the form of signals and which are continuously changeable in the regime of real time.

  11. Evaluation of Radiation Impacts of Spent Nuclear Fuel Storage (SNFS-2) of Chernobyl NPP - 13495

    International Nuclear Information System (INIS)

    Radiation effects are estimated for the operation of a new dry storage facility for spent nuclear fuel (SNFS-2) of Chernobyl NPP RBMK reactors. It is shown that radiation exposure during normal operation, design and beyond design basis accidents are minor and meet the criteria for safe use of radiation and nuclear facilities in Ukraine. (authors)

  12. Human actions treatment in the Juragua NPP pre-operational PSA

    International Nuclear Information System (INIS)

    The human reliability analysis is an important part of the Probabilistic Safety Analysis (PSA). Because Juragua NPP PSA has been accomplished during construction stage of the plant, no specific operational procedures nor experience for human reliability analysis task taking into account the worlds current methodologies in this field and the actual situation of the plant. This papers describes the approach we followed

  13. Post-Launch Calibration Support for VIIRS Onboard NASA NPP Spacecraft

    Science.gov (United States)

    Xiong, Xiaoxion; Chiang, Kwo-Fu; McIntire, Jeffrey; Schwaller, Matthew; Butler, James

    2011-01-01

    The NPP Instrument Calibration Support Element (NICSE) is one of the elements within the NASA NPP Science Data Segment (SDS). The primary responsibility of NICSE is to independently monitor and evaluate on-orbit radiometric and geometric performance of the Visible Infrared Imaging Radiometer Suite (VIIRS) instrument and to validate its Sensor Data Record (SDR) [1]. The NICSE interacts and works closely with other SDS Product Evaluation and Analysis Tools Elements (PEATE) and the NPP Science Team (ST) and supports their on-orbit data product calibration and validation efforts. The NICSE also works closely with the NPP Instrument Calibration Support Team (NICST) during sensor pre-launch testing in ambient and thermal vacuum environment [2]. This paper provides an overview of NICSE VIIRS sensor post-launch calibration support with a focus on the use of sensor on-board calibrators (OBC) for the radiometric calibration and characterization. It presents the current status of NICSE post-launch radiometric calibration tool development effort based on its design requirements

  14. Transformations of humus and soil mantle in the urbanized areas of the Chernobyl NPP exclusion zone

    International Nuclear Information System (INIS)

    Presented are investigations into the demutation processes of the towns plant community in the Chernobyl NPP exclusion zone (Pripyat, Chernobyl, Chernobyl-2). Demonstrated is the specific nature of the reduction of humus and soil mantle in the abandoned towns under the impact of the natural factors. 21 refs., 5 tab., 7 figs

  15. Mechanisms governing the physico-chemical processes of transfer in NPP circuits

    International Nuclear Information System (INIS)

    The paper deals with the theoretical physico-chemical processes of corrosion products and their radionuclide transport in NPS circuits by thermoelectromotive and electromotive forces of microgalvanic couples. The laboratory and rig test results as well as the NPP operating experience data confirm the developed theoretical concept validity

  16. Preliminary site investigation for LL and IL radwaste disposal for Qinshan NPP

    International Nuclear Information System (INIS)

    With the purpose of selecting a disposal site for the low- and intermediate-level radwastes arising from Qinshan NPP, site investigations were carried out in several districts of Zhejiang Province. Investigation objectives included the circumstances of geology, hydrogeology, environmental ecology, and social economy. On the basis of collected data, five possible sites were recommended for policy-making reference and further investigation

  17. Controlled test compiling and programming automatization for the NPP operator training system

    Energy Technology Data Exchange (ETDEWEB)

    Gevorkyan, A.S.; Muradyan, S.G.; Oganesyan, R.A.; Pogosyan, V.Sh.

    1984-01-01

    Problems of control test compiling and programming for the NPP operator training system (OTS) are considered. Types of control questions and answers to them used in the OTS for arrangement of admittance and current control of knowledge are given. A method for control test compiling and programming automation for OTS is described.

  18. Distinct characteristics of NPP HRD and establishment of KINGS in Korea

    International Nuclear Information System (INIS)

    Full text:Korean government set-up nuclear energy department within the ministry of education in 1956 and joined IAEA in 1957 and set up nuclear energy agency in 1959, and installed the first research reactor in 1962. The Korean Government started constructing NPP in 1971 that had started commercial operation in 1978. The first oil shock in 1973 had devastated Korean economy and that made Korean Government to accelerate the construction of NPPs. Since then Korea steadily constructed NPP as well as invested in the development of indigenized NPP technology. During 1990s, Korea developed KSNP PWR 600 MWe NPP and in the last decade Korea developed APR1400 MWe NPP. Through the time, the engineers and operators involved in every field of nuclear industry is getting old and started to retire. Someone freshly out from the university with bachelor or post graduate degree will take many years to be able to understand how things running and operating in nuclear industry. Even in many years of job assignment, one cannot experience and understand all aspect of nuclear industry. It is this reason to establish a special educational system to teach people already in the field and to be able to see the whole picture by systematically teaching most of the related subject. In order to prevent any influence from existing university system, it was determined to establish KINGS (KEPCO International Nuclear Graduate School) as separate and independent institution and as a post-graduate institution. The curriculum of KINGS was set up along this philosophy, and has only one academic department, for example NPP Engineering Department, to make more interactions among faculty and students. Also the curriculum is set up to teach practical experience; hence the graduates can bridge between industry and academia as well as fill in the large gap of technical experience of older generation. Also another aim is to make KINGS international institution to share experience of Korean NPP development

  19. Local network deployed around the Kozloduy NPP - a useful tool for seismological monitoring

    Science.gov (United States)

    Solakov, Dimcho; Simeonova, Stela; Dimitrova, Liliya; Slavcheva, Krasimira; Raykova, Plamena; Popova, Maria; Georgiev, Ivan

    2015-04-01

    Radiation risks may transcend national borders, and international cooperation serves to promote and enhance safety globally by exchanging experience and by improving capabilities to control hazards, to prevent accidents, to respond to emergencies and to mitigate any harmful consequences. International safety standards provide support for states in meeting their obligations under general principles of international law, such as those relating to environmental protection. Seismic safety is a key element of NPP safe operation. Safety and security measures have in common the aim of protecting human life and health and the environment. The Kozloduy NPP site is located in the stable part of the Moesian platform (area of about 50000 km2). From seismological point of view the Moesian platform is the most quite area on the territory of Bulgaria. There are neither historical nor instrumental earthquakes with M>4.5 occurred within the platform. The near region (area with radial extent of 30 km) of the NPP site is characterized with very low seismic activity. The strongest recorded quake is the 1987 earthquake МS=3.6, localized 22 km northwest of the Kozloduy NPP site on the territory of Romania. In line with international practice, the geological, geophysical and seismological characteristics of the region around the site have been investigated for the purpose of evaluating the seismic hazards at the NPP site. A local network (LSN) of sensitive seismographs having a recording capability for micro-earthquakes have been installed around Kozloduy NPP and operated since 1997. The operation and data processing, data interpretation, and reporting of the local micro-earthquake network are linked to the national seismic network (NOTSSI). A real-time data transfer from stations to National Data Center (in Sofia) was implemented using the VPN and MAN networks of the Bulgarian Telecommunication. Real-time and interactive data processing are performed by the Seismic Network Data

  20. The impact of CTRF decommissioning radioactive waste at Saligny radioactive waste repository. A balance between requirements and ethical aspects of radioactive waste management for future generations

    International Nuclear Information System (INIS)

    Full text: In this paper presented are the technical and non-technical conditions and requirements posed by decommissioning of Detritiation Plant (CTRF) at Cernavoda NPP and waste management resulting from this operation. Radioactive waste resulting from decommissioning will be stored at The Final Repository for Low and Medium Active Waste (DFDSMA) at Saligny. As this repository was dimensioned for radwastes resulting from only four CANDU 6 units, additional amounts of radwastes could conflict with the limited storage capacity. Moreover, in case of decommissioning of Detritiation Plant a balance between ethical aspects towards the future generations and requirements of radwaste management appears to be necessary. (authors)

  1. Effect of dietary NPP level and phytase supplementation on the laying performance over one year period

    Directory of Open Access Journals (Sweden)

    Annamaria Tischler

    2015-06-01

    Full Text Available Our trial was aimed to study the effect of different dietary non-phytin phosphorus (NPP levels with and without phytase enzyme supplementation on laying performance and eggshell quality of Tetra SL-LL in the last 25 weeks of the long-term (17 months egg production. A total of 69 Tetra SL-LL layers were allocated into 3 dietary treatments. Two diets with different levels of NPP (2.45 or 2.15 g/kg, HP and LP, respectively were formulated, and 0 or 300 FTU/kg phytase enzyme was added to low NPP feed (LP and LP+E, respectively. Dietary Ca was uniformly adjusted (38.2 g/kg to feed in each treatment. In the course of the trial, intensity of egg production (%, egg weight (g/egg, number of the broken eggs and feed intake (g/d/bird were recorded. Every 2 weeks 20 eggs per treatment were broken to determine the shell strength and thickness. Our results show that low NPP diet had detrimental effect on the intensity of egg production (P<0.05 and phytase added to the LP diet resulted the lowest number of broken eggs (P<0.05. In conclusion, NPP content of the layer diet can be reduced from 2.45 to 2.15 g/kg in the last 25 weeks of the elongated laying term (12-17 month of laying, if supplemented with 300 FTU/kg phytase enzyme without compromising the egg production, and in the same time it can improve eggshell quality and reduce the number of broken eggs.

  2. The sensitivity of NPP to climate controls in northern China estimated by CLM model coupled with RS and GIS technology

    Science.gov (United States)

    Gao, Zhiqiang; Gao, Wei; Slusser, James R.; Pan, Xiaoling; Ma, Yingjun

    2003-07-01

    The continuing rise in atmospheric CO2 is considered as a main cause of the future changes in global climate. Predicted climate changes include an increase in mean annual air temperature and alterations in precipitation pattern and cloud cover. Net primary productivity (NPP) measures products of major economic and social importance, such as agricultural crop yield and forest production. It is important to understand the response of vegetation to the possible climate changes. While the Global NPP is hard to be measured directly, its global spatial and temporal dynamics can be investigated by a combination of ecosystem process modeling and monitoring by remote sensing (RS). NPP has been linked to climatic patterns by approaches ranging from simple correlations to sophisticated simulation models. This study was conducted in a range where the productivity and climate exist along an east-west transect in northern China. We used modified Common Land Surface Model (CLM) to simulate the NPP combined with satellite data and assessed the response of NPP under different climate change controls with different land surface vegetation types in study areas. The feasibility of the CLM model was tested and parameterized based on the ecological characteristics. The response of NPP to increased temperature was more sensitive to the doubled CO2 climate because the temperature is the limited factor to vegetation growth in study areas. The responses of NPP to different climate controls were also influenced by different vegetation types and ecological characteristics.

  3. Prioritization of Delay Factors for NPP Construction Risk in International Project by Using AHP Methodology

    International Nuclear Information System (INIS)

    It is crucial for the nuclear power plant project decision makers and management personnel to identify the actual factors of construction delay and their ranking in order to take preventive actions. NPP project is complex in nature and the construction phase is one of the most key phase which is subject to many factors result from many sources. From experience, nuclear projects have faced challenges similar to other complex mega projects with additional nuclear specific issues and life time cost of nuclear reactor is concentrated upfront as capital cost, and therefore delays in construction may become intolerable in terms of both lost revenues and interest on the capital. Budget over-runs and delays on next generation new build nuclear projects in recent years clearly demonstrate that the nuclear industry continues to repeat its failed management and project control processes of the past. Similar to major infra-structure projects, actual completion times can vary substantially from initial estimates but this uncertainty is too crucial to the nuclear industry due to high levels of capital at risk, for every year a project is delayed the levelized cost of electricity increases by approximately 8-10%. causes of delay, to develop a generalized AHP model for delay factors, and to prioritize the risk in different factors in various levels of construction phase in international turnkey NPP project. This paper describes and prioritizes Nuclear Power Plant (NPP) construction schedule delay factor for turnkey international project. This study also determines the different party's importance in percentage behind the construction schedule delay of NPP which constitutes main contractor (28.4%), regulatory authority (27.3%), financial and country factor (23.5%), and utility (20.8%). Decision makers of nuclear industry can understand the significance of different factors on NPP construction phase and they can apply risk informed decision making to avoid unexpected

  4. Thiazolo[3,2-a]benzimidazol-3(2H)-one derivatives: Structure-activity relationships of selective nucleotide pyrophosphatase/phosphodiesterase1 (NPP1) inhibitors.

    Science.gov (United States)

    Lee, Sang-Yong; Perotti, Arianna; De Jonghe, Steven; Herdewijn, Piet; Hanck, Theodor; Müller, Christa E

    2016-07-15

    Ecto-nucleotide pyrophosphatase/phosphodiesterase1 (NPP1) is the most important member of the NPP family, which consists of seven closely related proteins (NPP1-NPP7). This glycoprotein is a membrane-associated or secreted enzyme, which catalyzes the hydrolysis of a wide range of phosphodiester bonds, e.g., in nucleoside triphosphates, dinucleotides and nucleotide sugars. NPP1 plays a crucial role in various physiological functions including bone mineralization, soft-tissue calcification, and insulin receptor signaling. Recently, an upregulated expression of NPP1 has been observed in astrocytic brain cancers. Therefore, NPP1 has been proposed as a novel drug target for the treatment of glioblastoma. Despite their therapeutic potential, only few NPP1 inhibitors have been reported to date, which are in most cases non- or only moderately selective. The best investigated NPP1 inhibitors so far are nucleotide derivatives and analogs, however they are not orally bioavailable due to their high polarity. We identified thiazolo[3,2-a]benzimidazol-3(2H)-one derivatives as a new class of NPP1 inhibitors with drug-like properties. Among the 25 derivatives investigated in the present study, 2-[(5-iodo-2-furanyl)methylene]thiazolo[3,2-a]benzimidazol-3(2H)-one (17) was found to be the most potent NPP1 inhibitor with a Ki value of 467nM versus ATP as a substrate and an un-competitive mechanism of inhibition. Compound 17 did not inhibit other human ecto-nucleotidases, including NTPDase1 (CD39), NTPDases2-3, NPP2, NPP3, tissue-nonspecific alkaline phosphatase (TNAP), and ecto-5'-nucleotidase (eN, CD73), and is thus highly selective for NPP1. PMID:27265686

  5. Evolution of NPP personnel training: trends, new needs and performance improvement focus

    International Nuclear Information System (INIS)

    Full text: INTRODUCTION. During recent decades new training needs and demands for improving human performance have appeared in the nuclear industry, including the following: integrated management systems; more demanding safety requirements; implementation of emergency procedures; more attention to emergency preparedness; training on the beyond design basis accident (BDBA) management; challenge to increase both NPP and training efficiency and effectiveness; equipment and workforce ageing; use of training as a tool for preservation of knowledge; modernization of plants; new designs; upgrades of training tools including full-scope simulators; programmes for optimization of NPP maintenance; a growing number of decommissioning projects; availability of new computer-based training technologies; increasing attention to the competence of NPP managers; development of infrastructures in countries expanding their nuclear power sectors or initiating nuclear power programmes. The opening of electricity markets has led some nuclear power plant operating organizations to be under serious economic pressure with a demand for cost reductions and performance improvements. These factors necessitate NPP operating organizations to make their training more cost-effective. As the nuclear power industry continues to be challenged to maintain high safety standards, while responding to the pressures of more competitive energy markets, it becomes more important than ever to maintain excellence in human performance and ensure that NPP personnel training adds value to the organization. It has been increasingly recognized that in order to achieve excellence in human performance, in addition to technical competencies it is also important to focus on open communication; teamwork; leadership; problem resolution; safety consciousness; business performance; ethics and professionalism. TRAINING TRENDS. Operational and safety performance indicators have shown significant improvements in both NPP and

  6. Nuclear power plant (A-1 NPP) SE a.s., Bohunice A-1

    International Nuclear Information System (INIS)

    The A-1 NPP was connected to the grid on 25 December 1972. The first serious refuelling accident happened on 5 April 1976. The second accident occurred on 22 February 1977 when a fouled fuel assembly was overheated, melted, and consequently radioactivity entered the whole primary circuit of steam generators, and a portion of it also leaked into the secondary circuit. The accident was classified as INES 4 level. There were no leaks of radioactivity into environment during the accident. A programme and schedule of bringing the A-1 NPP into a radiation-safe status was precise by subsequent decrees of the Slovak Government in 1993-1994. In January 1995, the Project was submitted to Nuclear Regulatory Authority of the Slovak Republic (NRA SR) and updated schedule of works was approved by the Government of the Slovak Republic. The radiation-safe status is characterised by minimizing of excluding a risk of negative environmental impacts of a NPP. There were 439 of total of 571 spent fuel assemblies transported to the former Soviet Union in 1984 through 1990. The remaining 132 assemblies are 'difficult-to-handle', ones the assemblies can not be taken out of their cases. Current solution the activities associated with transport and improvement of a safe storage of the spent fuel, issues related to processing, treatment, and storage of liquid radioactive wastes is represented by Bohunice treatment centre that has been built since 1993. In addition to Slovak partners, there are also foreign ones who are involved in bringing A-1 NPP into a radiation-safe status. The largest share of works is taken by British AEA Technology together with SGN, France. Other European countries are involved in A-1 NPP decommissioning, too, by providing technical assistance within PHARE programmes. Japan also provides funding of a broad programme of information exchange about NPPs decommissioning. Activities of nuclear safety inspectors were performed according to NRA SR yearly plan of inspection

  7. Experience for plant monitoring design in Italian BWR NPP and future trends in man-machine interface

    International Nuclear Information System (INIS)

    TMI accidental sequence and daily-gained operating experience on italian and abroad NPPs have affected in depth the approach to the design of information presentation to the Control Room staff. It has been cleared that most problems in plant operation arise from a poor and inadequate information system. The main lacks have been identified in the Control Room lay-out and information organization. This has pushed designers both to improve the Control Room environment and to better exploit the computer data processing and data presentation capabilities. The paper deals with the basic criteria for the design and the design review of a computerized system to be inserted in a hybrid Control Room in Italian 981 Mwe BWR-6 NPP, where the concepts outlined above were taken-up from the very beginning. The Control Room keeps conventional instrumentation arranged in a human-factor lay-out, according to post-TMI requirements, and adds a powerful computer-based information system for advanced alarm presentation and plant supervision during both normal and emergency conditions with high data reliability. Colour videounits and operating panels are functionally integrated to create powerful operator work-stations. Emphasis is mostly given on the revision work for video-unit displays and Man-System Communication carried out in cooperation with Halden Reactor Project human factor and plant operation experts. The work peculiarity has been a strong care on the integration between conventional and computerized information presentation, with particular regard to common information and code consistency. (author)

  8. Atucha II NPP full scope simulator modelling with the thermal hydraulic code TRAC{sub R}T

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, Pablo Rey; Ruiz, Jose Antonio; Rivero, Norberto, E-mail: prey@tecnatom.e, E-mail: jaruiz@tecnatom.e, E-mail: nrivero@tecnatom.e [Tecnatom S.A., Madrid (Spain)

    2011-07-01

    In February 2010 NA-SA (Nucleoelectrica Argentina S.A.) awarded Tecnatom the Atucha II full scope simulator project. NA-SA is a public company owner of the Argentinean nuclear power plants. Atucha II is due to enter in operation shortly. Atucha II NPP is a PHWR type plant cooled by the water of the Parana River and has the same design as the Atucha I unit, doubling its power capacity. Atucha II will produce 745 MWe utilizing heavy water as coolant and moderator, and natural uranium as fuel. A plant singular feature is the permanent core refueling. TRAC{sub R}T is the first real time thermal hydraulic six-equations code used in the training simulation industry for NSSS modeling. It is the result from adapting to real time the best estimate code TRACG. TRAC{sub R}T is based on first principle conservation equations for mass, energy and momentum for liquid and steam phases, with two phase flows under non homogeneous and non equilibrium conditions. At present, it has been successfully implemented in twelve full scope replica simulators in different training centers throughout the world. To ease the modeling task, TRAC{sub R}T includes a graphical pre-processing tool designed to optimize this process and alleviate the burden of entering alpha numerical data in an input file. (author)

  9. Extent estimation of different factors influence on the corrosion cracking of steels type X18H10T in NPP

    Energy Technology Data Exchange (ETDEWEB)

    Stjazhkin, P.S.; Kritski, V.G.; Simanovski, V.M.; Kovalev, S.M.; Malov, M.Ju.; Butorin, S.L. [All-Russean Design and Scientific Research Inst. of Complex Power Technology (VNIPIET), St. Petersburg (Russian Federation)

    2002-07-01

    1. Results of the performed complex study of chemical and physical factors effect on pipelines DU-300 integrity proves that in HT and going to power conditions under reactor RBMK-1000 operation there are most favourable conditions for origin and further undergrowth of crack in near-joint zones of pipelines and equipment made of steel X18H10T. These conditions are defined by high concentration of oxygen and electric conductivity of the coolant, higher in comparison with NOC (operation at power) stressed-and-strained state of units being loaded with additional dynamic loads. 2. Results received are of an evaluating character, they show only that under start-up operations after thermal shutdown an accelerated growth of cracks is most probable. 3. In view of a general trend of prolongation of operation terms of NPP with RBMK-1000 (LNPP including), realization of procedures to decrease probability of occurrence and evolution of CCS in equipment and pipelines and introduction of a system of corrosion monitoring is one of the actual tasks. 4. An additional measure can be a validated transition to hydro-pressing of the circuit at lower temperature (80-90 C). (authors)

  10. The results of fluorescence spectrums of oak and birch leaves investigation from the 30-km influenced zone of Chernobyl NPP

    International Nuclear Information System (INIS)

    The results of a long-term research of laser induced fluorescence of foliage tree' leaves (oak, birch) that grow in different conditions of radioactive pollution (30-km zone of Chernobyl NPP) are presented

  11. Co-operation - the key to success

    International Nuclear Information System (INIS)

    The Romanian nuclear power industry is still a young one. Less than six years elapsed since the Unit 1 of Cernavoda NPP started its commercial operation. Nevertheless, the performance indicators recorded by the Unit 1 during this period are very good what is doubtless the combined effect of a good design, high quality main equipment, correct installation and a very qualified, skilled operation. The cooperation established during the construction between the station's personnel, designers, equipment manufacturers and other organizations is going on and should be developed in the future during the work of Unit 2 completion which is planned to be connected to the national electricity grid by the year 2005. Preparation of that event includes recruitment of new personnel and training of the existing personnel. This process is a task of the station's Training Center which have projects in cooperation with University 'Politehnica' of Bucharest. The events in 1989 blocked for a while the activities related to Unit 2 which has been although restarted after a delay of several years. In the new circumstances, new policy concerning the profile and size of the infrastructure, particularly, the contribution of the Romanian nuclear power industry have been defined. Although, the international cooperation in this field remains a 'must', the benefits of which should be used by Romania as much as possible. This is particularly important having in view that Romania has operated only a single nuclear unit with a history of only six years of operation. Hence, the need of developing international cooperation not only with AECL - Canada and ANSALDO - Italy but also with organizations like General Electric - USA, Siemens - Germany, NEXANS -France, Furmanite - UK, etc. We have also various connections with organizations of abroad operating nuclear power stations similar with Cernavoda NPP, from Canada, Korea, Argentina, India and China. As IAEA and WANO member we hosted in Cernavoda

  12. Establishing a relationship with media

    International Nuclear Information System (INIS)

    The Cernavoda NPP site is in Constanta County in the Dobrogea region. Within a 30-km radius of the Cernavoda NPP site there are several historical monuments and archaeologically significant ruins, some of which date to Greek and Roman times. There are also four natural reserves. None of these features are sufficiently close to the NPP to be disturbed by its operation The start of the nuclear program in Romania, about 20 years ago, was a high-level government decision based on economical and political considerations, but without any commitment or acceptance of the people. Unit 1 delivers to the national grid 20% of the national electricity demand, in 1998 the gross capacity factor was 86.19%. Cernavoda is the only nuclear station operating in the country. The plant has been in commercial operation a little more than three years, so the Public Relations Department is a fledgling one. The site PR group was first formed during the latter stages of the construction. The PR group has to deal with the changing of the access to the information, still going on in Romania. First, the PR group had the public who used to view the information with apathy and scepticism, as the information was coming from a single controlled source. The same public today views the information with the scepticism and apathy, confused by the unrestricted access to the information. First, the information was unbelievable, and now it is bewildering. The PR group is in the middle of this change. We must convince the public that the messages we put out are factual and that this is an honest exchange. The challenge before is to build a bridge of understanding and trust between the NPP and the public. The PR group has the necessary foundation on the NPP side and the full commitment from the management. What are needed are a formation of a group of public sufficiently interested in the affairs of the NPP and the influence of the NPP on the life of community

  13. Radiometric Inter-Calibration between Himawari-8 AHI and S-NPP VIIRS for the Solar Reflective Bands

    OpenAIRE

    Fangfang Yu; Xiangqian Wu

    2016-01-01

    The Advanced Himawari Imager (AHI) on-board Himawari-8, which was launched on 7 October 2014, is the first geostationary instrument housed with a solar diffuser to provide accurate onboard calibrated data for the visible and near-infrared (VNIR) bands. In this study, the Ray-matching and collocated Deep Convective Cloud (DCC) methods, both of which are based on incidently collocated homogeneous pairs between AHI and Suomi NPP (S-NPP) Visible Infrared Imaging Radiometer Suite (VIIRS), are used...

  14. Accident at TEPCo’s Fukushima-Daiichi NPP - LL for Operator/Industry

    International Nuclear Information System (INIS)

    Lessons Learned - Emergency Management: • Loss of communication tool and plant information (SPDS) at NPP; • Dissemination of information: - Damage to social infrastructure by earthquake hampered dissemination of information to local government and residents: - Lack of Information sharing with local residents on dispersion of FP (SPEEDI) and risk of radiation with neighboring countries on release of slightly-contaminated water: - “Data but not information”; •Who is in charge?: - Ambiguity in delineation of responsibility; - Recognized role by Joint (Government and TEPCO) ERC and local resources center 20—30km away from NPP; • Offsite center: function was lost by loss of electricity and radiation; • Effective channeling of emergency supports: - Systematize domestic/foreign helping hands for logistics/experts

  15. An application of A.I. to organizational learning in an operating NPP

    International Nuclear Information System (INIS)

    An A.I. type approach is developed in order to rapidly and systematically integrate the various elements of human and structural learning (e.g. cognitive representations, feedback and interactions within an operating NPP. The objective followed is to develop throughout a functioning plant and over a relatively brief period (6 weeks), a measurement and diagnostic program involving all plant personnel. Measurements are positioned within a three-dimensional polarized factor space and feedback to participants with the transfer of analytic tools. This program has been applied in a French nuclear power plant. The gain in organizational knowledge is tested. One year after first-wave measures, measurement is repeated with the same population and the same objects. Interim evolutions along NPP criteria (e.g. lost-time accident rate) are observed. The parallel evolutions between participant diagnostic data and operating criteria seem to indicate an improved level of organizational learning

  16. Women in nuclear energy – motivation and prospects at Kozloduy NPP report

    International Nuclear Information System (INIS)

    The report presents part of the study of the staff motivation at Kozloduy NPP plc, which is performed annually. A total of 25 factors have been considered, and for 8 of them the internal motivation characteristics have been discussed, while the remaining 17 factors determine the satisfaction from external motivation stimuli: positive ones (remuneration, bonuses, awards, etc.), as well as negative (little lead time, sanctions, punishments, excessive control in the performance of tasks, etc.). Women in the nuclear industry contribute to the unique image of nuclear organisations and are an especially valued asset. In the selection of staff for vacancies there is no sex discrimination, and it is increasingly becoming evident from the number of women employed in jobs considered until recently as typically male. The satisfaction from the measured Internal motivation factors concerning the women working at Kozloduy NPP is presented in this work.

  17. Analysis of a buried pipeline at WWER-440/213 Paks NPP

    International Nuclear Information System (INIS)

    According to regulations, all safety structures of a NPP must be designed to withstand loads induced by earthquakes. This applies to safety related underground piping systems. These structures are typically embedded in about 2-3 m of layered soil, and sometimes protected by concrete slabs resting on the ground surface. A rigorous solution for the dynamic response of such a structure would require accounting for nonlinear and three dimensional effects. A non-linear analysis is possible by using specialized computer codes and material models to account for non-linear behaviour of the soil. The aim of this paper was to reanalyze the pipeline of Paks NPP in order to demonstrate its dynamic behaviour interacting with the soil and the connected buildings as well as to determine the dynamic responses and the stresses in typical regions of the pipeline. To perform the numerical analysis a three dimensional finite element code (SSASSI/S) based on 'flexible volume method' was applied

  18. Impact of EM Emissions from WSN Nodes on Sensitive Protection Equipment in NPP - an experimental characterization

    International Nuclear Information System (INIS)

    There is a concern about the impacts of EMI/RFI from wireless devices on the sensitive instruments in the existing safety and protection systems in a NPP. This concern is legitimate, as several shut downs of NPPs have been attributed to the EMI/RFI from the wireless devices. However, these experiences are mostly due the use of higher-powered wireless devices such as a walkie-talkie. In contrast, a typical low-power WSN module, operating at a higher frequency bands appears to have minimal EMI/RFI impacts to safety instruments. The case studies and experimental results have also supported this observation. It is therefore concluded that a WSN system that uses low-power transmitters and operates at high frequency bands cause no noticeable adverse effects to the instruments in safety related I and C systems in a NPP

  19. Impact of EM Emissions from WSN Nodes on Sensitive Protection Equipment in NPP - an experimental characterization

    Energy Technology Data Exchange (ETDEWEB)

    Ataul, Bari; Wang, Quan; Jin, Jiang; Chen, Dongyi [University of Western Ontario, Ontario (China); Li, Liqian [Atomic Energy of Canada Limited, Chalk River (Canada); Chen, Dongyi [University of Western Ontario, Ontario (Canada)

    2014-08-15

    There is a concern about the impacts of EMI/RFI from wireless devices on the sensitive instruments in the existing safety and protection systems in a NPP. This concern is legitimate, as several shut downs of NPPs have been attributed to the EMI/RFI from the wireless devices. However, these experiences are mostly due the use of higher-powered wireless devices such as a walkie-talkie. In contrast, a typical low-power WSN module, operating at a higher frequency bands appears to have minimal EMI/RFI impacts to safety instruments. The case studies and experimental results have also supported this observation. It is therefore concluded that a WSN system that uses low-power transmitters and operates at high frequency bands cause no noticeable adverse effects to the instruments in safety related I and C systems in a NPP.

  20. Requirements on mechanistic NPP models used in CSS for diagnostics and predictions

    International Nuclear Information System (INIS)

    Mechanistic models have for several years with good experience been used for operators' support in electric power dispatching centres. Some models of limited scope have already been in use at nuclear power plants. It is considered that also advanced mechanistic models in combination with present computer technology with preference could be used in Computerized Support Systems (CSS) for the assistance of Nuclear Power Plant (NPP) operators. Requirements with respect to accuracy, validity range, speed flexibility and level of detail on the models used for such purposes are discussed. Quality Assurance, Verification and Validation efforts are considered. A long term commitment in the field of mechanistic modelling and real time simulation is considered as the key to successful implementations. The Advanced PROcess Simulation (APROS) code system and simulation environment developed at the Technical Research Centre of Finland (VTT) is intended also for CSS applications in NPP control rooms. (author). 4 refs