Load flow analysis for determining the location of NPP power distribution in West Kalimantan

International Nuclear Information System (INIS)

Citra Candranurani; Rizki Finnansyah Setya Budi; Sahala M Lumbanraja

2015-01-01

Electricity crisis condition happened in West Kalimantan (Kalbar) as a result of power plant capacity almost equal to the peak load. The system will experience a shortfall if there are plants that not operating and do not have reserve. The policy of electricity planning until 2022 is replacing diesel power plant with steam power plant. For long-term planning is required the role of new and renewable energy in order to reduce dependency on fossil fuel consumption, such as NPP utilization. The purpose of this study was to determine the optimum location of the NPP power distribution in order to prepare electricity infrastructure. Load flow calculation in this study using ETAP 12.5 software. NPP is planned to supply base load, so the optimum capacity factor is above 80 %. The result show that there are three location where NPP can generate over 80 % of its capacity, namely: Mempawah Substation, Singkawang Substation, and Sambas Substation. The most optimum located in Mempawah Substation with capacity factor 83.5 %. The location of the three Substation are onshore and in line with one requirement for NPP construction, namely: the availability of cooling water. (author)

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

International Nuclear Information System (INIS)

Vaneev, M.

2001-01-01

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

Assessment of financial expenditure for Rivne NPP power units decommissioning

International Nuclear Information System (INIS)

Nosovskij, A.V.; Salij, L.M.

2007-01-01

The article covers some financial aspects of developing a decommissioning concept for Rivne NPP power units with reactor VVER-440 and VVER-1000. Possible methodological approaches to costs estimate have been analyzed. Preliminary results of cost estimation are presented for two decommissioning options: deferred and immediate dismantling. Principally possible options for accumulating assets have been analyzed to finance measures related to Rivne NPP decommissioning. A mathematical model has been proposed for creating decommissioning financial reserve

“Through the Letter Sent with my Envoys to Kiev” St. Dimitry`s of Rostov Contacts with Kiev and Chernigov in 1701–1709

Directory of Open Access Journals (Sweden)

Krylov Aleksei

2016-10-01

Full Text Available The article examines st. Dimitry’s of Rostov contacts with Kiev and Chernigov in 1701–1709. Dimitry’s correspondence is vast, but addressees of the most of the known letters are Dmitry’s Moscow friend and Great Russian hierarchs. Problem of st. Dimitry’s contacts with his Little Russian acquaintances still remain obscure. This article deals with the information of st. Dimitry of Rostov correspondence with addressees in Kiev and Chernigov and the circumstances of Dimitry’s visit to Chernigov in 1704. In time of his episcopal service st. Dimitry exchanged letters with Josaph Krokowski, archimandrit of Kievan Lauras and future metropolitan of Kiev. Letters were sent with agents of both hierarchs. This correspondence was devoted to the publication of the “Lives of the Saints” in the Lavra’s typography. There are no evedencies of st. Dimitry writing letteres to members of Chernigov clergy in 1701–1709, although st. John Maximovich archbishop of Chernigov sent his new books to Dimitry of Rostov. However in february of 1704st. Dmitry undertook a journey to Chernigov that left almost no traces in sources. The main evidence is record of Pachomios of Roman, a Moldavian ascetic, about himself meeting Rostov metropolitan in Chernigov in 1704. This trip was an exeptional event and could be connected with the demise of Parthenios Neboza, metropolitan of Holmogory, who died suddenly on 2 january 1704 in Yaroslavl. Author concludes that Dimitry of Rostov in 1701–1709 was not isolated from his old friends and mantained his ties with educated clergy of Little Russia during the years of his Episcopal service in Moscow and Rostov.

76 FR 46330 - NUREG-1934, Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG); Second Draft...

Science.gov (United States)

2011-08-02

... NUCLEAR REGULATORY COMMISSION [NRC-2009-0568] NUREG-1934, Nuclear Power Plant Fire Modeling... 1023259), ``Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG), Second Draft Report for...), ``Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG), Second Draft for Comment,'' is...

Arrangement of the Krsko NPP protection scheme for the power system malfunction cases

International Nuclear Information System (INIS)

Omahen, P.; Pavsek, J.; Dirnbek, V.

1996-01-01

The Krsko NPP has been designed with the capability to reject 100% of its rated power and runback to the station electrical load. However, an adequate detection system of the outside network degradation is needed for the activation of the existing load drop anticipated (LDA) function. The Krsko NPP electrical, turbine and generator protection systems were carefully evaluated in order to redesign some of its functions. These additional functions should be able to protect and disconnect the plant from the system whenever some serious trouble of the outside electric power system is detected. On the other side, preventive measures should be introduced to avoid unnecessary plant disconnection or unnecessary power system collapse due to such disconnection. At the end, the paper presents a precise design of additional function possibilities for the Krsko NPP electrical protection system. A critical evaluation of these functions is given and the best option is proposed. (author)

NPP life management (abstracts)

International Nuclear Information System (INIS)

Litvinskij, L.L.; Barbashev, S.V.

2002-01-01

Abstracts of the papers presented at the International conference of the Ukrainian Nuclear Society 'NPP Life Management'. The following problems are considered: modernization of the NPP; NPP life management; waste and spent nuclear fuel management; decommissioning issues; control systems (including radiation and ecological control systems); information and control systems; legal and regulatory framework. State nuclear regulatory control; PR in nuclear power; training of personnel; economics of nuclear power engineering

Digital Components in Swedish NPP Power Systems

International Nuclear Information System (INIS)

Karlsson, Mattias; Eriksson, Tage

2015-01-01

Swedish nuclear power plants have over the last 20 years of operation modernised or exchanged several systems and components of the electrical power system. Within these works, new components based on digital technology have been employed in order to realize functionality that was previously achieved by using electro-mechanical or analogue technology. Components and systems such as relay protection, rectifiers, inverters, variable speed drives and diesel-generator sets are today equipped with digital components. Several of the systems and components fulfil functions with a safety-role in the NPP. Recently, however, a number of incidents have occurred which highlight deficiencies in the design or HMI of the equipment, which warrants questions whether there are generic problems with some applications of digital components that needs to be addressed. The use of digital components has presented cost effective solutions, or even the only available solution on the market enabling a modernisation. The vast majority of systems using digital components have been operating without problems and often contribute to improved safety but the challenge of non-detectable, or non-identifiable, failure modes remain. In this paper, the extent to which digital components are used in Swedish NPP power systems will be presented including a description of typical applications. Based on data from maintenance records and fault reports, as well as interviews with designers and maintenance personnel, the main areas where problems have been encountered and where possible risks have been identified will be described. The paper intends to investigate any 'tell-tales' that could give signals of unwanted behaviour. Furthermore, particular benefits experienced by using digital components will be highlighted. The paper will also discuss the safety relevance of these findings and suggest measures to improve safety in the application of digital components in power systems. (authors)

Two managerial grids in NPP

International Nuclear Information System (INIS)

Zhao Hui

2012-01-01

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)

The Upper Miocene of the Rostov Dome (Eastern Paratethys: Implication of the chronostratigraphy and bivalvia-based biostratigraphy

Directory of Open Access Journals (Sweden)

Ruban Dmitry A.

2005-01-01

Full Text Available The Rostov Dome is located in the south of the Russian Platform. In the Late Miocene this area was embraced by the Eastern Paratethys. The implications of a recently developed Neogene chronostratigraphy to the studied area are discussed. The Sarmatian regional stage corresponds to the upper part of the Langhian, the entire Serravalian and the lower part of the Tortonian global stages; the Maeotian regional stage corresponds to the upper part of the Tortonian and the lowermost horizons of the Messinian global stages; the Pontian regional stage corresponds to most of the Messinian and the lowermost Zanclean global stages. A first Bivalvia-based bio-stratigraphic framework is proposed for the territory of the Rostov Dome. Five biozones were established within the Serravalian-Messinian: Tapes vitalianus, Cerastoderma fittoni-Cerastoderma subfittoni, Congeria panticapaea, Congeria amygdaloides navicula and Monodacna pseudocatillus-Prosodacna schirvanica.

Uninterruptible power supply model of independent voltage inverter of NPP electrical equipment

International Nuclear Information System (INIS)

Rozhkov, V.V.; Ajdaralieva, V.Eh.

2010-01-01

A package of main transforming units models of advanced uninterruptible power supply systems of NPP electrical equipment was developed. The package of models allows investigating the basic modes of uninterruptible power supply systems operation by computer modeling. Simulation results were presented. Recommendations on choice of parameters of power circuit elements as well as on diagnostics and adjustment of regulators of converters control systems were given [ru

Level 1 shutdown and low power operation of Mochovce NPP, Unit 1, Slovakia

International Nuclear Information System (INIS)

Halada, P.; Cillik, I.; Stojka, T.; Kuzma, M.; Prochaska, J.; Vrtik, L.

2004-01-01

The paper presents general approach, used methods and form of documentation of the results that have been applied within the shutdown and low power PSA (SPSA) study for Mochovce NPP, Unit 1, Slovakia. The SPSA project was realized by VUJE Trnava Inc., Slovakia in 2001-2002 years. The Level 1 SPSA study for Mochovce NPP Unit 1 covers internal events as well as internal (fires, floods and heavy load drop) and external (aircraft crash, extreme meteorological conditions, seismic event and influence of surrounding industry) hazards. Mochovce NPP consists of two operating units equipped with VVER 440/V213 reactors safety upgraded before construction finishing and operation start. 87 safety measures based on VVER 440 operational experience and international mission insights were implemented to enhance its operational and nuclear safety. The SPSA relates to full power PSA (FPSA) as a continuation of the effort to create a harmonized level 1 PSA model for all operational modes of the plant with the goal to use it for further purposes as follows: Real Time Risk Monitor, Maintenance Optimization, Technical Specifications Optimization, Living PSA. (author)

A Study on Human Factors in Maintenance of a Nuclear Power Plant (NPP)

International Nuclear Information System (INIS)

Park, Young Ho; Seong, Poong Hyun

2006-01-01

In human factors research, more attention has been devoted to the operation of a nuclear power plant (NPP) than to their maintenance. However, more NPP incidents are caused by inadequate maintenance rather than by faulty operation. There is a trend in NPP toward introducing digital technology into safety and non-safety systems. This lead to changes of maintenance, and support systems such as diagnosis system, augmentation system and handy terminal will be developed. In this context, it is important to identify tasks of human related to each phase of maintenance and their relation in order to apply those to maintenance. However, there are few researches of human factors in maintenance. This paper studies on framework of cognitive task analysis for developing maintenance support systems

Estimation of the loss of Offsite power frequency for the probabilistic safety assessment of the Juragua NPP

International Nuclear Information System (INIS)

Vilaragut Llanes, J.J.; Valhuerdi Debesa, C.

1996-01-01

The loss offsite power is defined as the interruption of the preferred power supply to the essential and non essential switchgear buses necessitating or resulting in the use of emergency AC power supply. Because many safety system required for reactor core decay heat removal and containment heat removal depend on AC power, a loss of offsite power, if emergency power supply (diesel generators) fails, could be severe accidents The purpose of this work was to determine, for the Probabilistic Safety Assessment of the Juragua NPP, the causes, frequency and duration relationships of the loss of offsite power. A description is presented of the different factor that determine the occurrence of this event and the characteristics for the Juragua NPP

Advances in safety countermeasures at the Tomari NPP of Hokkaido Electric Power on the basis of Fukushima Daiichi NPP accident. Fire protection and other advances

International Nuclear Information System (INIS)

Shibata, Taku; Dasai, Katsumi

2014-01-01

Fire protections for the nuclear power plants have been based on the fire laws and the conventional guide. After Fukushima Daiichi NPP accident, many safety countermeasures - also about Fire Protection - have been discussed in the Japanese authorities. This paper shows our present activities in the Tomari NPP about the fire protections from the view points of Fire Prevention, Fire Detection/Suppression Systems and Fire Protection, and other advances. (author)

Study on the power control system for NPP power unit with the WWER-440 reactor

International Nuclear Information System (INIS)

Aleksandrova, N.D.; Naumov, A.V.

1981-01-01

Results of model investigations into basic version of the power control systems (PCS) conformably to the WWER-440 NPP power unit are stated. Transient processes in the power unit system when being two PCS versions during perturbations of different parameters: unit power, vapour pressure or position of control rods have been simulated. Investigations into the different PCS versions show that quality of operation of a traditional scheme with a turbine power controller and reactor pressure controller can be significantly improved with the introduction of a high-speed signal of pressure into the reactor controller. The PCS version with the compensation of interrelations between the turbine and reactor controllers constructed according to the same principles as the standard schemes of power units of thermal electric power plant is perspective as well [ru

Operation Aspect of the Main Control Room of NPP

International Nuclear Information System (INIS)

Sahala M Lumbanraja

2009-01-01

The main control room of Nuclear Power Plant (NPP) is operational centre to control all of the operation activity of NPP. NPP must be operated carefully and safely. Many aspect that contributed to operation of NPP, such as man power whose operated, technology type used, ergonomic of main control room, operational management, etc. The disturbances of communication in control room must be anticipated so the high availability of NPP can be achieved. The ergonomic of the NPP control room that will be used in Indonesia must be designed suitable to anthropometric of Indonesia society. (author)

Nuclear power plant maintenance personnel reliability prediction (NPP/MPRP) effort at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Knee, H.E.; Haas, P.M.; Siegel, A.I.

1981-01-01

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

Leningrad NPP and energetics of north-western Russia

International Nuclear Information System (INIS)

Belov, I.

2000-01-01

Problems of Leningrad NPP operating units modernization, their design service life finishing by year of 2010, are discussed. To assure safe operation of unit 1 investments in the amount of 30 mln. dol are necessary. Estimations suggest economic efficiency of the measures, permitting saving of 300 mln. dol worth of gas. Unfortunately, without a rise in tariff for electric power produced by NPP it seems impossible. It is recommended that substantiated tariffs are set for electric power produced by NPP starting from January, 2000. The measure is indispensable for raising investment funds intended for operating NPP modernization [ru

The experience of strengthening subsidence of the soil under the existing building in the city of Rostov-on-Don

Directory of Open Access Journals (Sweden)

Prokopov Albert

2017-01-01

Full Text Available Described problem for multi-storey residential development in the city of Rostov-on-Don on collapsible soils. The analysis of the technical and technological peculiarities of solidification under conditions of maintained buildings. Examples of projects of consolidation subsidence of foundation soils of buildings in operation 50–70 years.

Application of linear scheduling method (LSM) for nuclear power plant (NPP) construction

International Nuclear Information System (INIS)

Kim, Woojoong; Ryu, Dongsoo; Jung, Youngsoo

2014-01-01

Highlights: • Mixed use of linear scheduling method with traditional CPM is suggested for NPP. • A methodology for selecting promising areas for LSM application is proposed. • A case-study is conducted to validate the proposed LSM selection methodology. • A case-study of reducing NPP construction duration by using LSM is introduced. - Abstract: According to a forecast, global energy demand is expected to increase by 56% from 2010 to 2040 (EIA, 2013). The nuclear power plant construction market is also growing with sharper competition. In nuclear power plant construction, scheduling is one of the most important functions due to its large size and complexity. Therefore, it is crucial to incorporate the ‘distinct characteristics of construction commodities and the complex characteristics of scheduling techniques’ (Jung and Woo, 2004) when selecting appropriate schedule control methods for nuclear power plant construction. However, among various types of construction scheduling techniques, the traditional critical path method (CPM) has been used most frequently in real-world practice. In this context, the purpose of this paper is to examine the viability and effectiveness of linear scheduling method (LSM) applications for specific areas in nuclear power plant construction. In order to identify the criteria for selecting scheduling techniques, the characteristics of CPM and LSM were compared and analyzed first through a literature review. Distinct characteristics of nuclear power plant construction were then explored by using a case project in order to develop a methodology to select effective areas of LSM application to nuclear power plant construction. Finally, promising areas for actual LSM application are suggested based on the proposed evaluation criteria and the case project. Findings and practical implications are discussed for further implementation

Application of linear scheduling method (LSM) for nuclear power plant (NPP) construction

Energy Technology Data Exchange (ETDEWEB)

Kim, Woojoong, E-mail: minidung@nate.com [Central Research Institute, Korea Hydro and Nuclear Power Co., Ltd, Daejeon 305-343 (Korea, Republic of); Ryu, Dongsoo, E-mail: energyboy@khnp.co.kr [Central Research Institute, Korea Hydro and Nuclear Power Co., Ltd, Daejeon 305-343 (Korea, Republic of); Jung, Youngsoo, E-mail: yjung97@mju.ac.kr [College of Architecture, Myongji University, Yongin 449-728 (Korea, Republic of)

2014-04-01

Highlights: • Mixed use of linear scheduling method with traditional CPM is suggested for NPP. • A methodology for selecting promising areas for LSM application is proposed. • A case-study is conducted to validate the proposed LSM selection methodology. • A case-study of reducing NPP construction duration by using LSM is introduced. - Abstract: According to a forecast, global energy demand is expected to increase by 56% from 2010 to 2040 (EIA, 2013). The nuclear power plant construction market is also growing with sharper competition. In nuclear power plant construction, scheduling is one of the most important functions due to its large size and complexity. Therefore, it is crucial to incorporate the ‘distinct characteristics of construction commodities and the complex characteristics of scheduling techniques’ (Jung and Woo, 2004) when selecting appropriate schedule control methods for nuclear power plant construction. However, among various types of construction scheduling techniques, the traditional critical path method (CPM) has been used most frequently in real-world practice. In this context, the purpose of this paper is to examine the viability and effectiveness of linear scheduling method (LSM) applications for specific areas in nuclear power plant construction. In order to identify the criteria for selecting scheduling techniques, the characteristics of CPM and LSM were compared and analyzed first through a literature review. Distinct characteristics of nuclear power plant construction were then explored by using a case project in order to develop a methodology to select effective areas of LSM application to nuclear power plant construction. Finally, promising areas for actual LSM application are suggested based on the proposed evaluation criteria and the case project. Findings and practical implications are discussed for further implementation.

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

International Nuclear Information System (INIS)

Lee, Jaiho; Song, Eunhye

2014-01-01

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

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

The nuclear power plant maintenance personnel reliability prediction (NPP/MPRP) effort at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Knee, H.E.; Haas, P.M.; Siegel, A.I.

1982-01-01

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

Unit Commissioning of “Belene” NPP (Bulgaria)

International Nuclear Information System (INIS)

2009-01-01

This presentations gives detailed information about the following topics about commissioning: principles of NPP commissioning; phases of NPP commissioning; organization of commissioning activities; duties and responsibilities of the parties for carrying out unit commissioning activities; responsibility and obligations of the sides during commissioning of power unit; documentation required for power unit commissioning; quality assurance for commissioning activities

Financial and organizational models of NPP construction projects

International Nuclear Information System (INIS)

Ivanov, Timur

2010-01-01

The recent evolution of financial and organizational models of NPP projects can be truly reputed to open a new page of the world market of NPP construction. The definition of the concrete model is based mostly on specific cooperation backgrounds and current terms and conditions under which the particular NPP project is being evolved. In this article the most commonly known strategies and schemes of financing structuring for export NPP construction projects are scrutinized. Special attention is paid to the analysis of BOO/BOT models which are based on the public-private partnership. Most BOO/BOT projects in the power sector has Power Purchase Agreements (PPA) as an integral part of them. The PPA key principles are studied here as well. The flexibility and adaptability of the public-private partnership models for financing and organization of the NPP projects contributes substantially to the competitiveness of the NPP projects especially under current economic conditions. (orig.)

Results and development prospects for the Cernavoda NPP

International Nuclear Information System (INIS)

Rotaru, Ioan

2001-01-01

The new competitive market in the power sector offers favorable conditions for continual developing of Nuclear Power in Romania. The principal arguments in this respect are: the CANDU technology is a western technology recognized world wide both for its operation reliability and its economical performances. The results obtained by Cernavoda NPP Unit 1 over a period of four years and a half commercial operation confirms the validity of the CANDU project in Romania in the new conditions of competitive market. Accomplishing the Unit 2 of Cernavoda NPP represents for the time being one of the most cost-effective investment in the Romanian power sector. Also, the participation of the local industry to the project implementation is important as it ensures the initial heavy water and nuclear fuel charging, specific materials and equipment production, design and construction works, etc. Heaving in view all these favorable arguments, the construction of Unit 2 of Cernavoda NPP represents one of the highest priorities of the State Budget of the present administration in year 2001. The Nuclear Power Project in Romania, based on CANDU technology meets national as well as EU regulations concerning nuclear power and as such its development poses no significant problems both in the context of EU extension and in the frame of the developing competitive market in the power sector. For SNN SA the main objectives in view for the next stage are: operating Cernavoda NPP Unit 1 in conditions of highest nuclear safety and economical efficiency; finalizing the Cernavoda NPP Unit 2 and creation of an organisation for operating the two units; promoting of a functional system characteristic to the competitive market economy and open to privatization; creating opportunities for exporting electrical energy. The contribution contains the following sections: 1. General overlook; 2. Performance of the power production in the year 2000; 2.1. Unit 1 of Cernavoda NPP; 2.2. Nuclear Fuel Plant

NPP Krsko secondary side analysis

International Nuclear Information System (INIS)

Fabijan, Lj.

1987-01-01

The purpose of this work is to analyze secondary side thermohydraulics response on steam generator tube plugging in order to ensure nominal NPP power. We had established that the additional opening of the governing valve No. 3 and 4 can compensate pressure drop caused by steam generator tube plugging. Two main steam flows with four governing valves were simulated. Steam expansion in turbine and feed water system was modeled separately. All important process point and steam moisture changes impact on nominal NPP power were analysed. (author)

Financial feasibility analysis on small medium reactor nuclear power plant (SMR NPP) project in Indonesia under uncertainty

International Nuclear Information System (INIS)

Nuryanti; Suparman; Mochamad Nasrullah; Elok Satiti Amitayani; Wiku Lulus Widodo

2015-01-01

NPP SMR is one alternative to overcome the Outside Java Bali region's dependence on diesel power plant. One crucial issue in the NPP project (including SMR) would be financing, associated with the capital-intensive nature of the project. In addition, the SMR NPP project also be vulnerable in occurrence of some uncertainties. Therefore, this study aimed to analyze the financial feasibility of SMR NPP project by accommodating the possibility of the uncertainties. The methodology used is probabilistic analysis which was performed by Monte Carlo technique. This technique simulates the relationship between the uncertainty variables with financial feasibility indicators. The results showed that in probabilistic approach, SMR NPP project is considered feasible on the 'most probable value' of electricity selling price of 15 cents/kWh, indicated by positive average value of NPV (US$ 135,324,004) and the average value of both of IRRs are bigger than MARR (IRR project = 10.65 %, IRR Equity = 14.29 %, while MARR = 10 %). The probability of rejection of the SMR project was about 20 %. The three main variables that are most influential in the project were: selling price of electricity, investment cost and inflation rate. (author)

An Extreme Meteorological Events Analysis For Nuclear Power Plant (NPP) Siting Project at Bangka Island, Indonesia

Science.gov (United States)

Septiadi, Deni; S, Yarianto Sugeng B.; Sriyana; Anzhar, Kurnia; Suntoko, Hadi

2018-03-01

The potential sources of meteorological phenomena in Nuclear Power Plant (NPP) area of interest are identified and the extreme values of the possible resulting hazards associated which such phenomena are evaluated to derive the appropriate design bases for the NPP. The appropriate design bases shall be determined according to the Nuclear Energy Regulatory Agency (Bapeten) applicable regulations, which presently do not indicate quantitative criteria for purposes of determining the design bases for meteorological hazards. These meteorological investigations are also carried out to evaluate the regional and site specific meteorological parameters which affect the transport and dispersion of radioactive effluents on the environment of the region around the NPP site. The meteorological hazards are to be monitored and assessed periodically over the lifetime of the plant to ensure that consistency with the design assumptions is maintained throughout the full lifetime of the facility.

Belene NPP

International Nuclear Information System (INIS)

Tsvetanov, P.

1990-01-01

The book presents the main results of the studies of the Bulgarian Academy of Sciences (BAS) on the construction of a new nuclear power plant at Belene on the Danube river. The programme of the studies comprises five areas: the socio-economic and energy development and the necessity of the commissioning; a technical project and design level of the equipment (safety, radioactivity control, waste disposal and economic efficiency of the power plant); the seismic properties of the construction site; the corresponding risk and design features of the plant; the ecological impacts of the NPP and public opinion. The studies in the different areas have been carried out by independent teams, fully responsible for the formulated topical conclusions. The general opinion of the BAS voiced in the book is that the construction of Belene NPP is not sufficiently substantiated and is considered unacceptable. 94 refs., 53 fig., 56 tabs. (R.Ts.)

On the NPP structural reliability

International Nuclear Information System (INIS)

Klemin, A.I.; Polyakov, E.F.

1980-01-01

Reviewed are the main statements peculiarities and possibilities of the first branch guiding technical material (GTM) ''The methods of calculation of structural reliability of NPP and its systems at the stage of projecting''. It is stated, that in GTM presented are recomendations on the calculation of reliability of such specific systems, as the system of the reactor control and protection the system of measuring instruments and automatics and safe systems. GTM are based on analytical methods of modern theory of realibility with the Use of metodology of minimal cross sections of complex systems. It is stressed, that the calculations on the proposed methods permit to calculate a wide complex of reliability parameters, reflecting separately or together prorerties of NPP dependability and maintainability. For NPP, operating by a variable schedule of leading, aditionally considered are parameters, characterizing reliability with account of the proposed regime of power change, i.e. taking into account failures, caused by decrease of the obtained power lower, than the reguired or increase of the required power higher, than the obtained

Radioactive wastes management of NPP

International Nuclear Information System (INIS)

Klyuchnikov, A.A.; Pazukhin, Eh.M.; Shigera, Yu. M.; Shigera, V.Yu.

2005-01-01

Modern knowledge in the field of radiation waste management on example of the most serious man-made accident at Chernobyl NPP are illuminated. This nuclear power plant that after accident in 1986 became in definite aspect an experimental scientific ground, includes all variety of problems which have to be solved by NPP personnel and specialists from scientific organizations. This book is aimed for large sphere of readers. It will be useful for students, engineers, specialists and those working in the field of nuclear power, ionizing source and radiation technology use for acquiring modern experience in nuclear material management

Training human resource for NPP in Vietnam

International Nuclear Information System (INIS)

Nguyen, Trung Tinh; Dam, Xuan Hiep

2008-01-01

Vietnam will establish the first NPP in the near future. With us the first important thing is the human resource, but now there is no university in Vietnam training nuclear engineers. In EPU (Electric Power University), now we are preparing for training nuclear engineers. In this paper, we review the nuclear man power and the way to train the high quality human resource for NPP and for other nuclear application in Vietnam. (author)

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.

Current status of NPP generation IV

International Nuclear Information System (INIS)

Yohanes Dwi Anggoro; Dharu Dewi; Nurlaila; Arief Tris Yuliyanto

2013-01-01

Today development of nuclear technology has reached the stage of research and development of Generation IV nuclear power plants (advanced reactor systems) which is an innovative development from the previous generation of nuclear power plants. There are six types of power generation IV reactors, namely: Very High Temperature Reactor (VHTR), Sodium-cooled Fast Reactor (SFR), Gas-cooled Fast Reactor (GFR), Lead-cooled Fast Reactor (LFR), Molten Salt Reactor (MSR), and Super Critical Water-cooled Reactor (SCWR). The purpose of this study is to know the development of Generation IV nuclear power plants that have been done by the thirteen countries that are members of the Gen IV International Forum (GIF). The method used is review study and refers to various studies related to the current status of research and development of generation IV nuclear power. The result of this study showed that the systems and technology on Generation IV nuclear power plants offer significant advances in sustainability, safety and reliability, economics, and proliferation resistance and physical protection. In addition, based on the research and development experience is estimated that: SFR can be used optimally in 2015, VHTR in 2020, while NPP types GFR, LFR, MSR, and SCWR in 2025. Utilization of NPP generation IV said to be optimal if fulfill the goal of NPP generation IV, such as: capable to generate energy sustainability and promote long-term availability of nuclear fuel, minimize nuclear waste and reduce the long term stewardship burden, has an advantage in the field of safety and reliability compared to the previous generation of NPP and VHTR technology have a good prospects in Indonesia. (author)

NPP Prevlaka - Preparation of construction

International Nuclear Information System (INIS)

Bojic, K.

1984-01-01

On the basis of study 'Optimal electricity generation structure till the year 2000' production of 3 x 500 MWe in nuclear power plants has been anticipated. Second Croatian-Slovenian NPP project will be based on the same principles the first one (NPP Krsko) was based on. Preconstruction investigation studies are performed at site Prevlaka on river Sava downstream of Zagreb. Licensing procedure has started with republic Urban countryside planning activities. Preconstruction activities are planned to be finished by the end of 1986. while the construction is expected to start during 1987. Parallel to investigation studies for NPP Prevlaka, evaluation of nuclear technology and reactor type is planned to be made. (author)

Akkuyu NPP – the first Turkish NPP. The new history of the project

International Nuclear Information System (INIS)

Tzocheva, V.

2012-01-01

An overview is given to the Turkish energy sector and nuclear power plans. The project for the construction of the first NPP in Turkey is presented. The general parameters of the Project are: CAPEX: $ 20 bln; Project design: NPP-2006; (VVER- 1200); Number of units: 4; Total capacity: 4 800 MW; Construction period: 2014 – 2023; PPA period; 15 years, fixed price terms. An account of the activities during 2011, the Worley Parsons participation are presented and a tentative project schedule is given

Automatic control system at the ''Loviisa'' NPP

International Nuclear Information System (INIS)

Kukhtevich, I.V.; Mal'tsev, B.K.; Sergievskaya, E.N.

1980-01-01

Automatic control system of the Loviisa-1 NPP (Finland) is described. According to operation conditions of Finland power system the Loviisa-1 NPP must operate in the mode of week and day control of loading schedule and participate in current control of power system frequency and capacity. With provision for these requirements NPP is equipped with the all-regime system for automatic control functioning during reactor start-up, shut-down, in normal and transient regimes and in emergency situations. The automatic control system includes: a data subsystem, an automatic control subsystem, a discrete control subsystem including remote, a subsystem for reactor control and protection and overall station system of protections: control and dosimetry inside the reactor. Structures of a data-computer complex, discrete control subsystems, reactor control and protection systems, neutron flux control system, inside-reactor control system, station protection system and system for control of fuel element tightness are presented in short. Two-year experience of the NPP operation confirmed advisability of the chosen volume of automatization. The Loviisa-1 NPP operates successfully in the mode of the week and day control of supervisor schedule and current control of frequency (short-term control)

Russian Federation country report

Energy Technology Data Exchange (ETDEWEB)

Labyntseva, Marina [Non governmental educational institution, ' ATOMPROF' , Aerodromnaya st., 4, 197348 St Petersburg (Russian Federation)

2008-07-01

Nuclear in the Russian Federation: 31 reactors at 10 nuclear power plants, 454 nuclear material storage facilities, 16475 sources of ionizing radiation, 1508 storage facilities for radioactive material and radioactive waste. Nuclear power: 10 nuclear power plants with total installed capacity of 23.242 GWe, Total nuclear electricity generation 160 bln kWh in 2007, Share of nuclear electricity in the overall electricity generation is 16%. Future of nuclear power: Nuclear power development program for the period from 2007 to 2020: Lifetime extension of existing units, Completion of construction of nuclear power units at existing sites (Rostov-2, Kalinin-4, Beloyarsk-4). Construction of new nuclear power plants near existing NPP (Novovoronezh NPP-2, Leningrad NPP-2, Kursk NPP-2,Kola NPP-2) and Construction of new nuclear power plants: (Nizhny Novgorod NPP, Tver NPP, Central NPP, South Urals NPP, Seversk NPP, Primorskaya NPP, 2 floating nuclear power plants at Severodvinsk and Pevek). Radioactive waste management: The Law on radioactive waste management will be introduced to State Duma in June 2008. The radioactive waste management strategy includes construction and reconstruction of: Storage facilities for some 120 thousand cubic meters, RW treatment complexes at nuclear fuel cycle enterprises, Storage facilities and RW treatment complexes at nuclear power plants, Storage facilities for RW coming from non-nuclear facilities for 140 thousand cubic meters, Decommissioning of 140 facilities, Decontamination of territories, buildings and constructions with the total area of 1658 thousand square meters. Development of competences: In 2006 about 313 thousand employees were working at nuclear industry (Top level managers - 0,6%, Intermediate level managers - 6,0%, Specialists - 31,6%, Workers - 62%). The demand of Rosatom State Corporation will be 7000 - 8000 persons annually of more then 140 professions, among them: 2800 persons with higher professional education, 2000

Dukovany NPP operation

International Nuclear Information System (INIS)

Vlcek, Jaroslav

2010-01-01

The topics discussed include: Dukovany NPP among CEZ Group power plants; International missions at the plant; Plant operation results; and Strategic goals and challenges. Historical data are presented in the graphical form, such as the unit capacity factor, unplanned capability loss factor, unplanned automatic scrams, fuel reliability, industrial safety accident rate, collective radiation exposure, WANO index, power generation data, and maximum achievable power by the end of year. Also discussed were the company culture and human resources, maintenance, power uprate, and related phenomena. (P.A.)

International Conference of Ukrainian Nuclear Society ''NPP's safety and protection''(annotations)

International Nuclear Information System (INIS)

Barbashev, S.V.

1997-01-01

The abstracts of reports submitted to the Conference include: - New developments of the safe nuclear installations; - NPP ecological safety; - Methods of personnel and population protection; - Waste management safety (at transportation, processing and storage); - Spent nuclear fuel management; - NPP life extension and decommissioning; - Public opinion as an element of NPP safety; - Training of personnel, scientific support and safety culture; - Forecasting of nuclear power and industry safe development; - Development of international cooperation in nuclear power

Modernization and safety improvement project of the NPP V-2 Jaslovske Bohunice

International Nuclear Information System (INIS)

Michal, V.; Losonsky, B.; Magdolen, J.

2000-01-01

This contribution deals with the form, present state, and results of the Nuclear Power Plants Research Institute (the Slovak acronym is VUJE - Vyskumny Ustav Jadrovych Elektrarni) participation in the NPP V-2 Jaslovske Bohunice Modernization and Safety Improvement Project. A short description of VUJE history, activity, and results is also presented as well as NPPs Jaslovske Bohunice characterization. VUJE was established in 1977 and deals with scientific and research needs of nuclear power plants, such as design, construction, commissioning and operation. The next fields of VUJE activity are, NPP reconstruction, NPP personnel training, radioactive waste management technology, and NPP decommissioning. The nuclear power plant, Jaslovske Bohunice, is situated approximately 15 km from the district town of Trnava in the southwestern region of the Slovak Republic. The construction of the first Czechoslovak NPP A-1 began on this site in 1957 .The construction of the double-unit NPP V-1 with WWER-440 (type V-230) reactor began in 1972. The first unit of NPP V-1 began operation in 1978 and the second in 1980. NPPs construction on the Bohunice site continued with NPP V-2, which has two units with WWER-440 (type V-213) reactors. Unit 1 and Unit 2 of NPP V-2 were commissioned in 1984 and 1985, respectively. Slovak electric utility Slovenske elektrarne (SE) is the owner/commissioner of NPP V-2. This NPP is responsible for more than 20% of the total electrical energy production of SE, making it an essential supporter of the Slovak economy. (authors)

Real-time management (RTM) by cloud computing system dynamics (CCSD) for risk analysis of Fukushima nuclear power plant (NPP) accident

Energy Technology Data Exchange (ETDEWEB)

Cho, Hyo Sung [Yonsei Univ., Wonju Gangwon-do (Korea, Republic of). Dept. of Radiation Convergence Engineering; Woo, Tae Ho [Yonsei Univ., Wonju Gangwon-do (Korea, Republic of). Dept. of Radiation Convergence Engineering; The Cyber Univ. of Korea, Seoul (Korea, Republic of). Dept. of Mechanical and Control Engineering

2017-03-15

The earthquake and tsunami induced accident of nuclear power plant (NPP) in Fukushima disaster is investigated by the real-time management (RTM) method. This non-linear logic of the safety management is applied to enhance the methodological confidence in the NPP reliability. The case study of the earthquake is modeled for the fast reaction characteristics of the RTM. The system dynamics (SD) modeling simulations and cloud computing are applied for the RTM method where the real time simulation has the fast and effective communication for the accident remediation and prevention. Current tablet computing system can improve the safety standard of the NPP. Finally, the procedure of the cloud computing system dynamics (CCSD) modeling is constructed.

Real-time management (RTM) by cloud computing system dynamics (CCSD) for risk analysis of Fukushima nuclear power plant (NPP) accident

International Nuclear Information System (INIS)

Cho, Hyo Sung; Woo, Tae Ho; The Cyber Univ. of Korea, Seoul

2017-01-01

The earthquake and tsunami induced accident of nuclear power plant (NPP) in Fukushima disaster is investigated by the real-time management (RTM) method. This non-linear logic of the safety management is applied to enhance the methodological confidence in the NPP reliability. The case study of the earthquake is modeled for the fast reaction characteristics of the RTM. The system dynamics (SD) modeling simulations and cloud computing are applied for the RTM method where the real time simulation has the fast and effective communication for the accident remediation and prevention. Current tablet computing system can improve the safety standard of the NPP. Finally, the procedure of the cloud computing system dynamics (CCSD) modeling is constructed.

Nuclear fuel operation at Balakovo NPP

International Nuclear Information System (INIS)

Morozov, A.

2015-01-01

The presentation addressed the positive experience of the TVS-2M assemblies implementation at Balakovo NPP in 18 month fuel cycles, at uprated power (104%) and the usage of the axial profiled Gd-rods in order to minimize the power peaking factors and linear heat rate in the upper part in some of the fuel rods. The results of the test operation of fuel rods with different claddings, made by E110M, E125 and E635M alloys at Balakovo NPP were also provided. The recently observed problem with the “white crust” on the cladding surfaces was also discussed

Safety upgrading program in NPP Mochovce

International Nuclear Information System (INIS)

Baumeister, P.

1999-01-01

EMO interest is to operate only nuclear power plants with high standards of nuclear safety. This aim EMO declare on preparation completion and commissioning of Mochovce Nuclear Power Plant. Wide co-operation of our company with International Atomic Energy Agency and west European Inst.ions and companies has been started with aim to fulfil the nuclear safety requirements for Mochovce NPP. Set of 87 safety measures was implemented at Mochovce Unit 1 and is under construction at Unit 2. Mochovce NPP approach to safety upgrading implementation is showed on chosen measures. This presentation is focused on the issues category III.(author)

Human Resources Training Requirement on NPP Operation and Maintenance

International Nuclear Information System (INIS)

Nurlaila; Yuliastuti

2009-01-01

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)

Monitoring program of surrounding of the NPP SE-EBO

International Nuclear Information System (INIS)

Dobis, L.; Kostial, J.

1997-01-01

The paper dealt with monitoring program of radiation control of surrounding of the NPP Bohunice, which has the aim: (1) to ensure the control of influence of work of the NPP Bohunice on the environment in their surrounding; (2) to ensure the back-ground for regular brief of control and supervisory organs about condition of the environment in surrounding of the NPP Bohunice; (3) to maintain the expected technical level of control of the NPP Bohunice and to exploit optimally the technical means; (4) to solicit permanently the data about the radioactivity of environment in surrounding of the NPP Bohunice for forming of files of the data; (5) to exploit purposefully the technical equipment, technical workers and to maintain their in permanent emergency and technical eligibility for the case of the breakdown; (6) to obtain permanently the files of the values for qualification of the reference levels. This program of monitoring includes the radiation control of surrounding of the NPP Bohunice, in the time of normal work of power-station's blocks, inclusively of all types of trouble-shooting and repairer works in surrounding of the NPP Bohunice, up to distance 20 km from power-station. The monitoring includes: outlets from the NPP Bohunice, monitoring of radiation characteristics in surrounding of the NPP Bohunice, (aerosols, fall-outs, soil), the links of food chains: (grass and fodder, milk, agriculture products), hydrosphere in surrounding (surface waters, drink water, bores of radiation control in complex of the NPP Bohunice, components of the hydrosphere), measurement of radiation from external sources (measurement of the dose rates, measurement of the doses [sk

Spain in South Ukraine NPP

International Nuclear Information System (INIS)

Ibanez, M.

1994-01-01

A Technical Assistance Protocol was signed between the Governments of the GIS and the Commission of the European Union (CEU) on August 2, 1991 and this was the starting point of the TACIS program. In this article, the activities described are those related to the TACIS-92/93/94 on site technical assistance to South Ukraine NPP (SUK NPP). Within the scope of the TACIS 92 Program the CEU and the Ukrainian Authorities agreed a list of projects to be implemented at South Ukraine NPP with the aim to improve the operational safety of the plant. This part of the program is called TACIS 92 on-site activities. The total budget allocated to these projects is a MECU. The European Union ''utility'' selected to lead this program at South Ukraine NPP was UNESA and the first contract to cover our activities was signed in July 1993 between the CEU (Mr. Pablo Benavides) and UNESA (Mr. Pedro Rivero). The projects will be implemented at SUK NPP but according to the contract UNESA is ''The Consultant'' and GOSKOMATON (The Ukrainian Sate Committee on Nuclear Power Utilization) is the ''Recipient Institution''. (Author)

The V-1 NPP and V-2 NPP upgrading

International Nuclear Information System (INIS)

1998-01-01

A brief account of activities in the V-1 NPP and V-2 NPP upgrading as well as maintenance carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. The V-1 NPP applied the so called 'Small Backfitting Programme'covering 81 points of the Czechoslovak Atomic energy Commission Decree No 5/91. Continual upgrading continued after the Backfitting Programme completion with the Safety Report and following Nuclear Regulatory Authority of Slovak Republic (NRA SR) Decrees No 1/94 and 110/94 setting spheres and procedure for adopting and implementation of measures enabling the units to operate further on. Results of expert missions, analyses and assessments of components identified by Basic Engineering became the basis for the development of the Gradual Reconstruction Programme. The Programme outputs underwent economic and probabilistic assessing their contribution to nuclear safety. This process resulted in finalizing the Gradual Reconstruction Programme which started to be implemented in 1996 and will be completed in 1999. It is implemented by the REKON consortium and covers 17 areas including Instrumentation and Control, self-consumption emergency supply, leakage monitoring, emergency core cooling system, seismic reinforcement and radioactivity localisation. Both units will reach internationally acceptable safety standards for the remaining life-time period. The V-2 NPP Upgrading and Safety Enhancement Programme includes results of activities performed in the course of last years to define all important activities leading to enhancement of nuclear safety and performance reliability and effectiveness within the plant life-time period and to establish conditions for extending the life-time of these units for 40 years. The V-2 NPP Upgrading and Safety Enhancement Programme aims to assure safe operation with a probability of the core damages less than 10 -4 /reactor · year

Constructive approaches to the space NPP designing

International Nuclear Information System (INIS)

Eremin, A.G.; Korobkov, L.S.; Matveev, A.V.; Trukhanov, Yu.L.; Pyshko, A.P.

2000-01-01

An example of designing a space NPP intended for power supply of telecommunication satellite is considered. It is shown that the designing approach based on the introduction of a leading criterion and dividing the design problems in two independent groups (reactor with radiation shield and equipment module) permits to develop the optimal design of a space NPP [ru

Safety culture at Mochovce NPP

International Nuclear Information System (INIS)

Markus, Jozef; Feik, Karol

2002-01-01

This article presents the approach of Mochovce NPP to the Safety culture. It presents activities, which have been taken by Mochovce NPP up to date in the area of Safety culture enhancement with the aim of getting the term into the subconscious of each employee, and thus minimising the human factor impact on occurrence of operational events in all safety areas. The article furthermore presents the most essential information on how the elements characterising a continuous progress in reaching the planned Safety culture goals of the company management have been implemented at Mochovce NPP, as well as the management's efforts to get among the best nuclear power plant operators in this area and to be an example for the others. (author)

On-the-job training and qualification of nuclear power plant personnel. OJT at the Loviisa NPP

International Nuclear Information System (INIS)

1996-01-01

On-the-job training and qualification process of nuclear power plant personnel is described, including the following issues: educational system of technical studies in Finland; training methods at the Loviisa NPP; on-the-job training of control room operators,field operators, maintenance personnel, other groups of the plant; qualifying examinations for different jobs

Research on the NPP human factors engineering operating experience review

International Nuclear Information System (INIS)

Ren Xiangchen; Miao Hongxing; Ning Zhonghe

2006-01-01

This paper addresses the importance of the human factors engineering (HFE) for the design of nuclear power plant (NPP), especially for the design of human-machine interface in the NPP. It also summarizes the scope and content of the NPP HFE. The function, scope, content and process of the NPP human factors engineering operating experience review (OER) are mainly focused on, and significantly discussed. Finally, it briefly introduces the situation of the studies on the OER in China. (authors)

NPP Krsko decommissioning concept

International Nuclear Information System (INIS)

Novsak, M.; Fink, K.; Spiler, J.

1996-01-01

At the end of the operational lifetime of a nuclear power plant (NPP) it is necessary to take measures for the decommissioning as stated in different international regulations and also in the national Slovenian law. Based on these requirements Slovenian authorities requested the development of a site specific decommissioning plan for the NPP Krsko. In September 1995, the Nuklearna Elektrarna Krsko (NEK) developed a site specific scope and content for a decommissioning plan including the assumptions for determination of the decommissioning costs. The NEK Decommissioning Plan contains sufficient information to fulfill the decommissioning requirements identified by NRC, IAEA and OECD - NEA regulations. In this paper the activities and results of development of NEK Decommissioning Plan consisting of the development of three decommissioning strategies for the NPP Krsko and selection of the most suitable strategy based on site specific, social, technical, radiological and economic aspects, cost estimates for the strategies including the costs for construction of final disposal facilities for fuel/high level waste (fuel/HLW) and low/intermediate level waste (LLW/ILW) and scheduling of all activities necessary for the decommissioning of the NPP Krsko are presented. (author)

NPP Krsko decommissioning concept

International Nuclear Information System (INIS)

Novsak, M.; Fink, K.; Spiler, J.

1996-01-01

At the end of the operational lifetime of a nuclear power plant (NPP) it is necessary to take measures for the decommissioning as stated in different international regulations and also in the national Slovenian law. Based on these requirements Slovenian authorities requested the development of a site specific decommissioning plan for the NPP KRSKO. In September 1995, the Nuklearna Elektrarna Krsko (NEK) developed a site specific scope and content for decommissioning plan including the assumptions for determination of the decommissioning costs. The NEK Decommissioning Plan contains sufficient information to fulfill decommissioning requirements identified by NRC, IAEA and OECD - NEA regulations. In this paper the activities and the results of development of NEK Decommissioning Plan consisting of the development of three decommissioning strategies for the NPP Krsko and selection of the most suitable strategy based on site specific, social, technical, radiological and economical aspects, cost estimates for the strategies including the costs for construction of final disposal facilities for fuel/high level waste (fuel/HLW) and low/intermediate level waste (LLW/ILW) and scheduling all activities necessary for the decommissioning of the NPP KRSKO are presented. (author)

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

International Nuclear Information System (INIS)

Dumitrache, Ion

2001-01-01

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

Analysis of an NPP Structure subjected to Vibrations Induced from Airplane Crashes

International Nuclear Information System (INIS)

Noh, Sang Hoon; Kim, Yong Soo; Kim, Chong Hak

2009-01-01

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

20 Years of Dukovany NPP Operation and Plans for Future

International Nuclear Information System (INIS)

Vlcek, J.

2006-01-01

NPP Dukovany (4x440MW), the first Czech nuclear power plant and a keystone of Czech Electricity Grid, in 2005 celebrated 20 years of successful operation. In my presentation I am going to speak about next areas. I will start about construction and commissioning history of Dukovany NPP, then I'll put forward what milestones of Dukovany NPP operation were accomplished, I'll say examples about our modernisation and investment activities (including replacement of IandC equipment, modifications for increasing of power and support grid services) and in the end our plans for future. (author)

Growth and development in school-age children from Rostov region, Russia: Comparison between urban and rural settings.

Science.gov (United States)

Voynov, V B; Kulba, S N; Arapova, Yu Yu

2017-12-01

The purposes of the current study were: (1) to describe growth and physical development and establish norms for schoolchildren from Rostov region in Russia; (2) to compare major characteristics of development between urban and rural children by sex and age. Nearly 200,000 children (198,712) aged between 7 and 17 years from 232 urban and rural schools of Rostov region (Southern Federal District of Russia) participated in the study. School age is a period of intensive growth and physiological and psychological development. Irregularities of personal development are caused by a multitude of factors, such as sex differences, heredity, socio-economic status of a family, standard of living, particular environmental conditions, and lifestyle. It has been established that children from the Southern Federal District of Russia had body mass index values higher than age-appropriate norms for all Russians (Total Russian, Rudnev et al., 2014) and World Health Organization charts. Children from urban settings were taller and heavier than children from rural settings. Sex is one of the most influential factors which play key role in determining specific characteristics of growth and personal development. According to our results, boys and girls both had similar age-related changes in weight and height, but their respective dynamics differed. Girls' height and weight values accelerated at the age 10 to 12 years and plateaued after the age fourteen, whereas in boys height and weight steadily increased with age, showing slight acceleration at the age 12 to 13 years, and reached a plateau by the age of seventeen. Copyright © 2017 Elsevier GmbH. All rights reserved.

Treatment of NPP wastes using vitrification

International Nuclear Information System (INIS)

Sobolev, I.A.; Lifanov, F.A.; Stefanovsky, S.V.; Kobelev, A.P.; Savkin, A.E.; Kornev, V.I.

1998-01-01

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/(cm 2 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)

Safety Analysis Report for Ignalina NPP

International Nuclear Information System (INIS)

Negrivoda, G.

1997-01-01

In December 1994 an agreement was signed between the European Bank for Reconstruction and Development and the Republic of Lithuania for the grant of 32.86 MECU for the safety Improvement at Ignalina NPP. One of the conditions for the provision of the grant, was a requirement for an in-depth analysis of the safety level at Ignalina NPP in the scope and according to the standards acceptable for a western nuclear power plant, and to publish a Safety Analysis Report (SAR). The report should investigate and analyze any factor that could limit a safe operation of the plant, and provide recommendations for actual safety improvements. According to the agreement, Lithuania had to finalize the SAR until 31 December, 1995. The bank has also organized and financed investigation of safety at Ignalina NPP and preparation of the SAR. EBRD made an agreement with Sweden's Vattenfall, which subcontracted well-known companies from Canada, USA, Germany, etc., and also the Russian Research and Development Institute of Power Engineering (NIKIET), reactor designer of Ignalina NPP. The SAR is a very comprehensive document and contains about 8000 pages of text, diagrams and tables. The main findings of the SAR are provided in the article. A large number of discrepancies with modern rules and western practices was detected, but they were not proved to be serious enough to require reactors shutdown. Based on the recommendations of the SAR Ignalina NPP has worked out Safety Improvement Program No. 2 (SIP-2), which is planned for three years and will cost 486 MLT. (author)

Application of GO methodology in reliability analysis of offsite power supply of Daya Bay NPP

International Nuclear Information System (INIS)

Shen Zupei; Li Xiaodong; Huang Xiangrui

2003-01-01

The author applies the GO methodology to reliability analysis of the offsite power supply system of Daya Bay NPP. The direct quantitative calculation formulas of the stable reliability target of the system with shared signals and the dynamic calculation formulas of the state probability for the unit with two states are derived. The method to solve the fault event sets of the system is also presented and all the fault event sets of the outer power supply system and their failure probability are obtained. The resumption reliability of the offsite power supply system after the stability failure of the power net is also calculated. The result shows that the GO methodology is very simple and useful in the stable and dynamic reliability analysis of the repairable system

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

Radioactive dispersion analysis for hypothetical nuclear power plant (NPP) candidate site in Perak state, Malaysia

Science.gov (United States)

Shamsuddin, Shazmeen Daniar; Basri, Nor Afifah; Omar, Nurlyana; Koh, Meng-Hock; Ramli, Ahmad Termizi; Saridan Wan Hassan, Wan Muhamad

2017-10-01

Malaysia is planning to build a nuclear power plant (NPP) by 2030 to diversify the national electricity supply and resources. Selection of an NPP site must consider various factors, especially nuclear safety consideration to fulfil the nuclear safety objectives. Environmental Risk Assessment Analysis is a part of safety requirements by the International Atomic Energy Agency (IAEA) prior to the NPP commissioning process. Risk Assessments Analysis (RIA) is compulsory for the NPP site evaluation. One of RIA methods are Radioactive Dispersion Analysis using probabilistic risk analysis software. It is also important to perform studies to estimate the impact to the neighbouring population in the case of a nuclear accident at the power plant. In the present work, aimed to study the impact of a hypothetical nuclear accident by simulating the dispersion pattern of radionuclides originated from a candidate site at Manjung, Perak. The work has been performed using the HotSpot Health Physics codes. Two types of radionuclides have been considered namely 137Cs and 131I. In calculations, the initial concentration of radioactive materials of Fukushima Daiichi accident data are used which are 2.06 x 1016 Bq and 1.68 x 1017 Bq respectively for the two radionuclides. The result shows that the dispersion distance obtained from both software are not the same. It shows that 137Cs and 131I can be dispersed as far as 16 km and 80 km away from the site during radiological accident respectively, reaching major towns in Perak. Using HOTSPOT, the estimated total effective dose equivalent (TEDE) for 137Cs and 131I at major towns in Perak such as Lumut and Sitiawan are 1.2 mSv and 9.9 mSv. As for Taiping, Ipoh, Kampar, and Teluk Intan the estimated TEDE is around 0.2 mSv and 1.6 mSv respectively. In conclusion, the dispersion can reach as far as 80 km from the site. However, estimated annual effective dose is not more than 1 mSv limit, which is considered acceptable in the point of view of

Radioactive dispersion analysis for hypothetical nuclear power plant (NPP candidate site in Perak state, Malaysia

Directory of Open Access Journals (Sweden)

Shamsuddin Shazmeen Daniar

2017-01-01

Full Text Available Malaysia is planning to build a nuclear power plant (NPP by 2030 to diversify the national electricity supply and resources. Selection of an NPP site must consider various factors, especially nuclear safety consideration to fulfil the nuclear safety objectives. Environmental Risk Assessment Analysis is a part of safety requirements by the International Atomic Energy Agency (IAEA prior to the NPP commissioning process. Risk Assessments Analysis (RIA is compulsory for the NPP site evaluation. One of RIA methods are Radioactive Dispersion Analysis using probabilistic risk analysis software. It is also important to perform studies to estimate the impact to the neighbouring population in the case of a nuclear accident at the power plant. In the present work, aimed to study the impact of a hypothetical nuclear accident by simulating the dispersion pattern of radionuclides originated from a candidate site at Manjung, Perak. The work has been performed using the HotSpot Health Physics codes. Two types of radionuclides have been considered namely 137Cs and 131I. In calculations, the initial concentration of radioactive materials of Fukushima Daiichi accident data are used which are 2.06 x 1016 Bq and 1.68 x 1017 Bq respectively for the two radionuclides. The result shows that the dispersion distance obtained from both software are not the same. It shows that 137Cs and 131I can be dispersed as far as 16 km and 80 km away from the site during radiological accident respectively, reaching major towns in Perak. Using HOTSPOT, the estimated total effective dose equivalent (TEDE for 137Cs and 131I at major towns in Perak such as Lumut and Sitiawan are 1.2 mSv and 9.9 mSv. As for Taiping, Ipoh, Kampar, and Teluk Intan the estimated TEDE is around 0.2 mSv and 1.6 mSv respectively. In conclusion, the dispersion can reach as far as 80 km from the site. However, estimated annual effective dose is not more than 1 mSv limit, which is considered acceptable in the point

Dukovany NPP - Safely 16 TERA

International Nuclear Information System (INIS)

Vlcek, J.

2008-01-01

In this presentation increasing of power output of the Dukovany NPP is reviewed. To operate all Dukovany Units safely with the perspective of long-term operation (LTO) of 50 - 60 years it is proposed.

NPP A-1 decommissioning - Phase I

International Nuclear Information System (INIS)

Krstenik, A.; Blazek, J.

2000-01-01

Nuclear power plant A-1 with output 150 MW e , with metallic natural uranium fuelled, CO 2 cooled and heavy water moderated reactor had been prematurely finally shut down in 1977. It is necessary to mention that neither operator nor regulatory and other authorities have been prepared for the solution of such situation. During next two consecutive years after shutdown main effort of operator focused on technical and administrative activities which are described in the previous paper together with approach, condition and constraints for NPP A-1 decommissioning as well as the work and research carried out up to the development and approval of the Project for NPP A-1 decommissioning - I. phase. Subject of this paper is description of: (1) An approach to NPP A -1 decommissioning; (2) An approach to development of the project for NPP A-1 decommissioning; (3) Project - tasks, scope, objectives; (4) Mode of the Project realisation; (5) Progress achieved up to the 1999 year. (authors)

New appraisement of siting for a NPP on Mures river

International Nuclear Information System (INIS)

Traian Mauna

2010-01-01

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)

Cernavoda NPP environmental management system - tool for managing the impact on the environment

International Nuclear Information System (INIS)

Gabriel, B.; Adrian, J.

2009-01-01

Nuclearelectrica SA (SNN SA) is a state owned company which produces nuclear-generated electricity, heat and CANDU 6 type nuclear fuel. The company has also an active participation in the power development program in Romania. The Cernavovoda NPP, one of the SNN branches is situated at 180 km east of Bucharest, in Constanta County at about 2 km SE from Cernavoda town is a CANDU 6 type. Cernavoda Nuclear Power Plant (NPP) is dedicated to generate electrical and thermal power, safely and efficiently for at least 30 years. Having an annual gross output of 5.2 - 5.4 MWh, the Cernavoda Unit 1 NPP provides 10% of the Romanian electric power production. Starting January 01 2007, the Cernavoda Unit 1 NPP supplied into the grid 5518346 MWh electric power and during 1997 - 2007 the Cernavoda Unit 1 NPP supplied into the grid 55769213 MWh electric powers. Over the same period Unit 1 also provided the partial district heating of the town of the Cernavoda supplying about 601517.9 Gcal. Romania second CANDU nuclear power plant, Cernavoda Unit 2, was officially placed in service on Friday, October 5, 2007 together with Unit 1, the CNE-Cernavoda Station is the largest power producer in the country. It now accounts for about 18 per cent of Romania energy supply and significantly reduces its dependency on expensive energy resources from outside of Europe. It provides a structured approach to planning and implementing environmental protection measures. It also establishes a framework for tracking, evaluating and communicating environmental performance. SNN SA mission is to operate the Cernavoda NPP - in a competitive, safe and environmental friendly manner so that the production is optimized and the economic life time of the plant is as long as possible. One major accomplishment is the achievement of ISO 14001 certification for our Environmental Management System (EMS) at Cernavoda NPP. The aim of this paper is to present the EMS implemented and to emphasize the outcomes of the

Seismic analysis of a NPP reactor building using spectrum-compatible power spectral density functions

International Nuclear Information System (INIS)

Venancio Filho, F.; DeCarvalho Santos, S.H.; Joia, L.A.

1987-01-01

A numerical methodology to obtain Power Spectral Density Functions (PSDF) of ground accelerations, compatible with a given design response spectrum is presented. The PSDF's are derived from the statistical analysis of the amplitudes of the frequency components in a set of artificially generated time-histories matching the given spectrum. A so obtained PSDF is then used in the stochastic analysis of a NPP Reactor Building. The main results of this analysis are compared with the ones obtained by deterministic methods

Safety enhancement concept for NPP of new generation with VVER reactors

International Nuclear Information System (INIS)

Bezlepkin, V.; Kukhtevich, I.; Semashko, S.; Svetlov, S.; Solodovnikov, A.

2004-01-01

With the present day conditions, in order to successfully promote new NPP designs in the electric power markets, it is necessary to ensure enhanced technical/economic performances provided that international safety requirements are properly adhered to. When compared with high-powered nuclear power plants, NPP VVER-640 design (medium powered) possesses a number of advantages for the regions with undeveloped energy systems. Reduced specific energy intensity of the core adopted in this type of reactor allows to ensure the emergency cooldown of the reactor plant by passive means and to minimize the 'human factor' risk and external effects and provide sound substantiations as to how to retain corium inside RPV in case of severe accidents. At the same time, high-powered NPPs seem to be promising for regions with developed energy systems. Among such designs, NPP VVER-1000 and VVER-1500 designs are the most desirable. Configuration of new generation NPP with VVER-1500 is to be selected based on the gained experience in designing NPPs of previous generations considering the latest safety requirements and situation in the domestic and global energy markets for the time being and in the short run. Recent IAEA publications and latest EUR requirements insist that the following key safety indices should be established for new NPP designs: - aggregated frequency of core melting is 10 -6 (1/year); - frequency of maximum accident release is 10 -7 (1/year). To meet the aforementioned criteria, it is necessary to implement some safety assurance principles recommended by IAEA (in-depth defence, single failure, redundancy, diversity, etc.), application of deterministic and probabilistic methods for selection of safety assurance activities and means and use of reasonable combination of active and passive systems. Application of VVER-640 concept to high-powered NPPs seems to be a formidable task due to a number of reasons, namely, it is quite difficult to carry out cooldown process

NPP construction cost in Canada

International Nuclear Information System (INIS)

Gorshkov, A.L.

1988-01-01

The structure of capital costs during NPP construction in Canada is considered. Capital costs comprise direct costs (cost of the ground and ground rights, infrastructure, reactor equipment, turbogenerators, electrotechnical equipment, auxiliary equipment), indirect costs (construction equipment and services, engineering works and management services, insurance payments, freight, training, operating expenditures), capital per cents for the period of construction and cost of heavy water storages. It proceeds from the analysis of the construction cost structure for a NPP with the CANDU reactor of unit power of 515, 740 and 880 MW, that direct costs make up on the average 62%

Current technological trends in development of NPP systems

International Nuclear Information System (INIS)

Florescu, Gheorghe; Panaitescu, Valeriu

2010-01-01

The recent nuclear research issues look for new technologies and continuous progress in finding different and efficient solutions for sustained and upraising energy demand. The trend of increasing energy consumption and occurring of new and large consumers, especially from Asian countries, imposes finding of new means for clean, large scale and sustained energy production. NPPs availability was continuously monitored and improved; at the same time the safety of the nuclear energy production was under surveillance. The present development of the new technologies, the discoveries of new materials and development of efficient technological processes offer the opportunities for their appropriate implementation and use in the NPP system configurations and functioning/operation. The new technologies and scientific discoveries, and also the international cooperation, offer the opportunities to mitigate the actual barriers in order to cumulate and use advanced energy production, to find new energy sources and to build improved, reliable and safe power plants. The monitoring systems, intelligent sensors and SSCs, nanotechnologies and new/intelligent materials constitute the main ways for improvement of the NPP systems configuration and processes. The paper presents: - The state of the art in the level of the currently applied technologies for nuclear power systems development; - The actual technological limits that need to be over passed for improving the NPP systems ; - The main systems that need improvement and reconfiguration for development of currently operating NPPs as well as raising the operation efficiency, availability and total safety; - The actual energy production issues; - The key arguments in sustaining the R and D new NPP systems development; - Future trends in NPP development; - The limitations in industrial processes knowledge and use. Appropriate R and D in the field of NPP systems have specific characteristics that were considered in paper completion

IAEA activities on NPP personnel training and qualification

International Nuclear Information System (INIS)

Kossilov, A.

1998-01-01

Activities of IAEA concerning training and qualification of NPP personnel consider the availability of sufficient number of competent personnel which is one of the most critical requirements for safe and reliable NPP operation and maintenance. Competence of personnel is essential for reducing the frequency of events connected to human errors and equipment failures. The IAEA Guidebook on Nuclear Power Plant Personnel Training and its Evaluation incorporates the experience gained worldwide and provides recommendations on the use of SAT being the best practice for attaining and maintaining the qualification and competence of NPP personnel and for quality assurance of training

Construction of large-thickness sand cushions for NPP foundations

International Nuclear Information System (INIS)

Krantsfel'd, Ya.L.; Losievskaya, I.K.; Kovalenko, R.P.; Mutalipov, A.

1982-01-01

A study is made on some technological peculiarities of preparation of NPP foundations and control methods of foundation density. As an example the experience of cement-sand foundation construction for two 900 MW power-units at the Koeberg South Africa NPP is briefly described. The experience of artificial foundation construction at this NPP indicates both the possibility of obtaining the required quality of cement-sand cushions and commercial construction of large volume of such cushions by acceptable rates and the necessity of unification of work quality characteristics

Regulatory aspects of NPP safety

International Nuclear Information System (INIS)

Kastchiev, G.

1999-01-01

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

Operation time extension for power units of the first generation NPP and the liability for potential damage

International Nuclear Information System (INIS)

Kovalevich, O.M.

2000-01-01

The problem on the operation time extension for the six operating NPP first generation power units is discussed. However it is not advisable to improve the safety of these power units up to the acceptable level, therefore there arises the contradiction between the operation time extension of these power units and potential damage for the population. The possibility of having the increased civilian-legal responsibility for potential harm and losses in case of an accident is proposed to be considered as a compensating measure. The measures for realization of this civilian-legal responsibility are described [ru

Qualification of NPP operations personnel

International Nuclear Information System (INIS)

Wang Jiao.

1987-01-01

Competence of personnel is one of the important problems for safety operation of nuclear power plant. This paper gives a description of some aspects, such as the administration of NPP, posts, competence of personnel, training, assessing the competence and personnel management

Start-up of NPP Krsko; Pokusno obratovanje NE Krsko

Energy Technology Data Exchange (ETDEWEB)

Spiler, J; Aralica, J [Nuklearna elektrana Krsko, Krsko (Yugoslavia)

1984-07-01

The report describes a review of start-up program and its realisation. There are also described some more significant start-up results with their evaluation. The most significant operation criteria are compared between NPP Krsko and other similar plants in the world. The comparison shows that after the first contractors and operation personnel efforts have been accomplished, our first nuclear power plant is a safe and reliable source of electric power. At the end there are listed NPP Krsko start-up recommendations and experience. (author)

Procedure for Application of Software Reliability Growth Models to NPP PSA

International Nuclear Information System (INIS)

Son, Han Seong; Kang, Hyun Gook; Chang, Seung Cheol

2009-01-01

As the use of software increases at nuclear power plants (NPPs), the necessity for including software reliability and/or safety into the NPP Probabilistic Safety Assessment (PSA) rises. This work proposes an application procedure of software reliability growth models (RGMs), which are most widely used to quantify software reliability, to NPP PSA. Through the proposed procedure, it can be determined if a software reliability growth model can be applied to the NPP PSA before its real application. The procedure proposed in this work is expected to be very helpful for incorporating software into NPP PSA

NPP Krsko natural circulation performance evaluation

International Nuclear Information System (INIS)

Segon, Velimir; Bajs, Tomislav; Frogheri, Monica

1999-01-01

The present document deals with an evaluation of the natural circulation performance of the Krsko nuclear power plant. Two calculation have been performed using the NPP Krsko nodalization (both similar to the LOBI A2-77 natural circulation experiment) - the first with the present steam generators at NPP Krsko (Westinghouse, 18% plugged), the second with the future steam generators (Siemens, 0% plugged). The results were evaluated using the natural circulation flow map derived in /1/, and were compared to evaluate the influence of the new steam generators on the natural circulation performance. (author)

Dissemination of Knowledge about NPP Instrumentation and Control Systems

International Nuclear Information System (INIS)

Yastrebenetsky, M.

2016-01-01

Full text: Instrumentation and control (I&C) systems are the most variable part in the nuclear power plants (NPP) comparatively with any other NPP systems. This statement is connected with the wide use of computers, rapid changes in information technologies, with the appearance of new computer complex electronic components, e.g., field programmable gate arrays (FPGA) and with appropriate point of their insertion into NPP I&C life cycle. The changes in NPP I&C systems require the dissemination of the knowledge about these systems. Lessons after Fukushima accident increase necessity of these actions. The elaboration and following dissemination of this knowledge took place in different directions: • Writing and issue of three new books about NPP I&C systems for specialists and for students which were issued in Ukrainian and USA public houses (the last book was issued in 2014); • Organization of five international scientific technical conferences, devoted to NPP I&C safety problems; • Elaboration of national (Ukrainian) standards and regulations pertaining to safety important NPP I&C systems (the last standard was issued in 2015) and participation in elaboration of international standards; • Lecturing for university students, NPP specialists and I&C designers. These actions in all directions are added to IAEA activity in the area NPP I&C systems (e.g., IAEA NP-T-3.12 “Core Knowledge on I&C systems in NPP”). (author

Near Regional and Site Investigations of the Temelin NPP Site

International Nuclear Information System (INIS)

Prachar, Ivan; Vacek, Jiri; Heralecky, Pavel

2011-01-01

The Temelin NPP is worldwide through heated discussion with nuclear energetic opposition. In addition this discussion goes beyond a border of the Czech Republic. On the other side, results of several international supervisions shown that Temelin NPP is fully comparable with the safest nuclear power plants in the world regarding its technical design and safety functions. This presentation deals with the near regional and site investigations of the Temelin NPP Site. It must be noted that although the Temelin site is situated in the area with low seismicity, item of seismicity is a basic argument against Temelin NPP and therefore a detail seismic hazard assessment was performed

Studies of Effect Analysis of Electromagnetic Pulses (EMP) in Operating Nuclear Power Plants (NPP)

Energy Technology Data Exchange (ETDEWEB)

Ye, Song Hae; Ryu, Ho Sun; Kim, Min Yi; Lee, Eui Jong [KHNP, Daejeon (Korea, Republic of)

2016-05-15

The effect analysis of electromagnetic pulses (EMPs) has been studied for the past year by the Central Research Institute of Korea Hydro Nuclear Power Co. (KHNP) in order to better establish safety measures in operating nuclear power plants. What is an electromagnetic pulse (EMP)? As a general term for high-power electromagnetic radiation, it refers to strong electromagnetic pulses that destroy only electronic equipment devices in a short period without loss of life. The effect analysis of EMPs in operating NPPs and their corresponding safety measures in terms of selecting target devices against EMP impact have been examined in this paper. In general, domestic nuclear power plants do apply the design of fail-safe concepts. For example, if key instruments of a system fail because of EMPs, the control rods of a nuclear reactor are dropped automatically in order to maintain safe conditions of the NPP. Reactor cooling presents no problem because the diesel generator will adopt the analog starting circuit least affected by the electromagnetic waves.

Temelin NPP commissioning experiences

International Nuclear Information System (INIS)

Hanus, V.

2002-01-01

The Building Permit for the Temelin NPP with four VVER units was issued in 1986, which is a long time ago. Since then, however, was taken a route that is very different from what anybody imagined. Described are the legislative and design changes and given is a current condition of the power plant

Licensing of the Ignalina NPP

International Nuclear Information System (INIS)

Kutas, S.

1999-01-01

Since 1991 State Nuclear Power Safety Inspectorate (VATESI) has regulated Ignalina NPP operation by issuing annual operating permits. Those have been issued following submission of specified documents by the Ignalina NPP that have been reviewed by VATESI. However, according to to the procedures that are now established in the Law on Nuclear Energy and subordinate regulations the use of nuclear energy in the Republic of Lithuania is subject to strict licensing. Therefore a decision about the licence for continued operation of unit 1 should be taken. Licence would be granted by VATESI in cooperation with the Ministry of Health, Ministry of Environment and the institutions of local authorities. Ignalina NPP presented to the VATESI safety analysis report (SAR) with other documents. SAR was made mainly by foreign experts and financed by European Bank for Reconstruction and Development (EBRD). VATESI in this process is supported by western regulators. A special project LAP - Licensing Assistance Project was launched to help VATESI perform licensing according western practices

Problems of complex automation of process at a NPP

International Nuclear Information System (INIS)

Naumov, A.V.

1981-01-01

The importance of theoretical investigation in determining the level and quality of NPP automation is discussed. Achievements gained in this direction are briefly reviewed on the example of domestic NPPs. Two models of the problem solution on function distribution between the operator and technical means are outlined. The processes subjected to automation are enumerated. Development of the optimal methods of power automatic control of power units is one of the most important problems of NPP automation. Automation of discrete operations especially during the start-up, shut-down or in imergency situations becomes important [ru

Quantitative analysis of psychological personality for NPP operators

International Nuclear Information System (INIS)

Gao Jia; Huang Xiangrui

1998-01-01

The author introduces the relevant personality quantitative psychological research work carried out by 'Prognoz' Laboratory and Taiwan, and presents the primary results of the research for Chinese Nuclear Power Plant (NPP) operator's psychological personality assessment, which based on the survey of MMPI, and presents the main contents for the personality quantitative psychological research in NPP of China. And emphasizes the need to carry out psychological selection and training in nuclear industry

Summary of NPP personnel training in Czech Republic

International Nuclear Information System (INIS)

1996-01-01

The preparation of NPP personnel is one of the most important phases of the process of construction, commissioning, operation and maintenance of nuclear power facilities. The objective is to improve personnel abilities so that they would be able to assure reliable, safe and economic operation of these facilities with high investment costs. It is the purpose of Nuclear Training Centre Brno (NTC Brno) to provide training and services which are responsive to the technological demands and emerging educational standards and criteria of the NPP and the nuclear industry. Fulfilling this purpose is a challenging task. The staff of NTC Brno, in a joint effort with NPP Dukovany and NPP Temelin, has responded to the challenge with comprehensive programs aimed at meeting customers needs. The programs are broadly based, yet flexible so that they can incorporate specific customer requirements

Challenges of Ignalina NPP Decommissioning - View of Lithuanian Operator

International Nuclear Information System (INIS)

Aksionov, P.

2017-01-01

The state enterprise Ignalina Nuclear Power Plant (INPP) operates 2 similar design units of RBMK-1500 water-cooled graphite-moderated channel-type power reactors (1500 MW electrical power). INPP is carrying out the decommissioning project of the 2 reactors which includes: -) the retrieval of the spent nuclear fuel from the power units and its transportation into the Interim Spent Fuel Storage Facility; -) equipment and building decontamination and dismantling; -) radioactive waste treatment and storage; and -) the operation of key systems to ensure nuclear, radiation and fire protection. Ignalina NPP decommissioning project is planned to be completed by 2038. The presentation will be focused on the ongoing decommissioning activities at Ignalina NPP. The overview of main aspects and challenges of INPP decommissioning will be provided

NPP electrical price and tariff in the world

International Nuclear Information System (INIS)

Mochamad Nasrullah and Sriyana

2010-01-01

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)

System for remote routine monitoring of power equipment at TPP and NPP

International Nuclear Information System (INIS)

Kantsedalov, V.G.; Samojlenko, V.P.; Doroshenko, V.A.

1988-01-01

A system for remote routine monitoring of TPP and NPP pipeline metals is described. The principal functional unit of the system is the unit of remote routine methods and techniques for studying and monitoring the metal and properties. The system is equipped with 5 types of routine monitoring equipment: robots, remote aggregated complexes, periodical diagnostic monitors, other means of metal diagnostics (endoscopes, introscopes). All current information enters the unit for estimating and forecasting the service life of power unit, where it is compared with the standard indices of reliability, duravility and efficiency. The system considered permits to reduce significantly or minimize the scope of works on metal monitoring during overhauls, increase intermonitoring and interrepairing compaigns to 8 years

Ideal scaling of BETHSY 9.1.B test results to NPP

International Nuclear Information System (INIS)

Petelin, S.; Guntel, I.

1995-01-01

The transient scenario standard problem 27 (ISP-27) was implemented in the RELAP5 analysis of small break loss of coolant accident for Krsko nuclear power plant (Krsko NPP). The objective was to evaluate the effectiveness of ISP-27 proposed accident management procedure for real NPP and to compare the physical phenomena known from experimental background with the phenomena predicted by RELAP5 simulation of real plant transient. The analyses showed that, if relevant break, power scaling criteria, primary and secondary pressure are fulfilled the RELAP5 model of Krsko NPP cannot completely ensure the simulation of typical thermal-hydraulic phenomena observed in BETHSY facility during ISP-27. Much better satisfaction is observed on ideal scaled up model. (author)

The Bohunice NPP V-1 units nuclear safety upgrading

International Nuclear Information System (INIS)

Mlcuch, M.

2000-01-01

Safety upgrading and operational reliability improvement was carried out by the Bohunice NPP V-1 staff continuously since the plant commissioning. By now, more than 1200 minor or major modifications have been implemented, either by the NPP maintenance staff or by the contractors. Based on findings of safety assessment missions invited by Bohunice NPP in 1990 - 1991, the Czecho-slovak Nuclear Regulatory Authority (CSKAE) issued the decision No. 5/91 of 81 safety upgrading measures to be taken in different areas. These improvements are referred to as the 'Small Reconstruction of the Bohunice V-1 NPP'. Realization of measures during Small reconstruction of the Bohunice NPP V-1 became a power plant, which further operation is acceptable from safety point of view, but it is also necessary further safety improvement. During the period of the Small Reconstruction the development of a Safety Report for the Gradual reconstruction has been completed. Based on this report the SR Nuclear Regulatory Authority issued the Decision No. 1/94, in which requires 59 upgrading measures in different areas to be addressed. The development of Basic Engineering of the Gradual Reconstruction has been contracted to the Siemens AG. Implementation of safety measures are provided through contract with the consortium REKON (which consists of Siemens AG company and Nuclear Power Plants Research Institute Trnava) and other Czech, Russian and Slovak companies. The Gradual Reconstruction of Bohunice NPP V-1 will be finished in 2000. By implementation of the measures carried out during Gradual Reconstruction achievement of an internationally acceptable nuclear safety level will be reached. (author)

Conference: Nuclear Safety at the Ignalina NPP - Achievements and Challenges

International Nuclear Information System (INIS)

1999-01-01

Brief description of conference which took place in Vilnius on 8-9 April 1999 is presented. The aim of the international conference is to review the work carried out, to evaluate its influence on the nuclear safety, to get acquainted with the safety system of the Ignalina NPP. On December 31, the Ignalina NPP celebrated its 15 year anniversary. During that period the Ignalina NPP has produced more than 182 billion kWh of electricity. Nuclear power is not only immense economic benefit but also a syndrome of fear of an atomic bomb and the Chernobyl accident that has formed over the years. Numerous comprehensive international studies have been performed at the Ignalina NPP. After the Chernobyl accident many steps have been taken to improve the safety of the Ignalina NPP. The introduced changes guaranteed that the void coefficient remained negative in all possible circumstances. The Ignalina NPP is intensively preparing for licensing of unit 1

Replacement of the computerized control system at NPP under operation

International Nuclear Information System (INIS)

Ermolaev, A.D.; Rakitin, I.D.

1985-01-01

Reasons and preconditions for replacement of the computerized control systems (CCS) at NPP under operation are consi-- dered. Problems dealing with management of CCS replacement, maintenance of a new CCS as well as NPP personnel training for the new system maintenance are discussed. A necessity of NPP personnel participation in these works in order to adapt CCS to requirements of NPP operation personnel and to initiate the training process is underlined. Replacement of CCS at NPP under operation is associated, as a rule, with obsolescence of old systems not ensuring growing requirements to NPP workability and safety. Principles observed at CCS replacement are reduced, mainly, to the following; maximum utilizatian of existing equipment, metal strUctures, cables, instruments, power supplies, ventilation system minimum of construction works and new communications; the least change of acting panels and boxes; changes in control desks should be introduced on the basis of the analysis of operator actions '

The Chernobyl NPP decommissioning: Current status and alternatives

International Nuclear Information System (INIS)

Mikolaitchouk, H.; Steinberg, N.

1996-01-01

After the Chernobyl accident of April 26, 1986, many contradictory decisions were taken concerning the Chernobyl nuclear power plant (NPP) future. The principal source of contradictions was a deadline for a final shutdown of the Chernobyl NPP units. Alterations in a political and socioeconomic environment resulted in the latest decision of the Ukrainian Authorities about 2000 as a deadline for a beginning of the Chernobyl NPP decommissioning. The date seems a sound compromise among the parties concerned. However, in order to meet the data a lot of work should be done. First of all, a decommissioning strategy has to be established. The problem is complicated due to both site-specific aspects and an absence of proven solutions for the RBMK-type reactor decommissioning. In the paper the problem of decommissioning option selection is considered taking into account an influence of the following factors: relevant legislative and regulatory requirements; resources required to carry out decommissioning (man-power, equipment, technologies, waste management infrastructure, etc.); radiological and physical status of the plant, including structural integrity and predictable age and weather effects; impact of planned activities at the destroyed unit 4 and within the 30-km exclusion zone of the Chernobyl NPP; planed use of the site; socio-economic considerations

On improving the NPP construction long-term planning

International Nuclear Information System (INIS)

Solov'ev, M.M.

1980-01-01

General approaches to solving the problems of long-term planning of the construction-mounting work volume and introduction of power capacities at different paces of power unit commission and norms of construction time are considered. Problems associated with location and development of subsidiary industries providing NPP construction are discussed. It is shown that decrease of WWER-1000 reactor type NPP construction time from 24 to 12 months results in reduction of required high-skilled engineers, managerial staff, unique construction mechanisms and engines as well as in improvement of conditions for conducting measures on work arrangement during preparation of construction industry and mounting of the first assemblies

Improvement of operational performance and increase of safety of WWER-1000/V-392

International Nuclear Information System (INIS)

Kurakov, Y.A.; Dragunov, Y.G.; Podshibiakin, A.K.; Fil, N.S.; Krushelnitsky, V.N.; Berkovich, V.M.

2001-01-01

The national programme of nuclear power development approved by the Russian Federation Government in 1998 considers the design of WWER-1000/V-392 power unit as a priority project of the new generation NPP with improved operational performances and increased safety. The pilot unit of this design (NVAES-2) is licensed for construction at the Novovoronezh NPP site. The NVAES-2 design is developed on the basis of standard power unit with reactor plant V-320. Twenty units of this type are in operation at the nuclear power plants in Russia, Ukraine and Bulgaria having totally about 270 reactor-years of operation. Two more V-320 units are being commissioned this year at Rostov NPP and Temelin NPP. So, the WWER-1000/V-392 design is as a whole an evolutionary development of the operating standard unit WWER-1000/V-320. Many technical solutions aimed at increase of safety and improvement of operational performance of the plant are implemented in the NVAES-2 design, such as advanced reactor WWER-1000, passive system of residual power removal, passive system of the core flooding under loss-of-coolant accidents, and others. NVAES-2 design refers to a class of advanced light water reactors and corresponds to the international requirements imposed to the nuclear power plants to be put into operation after the year 2000. New V-392 power unit has a good perspective from the view point of extensive implementation in the framework of the nuclear electricity production in Russia. Design decisions on NVAES-2 power unit with WWER-1000/V-392 reactor plant which assure significantly higher safety level and improve economical performance as compared to the operating WWER-1000 units are briefly considered in the present paper. (author)

Programmes design for Bohunice NPP personnel other than control room operators

International Nuclear Information System (INIS)

Kalincik, L.

2002-01-01

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

Lifetime evaluation of Bohunice NPP components

International Nuclear Information System (INIS)

Kupca, L.

2001-01-01

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)

Consideration on application of RAP to G-II NPP

International Nuclear Information System (INIS)

Shen Shen

2010-01-01

The design (D-RAP) for nuclear power plant has been adopted internationally in new-build advanced nuclear power plant design, which increases the ability of the risk-significant SSCs to carry out its functions during the accident circumstances especially in the severe accident situation, and reduces the risk of a nuclear power plant. The concept of reliability assurance program for advanced nuclear power plant can also be applied to nuclear power plants which second-generation NPP technology is used. Through analysis and research, the risk-significant SSCs in actual NPP can also be screened, and these SSCs can be managed appropriately, so that can improve the overall plant ability to against the severe accident, reduce the risk, and improve their safety and economy. Also such technology used does not exist any insurmountable technical difficulties and a lot of money input. (authors)

Medical consequences of NPP and TPP operation

International Nuclear Information System (INIS)

Bliznakov, V.

1996-01-01

Results from a comparative analysis of health conditions of the staff in the Kozloduy NPP and the Maritsa Iztok TPP are reported. It is found that the general disease incidence with temporary incapacity for work of Kozloduy workers is lower than those data for the workers at thermal power stations. The incidence of some social diseases like neoplasms, TBC, hypertension, ischemia etc. is also lower for the staff of NPP. No cases of radiation injuries have been registered for a period of 21 years

Safeguards at Kozloduy NPP - Experience and expectations

International Nuclear Information System (INIS)

Elenkov, Todor

2001-01-01

Bulgaria is a party of Non Proliferation Treaty since 5 September 1969. The agreement between IAEA and Bulgaria - INFCIRC 178 - has been in force since 29 February 1972. At that time Bulgaria had one research reactor IRT-2000 in Sofia and two power reactors of WWER-440 type under construction. Now at Kozloduy NPP site there are 4 facilities, which consist of 4 WWER-440 and 2 WWER-1000 type power reactors, producing almost 50% of the electricity in Bulgaria and 1 wet away from reactor spent fuel storage. In 1991 under the green movements and social pressure, the research reactor in Sofia was closed and the construction of the second NPP in Belene with 2 WWER-1000 type reactors was halted. After the transfer in 1994 of the fresh fuel from the research reactor to Kozloduy due to security reasons practically NPP Kozloduy remains the only significant (from safeguards point of view) nuclear site in Bulgaria. In 1972 a 'Nuclear Fuel' group was formed at the Physicists Department in NPP Kozloduy with responsibilities to carry out for safeguards records and reports, fresh and spent fuel transport and control. In 1990 this group was transferred to the Safety Section and since 1992 it exists as 'Control and Accounting for of the Nuclear Materials' - a section in the Safety Department. Currently the section serves all four facilities in NPP Kozloduy and has four people: section head, chief inspector and two inspectors. The main activities of the section include: a) Control of the nuclear fuel location as well as meeting the storage and transport conditions regulations; b) Control of the conditions for normal operations of the installed IAEA surveillance systems; c) Preparation of documents for licensing of fresh and spent nuclear fuel transport; d) Preparation of the official information on nuclear materials location and quantity; e) Preparation of accounting records and the reports for IAEA (ICR, PIL, MBR); f) Co-ordination of the IAEA safeguards inspection activities at NPP

Compex system for teaching and training operators for TPP and NPP power units

International Nuclear Information System (INIS)

Tsiptsyura, R.D.

1985-01-01

Requirements, taken as a principle for constructing the system for operator teaching and training (OTT), have been formulated on the basis of investigation of operators' work at TPP and NPP power units. Functional structure and a structural block-diagram for OTT are built. As a criterion, which determines the structure of any trainers, being a part of OTT a requirement has been chosen satisfying the correspondence beetween habits developed with the help of trainers and habits of real operators' work. Results of analysis permit to confirm that refusal or under statement of the role of any stage of operator training leads to reduction of quality of his training

A reliability evaluation method for NPP safety DCS application software

International Nuclear Information System (INIS)

Li Yunjian; Zhang Lei; Liu Yuan

2014-01-01

In the field of nuclear power plant (NPP) digital i and c application, reliability evaluation for safety DCS application software is a key obstacle to be removed. In order to quantitatively evaluate reliability of NPP safety DCS application software, this paper propose a reliability evaluating method based on software development life cycle every stage's v and v defects density characteristics, by which the operating reliability level of the software can be predicted before its delivery, and helps to improve the reliability of NPP safety important software. (authors)

Some problems of NPP construction base improvement

International Nuclear Information System (INIS)

Movchan, S.V.

1984-01-01

NPP construction bases are characterized by high cost of construction and large area. Duration of base construction makes up 3-4 years, labour contents for their erection constitute 600-900 thousand man-days. Delays in organizing functional base services essentially decelerate construction rates of the main NPP buildings. Maximum joining of separate buildings by their functional assignment and structural peculiarities, wide application of container buildings, partial utilization of permanent buildings of production centre for construction needs; transition to new organizational form of construction based on industrial production of buildings; production of volumetric structural-technological cells with mounted equipment manufactured at specialized plants, mounting NPP components with stock produced cells, consideration of the problem of large power centre creation are necessary for reduction of construction centres, area reduction of cost and duration of their construction

Qinshan NPP large break LOCA safety analysis

International Nuclear Information System (INIS)

Shi Guobao; Tang Jiahuan; Zhou Quanfu; Wang Yangding

1997-01-01

Qinshan NPP is the first nuclear power plant in the mainland of China, a 300 MW(e) two-loop PWR. Large break LOCA is the design-basis accident of Qinshan NPP. Based on available computer codes, the own analysis method which complies with Appendix k of 10 CFR 50 has been established. The RELAP4/MOD7 code is employed for the calculations of blowdown, refill and reflood phase of the RCS respectively. The CONTEMPT-LT/028 code is used for the containment pressure and temperature analysis. The temperature transient in the hot rod is calculated using the FRAP-6T code. Conservative initial and functional assumptions were adopted during Qinshan NPP large break LOCA analysis. The results of the analysis show the applicable acceptance criteria for the loss-of-coolant accident are met

Safety upgrading of Bohunice V1 NPP

International Nuclear Information System (INIS)

2001-01-01

This CD is multimedia presentation of programme safety upgrading of Bohunice V1 NPP. It consist of next chapters: (1) Introductory speeches; (2) Nuclear power plant WWER 440; (3) Safety improvement; (4) Bohunice Nuclear power plants subsidiary; (5) Siemens; (6) REKON; (7) VUJE Trnava, Inc. - Engineering, Design and Research Organisation; (8) Album

Jose Cabrera NPP severe accident management activities

International Nuclear Information System (INIS)

Blanco, J.; Almeida, P.; Saiz, J.; Sastre, J.L.; Delgado, R.

1998-01-01

To prepare a common acting plan with respect to Severe Accident Management, in 1994 was founded the severe accident management ''ad-hoc'' working group from the Spanish Westinghouse PWR Nuclear Power Plant Owners Group. In this group actively collaborated the Jose Cabrera NPP Training Centre and the Department of Nuclear Engineering of UNION FENOSA. From this moment, Jose Cabrera NPP began the planning of its specific Severe Accident Management Program, which main point are Severe Accident Management Guidelines (SAMG). To elaborate this guidelines, the Spanish translation of Westinghouse Owners Group (WOG) Severe Accident Management Guidelines were considered the reference documents. The implementation of this Guidelines to Jose Cabrera NPP started on January 1997. Once the specific guidelines have been implemented to the plant, training activities for the personnel involved in severe accident issues will be developed. To prepare the training exercises MAAP4 code will be used, and with this intention, a specific Jose Cabrera NPP MAAP-GRAAPH screen has been developed. Furthermore, a wide selection of MAAP input files for the simulation of different scenarios and accidental events is available. (Author)

The comparative analysis of safety and economic competitiveness of the advanced high-power reactor projects of NPP

International Nuclear Information System (INIS)

Batyrbekov, G.A.; Makhanov, U.M.; Philimonova, R.A.; Kichutkina, E.G.

2002-01-01

The comparative analysis results of the safety and economic competitiveness of the seven advanced large sized reactors projects (900 MW and more) are submitted in that report: EPR, Frameatome France, Siemens Germany; EP-1000 Westinghouse, USA and Genesi Italy; Candu 9, Atomic Energy of Canada Ltd; System 80 +, ABB, USA; KNGR, group NSSS Engineering and Development, Korea Power Engineering Company, Inc; APWR, Electric Power company, Japan Atomic Power Company, Mitsubishi Heavy Industries, Westinghouse Electric; and WWER-1000 (V-392), Atomenergoproject/Gidropress Russian Federation. According to the economic competitiveness of listed compared power reactors the 14 criteria of safety have been accepted. These criteria: 1. Features of the barrier system of 'defence-in-depth'. 2. The self-security of a reactor under increase of power and reactivity of a reactor, decrease of the expense and phase transformations of the reactor core coolant (presence of negative feedbacks). 3. Presence of the reactor shutdown systems responding principles of a variety, independence and reservation. Presence of the passive means of initiation and operation of the emergency protection. 4. The emergency cooling of the core of reactor. A presence of the passive means of cooling. Presence of the water reservation for the water supply of the different safety systems. 5. The emergency electrical supply, its reliability and degree of reservation. 6. The prevention measures of the heavy accident with the melt core. The decrease of the heavy accident probability. 7. The account of the heavy accident under development of the levels of protection. 8. The protection levels of NPP, the technological criteria of efficiency of the each safety barriers and the limiting radiation criteria for the each level of protection , in particular for the design-basis and beyond-design-basis accidents. 9. The measures for reduction of the heavy accident consequences. The management by the beyond

Overview of Cernavoda NPP training programme

International Nuclear Information System (INIS)

Valache, Cornelia

2005-01-01

Full text: The paper presents a general assessment of Cernavoda NPP personnel training programme, highlighting the role of training in human performance improvement. Cernavoda NPP Personnel Training and Authorization Department (PTAD) is the one responsible for the training of Unit 1 and 2 staff. PTAD is structured in such a manner as to support and respond to all Cernavoda NPP training, qualification and authorization requirements. The training of personnel is continuously adapted based on IAEA Guides and INPO/WANO recommendations, to keep with world standards, based on the internal and external reviews. At Cernavoda NPP the Training Concept and the Training Programmes are based on SAT - Systematic Approach to Training. The Training Concept is established on a set of training documents (RD's, SI's, IDP's), which address all the SAT phases: Analysis, Design, Development, Implementation and Evaluation. The Training Programmes are structured on the initial and continuing personnel training. Their content and goals respond to the training specific needs for each plant major job family. In order to successfully support NPP training programmes, CNPP training center has upgraded classrooms with new presentation facilities and there are plans to expand the space of the building, to develop additional operator and maintenance skills facilities. There are also a number of general areas for improvement of PTAD activity, such as operators and maintenance training, initial and continuing training of both Unit 1 and 2 staff. By responding in a timely and completely manner to all plant training requirements PTAD will help in rising human performance of Cernavoda NPP personnel, supporting the safe, efficient and cost effective production of power. (author)

Principles of Defense-in-depth philosophy applied in NPP engineering management

International Nuclear Information System (INIS)

Wu Guangwei

2011-01-01

Based on the Defense-in-depth Concept in nuclear and radiation safety, Defense-in-depth Concept for design management of Nuclear Power Plant (NPP) is developed in this paper to analyze the feasibility and importance of the application of the basic principle: Defense-in-depth concept in NPP systems performed during the design control of NPP. This paper focuses on the NPP engineering management process, and according to the analysis of such process, 5 principles of Defense-in-depth Concept applied in NPP design management are raised: (1) preventing the non-conformities of design via effective design quality management system; (2) discovering and correcting non-conformities of design quality in time via design checkup and design review meeting; (3) carrying out timely analysis and treatment against design non-conformities which have been transferred to construction phase; (4) Assessing and judging the severe non-conformities in construction phase, putting forward treatment opinions and remedies accordingly so as to avoid the existence of such non-conformities in physical construction of NPP; (5) Paying 'return-visit' and performing 'post-assessment' for NPP design to assess the designed functions and safety of NPP comprehensively. (author)

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

International Nuclear Information System (INIS)

1997-01-01

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

New Emergency control center of Slovenske Elektrarne Bohunice NPP

International Nuclear Information System (INIS)

Pecko, E.

2012-01-01

Emergency preparedness of nuclear power plant and operation assurance in case of a possible emergency calls to have devices for emergency response with equipment for rapid detection and continuous evaluation of anticipated events. Chief executive body designated to manage a nuclear power plant during major events is the emergency committee (EC). Emergency Committee is a part of the Emergency Response Organization (ERO). The following centers are on alert to ensure the activities of the ERO - Emergency Response office: - control room (CR) and emergency control room (ECR); - emergency management center (EMC); - Monitoring Centre (MC); - emergency backup control center (EBCC); - congregations of civil protection (CP) and CP shelters; - communications with warning and notification system (VARVYR). From a historical and practical point of view in the vicinity of Jaslovske Bohunice has been set up a joint emergency control center. The center was located on the territory of the former already inoperative V1 NPP. V1 NPP is currently integrated into the organizational structure of JAVYS. Operating Bohunice V2 NPP plant is a designated part of the Slovenske Elektrarne, a. s., whose majority owner is an Italian operator ENEL. In terms of various relevant factors, it was decided to build a new emergency management center on the territory of operating V2 NPP, meet the current standards.

Spent fuel pool risk analysis for the Dukovany NPP

Energy Technology Data Exchange (ETDEWEB)

Hust' ak, S.; Jaros, M.; Kubicek, J. [UJV Rez, a.s., Husinec-Rez (Czech Republic)

2013-07-01

UJV Rez, a.s. maintains a Living Probabilistic Safety Assessment (Living PSA) program for Dukovany Nuclear Power Plant (NPP) in the Czech Republic. This project has been established as a framework for activities related to risk assessment and to support for risk-informed decision making at this plant. The most extensively used PSA application at Dukovany NPP is risk monitoring of instantaneous (point-in-time) risk during plant operation, especially for the purpose of configuration risk management during plant scheduled outages to avoid risk significant configurations. The scope of PSA for Dukovany NPP includes also determination of a risk contribution from spent fuel pool (SFP) operation to provide recommendations for the prevention and mitigation of SFP accidents and to be applicable for configuration risk management. This paper describes the analysis of internal initiating events (IEs) in PSA for Dukovany NPP, which can contribute to the risk from SFP operation. The analysis of those IEs was done more thoroughly in the PSA for Dukovany NPP in order to be used in instantaneous risk monitoring. (orig.)

Low level radioactive waste disposal in Kozloduy NPP in Bulgaria

International Nuclear Information System (INIS)

Stanchev, V.

2001-01-01

Kozloduy NPP is the biggest power plant in the Republic of Bulgaria. It is in operation since 1974 and for the past 25 years it has generated over 263 billion kWh electric power. The NPP share in the total electric production in 1998 was about 50%. It has six units in operation - four WWER 440 B-230 and two WWER 1000 B-320. In the nuclear reactor operation the generation of radioactive waste (RAW) is an inevitable process. The waste must be conditioned, stored and disposed of in a safe manner. There are no national radioactive waste disposal facilities, for waste generated by an NPP, in Bulgaria to the moment. This situation necessitates the storage of operational RAW to be carried out on site for a long period of time (30 to 50 years). Following the principle for protection of human health and environment now and in the future, Kozloduy NPP adopted the concept for conditioning the RAW to a stable solid form and placing the waste in a package which should keep its features for a sufficiently long term so that the package can be safely transported to the disposal site. (author)

Radiation monitoring in the NPP environment, control of radioactivity in NPP-environment system

International Nuclear Information System (INIS)

Egorov, Yu.A.

1987-01-01

Problems of radiation monitoring and control of the NPP-environment system (NPPES) are considered. Radiation control system at the NPP and in the environment provides for the control of the NPP, considered as the source of radioactive releases in the environment and for the environmental radiation climate control. It is shown, that the radiation control of the NPP-environment system must be based on the ecological normalization principles of the NPP environmental impacts. Ecological normalization should be individual for the NPP region of each ecosystem. The necessity to organize and conduct radiation ecological monitoring in the NPP regions is pointed out. Radiation ecological monitoring will provide for both environmental current radiation control and information for mathematical models, used in the NPPES radiation control

Computer-aided design system for a complex of problems on calculation and analysis of engineering and economical indexes of NPP power units

International Nuclear Information System (INIS)

Stepanov, V.I.; Koryagin, A.V.; Ruzankov, V.N.

1988-01-01

Computer-aided design system for a complex of problems concerning calculation and analysis of engineering and economical indices of NPP power units is described. In the system there are means for automated preparation and debugging of data base software complex, which realizes th plotted algorithm in the power unit control system. Besides, in the system there are devices for automated preparation and registration of technical documentation

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.

Revision of Krsko NPP Quality Assurance Plan

International Nuclear Information System (INIS)

Biscan, R.; Fifnja, I.; Kavsek, D.

2012-01-01

International standards from nuclear power plant operation area are being frequently upgraded and revised in accordance with the continuous improvement philosophy. This philosophy applies also to the area of Quality Assurance, which has also undergone significant improvement since the early 1950s. Besides just nuclear industry, there are also other international quality standards that are being continuously developed and revised, bringing needs for upgrades also in the nuclear application. Since the beginning of Krsko NPP construction, the overall Quality Assurance program and its applicable procedures were in place to assure that all planned and systematic actions necessary to provide adequate confidence that an item or service will satisfy given requirements to quality, are in place. The overall requirements for quality as one of the major objectives for Krsko NPP operation are also set forth in the Updated Safety Analyses Report, the document that serves as a base for operating license. During more than 30 years of Krsko NPP operation, the quality requirements and related documents were revised and upgraded in several attempts. The latest revision 6 of QD-1, Quality Assurance Plan was issued during the year 2011. The bases for the revision were: Changes of the Slovenian regulatory requirements (ZVISJV, JV5, JV9?), Changes of Krsko NPP licensing documents (USAR section 13?), SNSA inspection requirements, Changes of international standards (IAEA, ISO?), Conclusions of first PSR, Implementation of ISO standards in Krsko NPP (ISO14001, ISO17025), Changes of plant procedures, etc. One of the most obvious changes was the enlargement of the QA Plan scope to cover interdisciplinary areas defined in the plant management program MD-1, such as Safety culture, Self-assessment, Human performance, Industrial Safety etc. The attachment of the QA Plan defining relationships between certain standards was also updated to provide matrix for better correlation of requirements of

Technology for NPP decantate treatment realized at Kola NPP

International Nuclear Information System (INIS)

Stakhiv, Michael; Avezniyazov, Slava; Savkin, Alexander; Fedorov, Denis; Dmitriev, Sergei; Kornev, Vladimir

2007-01-01

At Moscow SIA 'Radon' jointly with JSC 'Alliance Gamma', the technology for NPP Decantate Treatment was developed, tested and realized at Kola NPP. This technology consists of dissolving the salt residue and subsequent treatment by ozonization, separation of the deposits formed from ozonization and selective cleaning by ferro-cyanide sorbents. The nonactive salt solution goes to an industrial waste disposal site or a repository specially developed at NPP sites for 'exempt waste' products by IAEA classification. This technology was realized at Kola NPP in December 2006 year. At this time more than 1000 m 3 of decantates log time stored are treated. It allows solving very old problem to empty decantates' tanks at NPPs in environmentally safe manner and with high volume reduction factor. (authors)

The local impacts of Borssele NPP closing down

International Nuclear Information System (INIS)

Mandos, J.L.

2000-01-01

The municipal council of Borsele considers that the use of nuclear energy is a question of national policy, but considers itself responsible for town and country planning, safety and employment. The two latter aspects are especially significant if plans for shutdown are concerned. Confidence in safety of the NPP in Borsele has increased in recent years due to transparent information policy of the power plant itself as well as the local government and most of the employees living in the area. If considering the circumstances under which the decision about the closure of NPP one could sees this is a purely political decision. The local government will continue the close cooperation with the National government and the Parliament in solving the problem of employment and social impact of NPP shutdown

Safety requirement of the nuclear power plants, after TMI-2 accident and their possible implementation on Bushehr NPP

International Nuclear Information System (INIS)

Mirhabibi, N.; Tochai, M.T.M.; Ashrafi, A.; Farnoudi, E.

1985-01-01

Based on the lessons learned from the TMI-2 accident and other research and developments, many improvements have been required for the design, manufacturing and operation of nuclear power plants in recent years. These requirements have already been implemented to the plants in operation and considered as new safety requirements for new plants. In the present paper these requirements and their possible implementation on Bushehr NPP are discussed. (Author)

The analysis of financial risk management application for NPP project in Indonesia

International Nuclear Information System (INIS)

Imam Bastori; Moch Djoko Birmano

2012-01-01

NPP Project is one of full dynamic, risky and challenging business. Application of financial risk management t in Nuclear Power Plant (NPP) project becomes one alternative to be considered carefully. This paper explains an analysis to make a decision in the risk management application so that it can be applied in the NPP's construction in Indonesia. As case study, is NPP of conventional PWR type of class 1150 MWe. To calculate the economics and financing of NPP is used Spreadsheet INOVASI, further the decision of financial risk management were analyzed using a Model of Cash Flow Adjustment, which developed by Richard Fairchild. The analysis showed that the Method of Cash Flow Adjustment developed by Richard Fairchild is better than the method of NPV Adjustment on a NPP project, because it have included the aspects of financial risk management. NPP project can only be executed if the NPV 2 0 and decision to execute the financial risk management should be based on NPVrm > NPV. The application of financial risk management in NPP project is not needed if an insurance premium more expensive than all costs of financial distress, unless the insurance company can give discount of at least 20%. (author)

Core Management of NPPs in China and Experience of Tianwan NPP

International Nuclear Information System (INIS)

Guohan, G.

2006-01-01

The Current Status of the NPPs in China; the Nuclear Power Development Plan till 2020; the Fuel Management and the Core Management Strategy of NPPs are briefly presented in this paper. The gained experience during construction of Taiwan NPP, new design features and major construction milestones of Taiwan NPP are also discussed. The full list of 21 non-conformance reports (NCR) submitted by Jiangsu Nuclear Power Company to NNSA during construction of Taiwan NPP is given. The main issues raised during FSAR review like: RP operation with incomplete number of primary loops; Sedimentation in the construction and piping of service water system; Location of postulated pipe break; Stratification analysis for surge line of pressurizer; Safety classification of equipment in primary circuit; Fire resistant capability of cable insulation; Fire Hazard Analysis; Optimization of protection against ionizing radiation ect. are also listed

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.

Polish media and public opinion on NPP Mochovce commissioning

International Nuclear Information System (INIS)

Latek, Stanislaw

1999-01-01

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

The main trends of work on ageing and lifetime management of NPP

International Nuclear Information System (INIS)

Dragunov, Yu.

1994-01-01

The main trends of work on aging and lifetime management of nuclear power plants(NPP) in Russia are described including Russian research programs on NPP components lifetime assurance, technical assistance program for CIS, measures for life extension of reactor pressure vessels, steam generator collectors and components for advances reactor plants. Figs and tabs

Retrofitting of NPP Computer systems

International Nuclear Information System (INIS)

Pettersen, G.

1994-01-01

Retrofitting of nuclear power plant control rooms is a continuing process for most utilities. This involves introducing and/or extending computer-based solutions for surveillance and control as well as improving the human-computer interface. The paper describes typical requirements when retrofitting NPP process computer systems, and focuses on the activities of Institute for energieteknikk, OECD Halden Reactor project with respect to such retrofitting, using examples from actual delivery projects. In particular, a project carried out for Forsmarksverket in Sweden comprising upgrade of the operator system in the control rooms of units 1 and 2 is described. As many of the problems of retrofitting NPP process computer systems are similar to such work in other kinds of process industries, an example from a non-nuclear application area is also given

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)

Integrated tool for NPP lifetime management in Spain

International Nuclear Information System (INIS)

Francia, L.; Lopez de Santa Maria, J.; Cardoso, A.

2001-01-01

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)

Financing nuclear projects. Case study: Unit 2 Cernavoda NPP

International Nuclear Information System (INIS)

Chirica, T.; Pall, S.; Lebedev, A.; Dobrin, M.

2003-01-01

The implementation of a Nuclear Power Plant (NPP) in a country is a major undertaking for all entities involved, due to the necessity of planning work and co-ordination of the implementation process of the different fields of interest, starting with the governmental authorities and ending with the people. Having in view the specific investment cost (relatively high) for a NPP, to find an adequate financing structure is possible through an iterative process that involves first an assessment of the technical performances of the project and second, the mathematical modelling of the financing structure effects on the project. In this respect, the paper proposed will be focused on the main steps needed in order to promote an investment project in nuclear field, starting with the decision phase, providing the documentations requested by the local and international authorities to promote the project and ending with the negotiation of the contracts (commercial contract, financing contract, power purchase contract, etc.) The case study will be focused on the phases achieved in order to promote the Unit 2 Cernavoda NPP completion works project. (author)

Robot dispatching Scenario for Accident Condition Monitoring of NPP

International Nuclear Information System (INIS)

Kim, Jongseog

2013-01-01

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

Standard protocol for evaluation of environmental transfer factors around NPP sites

International Nuclear Information System (INIS)

Hegde, A.G.; Verma, P.C.; Rao, D.D.

2009-01-01

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)

Tendencies of ecological changes in the region of Ignalina NPP and in Lake Drukshiai

International Nuclear Information System (INIS)

Pashkauskas, R.; Mazeika, J.; Baubinas, R.

1999-01-01

Since 1979, when the construction of the Ignalina Nuclear Power Plant started, a group of specialists from Lithuania research and academic institutions began to investigate both Lake Drukshiai - the cooler of the Ignalina NPP and the neighbouring area. The investigations were aimed not only at monitoring the environmental consequences of the Ignalina NPP impact but also at forecasting changes of the ecosystems. The State Scientific Program 'Ignalina Nuclear Power Plant and the Environment' was the result of final stage of complex investigations. This conference paper contains data on the changes of thermal state and water balance of Lake Drukshiai, the effect of permanent thermal and chemical pollution on the chemical composition and hydrochemical regime, the pollution of the lake water, the geochemical-contaminated state, the condition, dynamics and the changes of hydrobiont communities in Lake Drukshiai. Radioecological and eco toxicological state of Ignalina NPP region and Lake Drukshiai is estimated as well as changes in Lake Drukshiai and Ignalina NPP surrounding area ecosystems under the combine anthropogenic impact of the plant influence are elucidated. The findings on medical and biological studies in the Ignalina NPP influence population zone and the evidence of impact of Ignalina NPP on social-territorial processes in the region are presented as well

Decommissioning of Brennilis NPP

International Nuclear Information System (INIS)

Baize, Jean-Marc

1998-01-01

This EDF press communique give information related to the decommissioning of the Brennilis NPP. The following five items are developed in this report: 1. the level-2 decommissioning operations at the Brennilis NPP; 2. the Brennilis NPP, a pilot operation from the commissioning up to the decommissioning; 3. history of the Brennilis NPP decommissioning; 4. the types of radioactive wastes generated by the Brennilis NPP decommissioning; 5. the Brennilis NPP - a yard management as a function of the wastes. The document contains also seven appendices addressing the following subjects: 1. the share of decommissioning assigned to EDF and the decommissioning steps; 2. the EDF installations in course of decommissioning; 3. the CEA decommissioned installations or in course of decommissioning; 4. regulations; 5. costs; 6. waste management - principles; 7. data on the decommissioning yard

Approaches to the mathematical description of NPP operational safety management and oversight

International Nuclear Information System (INIS)

Bilej, D.V.; Berzhanskij, S.V.

2014-01-01

The paper presents analysis of features related to NPP operational safety management and oversight. According to analysis results, approaches are proposed to perform mathematical description of specific processes and to develop a scale for management to the current safety level as regards NPP power generation. Proposed approaches are making experimental equations and process approach of ISO-9001 quality system

Remote technology in RBMK-1000 spent fuel management at NPP site

International Nuclear Information System (INIS)

Makarchuk, T.F.; Kozlov, Y.V.; Tikhonov, N.S.; Tokarenko, A.I.; Spichev, V.V.; Kaljazin, N.N.

1999-01-01

The report describes the remote technologies employed in the nuclear power plant with RBMK-1000 type. Spent fuel transfer and handling operations at reactor (AR) and away from reactor (AFR) on reactor site (RS) facilities are illustrated by the example of the Leningradskaya NPP and are typical for all NPPs with RBMK-1000. The current approach to spent fuel management at NPP sites is also presented. (author)

Decommissioning of NPP A-1

International Nuclear Information System (INIS)

Anon

2009-01-01

In this presentation the Operation history of A1 NPP, Project 'Decommissioning of A1 NPP' - I stage, Project 'Decommissioning of A1 NPP ' - II stage and Next stages of Project 'Decommissioning of A1 NPP ' are discussed.

Cernavoda NPP Unit 1 - a plant of several generations

International Nuclear Information System (INIS)

Rotaru, I.; Metes, M.; Anghelescu, M.S.

2001-01-01

The paper reflects some key aspects related to the shift of generations during the project's development, including the present stage. Further, the place of Cernavoda NPP Unit 1 in the Romanian power sector and among other nuclear stations in the world is presented. The operational performances achieved 'in service' up to the end of 1999, with reference to the performance indicators for electrical energy production, nuclear safety, radiation protection, radioactive wastes and nuclear fuel are illustrated. For all of these items, comparisons are performed with similar indicators reported by other worldwide nuclear power plants, in order to assess our results. Finally, some comments about Cernavoda NPP Unit 2 project status and need to completion and commissioning it are included. (authors)

Regulatory review of NPP Krsko Periodic Safety Review

International Nuclear Information System (INIS)

Lovincic, D.; Muehleisen, A.; Persic, A.

2004-01-01

At the request of the Slovenian Nuclear Safety Administration (SNSA), Krsko NPP prepared a Periodic Safety Review (PSR) program in January 2001. This is the first PSR of NPP Krsko, the only nuclear power plant in Slovenia. The program was reviewed by the IAEA mission in May 2001 and approved by SNSA in July 2001. The program is made in accordance with the IAEA Safety Guide 'Periodic Safety Review of Operational Nuclear Power Plants' No. 50-SG-012 and with European practice. It contains a systematic review of operation of the NPP Krsko, including the review of the changes as a result of the modernization of the facility. The main tasks of PSR are review of plant status for each safety factor, development of aging and life cycle management program, review of seismic design and PSHA analysis and update of regulatory compliance program. The prioritization process of findings and action plan are also important tasks of PSR. The basic safety factors of the PSR review are: Operational Experience, Safety Assessment and Analyses, Equipment Qualification and Ageing Management, Safety Culture, Emergency Planing, Environmental Impact and Radioactive Waste, Compliance with license requirements and Prioritization. It had been agreed that SNSA will have reviewed all PSR reports generated during the PSR process. At the end of 2003 the PSR Summary Report with selected recommendations for action plan was completed and delivered to SNSA for review. The paper presents regulatory review of NPP Krsko PSR with emphasis on the evaluation of the PSR issues ranking process. (author)

ASSET experience at Paks NPP

International Nuclear Information System (INIS)

Szabo, I.

1997-01-01

At Paks NPP special attention has been paid to international reviews since the very beginning of operation. Several international teams visited Paks in order to provide independent assessment of plant performance, conditions and safety. Paks NPP Management has the further intention to invite international reviews regularly (yearly) in the future as well. The experience gained during these reviews helped to establish a unified process of preparation for the reviews, performing them and handling the results. The Safety Department is in charge of organization of the whole process. All these reviews have their specific features and they are focused on different areas. The ASSET reviews provides the assessment of plant performance and safety through the analysis of safety significant events, which have occurred at the nuclear power plant. This approach makes this review specific and different from the other ones

ASSET experience at Paks NPP

Energy Technology Data Exchange (ETDEWEB)

Szabo, I [Operational Safety Dept., Paks NPP, Paks (Hungary)

1997-10-01

At Paks NPP special attention has been paid to international reviews since the very beginning of operation. Several international teams visited Paks in order to provide independent assessment of plant performance, conditions and safety. Paks NPP Management has the further intention to invite international reviews regularly (yearly) in the future as well. The experience gained during these reviews helped to establish a unified process of preparation for the reviews, performing them and handling the results. The Safety Department is in charge of organization of the whole process. All these reviews have their specific features and they are focused on different areas. The ASSET reviews provides the assessment of plant performance and safety through the analysis of safety significant events, which have occurred at the nuclear power plant. This approach makes this review specific and different from the other ones.

Nuclear and thermal power plant power ramping capability

International Nuclear Information System (INIS)

Golovach, E.A.

1983-01-01

The possibilities of step power increase by NPP and TPP units under emergency conditions of power grids operation are considered. The data analysis has shown that power units ramping capability with WWER-440, WWER-1000 and RBMK-1000 reactors is higher than that of 300 MW power units on fossil fuel, at the initial time interval (0-30 s). These NPP power units satisfy as to ramping capability the energy system requirements. Higher NPP power units ramping capability is explained by the fact that relative pressure before turbine valves is decreased less than in straight-through boilers while the steam volumes time constant of steam separator-superheaters is less than that of intermediate superheatings. Higher power unit ramping capability with WWER-440 and RBMK-1000 reactors as compared with the WWER-1000 reactor is pointed out as well as the increase of WWER-1000 power unit capability using high-speed turbines

Wireless Power System Design for Mobile Robots used in Nuclear Power Plants

International Nuclear Information System (INIS)

Choi, S. Y.; Yoo, S. J.; Lee, Kun J.; Rim, C. T.

2012-01-01

The robots used in nuclear power plants (NPP) have received much attention in recent years due to the Fukushima nuclear accident, which is considered as one of the worst nuclear disasters. In general, the NPP robots can play important roles in fuel exchange, repair work, radiation monitoring, rescue, and scouting out NPP. Under these conditions, human access to NPP during normal and emergency operations is strictly restricted due to the risks of high level radiation and contamination. However, in practice, robots have not been widely used in NPP because of the following limitations. First, the NPP robots cannot be of multi-purpose use because of their mission complexity and uniqueness. Second, the demand of the NPP robots is low due to the limited number of NPP over the world. Third, the NPP robots developed so far have no enough confidence in spite of the improvement of robot technology. Lastly, the NPP robots cannot carry on their mission continuously due to the limited energy capacity of the battery: mobile robots should stop working every two hours to recharge their batteries and spend least twenty minutes. As the solutions for this 'energy hungry' problem, high capacity batteries, quick battery chargers, power cables, and internal combustion engines were proposed; however, they still have the problems such as limited mission time and range, frequent recharging, or exhausting emission and noise. In this paper, the wireless power transfer systems (WPTS) for NPP robots are proposed. This technology can let NPP robots free from mission time and range limits, and exhausting emission. The requirements for the NPP robots are newly proposed, and two types of WPTS, roaming and railway, are suggested in this paper

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

International Nuclear Information System (INIS)

Lipar, M.

1998-01-01

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)

The NPP Isar comprehensive Aging Management Program

International Nuclear Information System (INIS)

Zander, Andre; Ertl, Stefan

2012-01-01

The majority of System, Structure and Components (SSC) in a nuclear power plants are designed to experience a service life, which is far above the intended design life. In most cases, only a small percentage of SSCs are subject to significant aging effects, which may affect the integrity or the function of the component. The process of aging management (AM) has the objective to monitor and control degradation effects which may compromise safety functions of the plant. And furthermore, to ensure, that testing and maintenance programs sufficiently provide preventive measures to control degradation effects. Safety-related aspects and the targeted high availability of the power plant as well as the requirements stipulated by German regulatory authorities prompted the operator of NPP ISAR to introduce an aging surveillance program. The NPP Isar as well as the German NPPs has to be following in the scope of aging management the KTA 1403 guideline. The NPP Isar surveillance program based on the KTA 1403 guideline covers the following aspects: - Scoping and screening of safety relevant Systems, Structures and Components (SSC); - Identification of possible degradation mechanisms for safety relevant SSC; - Ensure, that testing and maintenance programs sufficiently provide preventive measures to control degradation effects; - Transferability check of industry experience (internal and external events); - Annual preparation of an AM status report. (author)

Structure study and design of Qinshan NPP PCCV

International Nuclear Information System (INIS)

Xia Zufeng; Xu Yongzhi; Wang Tianzhen; Wu Jibiao

1993-02-01

The design process of Qinshan NPP (nuclear power plant) PCCV (prestressed concrete containment vessel) is summarized. The tendon test, structural description, design bases and analysis method are introduced. The arrangement for preventing concrete from cracking and design features of post-tensioning system and steel liner are presented. The results of model test and non-linear analysis for ultimate load in Qinshan NPP PCCV are also given. Through the integrity test of PCCV, it shows that the test values are in agreement with predicted values, the structure is excellent and the performance of leak tightness conforms to the safety requirements

NPP life management program - status report for Slovenia

International Nuclear Information System (INIS)

Glumac, B.

1998-01-01

Status report on NPP life management in Slovenia is dealing with possible life extension of NPP Krsko which comprises: replacement of steam generator; power upgrade; exchange of plant process computer; snubber reduction program, additional forced ventilation cooling system. Fuel improvements are predicted as well as the problems of storing spent fuel, low and intermediate waste if the plant is to operate through 2023 and possibly beyond that date. Related research activities are concerned with radiation damage, modelling of reactor core parameters by Monte Carlo calculations and PSA and severe accidents studies. Most of the activities are performed in cooperation with foreign organisations

The post-accidents exploitation of Chernobyl NPP

International Nuclear Information System (INIS)

Nosovskij, A.V.

1996-01-01

Problems facing the Chernobyl NPP personnel since its commissioning and during its post-accident operation are considered. The accomplished measures on improving the power units safety, normalization of the radiation situation as well as the impact of psychological factor at the safety culture level are discussed

Experience with high percent step load decrease from full power in NPP Krsko

International Nuclear Information System (INIS)

Vukovic, V.

2000-01-01

The control system of NPP Kriko, is designed to automatically control the reactor in the power range between 15 and 100 percent of rated power for the following designed transients; - 10 percent step change in load; 5 percent per minute loading and unloading; step full load decrease with the aid of automatically initiated and controlled steam dump. Because station operation below 15 percent of rated power is designed for a period of time during startup or standby conditions, automatic control below 15 percent is not provided. The steam dump accomplishes the following functional tasks: it permits the nuclear plants to accept a sudden 95 percent loss of load without incurring reactor trip; it removes stored energy and residual heat following a reactor trip and brings the plant to equilibrium no-load conditions without actuation of the steam generator safety valves; it permits control of the steam generator pressure at no-load conditions and permits a manually controlled cooldown of the plant. The first two functional tasks are controlled by Tavg. The third is controlled by steam pressure. Interlocks minimise any possibility of an inadvertent actuation of steam dump system. This paper discusses relationships between designed (described) characteristics of plant and the data which are obtained during startup and/or first ten years of operation. (author)

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

International Nuclear Information System (INIS)

Guilin, L.; Defu, L.; Huajun, L.; Fengqing, W.; Tao, Z.

2012-01-01

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)

ZZ PWR-AXBUPRO-GKN, Measured Axial Burnup Profiles, NPP Neckarewstheim

International Nuclear Information System (INIS)

Neuber, Jens-Christian; Lamprecht, Thomas

1999-01-01

Description or function: PWR-AXBUPRO-GKN12 contains Axial Burnup Shapes released by Siemens AG Power Generation Group. It contains data sets relative to following NPP and initial enrichment: - NPP Neckarwestheim 1, Fuel assemblies with an initial enrichment of 3.5 wt.-% 235-U; - NPP Neckarwestheim 2, Fuel assemblies with an initial enrichment of 3.5 wt.-% 235-U; - NPP Neckarwestheim 2, Fuel assemblies with an initial enrichment of 3.8 wt.-% 235-U; - NPP Neckarwestheim 2, Fuel assemblies with an initial enrichment of 4.0 wt.-% 235-U. In each of these files the axial shapes are listed one after the other. Each shape is characterised by: - the number of the cycle; - the number of the fuel assembly. - axial burnup shape characteristics: - height (in centimeter) of the nodes with respect to the active length of the fuel assemblies normalized to the cold, unirradiated state. - the nodal burnup (in MWd/kg U). - fuel assembly design data as well as core geometry and operating data pertinent to depletion calculations: NPP Neckarwestheim 1 (GKN1) - (square pitch lattice 15X15 - thermal Power 2497 MW)thermal Power 2497 MW); More than 700 EOC axial shapes from cycle 18 up. From cycle 18 to cycle 20 a change from an Out-In-Loading to an In-Out-Loading has taken place. Fuel assemblies up to number 1093 have spacer grids made of Inconel, whereas all the fuel assemblies from number 1094 up have spacer grids made of Zircaloy. Discharge burnups range from: 9.7 to 52.8 MWd/kg. NPP Neckarwestheim 2 (GKN2) - (square pitch lattice 18X18 - thermal Power 3850 MW) more than 500 EOC axial shapes from cycle 5 up: - More than 170 shapes for an initial fuel enrichment of 3.5 wt.-% 235-U, discharge burnup ranges from 16.3 to 44.4 MWd/kg; - more than 170 shapes for an initial fuel enrichment of 3.8 wt.-% 235-U, discharge burnup ranges from 14.0 to 52.8 MWd/kg; - more than 180 shapes for an initial fuel enrichment of 4.0 wt.-% 235-U. discharge burnup ranges from 15.5 to 48.9 MWd/kg. PWR AXBUPRO

Mochovce NPP simulator

International Nuclear Information System (INIS)

Ziakova, M.

1998-01-01

Mochovce NPP simulator basic features and detailed description of its characteristics are presented with its performance, certification and application for training of NPP operators as well as the training scenario

Wireless Power System Design for Mobile Robots used in Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Choi, S. Y.; Yoo, S. J.; Lee, Kun J.; Rim, C. T. [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2012-05-15

The robots used in nuclear power plants (NPP) have received much attention in recent years due to the Fukushima nuclear accident, which is considered as one of the worst nuclear disasters. In general, the NPP robots can play important roles in fuel exchange, repair work, radiation monitoring, rescue, and scouting out NPP. Under these conditions, human access to NPP during normal and emergency operations is strictly restricted due to the risks of high level radiation and contamination. However, in practice, robots have not been widely used in NPP because of the following limitations. First, the NPP robots cannot be of multi-purpose use because of their mission complexity and uniqueness. Second, the demand of the NPP robots is low due to the limited number of NPP over the world. Third, the NPP robots developed so far have no enough confidence in spite of the improvement of robot technology. Lastly, the NPP robots cannot carry on their mission continuously due to the limited energy capacity of the battery: mobile robots should stop working every two hours to recharge their batteries and spend least twenty minutes. As the solutions for this 'energy hungry' problem, high capacity batteries, quick battery chargers, power cables, and internal combustion engines were proposed; however, they still have the problems such as limited mission time and range, frequent recharging, or exhausting emission and noise. In this paper, the wireless power transfer systems (WPTS) for NPP robots are proposed. This technology can let NPP robots free from mission time and range limits, and exhausting emission. The requirements for the NPP robots are newly proposed, and two types of WPTS, roaming and railway, are suggested in this paper

The landscape basis of the complex monitoring of 30-km zone of NPP

International Nuclear Information System (INIS)

Malisheva, L.L.; Romanchuk, S.P.; Schur, U.V.; Rybalko, S.I.; Proskura, N.I.; Lury, D.I.

1992-01-01

This publication reviews works on the problem of creation the landscape basis of complex monitoring in 30 km zone of NPP(nuclear power plants). The objectives, subject and designation of monitoring system are considered. The monitoring network and organization of systematical observations are justified. The structure of radiation monitoring in NPP 30 km zone is considered in details. (author)

NPP Krsko full scope simulator verification and qualification

International Nuclear Information System (INIS)

Krajnc, B.; Glaser, B.; Novsak, M.; Spiler, J.

1998-01-01

NPP Krsko (NEK) will, as a part of the Modernization plan, obtain also Krsko Full Scope Simulator (KFSS). Contract has been awarded to CAE Electronics for the design, construction and integration. KFSS will support in real time, the training for the complete range of operation, which can be performed from the main control room and some selected plant areas (remote shutdown panels, etc). Based on the lessons learned on development of NPP Krsko Basic Principle Simulator we decided for active approach. That means that NPP Krsko personnel will be heavily involved into all phases of KFSS development and testing. Since NPP Krsko is going to replace the existing steam generators, raise the nominal power and perform necessary modifications to support the power uprate, it was decided that the development of the KFSS will be conducted in two steps: 1. Development of the models as well as all the hardware interface in the MCR for the existing plant Cycle 15 and then, 2. Models and hardware will be modified, added or replaced as needed to take into account the steam generator replacement and plant uprate projects. In spite of the fact that the simulator will be used for the training of the plant operators for the uprated conditions and with new steam generators, the upper described approach was selected since we want to be sure that the models will at the beginning adequately simulate the existing plant. For the existing conditions we have available reference data for different plant conditions, as well as data for different plant transients. By verifying that simulator will be able adequately simulate the existing conditions the level of confidence for the uprated simulator will be much higher. This is of special importance since it will support initial training for modernized plant conditions. In this paper the plan for verification and qualification of KFSS as well as the amount of the work needed on NPP Krsko side to develop the test acceptance criteria will be presented.(author)

Use of operator training and simulating complexes for development of NPP APCS

International Nuclear Information System (INIS)

Malkin, S.D.; Rakitin, I.D.; Sivokon', V.P.

2002-01-01

The evolution of NPP educational facilities - from systems of training of personnel to power simulating systems for the development of Automatic Process Control System (APCS) and safety analysis is followed. High efficiency of simulating systems application for the development of NPP APCS including optimization of man-machine system interface was shown by experiments of USA, France, Japan, United Kingdom, conforming examples were given [ru

Improved Nuclear Power Plant maintenance. Application to Cofrentes NPP

International Nuclear Information System (INIS)

Serradell, V.

2002-01-01

The Industrial Safety and Environment Group (MEDASEGI) of the Valencia Polytechnic University (UPV) develops its activities in the fields of environmental radioactivity metrology and risk analysis and management aimed at improving industrial safety. The different lines of research developed by this group include collaboration with Cofrentes NPP. This collaboration began in 1993 and has primarily focused on issues related to improved maintenance and currently on life management. (Author)

Safety analysis of Ignalina NPP during shutdown conditions

International Nuclear Information System (INIS)

Kaliatka, A.; Uspuras, E.

2000-01-01

The accident analysis for the Ignalina NPP with RBMK-1500 reactors at normal operating conditions and at minimum controlled power level (during startup of the reactor) has been performed in the frame of the project I n-Depth Safety Assessment of the Ignalina NPP , which was completed in 1996. However, the plant conditions during the reactor shutdown differ from conditions during reactor operation at full power (equipment status in protection systems, set points for actuation of safety and protection systems, etc.). Results of RELAP5 simulation of two worst initiating events during reactor shutdown - Pressure Header rupture in case of steam reactor cooldown as well as Pressure Header rupture in case of water reactor cooldown are discussed in the paper. Results of analysis shown that reactor are reliably cooled in both cases. Further analysis for all range of initial events during reactor shutdown and at shutdown conditions is recommended. (author)

Qinshan CANDU NPP outage performance improvement through benchmarking

International Nuclear Information System (INIS)

Jiang Fuming

2005-01-01

With the increasingly fierce competition in the deregulated Energy Market, the optimization of outage duration has become one of the focal points for the Nuclear Power Plant owners around the world. People are seeking various ways to shorten the outage duration of NPP. Great efforts have been made in the Light Water Reactor (LWR) family with the concept of benchmarking and evaluation, which great reduced the outage duration and improved outage performance. The average capacity factor of LWRs has been greatly improved over the last three decades, which now is close to 90%. CANDU (Pressurized Heavy Water Reactor) stations, with its unique feature of on power refueling, of nuclear fuel remaining in the reactor all through the planned outage, have given raise to more stringent safety requirements during planned outage. In addition, the above feature gives more variations to the critical path of planned outage in different station. In order to benchmarking again the best practices in the CANDU stations, Third Qinshan Nuclear Power Company (TQNPC) have initiated the benchmarking program among the CANDU stations aiming to standardize the outage maintenance windows and optimize the outage duration. The initial benchmarking has resulted the optimization of outage duration in Qinshan CANDU NPP and the formulation of its first long-term outage plan. This paper describes the benchmarking works that have been proven to be useful for optimizing outage duration in Qinshan CANDU NPP, and the vision of further optimize the duration with joint effort from the CANDU community. (authors)

Optimization of radiation protection at Bohunice NPP

International Nuclear Information System (INIS)

Dobis, L.; Svitek, J.

2003-01-01

Bohunice Nuclear Power Plant is situated in south - western part of Slovakia about 50 km away from Bratislava. There are four PWR reactors 440 MW e each - two units with reactors WWER - 230 (V1 NPP) and two units with WWER - 213 (V2 NPP). requirements for the optimization process are given in the mentioned Code No.12 of Ministry of Health. Code 12 stipulates the technical and organizational requirements for proving the Rational Achievable Level (RAL) of radiation protection. This level can be proved by means of the comparison of the dose distribution to the costs of protection. An example of two figures of dose constraints is: collective dose 20 man mSv for the specific task; individual exposure 1 mSv per day. The values of the financial equivalents of personal exposure - so called the alpha coefficients - are used for the calculation of the benefit of proposed measures. Impact of legislative changes into Bohunice NPP and optimization process are presented. Apparently the new law and the associate code created a base of transparent and understandable policy of radiation protection and optimization in Slovak Republic. The radiation protection legislative was implemented into the praxis and persons became familiar with it. Defining clear and unambiguous terms facilitated the communication between users and the regulatory body - State Health Institute. Optimization was generally accepted by the workers and managers and began to be a part of safety culture of operation at nuclear power plants. (authors)

The evolution of the fuel cycle in the Dukovany NPP

Energy Technology Data Exchange (ETDEWEB)

Bajgl, J [Jaderna Elektrarna, Dukovany (Czech Republic)

1994-12-31

The ten-year operational experience of four WWER-440 units in Dukovany NPP with a total number of 35 cycles is outlined. The strategy of fuel reloading has been changed from out-in schemes to low-leakage patterns. The linear pin power limitation will be introduced. The main physical limits and conditions for the NPP operation are listed. The main goal is to go to a full 4-year fuel cycle in which the burnup will be about 40 Mwd/kg U. 6 tabs.

Sitting Safety Aspects of Second Romanian NPP

International Nuclear Information System (INIS)

Mauna, T.

2010-01-01

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

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

International Nuclear Information System (INIS)

1996-01-01

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

NPP Temelin instrumentation and control system upgrade and verification

International Nuclear Information System (INIS)

Ubra, O.; Petrlik, J.

1998-01-01

Two units of Ver 1000 type of the Czech nuclear power plant Temelin, which are under construction are being upgraded with the latest instrumentation and control system delivered by WEC. To confirm that the functional design of the new Reactor Control and Limitation System, Turbine Control System and Plant Control System are in compliance with the Czech customer requirements and that these requirements are compatible with NPP Temelin upgraded technology, the verification of the control systems has been performed. The method of transient analysis has been applied. Some details of the NPP Temelin Reactor Control and Limitation System verification are presented.(author)

Nuclear power in the South Korea

International Nuclear Information System (INIS)

Molodtsov, S.D.

1988-01-01

Data on the state of nuclear power in the South Korea are presented. In the end of 1987 7 power units with 5380 MW total power were in operation in the South Korea. The share of NPP capacity was equal to 26% of the total electric power plant capacity of the country. The cost of NPP power production was equal to 2.2 cent (kw.h). The total established NPP capacity should achieve 7.3 GW by 1990, and exceed 9 GW by 2000

A comparison of the Kozloduy NPP and Temelin NPP I and C projects

International Nuclear Information System (INIS)

Cook, B.M.

2004-01-01

Because Kozloduy NPP and Temelin NPP are both VVER 1000 plants of roughly the same vintage, they are very similar in design. However, from the viewpoint of their I and C modernization projects, there are significant differences between these plants. Some of these differences stem from the evolution of I and C technology over the relatively short period between the two projects. Other differences arise from the fact that the Kozloduy project is a phased upgrade of the I and C systems in an operating plant while the Temelin project was a 'one time' installation of the entire plant I and C system. This paper discusses these differences as well as trends in the nuclear I and C field that will shape the industry in the future. In addition to technology evolution, the comparative advantages or problems in phased upgrade versus 'one time' installations are discussed. Conclusions drawn provide insight for the planning of future I and C upgrades in VVERs and other types of nuclear power plants. (author)

Enhancing NPP Safety Through an Effective Dependability Management

Energy Technology Data Exchange (ETDEWEB)

Vieru, G., E-mail: g_vieru@yahoo.com [AREN, Bucharest (Romania)

2014-10-15

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)

Improvement of automatic control systems of high-power turbines of PAO tubroatom for nuclear power plants

Science.gov (United States)

Shvetsov, V. L.; Babaev, I. N.

2017-09-01

The main technical solutions applied by PAO Turboatom used as the compensatory measures at the increase of the period of nonstop operation of nuclear power plants' (NPP) turbines with VVER-1000 type reactors up to 18 months are (1) replacing the standard hydraulic speed controller with an electronic one, (2) introduction of overclocking protection, (3) modernization of units of stop-control valves of high pressures, (4) installation of locking dampers on the receiver tubes of turbines of the first and second modification, and (5) improving the quality of repairs by reviewing the requirements for their implementation. The introduction of complex diagnostics of a control system on the basis of automatic treatment of results of registration of working parameters of the turbine is allocated as a separate prospective direction. Using an electronic controller of speed makes it possible to simplify the procedure of its inclusion in work at the failure of an electro-hydraulic system of control and vice versa. The regimes of maintaining the turbine rotor speed, steam pressure on the outlet of turbine, and the positions of main servomotors were introduced into the functions of the electronic controller. An electronic controller of speed includes its own electro-hydraulic transducer, turbine rotor speed sensor, and sensors of the position of main servomotors. Into the functions of electro- hydraulic control system and electronic speed controller, the function of overclocking protection, which determines the formation of commands for stopping the turbine at the exceeding of both the defined level of rotation speed and the defined combination of achieved rotation speed and angular acceleration of rotor, was introduced. To simplify the correction of forces acting on the control valve cups, the design of the cups was changed, and it has the profiled inserts. The solutions proposed were implemented on K-1100-60/1500-2M turbines of Rostov NPP. From the composition of control system

LTO License Application Project NPP Borssele

International Nuclear Information System (INIS)

Jong, A.E. de; Blom, F.J.; Leilich, J.

2012-01-01

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)

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.

Practical experience with the leaky-fuel monitoring at Bohunice NPP

International Nuclear Information System (INIS)

Kacmar, M.; Cizek, J.

2001-01-01

The first part of this paper describes practical experience with the fuel monitoring in operating reactors from point of view possible leakages. Summarized in the paper are numbers leaky fuel assemblies both for NPP and for particular units. Some failure causes are discussed for operational conditions of Bohunice NPP. In the second part of paper critical power ramps on hot fuel rod of leaky fuel assemblies are analysed to eliminate failures from PCI. The main aim of the paper is the need to understand the mechanism and causes of failures (Authors)

International Collaboration in the Development of NPP Software

International Nuclear Information System (INIS)

Jiang, S.; Liu, L.; Yu, H.

2015-01-01

In this paper, we first review the progress and current status of international collaboration and technical exchange in the development of nuclear power plant (NPP) software by The State Nuclear Power Software Development Center (SNPSDC) in China. Then we discuss the importance of the international collaboration and exchange in the trend of globalisation of NPP technology. We also identify the role and contribution of professional women in this process. SNPSDC, the first professional software development centre for NPP in China, has been developing COSINE — a self-reliance NPP design and analysis software product with China brand—since 2010. Through participating in OECD/NEA’s joint projects, such as ROSA-2 Project, PKL–3 Project, HYMERES Project and ATLAS Project, SNPSDC shared data with other countries involved with respect to particular areas, such as high quality reactor thermal hydraulics test data. SNPSDC’s engineers have also been actively participating in international technical and research exchange for presenting their innovative work to the community while learning from peers. Our record shows that over 30 papers have been presented in international conferences with respect to nuclear reactor thermal hydraulics, safety analysis, reactor physics and software engineering within the past 4 years. The above international collaboration and technical exchange helped SNPSDC’s engineers to keep up with the state-of-art technology in this field. The large amount of valuable experimental data transferred to SNPSDC ensured the functionality, usability and reliability of software while greatly reduced the cost and shortened the cycle of development. Female engineers and other employees of SNPSDC either drove or got actively involved in a lot of aspects of the above collaboration and exchange, such as technical communication, business negotiation and overseas affairs management. These professional women played an irreplaceable role in this project by

Tritium liquid effluents from the Krsko NPP

International Nuclear Information System (INIS)

Savli, S.; Krizman, M.; Nemec, T.; Cindro, M.; Stritar, A.; Vokal Nemec, B.; Janzekovic, H.

2007-01-01

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)

Russian normative approach to the question of management of NPP life time

International Nuclear Information System (INIS)

Karpunin, N.I.

2002-01-01

Full text: In Russia, the designated service life of a nuclear power plant (NPP) is 30 years. During the period 2001-2010, 15 Russian NPP units will reach the end of their service life. The 'Basic Provisions of NPP Safety Assurance', OPB-88/97, Item 5.1.14, provide for a possible extension of NPP operation beyond the designated service life. For such an extension, the NPP operating organization must apply for a license renewal to Gosatomnadzor, which needs to specify the relevant requirements. GAN is developing regulatory documents to provide a basis for NPP license renewal/extension of NPP operation, which would benefit from international experience. In accordance with 'The program of Atomic Energy Development in the Russian Federation for 1998-2005 and up to 2010' adopted by Decree No. 815 of the Government of the Russian Federation on 21 July 1998, priority is placed on the preparation of NPPs for extension of service life and on ensuring safety in the extended operating period. The length of the extension beyond the designated service life is to be determined on the basis of a range of technical and economic considerations, including: The ability to ensure and maintain operational safety; Sufficient residual service life of the unit's non-repairable components; The availability of temporary storage facilities for the additional spent nuclear fuel and radioactive waste, or the possibility of its transport off-site; The ability to ensure safe handling of the radioactive waste generated during the extension period; To extend the lifetime of an NPP unit, the plant Operator is required to perform the following tasks: Carry out a comprehensive survey of the NPP unit; Draw up a programme of preparation for lifetime extension; Prepare the NPP unit for operation in the extended period; Carry out the necessary tests. There are also some normative documents, which regulate management of NPP life time. (author)

Problem of nuclear power plant reliability

International Nuclear Information System (INIS)

Popyrin, L.S.; Nefedov, Yu.V.

1989-01-01

The problem of substantiation of rational and methods of ensurance of NPP reliability at the stage of its designing has been studied. It is shown that the optimal level of NPP reliability is determined by coordinating solution of the proiblems for optimization of reliability of power industry, heat and power supply and nuclear power generation systems comprising NPP, and problems of reliability optimization of NPP proper, as a complex engineering system. The conclusion is made that the greatest attention should be paid to the development of mathematical models of reliability, taking into account different methods of equipment redundancy, as well as dependence of failures on barious factors, improvement of NPP reliability indices, development of data base, working out of the complec of consistent standards of reliability. 230 refs.; 2 figs.; 1 tab

Application of the combined cycle LWR-gas turbine to PWR for NPP life extension, safety upgrade and improving economy

International Nuclear Information System (INIS)

Kuznetsov, Yu.N.; Gabaraev, B.A.

2002-01-01

Full text: The unconventional technology to extend the lifetime for the NPPs now in operation and make a construction of new NPPs cheaper - erection of steam-gas toppings to the nuclear power units - is considered in the paper. Application of the steam-gas toppings permits through reducing power of ageing reactors to extend lifetime of nuclear power unit, enhance its safety and at the same time to keep full load operation of NPP turbine and other balance-of-plant equipment. Proposed technology is examined for Russian VVER-440 reactor as an example and, also, as a pilot project, for Russian boiling VK-50 reactor now in operation Application of the steam-gas topping permits: extend the service life of ageing VVER-440 reactor by 10...15 years; use the turbine and other NPP balance-of-plant equipment at full power; increase the efficiency of combined cycle up to 48% and more; enhance the safety of NPP operation; utilize NPP balance-of-plant equipment after reactor decommissioning; perform the cost-effective operation in maneuvering modes; increase capacity factor of the plant. The construction of pilot project on the basis of the VK-50 reactor will allow not only to demonstrate new technology but also to attain appreciable economic effect including that obtained due to using the available reserves of the NPP turbine. (author)

Comparison of the effects of nuclear power plants and thermal power plants on the environment

International Nuclear Information System (INIS)

Sivintsev, Yu.V.; Teverovskij, E.N.

1976-01-01

A comparison of ecological effects produced by a thermal power station (TPS) and a nuclear power plant (NPP) of similar electric capacity has been made. The ecological advantages of NPP over TPS are revealed in analysis of aerosol and gas blow-out and its danger for the environment. From the above data it follows that TPS as compared with NPP of similar electric capacity produces a 100 and 1000 fold higher air pollution effect than the latter. The dose of TPS radiation effect is minimum 500 times higher than that of NPP at normal operation. Large-scale construction of NPP is one of the most perfect means of atmosphere protection against harmful industrial discharges

Introduction of the SAT based training programs at Paks NPP

International Nuclear Information System (INIS)

Kiss, I.

1998-01-01

An introduction of the SAT based training programs at Paks nuclear power plant is described in detail, including framework of project operation; project implementation; process of SAT applied at Paks NPP and the needs of its introduction

Screening of external hazards for NPP with bank type reactor. Modeling of safety related systems and equipment for RBMK. Probabilistic assessment of NPP safety on aircraft impact. Progress report

International Nuclear Information System (INIS)

Kostarev, V.

1999-01-01

This progress report was produced within the frame of IAEA research project on screening the hazards for NPP with bank type reactor. It covers the following tasks; development of the model for the primary loop system of RBMK; developing the models for safety related equipment of RBMK; developing of models for safety related models of EGP-6 type reactor (Bilibinskaya Nuclear Co-generated heat and Power Plant); and probabilistic assessment of NPP safety on aircraft impact

Development of Highly Survivable Power and Communication System for NPP Instruments under Severe Accident

Energy Technology Data Exchange (ETDEWEB)

Yoo, Seung J.; Gu, Beom W.; Nguyen, Duy T.; Choi, Bo H.; Rim, Chun T. [KAIST, Daejeon (Korea, Republic of); Lee, So I. [KHNP CRI, Daejeon (Korea, Republic of)

2014-10-15

According to the detail report from the Fukushima nuclear accident, the failure of conventional instruments is mainly due to the following reasons. 1) Insufficient backup battery capacity after the station black out (SBO) 2) The malfunction or damage of instruments due to the extremely harsh ambient condition after the severe accident 3) The cut-off of power and communication cable due to the physical shocks of hydrogen explosion after the severe accident Since the current equipment qualification (EQ) for the NPP instruments is based on the design basis accident such as loss of coolant accident (LOCA), conventional instruments, which are examined under EQ condition, cannot guarantee their normal operation during the severe accident. A 7m-long-distance wireless power transfer and a radio frequency (RF) communication were introduced with conventional wired system to increase a redundancy. A heat isolation box and a harness are adopted to provide a protection from the expected physical shocks such as missiles and drastic increase of ambient temperature and pressure. A detail design principle of the highly survivable power and communication system, which has 4 sub-systems of a DCRS wireless power transfer, a Zigbee wireless communication, a GFRP harness, and a passive type router with a fly back regulator, has been presented in this paper. Each sub-system has been designed to have a robust operation characteristic regardless of the estimated physical shocks after the severe accident.

Development of Highly Survivable Power and Communication System for NPP Instruments under Severe Accident

International Nuclear Information System (INIS)

Yoo, Seung J.; Gu, Beom W.; Nguyen, Duy T.; Choi, Bo H.; Rim, Chun T.; Lee, So I.

2014-01-01

According to the detail report from the Fukushima nuclear accident, the failure of conventional instruments is mainly due to the following reasons. 1) Insufficient backup battery capacity after the station black out (SBO) 2) The malfunction or damage of instruments due to the extremely harsh ambient condition after the severe accident 3) The cut-off of power and communication cable due to the physical shocks of hydrogen explosion after the severe accident Since the current equipment qualification (EQ) for the NPP instruments is based on the design basis accident such as loss of coolant accident (LOCA), conventional instruments, which are examined under EQ condition, cannot guarantee their normal operation during the severe accident. A 7m-long-distance wireless power transfer and a radio frequency (RF) communication were introduced with conventional wired system to increase a redundancy. A heat isolation box and a harness are adopted to provide a protection from the expected physical shocks such as missiles and drastic increase of ambient temperature and pressure. A detail design principle of the highly survivable power and communication system, which has 4 sub-systems of a DCRS wireless power transfer, a Zigbee wireless communication, a GFRP harness, and a passive type router with a fly back regulator, has been presented in this paper. Each sub-system has been designed to have a robust operation characteristic regardless of the estimated physical shocks after the severe accident

Irradiation Embrittlement Monitoring Programs of RPV's in the Slovak Republic NPP's

International Nuclear Information System (INIS)

Kupca, Ludovik

2006-01-01

Four types of surveillance programs were (are) realized in Slovak NPP's: 'Standard Surveillance Specimen Program' (SSSP) was finished in Jaslovske Bohunice V-2 Nuclear Power Plant (NPP) Units 3 and 4, 'Extended Surveillance Specimen Program' (ESSP), was prepared for Jaslovske Bohunice NPP V-2 with aim to validate the SSSP results, For the Mochovce NPP Unit 1 and 2 was prepared completely new surveillance program 'Modern Surveillance Specimen Program' (MSSP), based on the philosophy that the results of MSSP must be available during all NPP service life, For the Bohunice V-1 NPP was finished 'New Surveillance Specimen Program' (NSSP) coordinated by IAEA, which gave arguments for prolongation of service life these units for minimum 20 years, New Advanced Surveillance Specimen Program (ASSP) for Bohunice V-2 NPP (units 3 and 4) and Mochovce NPP (units 1, 2) is approved now. ASSP is dealing with the irradiation embrittlement of heat affected zone (HAZ) and RPV's austenitic cladding, which were not evaluated till this time in surveillance programs. SSSP started in 1979 and was finished in 1990. ESSP program started in 1995 and will be finished in 2007, was prepared with aim of: increasing of neutron fluence measurement accuracy, substantial improvement the irradiation temperature measurement, fixed orientation of samples to the centre of the reactor core, minimum differences of neutron dose for all the Charpy-V notch and COD specimens, the dose rate effect evaluation. In the year 1996 was started the new surveillance specimen program for the Mochovce RPV's unit-1 and 2, based on the fundamental postulate - to provide the irradiation embrittlement monitoring till the end of units operation. The 'New Surveillance Specimen Program' (NSSP) prepared in the year 1999 for the Bohunice V-1 NPP was finished in the year 2004. Main goal of this program was to evaluate the weld material properties degradation due to the irradiation and recovery efficiency by annealing too. The

Radioactive source management in Daya Bay NPP

International Nuclear Information System (INIS)

Mao Chun Yang

2000-01-01

'Small sources causes big accidents' had occurred worldwide many times. Radioactive source management in Nuclear Power Plant in very important for its safety record. This paper introduces the way and experience of radioactive source management in Daya Bay NPP from aspects of clarifying the responsibilities, centralizing the management of high radioactivity sources, work process management and experience feedback etc. (author)

Implementation of the KASKAD computer code system for WWER-440 at Kozloduy NPP

International Nuclear Information System (INIS)

Antonov, A.; Georgieva, N.; Spasova, V.

2003-01-01

Since 2002 at Kozloduy NPP - EP1 the code package KASKAD is used for WWER-440 reactor core calculations. The main codes entering this package are: BIPR-7A: 3-D diffusion and core analysis code; PERMAK-A: 2-D fine mesh diffusion code. The burnup calculations were performed for all cycles of the Kozloduy NPP Unit 1, Unit 2, Unit 3 and Unit 4. For the last 4-5 cycles of the Units were calculated control rods worth, critical boron concentration at zero power, reactivity coefficients and linear power. These results were analysed and were compared with experimental data. Some results were given in this paper

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

International Nuclear Information System (INIS)

Suyudi Soeliarno

1995-01-01

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

Nuclear Fuel in Cofrentes NPP

International Nuclear Information System (INIS)

2002-01-01

Fuel is an essential in the nuclear power generating business because of its direct implications on safety, generating costs and the operating conditions and limitations of the facility. Fuel management in Cofrentes NPP has been targeted at optimized operation, enhanced reliability and the search for an in-depth knowledge of the design and licensing processes that will provide Iberdrola,as the responsible operator, with access to independent control of safety aspects related to fuel and free access to manufacturing markets. (Author)

Decommissioning Study of Oskarshamn NPP

International Nuclear Information System (INIS)

Larsson, Helena; Anunti, Aake; Edelborg, Mathias

2013-06-01

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

Decommissioning study of Forsmark NPP

International Nuclear Information System (INIS)

Anunti, Aake; Larsson, Helena; Edelborg, Mathias

2013-06-01

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

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.

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.

Survey of public participation potential regarding the Muria NPP program

International Nuclear Information System (INIS)

Yarianto-SBS; Sri Hariani Syarif; Heni Susiati; Imam Hamzah; Fepriadi

2003-01-01

Socio-culture aspect is a part of site feasibility evaluation of Nuclear Power Plant (NPP)program. Indonesia is under going democratization, therefore the paradigm of development has also been changed where the people have freedom or liberty and they can express their opinion independently. The people are significant factor that involving in the decision making of regional development.Even the socio-culture, such as social riot can reject the site. Therefore socio-culture aspect should be considered in the NPP site evaluation. The first step of the study,mapping of public participation potential should be conducted by field survey. The method used in there search is quantitative approach with field survey guided by questioner without any treatment of object sampled. Qualitative approach was also conducted by in-depth interview technique to collect more detailed information. Information were collected from general public without any stratification in the 10 km radius from NPP site. Sampling method used was full random sampling technique. The results of survey show that the most of the people have significant potential for participating in the NPP Program. Conducive atmosphere should be maintained by social setting, therefore the present good momentum will not be lost. (author)

Implementation of the II. Stage decommissioning of A1 NPP

International Nuclear Information System (INIS)

Ficher, T.

2015-01-01

Presentation is focused on the implementation of the II. stage decommissioning of A1 NPP. Introductory part focuses on brief characteristics of the power plant with a history of operation, basic technical parameters and actions that were made after operation. The next section describes the basic schedule for decommissioning, structure of management and implementation of the II. stage decommissioning of the A1 NPP and objectives of the individual stages. The last and largest part of the presentation is devoted to detailed description of the II. stage decommissioning of the A1 NPP, its individual tasks and verbal and visual description of the activities that were performed. Presented is decommissioning of the technology and construction of external objects NPP A1 including storage tanks for liquid RAW, next are presented activities carried out in the Main Production Unit - decommissioning of non-operating technologies in various places/rooms, management of waste arising from these activities, treatment of case of A1 long-term spent fuel storage and long-term spent fuel storage. The subsequent section is devoted to the management and handling of contaminated soil, concrete and construction waste, including management of VLLW. (authors)

Fuel consumption organization at the Kola NPP

International Nuclear Information System (INIS)

Matveev, A.A.; Ignatenko, E.I.; Volkov, A.P.; Trofimov, B.A.

1981-01-01

Problems of using NPPs in the power systems including hydroelectric power plants and NPPs are considered on the example of the Kola power system. The methods of the WWER-440 reactor fuel loading formation, reactor power forcing, optimization of volumes and time of the NPP main equipment planned maintenance are discussed. It is concluded that the optimal methods for the WWER-440 reactor fuel loading formation are the following: reactor make-up with the lesser number of fuel assemblies with maximum designed enrichment; for the case of decreased loading energy capacity displacement of make-up fuel with 2.4% enrichment by the fuel with 3.6% enrichment when preserving the designed number of make-up fuel assemblies [ru

Dynamic model for tritium build-up at NPP with RBMK type reactors and its enviromental beraviour

International Nuclear Information System (INIS)

Badyaev, V.V.; Egorov, Yu.A.; Ivanov, E.A.; Stegachev, G.F.; Tolstykh, V.D.

1982-01-01

A model of tritium production dynamics for a high power NPP with RBMK type reactors is proposed and investigated. The main ''skeleton'' model structure for forecasting tritium buildup at a NPP and its exchange with the environment has been singled out at a heuristic level. Decomposition and layout of the units have been performed by global functional relations of the investigated objects (NPP and environment). the model accounts for only oxidized tritium forms. Water exchange between the NPP subsystems and environment is the main mechanism for tritium migration. The model does not account for scheduled periodic maintenance work effects, presence of stagnant zones in the station circuits, fuel burn-up, etc. The parametric identification method applied in the model makes the model adaptable to particular situations and considered systems of the NPP and environment. Completing the model with necessary and sufficient experimental data one can pass to certain forecasting problems and to NPP control as a tritium source in the environment

NPP Krsko Lifetime Extension - Business Impact for Hrvatska Elektroprivreda

International Nuclear Information System (INIS)

Vrankic, K.; Krejci, M.; Lebegner, J.

2006-01-01

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

Equipment Reliability Process in Krsko NPP

International Nuclear Information System (INIS)

Gluhak, M.

2016-01-01

To ensure long-term safe and reliable plant operation, equipment operability and availability must also be ensured by setting a group of processes to be established within the nuclear power plant. Equipment reliability process represents the integration and coordination of important equipment reliability activities into one process, which enables equipment performance and condition monitoring, preventive maintenance activities development, implementation and optimization, continuous improvement of the processes and long term planning. The initiative for introducing systematic approach for equipment reliability assuring came from US nuclear industry guided by INPO (Institute of Nuclear Power Operations) and by participation of several US nuclear utilities. As a result of the initiative, first edition of INPO document AP-913, 'Equipment Reliability Process Description' was issued and it became a basic document for implementation of equipment reliability process for the whole nuclear industry. The scope of equipment reliability process in Krsko NPP consists of following programs: equipment criticality classification, preventive maintenance program, corrective action program, system health reports and long-term investment plan. By implementation, supervision and continuous improvement of those programs, guided by more than thirty years of operating experience, Krsko NPP will continue to be on a track of safe and reliable operation until the end of prolonged life time. (author).

The Acceptance Strategy for Nuclear Power Plant In Indonesia

Science.gov (United States)

Suhaemi, Tjipta; Syaukat, Achmad

2010-06-01

THE ACCEPTANCE STRATEGY FOR NUCLEAR POWER PLANT IN INDONESIA. Indonesia has planned to build nuclear power plants. Some feasibility studies have been conducted intensively. However, the processes of NPP introduction are still uncertain. National Energy Plan in Indonesia, which has been made by some governmental agencies, does not yet give positive impact to the government decision to construct the nuclear power plant (NPP). This paper discusses the process of NPP introduction in Indonesia, which has been colored with debate of stakeholder and has delayed decision for go-nuclear. The technology paradigm is used to promote NPP as an alternative of reliable energy resources. This paradigm should be complemented with international politic-economic point of view. The international politic-economic point of view shows that structural powers, consisting of security, production, finance, and knowledge structures, within which the NPP is introduced, have dynamic characteristics. The process of NPP introduction in Indonesia contains some infrastructure development (R&D, legislation, regulation, energy planning, site study, public acceptance efforts, etc), but they need a better coherent NPP implementation program and NPP Acceptance Program. Strategic patterns for NPP acceptance described in this paper are made by considering nuclear regulation development and the interest of basic domestic participation. The first NPP program in Indonesia having proven technology and basic domestic participation is and important milestone toward and optimal national energy-mix.

Contamination control by laundry monitor at NPP

International Nuclear Information System (INIS)

Singh, Vishwanath P.; Rana, P.K.; Lokeshwar Rao, S.; Managanvi, S.S.

2010-01-01

The operation of nuclear power reactor produces electricity as well as small quantity of radioactive waste as gaseous, liquid and solid. The waste contains radionuclides produced by fission and activation in reactor systems with wide spectrum of energy and half life. The long-lived nuclides Sr, Cs, Ba, Iodine and Co etc compared to short-lived are important in view of radiation protection. The radioactive contamination on the materials, human body or other places where it is undesirable is enormously harmful to workers at Nuclear Power Plant (NPP). The spread of radioactive from controlled areas is very complex problem for power reactor plant management

Methodology transfer for the preparation of NPP decommissioning for leading personnel of the Ignalina NPP and for the representatives of Lithuanian authorities

International Nuclear Information System (INIS)

Ackermann, L.; Baecker, A.

2004-01-01

At request of the Lithuanian government to receive support for the preparation of the decommissioning of Ignalina NPP, a bilateral project was financed by the German federal government to transfer experience from the decommissioning of the Greifswald and Rheinsberg NPPs to the management staff of the Ignalina NPP and to the representatives of the Lithuanian authorities in charge of the decommissioning. The methodology transfer project was prepared and carried out under the leadership of the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH. The practical implementation was within the responsibility of Energiewerke Nord GmbH (EWN) in cooperation with other German subcontractors. The methodology transfer comprised the task fields of project management, project planning, licensing procedure and waste management as well as social aspects of the further development of the industrial site. Five intensive one-week seminars were conducted mainly at the Greifswald NPP site and the knowledge gained was then consolidated in two evaluation seminars at the Ignalina NPP. As the basis for the training realised in 2002 and 2003, EWN provided about 2000 power-point illustrations, more than 200 transparencies and four video films. The training handouts produced by EWN were delivered to the seminar participants in Russian and English language and documented in the database ''Technische Dokumentation Ost'' (DOKU OST) of GRS. (orig.)

Fusion of eastern and western technology in VVER 1000 NPP upgrade

International Nuclear Information System (INIS)

Ubra, O.; Fleischhans, J.; Kveton, M.

1997-01-01

An extensive modernization program upgrading two units of VVER 1000 type of the Czech nuclear power plant (NPP) Temelin to meet the latest international standards is presented. The program is based primarily on combination of eastern and western technology and it has been implemented during plant construction. The NPP Temelin was originally designed according to the standards of the former Soviet Union. After a series of reviews in the 1990s, a decision was made by the Temelin management of upgrade the design of the plant, including the supply of fuel and instrumentation and control system by a western company. The adoption of western technology and practices has helped to solve a large number of IAEA safety issues related to design and operation of VVER 1000 NPP. Details on the current Temelin design and other related safety matters are presented

NPP Decommissioning: the concept; state of activities

International Nuclear Information System (INIS)

Nemytov, S.; Zimin, V.

2001-01-01

The main principles of NPP decommissioning concept in Russia are given. The conditions with fulfillment of works on NPP unit pre-decommissioning and decommissioning including: development of the normative documentation, creation of special fund for financing NPP decommissioning activities, deriving the Gosatomnadzor license for decommissioning of shut down NPP units, development of the equipment and technologies for waste and spent fuel management are presented. The decommissioning cost and labour intensity of one WWER-440 unit are shown. The practical works, executed on shut down units at Beloyarsk NPP (Unit1 and 2) and Novo Voronezh NPP (Unit 1 and 2) are outlined

ESTE EMO and ESTE EBO - emergency response system for NPP Mochovce and NPP Bohunice V-2

International Nuclear Information System (INIS)

Caeny, P.; Chyly, M.; Suchon, D.; Smejkalova, E.; Fabova, V.; Mancikova, M.; Muller, P.

2009-01-01

Programs ESTE EMO and ESTE EBO are emergency response systems that help the crisis staff of the NPP in assessing the source term (predicted possible release of radionuclides to the atmosphere ), in assessing the urgent protective measures and sectors under threat, in assessing real release (symptoms of release really detected and observed), in calculating radiological impacts of real release, averted or avertable doses, potential doses and doses during transport or evacuation on specified routes. Both systems serve as instruments in case of severe accident (DBA or BDBA) at NPP Mochovce or NPP Bohunice, accidents with threat of release of radioactivity to the atmosphere. Systems are implemented at emergency centre of Mochovce NPP and Bohunice NPP and connected online to the sources of technological and radiological data from the reactor, primary circuit, confinement, secondary circuit, ventilation stack, from the area of NPP (TDS 1) and from the emergency planning zone (TDS 11). Systems are connected online to the sources of meteorological data, too. (authors)

ESTE EMO and ESTE EBO - emergency response system for NPP Mochovce and NPP Bohunice V-2

International Nuclear Information System (INIS)

Caeny, P.; Chyly, M.; Suchon, D.; Smejkalova, E.; Fabova, V.; Mancikova, M.; Muller, P.

2008-01-01

Programs ESTE EMO and ESTE EBO are emergency response systems that help the crisis staff of the NPP in assessing the source term (predicted possible release of radionuclides to the atmosphere ), in assessing the urgent protective measures and sectors under threat, in assessing real release (symptoms of release really detected and observed), in calculating radiological impacts of real release, averted or avertable doses, potential doses and doses during transport or evacuation on specified routes. Both systems serve as instruments in case of severe accident (DBA or BDBA) at NPP Mochovce or NPP Bohunice, accidents with threat of release of radioactivity to the atmosphere. Systems are implemented at emergency centre of Mochovce NPP and Bohunice NPP and connected online to the sources of technological and radiological data from the reactor, primary circuit, confinement, secondary circuit, ventilation stack, from the area of NPP (TDS 1) and from the emergency planning zone (TDS 11). Systems are connected online to the sources of meteorological data, too. (authors)

Using bentonite for NPP liquid waste treatment

International Nuclear Information System (INIS)

Bui Dang Hanh

2015-01-01

During operation, nuclear power plants (NPPs) release a large quantity of water waste containing radionuclides required treatment for protection of the radiation workers and the environment. This paper introduces processes used to treat water waste from Paks NPP in Hungary and it also presents the results of a study on the use of Vietnamese bentonite to remove radioactive Caesium from a simulated water waste containing Cs. (author)

New generation main control room of enhanced safety NPP with MKER reactor

International Nuclear Information System (INIS)

Golovanev, V.E.; Gorelov, A.I.; Proshin, V.A.

1994-01-01

Russia is planning to begin the gradual substitution RMBK NPP units, whose resources were worked out itself, to NPP units with a 800 MW multiloop boiling water power reactor (MKER-800) enhanced safety at next ten-year period. Main drawbacks of RBMK Reactor were completely removed in design of MKER-800 reactor. Moreover some special decisions were made to give MKER-800 self-safety properties. The proposed design of the MKER-800 enhanced safety reactor is not only fully free from the drawbacks of the RBMK reactors, but also show a number of advantages of channel-type reactors. This Paper presents some preliminary proposals of MCR Design, that developed Research and Development Institute of Power Energy (RDIPE). 6 refs, 2 figs

Strengthening the control on radioactive sources - Cernavoda NPP operating experience

International Nuclear Information System (INIS)

Daian, I.; Simionov, V.

2005-01-01

This paper presents the national legal frame governing the radioactive source management, legislative requirements introduced during last years and current status of controlled radioactive sources program at Cernavoda NPP. 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. The legal representative of the nuclear power production sector in Romania is 'Nuclearelectrica' S.A. National Company (SNN). SNN is a governmental company controlled by the Ministry of Industry and Trade. The company has headquarters in Bucharest and three subsidiaries: - CNE-PROD Cernavoda (CNE-PROD), operating the Cernavoda NPP - Unit 1; - CNE-INVEST Cernavoda, in charge with the completion of Unit 2 and with the preservation of Units 3,4,5; - Nuclear Fuel Plant in Pitesti (FCN). Unit 1 is in commercial operation since December 2, 1996, Unit 2 is under construction (80% completed) and Units 3, 4, 5 are under preservation. The operation of Cernavoda NPP implies use of radioactive sources that may present a significant risk to health, property and the environment when control is lost. Within the last years CNCAN issued new regulations stating clear responsibilities for the different institutions involved in radioactive materials control programs. To manage radioactive sources in a safe way CNE-PROD established and revised the Controlled Radioactive Sources Program, as part of Station Radiation Protection Regulation, ensuring strict recording of the radioactive sources and their usage, ensuring physical and radiological security, protecting the personnel, members of the public and the environment from the hazards of ionizing radiation during the life cycle of the plant, including decommissioning. (authors)

Strengthening the control on radioactive sources - Cernavoda NPP operating experience

International Nuclear Information System (INIS)

Daian, I.; Simionov, V.

2005-01-01

Full text: This paper presents the national legal frame governing the radioactive source management, legislative requirements introduced during last years and current status of controlled radioactive sources program at Cernavoda NPP. 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. The legal representative of the nuclear power production sector in Romania is 'Nuclearelectrica' S.A. National Company (SNN). SNN is a governmental company controlled by the Ministry of Industry and Trade. The company has headquarters in Bucharest and three subsidiaries: - CNE-PROD Cernavoda (CNE-PROD), operating the Cernavoda NPP - Unit 1; - CNE-INVEST Cernavoda, in charge with the completion of Unit 2 and with the preservation of Units 3,4,5; - Nuclear Fuel Plant in Pitesti (FCN). Unit 1 is in commercial operation since December 2, 1996, Unit 2 is under construction (80% completed) and Units 3, 4, 5 are under preservation. The operation of Cernavoda NPP implies use of radioactive sources that may present a significant risk to health, property and the environment when control is lost. Within the last years CNCAN issued new regulations stating clear responsibilities for the different institutions involved in radioactive materials control programs. To manage radioactive sources in a safe way CNE-PROD established and revised the Controlled Radioactive Sources Program, as part of Station Radiation Protection Regulation, ensuring strict recording of the radioactive sources and their usage, ensuring physical and radiological security, protecting the personnel, members of the public and the environment from the hazards of ionizing radiation during the life cycle of the plant. (authors)

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

International Nuclear Information System (INIS)

Bokor, J.; Gaspar, P.; Hetthessy, J.; Szabo, G.

1998-01-01

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)

Feature extraction and sensor selection for NPP initiating event identification

International Nuclear Information System (INIS)

Lin, Ting-Han; Wu, Shun-Chi; Chen, Kuang-You; Chou, Hwai-Pwu

2017-01-01

Highlights: • A two-stage feature extraction scheme for NPP initiating event identification. • With stBP, interrelations among the sensors can be retained for identification. • With dSFS, sensors that are crucial for identification can be efficiently selected. • Efficacy of the scheme is illustrated with data from the Maanshan NPP simulator. - Abstract: Initiating event identification is essential in managing nuclear power plant (NPP) severe accidents. In this paper, a novel two-stage feature extraction scheme that incorporates the proposed sensor type-wise block projection (stBP) and deflatable sequential forward selection (dSFS) is used to elicit the discriminant information in the data obtained from various NPP sensors to facilitate event identification. With the stBP, the primal features can be extracted without eliminating the interrelations among the sensors of the same type. The extracted features are then subjected to a further dimensionality reduction by selecting the sensors that are most relevant to the events under consideration. This selection is not easy, and a combinatorial optimization technique is normally required. With the dSFS, an optimal sensor set can be found with less computational load. Moreover, its sensor deflation stage allows sensors in the preselected set to be iteratively refined to avoid being trapped into a local optimum. Results from detailed experiments containing data of 12 event categories and a total of 112 events generated with a Taiwan’s Maanshan NPP simulator are presented to illustrate the efficacy of the proposed scheme.

Computer Security of NPP Instrumentation and Control Systems: Cyber Threats

International Nuclear Information System (INIS)

Klevtsov, A.L.; Trubchaninov, S.A.

2015-01-01

The paper is devoted to cyber threats, as one of the aspects in computer security of instrumentation and control systems for nuclear power plants (NPP). The basic concepts, terms and definitions are shortly addressed. The paper presents a detailed analysis of potential cyber threats during the design and operation of NPP instrumentation and control systems. Eleven major types of threats are considered, including: the malicious software and hardware Trojans (in particular, in commercial-off-the-shelf software and hardware), computer attacks through data networks and intrusion of malicious software from an external storage media and portable devices. Particular attention is paid to the potential use of lower safety class software as a way of harmful effects (including the intrusion of malicious fragments of code) on higher safety class software. The examples of actual incidents at various nuclear facilities caused by intentional cyber attacks or unintentional computer errors during the operation of software of systems important to NPP safety.

On the accounting of technology progress rates and obsolescence of production funds when determining depreciation for NPP renovation

International Nuclear Information System (INIS)

Khachyan, G.A.; Petrov, I.M.; Vorob'ev, I.E.; Nizhnik, I.A.; Pylypyuk, R.V.

1986-01-01

Questions, related to determining the economically grounded service life of NPP main production funds are considered. It is recommended to differentiate the depreciation standards by the operation duration. It is proposed to arrange the NPP buildings taking into account modern rates of technical progress in power engineering

Requirements on mechanistic NPP models used in CSS for diagnostics and predictions

International Nuclear Information System (INIS)

Juslin, K.

1996-01-01

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

Financing Nuclear Projects. Case Study: Unit 2 Cernavoda NPP

International Nuclear Information System (INIS)

Chirica, Teodor; Constantin, Carmencita; Dobrin, Marian

2003-01-01

The implementation of a Nuclear Power Plant (NPP) is a major undertaking for all entities involved, due to the necessity of planning work and coordination of the implementation process of the different fields of interest, starting with the governmental authorities and ending with the public. Having in view the specific investment costs (relatively high) for a NPP, finding an adequate financing structure is possible through an iterative process that involves first an assessment of the technical performances of the project and secondly, the mathematical modelling of the financing structure effects on the projects. In this respect, the paper will be focused on the main steps needed in order to promote an investment project in nuclear field, starting with the decision phase, providing the documentation requested by the local and international authorities to promote the project and ending with the negotiation of the contracts (commercial contract, financing contract, purchase contract, etc). The case study will be focused on the phases achieved in order to promote the Unit 2 NPP Cernavoda completion works project. (authors)

Cernavoda NPP impact study on terrestrial and aquatic biota. Preliminary results

International Nuclear Information System (INIS)

Bobric, Elena; Bucur, Cristina; Popescu, Ion; Simionov, Vasile; Titescu, Gheorghe; Varlam, Carmen

2010-01-01

Recently, the awareness of the vulnerability of the environment has increased and the need to protect it against industrial pollutants has been recognized. The concept of sustainable development, requires new and developing international policies for environmental protection. See 'Protection of the environment from the effects of ionizing radiation' IAEA-TECDOC-1091, International Atomic Energy Agency, Vienna. As it is recommended in 'Cernavoda Unit No. 2 NPP Environmental Impact Assessment CES-03702-IAD-006', it is Cernavoda NPP responsibility to conduct an Ecological Risk Assessment study, mainly to assess the impact of nuclear power plant operation on terrestrial and aquatic biota. Long records from normal operation of Cernavoda Unit 1, wind pattern, meteorological conditions, and source terms data were used to evaluate areas of interest for environmental impact, conducting to a circle of 20 km radius around mentioned nuclear objective. The screening campaign established tritium level (because Cernavoda NPP is a CANDU type reactor, and tritium is the most important radioisotope evacuated in the environment) in air, water, soil and vegetation, focusing the interest area on particular ecosystem. Using these primary data it was evaluated which are the monitored ecological receptors and which are the measurement endpoints.This paper presents the Ecological Risk Assessment at Cernavoda NPP technical requirements, and the preliminary results of evaluating criteria for representative ecosystem components at Cernavoda NPP. (authors)

Improving the Assessment of Regional Economic Potential (on Example of Rostov Region

Directory of Open Access Journals (Sweden)

Nikolai A. Kurianov

2017-06-01

Full Text Available The article discusses a number of problematic issues concerning the possibility of improving existing approaches to assessing regional economic potential. Based on the analysis of existing approaches it is concluded that presence of a number of inherent common disadvantages, which include the exclusion of complex assessment elements of intangible resources, isolation from development goals in the region, ignoring the possibility of incremental reserves development static evaluation results. To overcome these ambiguities the authors' approach to improving assessment procedures based on the allocation of the essential nature of the category «regional economic potential», which unites, on the one hand, the resources available for regional development (actual potential, and on the other hand, resources in respect of which the region has the opportunity to attract them as a tool for further development of (stochastic potential. As the degree of implementation of this option is determined by the quality of regional governance, the most important element of the economic potential of the region is also an effective mechanism for management of existing and potential resources of various types. The practical implementation of the proposed methodology suppose, for example, estimate the economic potential of the Rostov region. At the first stage of the evaluation determine the most important elements of this potential and their ranking, on the second – assessment of the status of these elements from the point of view of their availability, ability to attract and management efficiency, and the third – the normalized assessment of regional economic potential.

NPP service life management

International Nuclear Information System (INIS)

Elagin, Yu.P.

2001-01-01

Problems of NPP service life management and service life prolongation are reviewed. Methods for the prolongation of the French NPP service life are discussed, priority directions of nuclear block service life management in regard to aging in the context of the European program of investigation into the materials aging are identified. Questions of the provision of the 60 years service life of the Mihama 1 block (Japan) and decision of the problem of the control equipment aging in Great Britain are discussed. Situation with the prolongation of licenses on the NPP operation in the USA and Spain is considered [ru

Supercompaction of radioactive waste at NPP Krsko

International Nuclear Information System (INIS)

Fink, K.; Sirola, P.

1996-01-01

The problem of radioactive waste management is both scientifically and technically complex and also deeply emotional issue. In the last twenty years the first two aspects have been mostly resolved up to the point of safe implementation. In the Republic of Slovenia, certain fundamentalist approaches in politics and the use of radioactive waste problem as a political tool, brought the final radioactive repository siting effort to a stop. Although small amounts of radioactive waste are produced in research institutes, hospitals and industry, major source of radioactive waste in Slovenia is the Nuclear Power Plant Krsko. When Krsko NPP was originally built, plans were made to construct a permanent radioactive waste disposal facility. This facility was supposed to be available to receive waste from the plant long before the on site storage facility was full. However, the permanent disposal facility is not yet available, and it became necessary to retain the wastes produced at the plant in the on-site storage facility for an extended period of time. Temporary radioactive storage capacity at the plant site has limited capacity and having no other options available NPP Krsko is undertaking major efforts to reduce waste volume generated to allow normal operation. This article describes the Radioactive Waste Compaction Campaign performed from November, 1994 through November, 1995 at Krsko NPP, to enhance the efficiency and safety of storage of radioactive waste. The campaign involved the retrieval, segmented gamma-spectrum measurement, dose rate measurement, compaction, re-packaging, and systematic storage of radioactive wastes which had been stored in the NPP radioactive waste storage building since plant commissioning. (author)

Perspectives of Living PSA in NPP Krsko

International Nuclear Information System (INIS)

Vrbanic, I.; Kastelan, M.

1996-01-01

Nuclear power plant Krsko has completed the Level 1/Level 2 Probabilistic Safety Analysis (PSA) for internal initiating events and is in the process of completing the same for the external initiators. The analysis completed up to now has provided a valuable insight into a plant risk profile. In NPP Krsko there is a plan to use the PSA model as a permanent tool for the risk based applications and incorporate it into a decision making process. In order to achieve this there is a need to permanently maintain the PSA model in a manner that it reflects both the plan configuration/design at a time point and the operational experience up to the time point. All the activities aimed toward keeping the PSA model up-to-dated in this sense are usually referred to as a Living PSA (LPSA) program. NPP Krsko is in the process of defining and proceduralizing a LPSA program that would be plant specific and based on known world practices. Further, in order to be suitable for risk based applications the PSA model must be flexible in a sense that modifications to the base case model may be done easily and requantifications performed quickly as to evaluate various conditions imposed by real or hypothetical situations. NPP Krsko PSA model has been based on licensing type software. The requirements specified above dictate the transfer of the overall model to an application oriented software of newer generation with larger capabilities. The transfer becomes a part of a mentioned ongoing effort aimed at establishing LPSA model and concept. The paper present this effort and the perspectives of LPSA concept and risk based applications in NPP Krsko. (author)

Analysis of the foreign systems for classification and marking the NPP unit components during their application in information systems

International Nuclear Information System (INIS)

Bylkin, B.K.; Shaposhnikov, V.A.; Sadovoj, Yu.K.; Tikhonovskij, V.L.; Chujko, D.V.

2006-01-01

Procedures accepted and permitted in an information system (IS) to arrange and to rank information drawn up to ensure the information support of decommissioning of an NPP power unit affect the application convenience and efficiency of the IS taken as a whole. The IS supporting the decommissioning efforts stores large volume of information, that is why, the problem to choose systems to ensure information ranking is the urgent one. The paper deals with the analysis of the foreign systems to rank the components used during an NPP operation. Besides, one considers the application of the mentioned systems to arrange and to rank the information on decommissioning of an NPP power unit presented to users [ru

SEDRIO/INCORE, an automatic optimal loading pattern search system for PWR NPP reload core using an expert system

International Nuclear Information System (INIS)

Xian Chunyu; Zhang Zongyao

2003-01-01

The expert knowledge library for Daya Bay and Qinshan phase II NPP has been established based on expert knowledge, and the reload core loading pattern heuristic search is performed. The in-core fuel management code system INCORE that has been used in engineering design is employed for neutron calculation, and loading pattern is evaluated by using of cycle length and core radial power peaking factor. The developed system SEDRIO/INCORE has been applied in cycle 4 for unit 2 of Daya Bay NPP and cycle 4 for Phase II in Qinshan NPP. The application demonstrated that the loading patterns obtained by SEDRIO/INCORE system are much better than reference ones from the view of the radial power peak and the cycle length

Integrated risk assessment for multi-unit NPP sites—A comparison

International Nuclear Information System (INIS)

Kumar, C. Senthil; Hassija, Varun; Velusamy, K.; Balasubramaniyan, V.

2015-01-01

Highlights: • Framework for integrated risk assessment for multi-unit NPP sites. • Categorization of external and internal events. • Modelling of key issues: mission time, cliff-edge, common cause failures, etc. • Safety goals for multi-unit NPP sites. • Comparison of site core damage frequency in one, two, three and four unit sites. - Abstract: Most of the nuclear power producing sites in the world houses multiple units. Such sites are faced with hazards generated from external events: earthquake, tsunami, flood, etc. and can threaten the safety of nuclear power plants. Further, risk from a multiple unit site and its impact on the public and environment was evident during the Fukushima nuclear disaster in March 2011. It is therefore important to evolve a methodology to systematically assess the risk from multi-unit site. For a single unit site, probabilistic risk assessment technique identifies the potential accident scenarios, their consequences, and estimates the core damage frequency that arise due to internal and external hazards. This challenging task becomes even more complex for a multiple unit site, especially when the external hazards that has the potential to generate one or more correlated hazards or a combination of non-correlated hazards are to be modelled. This paper presents an approach to evaluate risk for multiple NPP sites and also compare the risk for sites housing single, double and multiple nuclear plants.

Integrated risk assessment for multi-unit NPP sites—A comparison

Energy Technology Data Exchange (ETDEWEB)

Kumar, C. Senthil, E-mail: cskumar@igcar.gov.in [AERB-Safety Research Institute, Kalpakkam (India); Hassija, Varun; Velusamy, K. [Reactor Design Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India); Balasubramaniyan, V. [AERB-Safety Research Institute, Kalpakkam (India)

2015-11-15

Highlights: • Framework for integrated risk assessment for multi-unit NPP sites. • Categorization of external and internal events. • Modelling of key issues: mission time, cliff-edge, common cause failures, etc. • Safety goals for multi-unit NPP sites. • Comparison of site core damage frequency in one, two, three and four unit sites. - Abstract: Most of the nuclear power producing sites in the world houses multiple units. Such sites are faced with hazards generated from external events: earthquake, tsunami, flood, etc. and can threaten the safety of nuclear power plants. Further, risk from a multiple unit site and its impact on the public and environment was evident during the Fukushima nuclear disaster in March 2011. It is therefore important to evolve a methodology to systematically assess the risk from multi-unit site. For a single unit site, probabilistic risk assessment technique identifies the potential accident scenarios, their consequences, and estimates the core damage frequency that arise due to internal and external hazards. This challenging task becomes even more complex for a multiple unit site, especially when the external hazards that has the potential to generate one or more correlated hazards or a combination of non-correlated hazards are to be modelled. This paper presents an approach to evaluate risk for multiple NPP sites and also compare the risk for sites housing single, double and multiple nuclear plants.

Nuclear power plant V-2

International Nuclear Information System (INIS)

1998-01-01

The nuclear power plant Bohunice V -2 is briefly described. This NPP consists from two reactor units. Their main time characteristics are (Reactor Unit 1, Reactor Unit 2): beginning of construction - December 1976; first controlled reactor power - 7 August 1984, 2 August 1985; connection to the grid - 20 August 1984, 9 August 1985; commercial operation - 14 February 1985, 18 December 1985. This leaflet contains: NPP V-2 construction; Major technological equipment [WWER 440 V230 type reactor; Nuclear Power plant operation safety (Safety barriers; Safety systems [Active safety systems, Passive safety systems]); Centralized heat supply system; Scheme of Bohunice V-2 NPP and technical data

On the prohibition of automatic redundant power supply of 6 and 0.4 kV auxiliary sections at Leningrad NPP

International Nuclear Information System (INIS)

Mokeev, S.F.

1987-01-01

At Leningrad NPP the automatic switching on of the auxiliary power supply sources of 6 and 0.4 kV is prohibited to provide personnel safety and preserve destruction of electroequipment. With excess of current maximum value in the 6 kV section immediate detachment of all electric motors occurs. At that moment by the switchers detechment emergency signal it occurs immediate swithing on of auxiliary systems or emergency switching on of auxiliary supply of the main circulating pumps, that insreases abruptly operation reliability of plant technological department

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

Science.gov (United States)

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

2015-04-01

The nature of Nuclear Power Plant (NPP) projects are: long duration (10-15 years for new build), high capital investment, reasonable risks and highly regulated industries to meet national & international requirement on Safety, Security, Safeguards (3S) and Liabilities. It requires long term planning and commitment from siting to final disposal of waste/spent fuel. Potential financial and regulatory risks are common in massive NPP projects and will be magnified in the case of using unproven technology. If the risks are not properly managed, it can lead to high project and operation costs, and, fail to fulfil its objectives to provide compatible electricity prices and. energy security. To ensure successful, the government and investors need to ensure that the NPP project is bankable with low cost of project and funding, have fair treatment and proper risk mitigation, and able to complete on time with no cost overrun. One of the requirements as prerequisite for the development of NPP as stipulated by the International Atomic Energy Agency (IAEA) is the establishment of a Legal and Regulatory Framework. The main objective of nuclear law is to ensure that the activities and projects carried-out in the country are legal and compliant to national and international requirements. The law should also be able to provide fair treatment of risks on its activities that is acceptable to investors. The challenge for a newcomer country is to develop a balanced and comprehensive national nuclear law that meet these objectives while taking into consideration various stakeholders' interest without compromising on safety, security, safeguard, liability requirements and other international obligations. This paper highlights the nature of NPP projects, its potential and associated financial and regulatory risks, and its major concerns and challenges. It proposes possible risks treatment and mitigation through the formulation of a balanced and comprehensive legislation by clear

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

International Nuclear Information System (INIS)

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

2015-01-01

The nature of Nuclear Power Plant (NPP) projects are: long duration (10-15 years for new build), high capital investment, reasonable risks and highly regulated industries to meet national and international requirement on Safety, Security, Safeguards (3S) and Liabilities. It requires long term planning and commitment from siting to final disposal of waste/spent fuel. Potential financial and regulatory risks are common in massive NPP projects and will be magnified in the case of using unproven technology. If the risks are not properly managed, it can lead to high project and operation costs, and, fail to fulfil its objectives to provide compatible electricity prices and. energy security. To ensure successful, the government and investors need to ensure that the NPP project is bankable with low cost of project and funding, have fair treatment and proper risk mitigation, and able to complete on time with no cost overrun. One of the requirements as prerequisite for the development of NPP as stipulated by the International Atomic Energy Agency (IAEA) is the establishment of a Legal and Regulatory Framework. The main objective of nuclear law is to ensure that the activities and projects carried-out in the country are legal and compliant to national and international requirements. The law should also be able to provide fair treatment of risks on its activities that is acceptable to investors. The challenge for a newcomer country is to develop a balanced and comprehensive national nuclear law that meet these objectives while taking into consideration various stakeholders’ interest without compromising on safety, security, safeguard, liability requirements and other international obligations. This paper highlights the nature of NPP projects, its potential and associated financial and regulatory risks, and its major concerns and challenges. It proposes possible risks treatment and mitigation through the formulation of a balanced and comprehensive legislation by clear

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-04-29

The nature of Nuclear Power Plant (NPP) projects are: long duration (10-15 years for new build), high capital investment, reasonable risks and highly regulated industries to meet national and international requirement on Safety, Security, Safeguards (3S) and Liabilities. It requires long term planning and commitment from siting to final disposal of waste/spent fuel. Potential financial and regulatory risks are common in massive NPP projects and will be magnified in the case of using unproven technology. If the risks are not properly managed, it can lead to high project and operation costs, and, fail to fulfil its objectives to provide compatible electricity prices and. energy security. To ensure successful, the government and investors need to ensure that the NPP project is bankable with low cost of project and funding, have fair treatment and proper risk mitigation, and able to complete on time with no cost overrun. One of the requirements as prerequisite for the development of NPP as stipulated by the International Atomic Energy Agency (IAEA) is the establishment of a Legal and Regulatory Framework. The main objective of nuclear law is to ensure that the activities and projects carried-out in the country are legal and compliant to national and international requirements. The law should also be able to provide fair treatment of risks on its activities that is acceptable to investors. The challenge for a newcomer country is to develop a balanced and comprehensive national nuclear law that meet these objectives while taking into consideration various stakeholders’ interest without compromising on safety, security, safeguard, liability requirements and other international obligations. This paper highlights the nature of NPP projects, its potential and associated financial and regulatory risks, and its major concerns and challenges. It proposes possible risks treatment and mitigation through the formulation of a balanced and comprehensive legislation by clear

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

International Nuclear Information System (INIS)

Grgic, M.; Fabjan, L.; Premru, U.

1977-01-01

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

Comparative analysis of events at NPP of Ukraine during 1993-1995

Energy Technology Data Exchange (ETDEWEB)

Koltakov, V [Ministry for Environment Protection and Nuclear and Radiation Safety of Ukraine Nuclear Regulatory Administration Scientific and Technical Centre, Kiev (Ukraine)

1997-12-31

The suggested comparative analyses of malfunctions in operation of Ukrainian NPP during the last 3 year shows a tendency for decreasing the total number of malfunctions, out of plan power changes and malefactions connected with safety system nonavailability. 6 tabs.

Comparative analysis of events at NPP of Ukraine during 1993-1995

International Nuclear Information System (INIS)

Koltakov, V.

1996-01-01

The suggested comparative analyses of malfunctions in operation of Ukrainian NPP during the last 3 year shows a tendency for decreasing the total number of malfunctions, out of plan power changes and malefactions connected with safety system nonavailability. 6 tabs

Modernization programme at Dukovany NPP

International Nuclear Information System (INIS)

Trnka, M.

2000-01-01

The main goal of each NPP is to produce electricity safely, economically and without influence to environment. For Dukovany NPP it means to upgrade all documentation and perform the Equipment Upgrading Programme. All these activities are time and money consuming and therefore the determination of priority of all items was necessary. In the presentation there are mentioned some important changes in documentation, results of PSA studies and reason for Equipment Upgrading Programme performance. It was selected the most important item from the list of Equipment Upgrading Programme the I and C upgrading. Management has decided that Dukovany NPP will become among the best NPPs with WWER type of reactor. It seems this decision is the best way how to extend lifetime of the NPP. (author)

AGNES - safety reassessment of Paks NPP

International Nuclear Information System (INIS)

Gado, J.

1995-01-01

The main goal of the AGNES (Advanced General and New Evaluation of Safety) project for the reassessment of the safety of Paks Nuclear Power Plant, Hungary, was to improve the safety culture of the technology at Paks. A report was prepared on the reassessment of the Paks NPP safety. The analysis was divided into four groups: systems analysis, analysis of design basis accidents, severe accident analysis, and level 1 probabilistic safety analysis. Proposed safety enhancement measures are discussed. (N.T.)

Some aspects of correction additions optimisation of water chemistry regime of Kozloduy NPP power units 3 and 4

International Nuclear Information System (INIS)

Topalova, I.

2005-01-01

Optimization of the water-chemistry regime is a major corrective measure for minimization of the corrosion processes of the nuclear power unit equipment. Research done in NPP Kozloduy III - IV power units concerning the migration of the corrosion products in the water of secondary circuit as well as the connection between corrosion processes and fluctuation in parameters of the applied water-chemistry regime are reported. Analysis of the dependences obtained lead to conclusions for optimization of the water chemistry regime of secondary circuit and minimization of the corrosion processes and improvement of corrosion condition of metal surfaces. The research is done for the circuit of each of the 8 turbines of the two power units for a period of 10 days. Data received is quantitatively representative /40-50 points/ for performing of analysis and reaching certain conclusions for the water chemistry regime and development of corrosion processes. Dependence of iron and copper concentration in the work medium on the pH, ammonia and hydrazine concentration as well as the dependence of pH on ammonia concentration in case of different quantity and composition of corrosion products on the different power units' equipment metal surfaces are shown. (author)

Operating Experience at NPP Krsko

International Nuclear Information System (INIS)

Kavsek, D.; Bach, B.

1998-01-01

Systematic analysis of operational experience by assessment of internal and industry events and the feedback of lessons learned is one of the essential activities in the improvement of the operational safety and reliability of the nuclear power plant. At NPP Krsko we have developed a document called ''Operating Experience Assessment Program''. Its purpose is to establish administrative guidance for the processing of operating events including on-site and industry events. Assessment of internal events is based on the following methods: Event and Causal Factor Charting, Change Analysis, Barrier Analysis, MORT (Management Oversight and Risk Tree Analysis) and Human Performance Evaluation. The operating experience group has developed a sophisticated program entitled ''Operating experience tracking system'' (OETS) in response to the need for a more efficient way of processing internal and industry operating experience information. The Operating Experience Tracking System is used to initiate and track operational events including recommended actions follow up. Six screens of the system contain diverse essential information which allows tracking of operational events and enables different kinds of browsing. OETS is a part of the NPP Krsko nuclear network system and can be easily accessed by all plant personnel. (author)

Prospects for nuclear power development in Kazakhstan

International Nuclear Information System (INIS)

Batyrbekov, E.G.

2014-01-01

Full text : The possible use of NPP with single medium-sized units (600-700 MW) and large-sized units (over 1000 MW) is considered in the Republic of Kazakhstan as base electric power sources in order to meet the rising demand of electric power in conditions of national economy development. The results of feasibility studies on NPP construction estimability in Kazakhstan which were pursued within by efforts of NNC RK and other Kazakhstan organizations with methodical support of JAPC (Japan) within the period from 2006 to 2009, are discussed. The feasibility studies have been conducted based on data on electric power consumption and generation considering characteristics of electrical power systems and plans for transmitting lines construction in Kazakhstan, available conditions for NPP siting (cooling water, roads and communication lines, human resources, other elements of infrastructure and control), natural conditions, potential hazards for NPP caused with industrial economic activity; social factors, consequences of NPP impact on the environment including the radiation effect on population in case of radiation accident

Prospects of increasing the engineering level of NPP components

International Nuclear Information System (INIS)

Filippov, G.A.

1987-01-01

Consideration is being given to main problems related to development and industrial introduction of NPP components corresponding to the perspective world-wide engineering level. The nearest task in this field is to elevate the engineering level of developed and being produced power equipment up to the level of similar equipment, manufactured by leading foreign companies

Emergency preparedness at Ignalina NPP

International Nuclear Information System (INIS)

Kairys, A.

1998-01-01

Brief review of Ignalina NPP safety upgrading and personnel preparedness to act in cases of accidents is presented. Though great activities are performed in enhancing the plant operation safety, the Ignalina NPP management pays a lot of attention to preparedness for emergency elimination and take measures to stop emergency spreading. A new Ignalina NPP emergency preparedness plan was drawn up and became operational. It is the main document to carry out organizational, technical, medical, evacuation and other activities to protect plant personnel, population, the plant and the environment from accident consequences. Great assistance was rendered by Swedish experts in drawing this new emergency preparedness plan. The plan consists of 3 parts: general part, operative part and appendixes. The plan is applied to the Ignalina NPP personnel, Special and Fire Brigade and also to other contractor organizations personnel carrying out works at Ignalina NPP. There are set the following emergency classes: incident, emergency situation, alert, local emergency, general emergency. Separate intervention level corresponds to each emergency class. Overview of personnel training to act in case of an emergency is also presented

NPP long term operation in Spain - First application for license renewal

International Nuclear Information System (INIS)

Francia, L.; Gorrochategui, I.; Marcos, R.

2007-01-01

Full text: In the operation of the Spanish nuclear power plants (NPP), safety is always the prime consideration. Plant Life Management Programmes have been set up with the strategic objective to operate the NPPs as long as they are considered safe and reliable. The safety of each NPP is reviewed by the Spanish nuclear regulatory authority (CSN) under a continuous process. In addition, experience is gained from operating the plants and from exchanges with operators of similar units. Current Spanish regulatory framework for renewing NPP operating licenses requires performing a Periodic Safety Review (PSR) to be performed every 10 years and submitted when applying for a new renewal of the NPP operating license. A few years ago, CSN issued a document regarding the licensing requirements that nuclear power plants should meet in order to be granted with an operating license for long term operation (i.e, operation beyond the original plant design life, typically 40 years). Besides the traditional PSR requirements, specific requirements regarding to long term operation (LTO) include: - An Aging Management and Evaluation Program, including the identification and evaluation of Time Limited Aging Analysis (TLAA). - An updated Radiological Impact Study. - A review and assessment of regulation/standard applicability. Garona NPP (GE, BWR/3 design) operated by Spanish utility Nuclenor from 1971 has a current operating license up to 2009. A decision was made to apply for a new operating license, being Garona plant the first one in Spain to face with the new long term operation requirements. The paper will provide an overview of the methodology used in Spain to address and perform the required analyses to support the LTO application for the operating license renewal. In particular, focus will be paid on the project developed in Garona (2002-2006) whose result has been the first Spanish application for License Renewal for LTO. Also it will be reported the ongoing work necessary to

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. © 2015 John Wiley & Sons Ltd.

Risks for marine coastal ecosystems from anthropogenic loading in the Leningrad NPP environs

International Nuclear Information System (INIS)

Zimina, L.; Zimin, V.; Shchukina, T.; Pomiluiko, G.; Ryabova, V.

1998-01-01

Data on conditions and variations in phytoplankton, zooplankton and fish communities, chlorophyll 'a' and hydrochemical parameters in the coastal waters of Koporskaya Bay (cooling water body of the Leningrad NPP) were analyzed. The most significant anthropogenic factors issued from the Leningrad nuclear power plant activity are of non-radioactive character, as it was recognized during long-time (20 years) ecological monitoring. Main factors influenced ecosystem of the NPP cooling water body are thermal water discharge and nutrient outflows from the bay catchment area. (authors)

Study on mid and long-term strategic plan formulation for newly-constructed NPP

International Nuclear Information System (INIS)

Song Lin

2014-01-01

Mid and Long-term strategic plan plays a key role for the management of a newly constructed nuclear power company. Among others, process, goals, and risk management, are the primary concerns during plan preparing. The article analyzed these three areas for Fuqing NPP, including the formulating process for the plan, the mid and long-term goal setting of the company, the major risk analysis and countermeasure selection therefore. Through that solutions and suggestions for strategic plan formulation were concluded for newly-constructed NPP. (author)

'Kozloduy' NPP geological environment as a barrier against radionuclide migration

International Nuclear Information System (INIS)

Antonov, D.

2000-01-01

The aim of this report is to present an analysis of the geological settings along Kozloduy NPP area from the viewpoint of a natural, protective barrier against unacceptable radionuclides migration in the environment. Possible sources of such migration could be an eventual accident in an active nuclear plant; radioactive releases from decommissioned Power Units or from temporary or permanent radioactive waste repositories. The report is directed mainly to the last case, and especially to the site selection for near surface short lived low and intermediate level (LILW) radioactive repository. The main conclusion of the geological settings assessment and of the many years monitoring is that the Kozloduy NPP area offers good possibilities for site selection of LILW repository. (author)

The Influence of Quality Assurance and Supportive Supervision on the Quality of Medical Care in Children’s Hospitals of the Municipal Level of the Rostov Region

Directory of Open Access Journals (Sweden)

Tatiana V. Kulichenko

2017-01-01

Full Text Available Background. Improving the quality of medical care is the absolute priority of the World Health Organization and all socially-oriented ministries and departments around the world.Objective. Our aim was to evaluate the effectiveness of quality  assurance and supportive supervision in municipal hospitals to improve the quality of medical care for children (by the example of the Rostov region.Methods. The open observational study included 10 second-level hospitals in the Rostov Region. At the start of the project, the quality of inpatient care for children in the region was audited based on recommendations and tools of the World Health Organization, and training of medical personnel was organized. Monitoring visits to hospitals were carried out by experts every 3 months (supportive supervision. Reaudit of the quality of care was conducted a year later.Results. As a result of regular quality assurance and supportive supervision of hospitals during the first year of operation, such indicators of the quality of medical care as the availability of medical equipment for emergency care for children, the infrastructure of children’s departments, the triage and provision of emergency care in children’s departments, managing patients with various acute conditions (fever, diarrhea, respiratory diseases, supporting care, internal quality assurance, accessibility to standards of care and clinical guidelines for the diagnosis and treatment of various diseases, respect for children’s rights were significantly (p < 0.05 improved.Conclusion. Supportive supervision and regular external quality assurances of hospitals contribute to a rapid increase in the quality of medical care for children.

The Acceptance Strategy for Nuclear Power Plant In Indonesia

International Nuclear Information System (INIS)

Suhaemi, Tjipta; Syaukat, Achmad

2010-01-01

Indonesia has planned to build nuclear power plants. Some feasibility studies have been conducted intensively. However, the processes of NPP introduction are still uncertain. National Energy Plan in Indonesia, which has been made by some governmental agencies, does not yet give positive impact to the government decision to construct the nuclear power plant (NPP). This paper discusses the process of NPP introduction in Indonesia, which has been colored with debate of stakeholder and has delayed decision for go-nuclear. The technology paradigm is used to promote NPP as an alternative of reliable energy resources. This paradigm should be complemented with international politic-economic point of view. The international politic-economic point of view shows that structural powers, consisting of security, production, finance, and knowledge structures, within which the NPP is introduced, have dynamic characteristics. The process of NPP introduction in Indonesia contains some infrastructure development (R and D, legislation, regulation, energy planning, site study, public acceptance efforts, etc), but they need a better coherent NPP implementation program and NPP Acceptance Program. Strategic patterns for NPP acceptance described in this paper are made by considering nuclear regulation development and the interest of basic domestic participation. The first NPP program in Indonesia having proven technology and basic domestic participation is and important milestone toward and optimal national energy-mix.

New approach of second Romanian NPP siting

International Nuclear Information System (INIS)

Mauna, Traian

2010-01-01

The NPP sitting studies in Romania began before 1975. The first Romanian NPP CANDU 6 type reactor gone to erection in 1980 on Cernavoda site planned to have 5 units. Gained the experience from Cernavoda NPP sitting, the first mission of new multi-branch of specialists team was to choose new NPP sites adapting the NPP Cernavoda project to the new parameters of close water cooling circuit and hard less and no rock foundation strata. The studies were carrying out in different stages on the inner rivers Olt, Mures, Somes in Transylvania historical region. This paper tries to reconsider shortly the old analysis according to the last IAEA Safety Standards, taking into account the new NPP generation requirement. Paper is focused on geological aspects and other local sites characteristics. (authors)

The seismic reassessment Mochovce NPP

International Nuclear Information System (INIS)

Baumeister, P.

2004-01-01

The design of Mochovce NPP was based on the Novo-Voronez type WWER-440/213 reactor - twin units. Seismic characteristic of this region is characterized by very low activity. Mochovce NPP site is located on the rock soil with volcanic layer (andesit). Seismic reassessment of Mochovce NPP was done in two steps: deterministic approach up to commissioning confirmed value Horizontal Peak Ground Acceleration HPGA=0.1 g and activities after commissioning as a consequence of the IAEA mission indicate higher hazard values. (author)

Fission product source from Ignalina NPP in case of loss-of-coolant accidents

International Nuclear Information System (INIS)

Ubonavicius, E.; Rimkevicius, S.

2001-01-01

The release of radioactive materials to the environment is of special importance in the case of any accident at Nuclear Power Plants (NPP). The integrated analysis of thermal-hydraulic parameters behavior and radioactive fission products (FP) transport and deposition in the compartments play an important role in the evaluation of FP release to the environment and determines the irradiation dozes of personnel and public. In this report the transport and the deposition of radioactive material in the Ignalina NPP unit 1 compartments as well as the FP source term to the environment in the case of design basis loss-of-coolant accidents are discussed. The calculation models for the evaluation of FP transport and deposition as well as the results of performed calculations of several accidents at Ignalina NPP are presented. (author)

Radioactive waste management at Cernavoda NPP after 5 years of experience

International Nuclear Information System (INIS)

Raducea, D.

2002-01-01

Many human activities generate waste but people are worried about those produced in nuclear power plants. Their concern is an unjustified fear toward the hazard from radioactive wastes because any country, which produces electrical power in this way, pays a lot of attention of all relevant parties involved in radioactive waste management. The same policy is applied for Cernavoda NPP. Our concept establishes the general approach required for the collection, handling, conditioning and storage of radioactive waste from Cernavoda NPP Unit 1 and will be ready for expansion when other units are brought into service. Among others, a major objective is to reduce the radioactive waste production and volume. In this regard we are trying to improve as much as possible our procedures and radioactive wastes management. Further, it will be presented the radioactive waste management, including the improvements in our program and the future plans.(author)

Ignalina NPP: living and working conditions

International Nuclear Information System (INIS)

Chiuzhas, A.

1998-01-01

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

Cernavoda NPP Unit 1 - a plant of several generations

International Nuclear Information System (INIS)

Rotaru, I.; Metes, M.; Anghelescu, M.S.

2000-01-01

Cernavoda NPP Unit 1, the first nuclear power unit in Romania, has a long and tormented history. It represents a rather unique case in Eastern Europe. The project started well before 1989 (the construction phase lasted 17 years and generations were involved in its completion), but it is effectively based on western technology (Candu). Meanwhile, the national nuclear program underwent many changes, affecting the lives and careers of Romanian nuclear professionals. Finally, on December 2 nd 1996, the unit began its c ommercial operation , being operated at its nominal power rating of 706 MW e . It now provides a reliable source of electricity for Romanian economy, supplying to the national grid about 10% of the country's average annual demand. The paper reflects some aspects related to the shift of generations during the project's development, including the present stage. The operational performances achieved 'in service' by Cernavoda NPP Unit 1 up to the end of 1999 , are also presented. Reference to the electrical energy production, performance indicators, production costs, nuclear safety, radiation protection, radioactive wastes, nuclear fuel consumption and nuclear fuel performances are included. Comparisons are performed with similar indicators reported by other worldwide nuclear power plants, in order to assess our results. (authors)

Investigation of Chernobyl NPP and recovery of environment and medical service in Ukraine

International Nuclear Information System (INIS)

Narabayashi, Tadashi; Hamamoto, Kazuko; Mizumachi, Wataru; Okamoto, Koji

2013-01-01

Fukushima Daiichi NPP accident will be terminated, if sufficient care of recovery for heart of people, economy and environment leads to happy Fukushima. It might be taken more than 20 years or more. The overseas NPP investigation group in the study committee for safety regulatory of NPP in PES division in JSME visited Chernobyl NPP, Ministry of Emergencies, National Institute for Strategic Studies under the President of Ukraine, Chernobyl Center, Slavutych, Research Center for Radiation Medicine of the National Academy of Medical Sciences of Ukraine, National University of Life and Environmental Science of Ukraine, Institute for Safety Problems of Nuclear Power Plants and Chernobyl Museum. The investigation of bases of their new technology for deep LRW cleaning of Fukushima genesis from the whole range of radionuclides, including uranium and transuranic elements, organic impurities and simultaneous concentration of radioactive components in a small volume. The recovery of environment and care of heart of people were good in Ukraine. The lessons derived from the accident, we can decide what we should do. (author)

The Improved Methods of Critical Component Classification for the SSCs of New NPP

International Nuclear Information System (INIS)

Lee, Sang Dae; Yeom, Dong Un; Hyun, Jin Woo

2010-01-01

Functional Importance Determination (FID) process classifies the components of a plant into four groups: Critical A, Critical B, Minor and No Impact. The output of FID can be used as the decision-making tool for maintenance work priority and the input data for preventive maintenance implementation. FID applied to new Nuclear Power Plant (NPP) can be accomplished by utilizing the function analysis results and safety significance determination results of Maintenance Rule (MR) program. Using Shin-Kori NPP as an example, this paper proposes the advanced critical component classification methods for FID utilizing MR scoping results

Crack resistance increasing in epoxide-rubber coatings of NPP room floors

International Nuclear Information System (INIS)

Khorenzhenko, V.I.

1986-01-01

Problems of crack resistance increasing in epoxide-rubber coatings for the floors are considered. Exploitation experience of the floors in the special rooms of NPP is given. Perspectivity of application of the compositions described as the building materials for nuclear power stations is pointed out

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

International Nuclear Information System (INIS)

1995-01-01

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

Automated personal dosimetry monitoring system for NPP

International Nuclear Information System (INIS)

Chanyshev, E.; Chechyotkin, N.; Kondratev, A.; Plyshevskaya, D.

2006-01-01

Full text: Radiation safety of personnel at nuclear power plants (NPP) is a priority aim. Degree of radiation exposure of personnel is defined by many factors: NPP design, operation of equipment, organizational management of radiation hazardous works and, certainly, safety culture of every employee. Automated Personal Dosimetry Monitoring System (A.P.D.M.S.) is applied at all nuclear power plants nowadays in Russia to eliminate the possibility of occupational radiation exposure beyond regulated level under different modes of NPP operation. A.P.D.M.S. provides individual radiation dose registration. In the paper the efforts of Design Bureau 'Promengineering' in construction of software and hardware complex of A.P.D.M.S. (S.H.W. A.P.D.M.S.) for NPP with PWR are presented. The developed complex is intended to automatize activities of radiation safety department when caring out individual dosimetry control. The complex covers all main processes concerning individual monitoring of external and internal radiation exposure as well as dose recording, management, and planning. S.H.W. A.P.D.M.S. is a multi-purpose system which software was designed on the modular approach. This approach presumes modification and extension of software using new components (modules) without changes in other components. Such structure makes the system flexible and allows modifying it in case of implementation a new radiation safety requirements and extending the scope of dosimetry monitoring. That gives the possibility to include with time new kinds of dosimetry control for Russian NPP in compliance with IAEA recommendations, for instance, control of the equivalent dose rate to the skin and the equivalent dose rate to the lens of the eye S.H.W. A.P.D.M.S. provides dosimetry control as follows: Current monitoring of external radiation exposure: - Gamma radiation dose measurement using radio-photoluminescent personal dosimeters. - Neutron radiation dose measurement using thermoluminescent

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

International Nuclear Information System (INIS)

Lee, Kwang Ho; Roh, Myung Sub

2013-01-01

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

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.

Safety Culture Survey in Krsko NPP

International Nuclear Information System (INIS)

Strucic, M.; Bilic Zadric, T.

2008-01-01

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

Selection of NPP for Kazakhstan

International Nuclear Information System (INIS)

Zhotabaev, Zh.R.

2003-01-01

Commercial NPP for Kazakhstan should to meet to several main requirements: 1). Safety operation (accident probability not more than 10 -6 1/p. year). 2). High efficiency > 40 %. 3). Possibility of use for high-temperature chemistry and hydrogen production. 4). Possibility for manufacturing of considerable part of equipment in Kazakhstan. 5). Possibility for fuel production and reprocessing in Kazakhstan. 6). Independence from existence of large water-supply sources. Comparative analysis of several NPP with different reactors (WWR-1000, Candu, BREST, VG-400; graphite molten salt reactor) shows that NPP with the graphite molten salt reactor meets to all above requirements, but hydrogen production it is possible by more complete 4-stage technology, since coolant temperature is 800 Deg. C. The principle advantage is possibility of manufacturing of main equipment and fuel in Kazakhstan that reduce the cost of NPP construction and operation

A brief overview of Ignalina NPP safety issues

International Nuclear Information System (INIS)

Almenas, K.; Ushpuras, E.

1998-01-01

A description of the safety of Ignalina NPP in a very popular form is presented. Answers to the most frequently recurring questions concerning the Ignalina NPP are provided based on recently completed international studies. Questions are like these: can a similar accident to the one that occurred in Chernobyl take place at Ignalina NPP, does the Ignalina NPP have a containment, what are the probabilities and potential consequences of accidents, etc. The brochure contains a short description of Ignalina NPP safety improvement programs

From Market Uncertainty to Policy Uncertainty for Investment in Power Generation: Real Options for NPP on Electricity Market

International Nuclear Information System (INIS)

Tomsic, Zeljko

2014-01-01

In the electricity sector, market participants must make decisions about capacity choice in a situation of radical uncertainty about future market conditions. Sector is normally characterised by non-storability and periodic and stochastic demand fluctuations. In these cases capacity determination is a decision for the long term, whereas production is adjusted in the short run. Capacities need to be installed well in advance (decision for investment even earlier because of long construction time and even longer in case of NPP to prepare all needed legal, financial and physical infrastructure), at times when firms face considerable demand and cost uncertainty when choosing their capacity. Paper looks on the main contributions in investment planning under uncertainty, in particular in the electricity market for capital intensive investments like NPP. The relationship between market and non-market factors (recent UK policy example) in determining investment signals in competitive electricity markets was analysed. Paper analyse the ability of competitive electricity markets to deliver the desired quantity and type of generation capacity and also investigates the variety of market imperfections operating in electricity generation and their impact on long-term dynamics for generation capacity, the most capital-intensive of the liberalised functions in the electricity supply industry. Paper analyses how price formation influences investment signals. Today, investment decisions are made by several operators that act independently. Number of factors (including market power, wholesale price volatility, lack of liquidity in the wholesale and financial market, policy and regulatory risks etc.) contribute to polluting the price signal and generating sub-optimal behaviour. Climate change policies can easily distort market signals, insulating renewables generation from market dynamics. This in turn reduces the proportion of the market that is effectively opened to competitive

IAEA activities in the field of NPP I and C

International Nuclear Information System (INIS)

Gloeckler, O.

2006-01-01

The paper discusses the current, and upcoming activities of the IAEA's Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI). The following particular I and C-related subjects are discussed in more detail: (1) the relation between improvements in I and C and NPP power up-rating projects, and (2) the I and C and human factor engineering issues of integrating analog and digital I and C systems in hybrid control rooms. (authors)

Can the Ignalina NPP be safe?

International Nuclear Information System (INIS)

Kutas, S.

1999-01-01

Many countries started using nuclear power before Lithuania, the IAEA and NEA were established and have been functioning efficiently, numerous conventions have been signed that control nuclear activities, nuclear safety regulations and standards have been set. Lithuania which is striving to integrate into the West European structures and to become a member of the 'club' of the world's nuclear states, has become a full and equal member of the IAEA and recognises its recommendations. Furthermore, it has signed or joined international conventions and is doing its best to introduce the practice of controlling nuclear safety applied in western countries. Nuclear safety cannot be taken as something finite that does not change. The requirements of nuclear and radiation safety are continuously redefined taking into consideration scientific discoveries and inventions as well as technical progress. Safety assurance can be the only criterion that should determine whether the nuclear power plant can be operated in Lithuania. The safety analysis report confirmed that the Ignalina NPP can be safely operated until the channel-graphite gap closes. The experiments conducted to date have convincingly shown that by the year 2000 the gap will not close in any of the fuel channels of unit 1. It can be hoped that the submitted studies, analyses and assessments will confirm that the Ignalina NPP meets Lithuania's nuclear safety requirements that have been drawn up in compliance with the recommendations of IAEA

Current evolutionary stage of L/ILW management at operating NPP in the USA

International Nuclear Information System (INIS)

Miller, C.C.

2001-01-01

The volume of Low and Intermediate Level Waste (L/ILW) from commercial nuclear power plants (NPP) buried annually in the USA has decreased dramatically over the last two decades. The reduction in disposal volume has occurred for both dry active wastes (DAW) and wet wastes (e.g., resins, filters and sludges). Decreased disposal volume has occurred at both Pressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs). The reduction in disposal volume occurred in stages. The major driver to reduce disposal volume in the commercial sector of the USA has been increasing burial costs. The current drive to further reduce overall NPP operating costs to meet a deregulated electric market in the USA has unexpectedly resulted in further waste reductions. This paper will review the stages of waste reduction and describe the current stage for NPP in the USA. (author)

Social problems and territorial experiences from closing down Tihange NPP

International Nuclear Information System (INIS)

Lizin, A.M.

2000-01-01

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

Some features of South-Ukrainian NPP information centre's interaction with mass media in post Chernobyl period

International Nuclear Information System (INIS)

Kiyashko, S.; Kurilchik, N.

1995-01-01

Using the above methods of interaction with the off-site media helped the South Ukraine NPP information centre achieve meaningful results in restoring the image of nuclear power ad making it more trustworthy. This is supported by a review of media Publications since 1989. Quantitative and qualitative modifications of the information flow to the media have yielded substantial changes of the structure of news releases about the South Ukraine NPP and nuclear power. Background information has increased from 1. 5 to 50 percent. Negative information is no longer dominating, and the Chernobyl topic is counterbalanced with diverse NucNet materials about nuclear from throughout the world. (author)

Concreting organization during Chernobylsk NPP construction

International Nuclear Information System (INIS)

Lysyuk, R.I.; Kareva, A.P.

1984-01-01

Conreting organization during the Chernobylsk NPP construction is described. Processes of extra heavy concrete production and placement, which specific mass constitutes 4t/m 3 at the age of 28 days wiath metallic aggregates and 3.3-3.5 t/m 3 at the same age without aggregates, are considered in short. Basic characteristics of this concrete are presented. At the 4th power unit labour contents for construction works were a 1.5 times lower as compared to the 3rd power unit erection. This progress was achieved by round-the-clock operation of the concrete plant with the 800 m 3 /day output and also by utilization of special equipment for mechanized concrete placement: concrete pumps, automatic concrete mixer, manipulators and concrete pipelines

The NPPR Trnava participation in the NPP V-2 modernisation and safety improvement project

International Nuclear Information System (INIS)

Michal, V.; Losonsky, B.; Magdolen, J.

1999-01-01

The presented contribution deals with form, present state and results of Nuclear Power Plants Research Inst.e participation in the NPP V-2 Jaslovske Bohunice Modernization and Safety Improvement Project.(author)

Safe 15 Terawatt of Temelin NPP

International Nuclear Information System (INIS)

Sula, M.

2010-01-01

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.

Development of a hardware-in- loop simulation platform for NPP main control systems

Directory of Open Access Journals (Sweden)

Liu Pengfei

2017-01-01

Full Text Available The simulation technology of the nuclear power plant are gradually applying to the nuclear power industry. However, most of the research on nuclear power plant simulation system only focus on pure computerized simulation at present, and it is difficult to fully display the characteristics of the simulating objects. In order to simulate the response characteristics of control system more really, a hardware-in-loop simulation platform of main control systems in the nuclear power plant has been developed in this paper. This simulation platform consists of thermal-hydraulic model, control and protection system model, physical DCS system and real-time interactive database. A physical industrial DCS system has been coupled to this platform to simulate the main control systems in the NPP, which makes the simulation result much closer to the actual control systems. The devoloped simulation platform has been validated by some steady and transient cases in this paper. This hardware-in-loop simulation platform can be used in the simulation and optimal design of NPP control systems. Furthermore, it can be used in the failure mode and effect analysis of the instrumentation and control systems in the nuclear power plant.

Bohunice Nuclear Power Plant Safety Upgrading Program

International Nuclear Information System (INIS)

Toth, A.; Fagula, L.

1996-01-01

Bohunice nuclear Power Plant generation represents almost 50% of the Slovak republic electric power production. Due to such high level of commitment to nuclear power in the power generation system, a special attention is given to safe and reliable operation of NPPs. Safety upgrading and operational reliability improvement of Bohunice V-1 NPP was carried out by the Bohunice staff continuously since the plant commissioning. In the 1990 - 1993 period extensive projects were realised. As a result of 'Small Reconstruction of the Bohunice V-1 NPP', the standards of both the nuclear safety and operational reliability have been significantly improved. The implementation of another modifications that will take place gradually during extended refuelling outages and overhauls in the course of 1996 through 1999, is referred to as the Gradual Reconstruction of the Bohunice V-1 Plant. The general goal of the V-1 NPP safety upgrading is the achievement of internationally acceptable level of nuclear safety. Extensive and financially demanding modification process of Bohunice V-2 NPP is likely to be implemented after a completion of the Gradual Reconstruction of the Bohunice V-1 NPP, since the year 1999. With this in mind, a first draft of the strategy of the Bohunice V-2 NPP upgrading program based on Probabilistic Safety assessment consideration was developed. A number of actions with a general effect on Bohunice site safety is evident. All these activities are aimed at reaching the essential objective of Bohunice NPP Management - to ensure a safe, reliable and effective electric energy and heat generation at the Bohunice site. (author)

Maintaining staff competence-a NPP operator viewpoint

International Nuclear Information System (INIS)

Patrakka, E.

2000-01-01

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

Analysis of the NPP-V1 primary circuit fast cooldown

International Nuclear Information System (INIS)

Filo, J.; Bazso, Z.; Vranka, L.

1994-01-01

Results of thermal-hydraulic calculations of the NPP-V1 primary circuit fast cooldown during small leakage through openings of diameter 20, 32 and 50 mm as well as analyses of cooldown following the steam pipeline break at nominal and null reactor power are given in this paper. 4 refs, 24 figs, 1 tab

IAEA Leads Operational Safety Mission to Smolensk Nuclear Power Plant

International Nuclear Information System (INIS)

2011-01-01

2008 and Rostov NPP in 2005. General information about OSART missions can be found on the IAEA Website. Background An OSART mission is designed as a review of programmes and activities essential to operational safety. It is not a regulatory inspection, nor is it a design review or a substitute for an exhaustive assessment of the plant's overall safety status. Experts participating in the IAEA's June 2010 International Conference on Operational Safety of Nuclear Power Plants (NPP) reviewed the experience of the OSART programme and concluded: In OSART missions NPPs are assessed against IAEA Safety Standards which reflect the current international consensus on what constitutes a high level of safety; and OSART recommendations and suggestions are of utmost importance for operational safety improvement of NPPs. (IAEA)

Training, education and qualification of NPP operating personnel in the Netherlands

International Nuclear Information System (INIS)

de Vrey, G.A.

1987-01-01

This paper outlines the organization and the requirements of the training, education and qualification of NPP operating personnel in the Netherlands. It describes the implementation of a formally required scheme of personnel qualification after TMI, and the current practice as developed by the training staff of both Dutch nuclear power plants. Attention is given to the specific circumstances and problems in the Netherlands, and the resulting program. The licensing criteria for control room operating personnel are discussed, including the level of government involvement. Measures are described to improve the approach to training of NPP personnel involved in safety relevant activities. Finally, some ideas are given for strategies to cope with adverse stress situations

Statistical Study of Corruption in the Region (on the Example of the Rostov Region

Directory of Open Access Journals (Sweden)

Kirill A. Belokrylov

2016-09-01

Full Text Available The paper proves the effectiveness of the using of statistical methods for evaluation of the corruption level as a result of its, on the one hand, latency, concealment of official statistical accounting, and on the other - the scale of corruption in Russia. The comparative analysis of the substantial characteristics of the nature of corruption by Russian and foreign scientists, as well as their reflection in the law has allowed to develop a questionnaire to adequately assess the levels, causes and the effectiveness of implementation of the policy on the fight against corruption as the most important social indicator of inefficient institutions. Analysis of the results of the economic and sociological survey of the population of the Rostov region revealed a shift of corruption performance in the region in the direction of the education system as a result of the dominance in the selection of students, but it led to the conclusion about the need to tighten legislation on the fight against corruption (72% of respondents, including the confiscation of the property (79,1%, the dismissal of corrupt officials, the ban on public office. The necessity of further in-depth statistical studies of corruption on the development of more effective measures is improved to combat it as a tool for removal of the Russian economy from the crisis and ensure that it is more sustainable growth than projected in the 2020s (the lost decade 1,5% positive GDP dynamics.

Application of fieldbus techniques in nuclear power plants

International Nuclear Information System (INIS)

Wang Xu; Chen Hang; Yu Shuxin; Zhang Xinli

2012-01-01

The successful application experience of fieldbus techniques in thermal power plants and nuclear power plants are outlined first. And then, the application of fieldbus techniques in domestic 3rd-generation nuclear power plant (NPP) project is discussed. After that, the solution to the potential problems of fieldbus techniques application in NPP is provided. (authors)

Engineering Center contribution to the Russian NPP aging management

International Nuclear Information System (INIS)

Bougaenko, S.

1993-01-01

The Engineering Center of strength, reliability and life of the nuclear equipment of the Minatom, Russia, has been set up by the decision of the management of the Russian Federation Ministry on the nuclear power (Russia Minatom) within the framework of the Research and Development Institute of Power Engineering (RDIPE). The Engineering Center is responsible for fulfilling the functions of the leading Institution of the Ministry concerning these issues and it is in charge of the development of the appropriate rules and standards package as well as their compliance with analogous international regulating documents. To put forward the national program on NPP aging management, and to implement it is one of the crucial tasks of the Engineering Center. This activity is conducted by both the cooperation between Russian Institution and experts and within the framework of the international collaboration. In the latter case it is worthy of noting the activity with respect to the American-Russian Working Group 12 ''NPP Aging and Life Extension'' and participation in appropriate programs of the IAEA. The major trends of the above activity are considered in this paper

Simulator experiments: effects of NPP operator experience on performance

International Nuclear Information System (INIS)

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

1985-01-01

Experiments are being conducted on nuclear power plant (NPP) control room training simulators by the Oak Ridge National Laboratory, its subcontractor, General Physics Corporation, and participating utilities. The experiments are sponsored by the Nuclear Regulatory Commission's (NRC) Human Factors and Safeguards Branch, Division of Risk Analysis and Operations, and are a continuation of prior research using simulators, supported by field data collection, to provide a technical basis for NRC human factors regulatory issues concerned with the operational safety of nuclear power plants. 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 (a) senior reactor operator (SRO) experience, (b) operating crew augmentation with an STA and (c) practice, as a crew, upon crew and individual operator performance, in response to anticipated plant transients. The FY84 experiments are a partial replication and extension of the FY83 experiment, but with PWR operators and simulator. Methodology and results to date are reported

Axial blanket enrichment optimization of the NPP Krsko fuel

International Nuclear Information System (INIS)

Kromar, M.; Kurincic, B.

2001-01-01

In this paper optimal axial blanket enrichment of the NPP Krsko fuel is investigated. Since the optimization is dictated by economic categories that can significantly vary in time, two step approach is applied. In the first step simple relationship between the equivalent change in enrichment of axial blankets and central fuel region is established. The relationship is afterwards processed with economic criteria and constraints to obtain optimal axial blanket enrichment. In the analysis realistic NPP Krsko conditions are considered. Except for the fuel enrichment all other fuel characteristics are the same as in the fuel used in the few most recent cycles. A typical reload cycle after the plant power uprate is examined. Analysis has shown that the current blanket enrichment is close to the optimal. Blanket enrichment reduction results in an approximately 100 000 US$ savings per fuel cycle.(author)

Safety reassessment of the Paks NPP (the AGNES project)

Energy Technology Data Exchange (ETDEWEB)

Gado, J [Hungarian Academy of Sciences, Budapest (Hungary). Central Research Inst. for Physics; Bajsz, J; Cserhati, A; Elter, J [Paksi Atomeroemue Vallalat, Paks (Hungary); Hollo, E [Energiagazdalkodasi Intezet, Budapest (Hungary); Kovacs, K [EROTERV Engineering and Contractor Co (Hungary); Maroti, L [Hungarian Academy of Sciences, Budapest (Hungary). Central Research Inst. for Physics; Miko, S [Paksi Atomeroemue Vallalat, Paks (Hungary); Techy, Z [Energiagazdalkodasi Intezet, Budapest (Hungary); Vidovszky, I [Hungarian Academy of Sciences, Budapest (Hungary). Central Research Inst. for Physics

1996-12-31

The reassessment of the Paks NPP safety according to internationally recognized criteria of the Advanced General and New Evaluation of Safety (AGNES) project is outlined. The Paks NPP consists of four WWER-440/V-213 units. The following groups of analysis have been performed: system analysis and description; analysis of design basis accidents; severe accidents analysis; level 1 probabilistic safety analysis. Postulated accidents (PA) and Anticipated Operational Occurrences (AOO) are estimated in detail for the following initiating events: increase/decrease in secondary heat removal; decrease in primary coolant inventory; increase/decrease of reactor coolant inventory; reactivity and power distribution anomalies; analysis of transients with the failure of reactor scram (ATWS); pressurized thermal shock analyses. Severe accident analysis was made for the accidents on in-vessel phase and containment phase, for radioactive release and for accident management.

Low-dose effects hypothesis and observations on NPP personal

Energy Technology Data Exchange (ETDEWEB)

Georgieva, R.; Acheva, A.; Boteva, R.; Chobanova, N.; Djounova, J.; Gyuleva, I.; Ivanova, K.; Kurchatova, G.; Milchev, A.; Negoicheva, K.; Nikolov, V.; Panova, D.; Pejankov, I.; Rupova, I.; Stankova, K.; Zacharieva, E. [Radiobiology Department, National Centre of Radiobiology and Radiation Protection, Sofia (Bulgaria)

2013-07-01

In the modern world the use of various sources of ionizing radiation is nearly ubiquitous. They have numerous applications in industry, medicine, science, agriculture, etc. Radiation doses to workers nevertheless are commensurable to the natural background exposure. Published data on the health effects of occupational radiation exposure are often contradictory. Addressing the issue of „negative” (bystander effects, genomic instability) and „positive” (adaptive response, radiation hormesis) effects of low doses is important and has a significant social and economic impact. In this paper we summarize the results of our extensive monitoring of nuclear power plant (NPP) staff. We believe it is a cohort suitable for analysis of health effects at low doses, because of their good medical and dosimetric control. Our results rather support the idea of absence of adverse health effects in NPP workers. (author)

Safety reassessment of the Paks NPP (the AGNES project)

International Nuclear Information System (INIS)

Gado, J.; Hollo, E.; Kovacs, K.; Maroti, L.; Techy, Z.; Vidovszky, I.

1995-01-01

The reassessment of the Paks NPP safety according to internationally recognized criteria of the Advanced General and New Evaluation of Safety (AGNES) project is outlined. The Paks NPP consists of four WWER-440/V-213 units. The following groups of analysis have been performed: system analysis and description; analysis of design basis accidents; severe accidents analysis; level 1 probabilistic safety analysis. Postulated accidents (PA) and Anticipated Operational Occurrences (AOO) are estimated in detail for the following initiating events: increase/decrease in secondary heat removal; decrease in primary coolant inventory; increase/decrease of reactor coolant inventory; reactivity and power distribution anomalies; analysis of transients with the failure of reactor scram (ATWS); pressurized thermal shock analyses. Severe accident analysis was made for the accidents on in-vessel phase and containment phase, for radioactive release and for accident management

Simulation of dynamic response of nuclear power plant based on user-defined model in PSASP

International Nuclear Information System (INIS)

Zhao Jie; Liu Dichen; Xiong Li; Chen Qi; Du Zhi; Lei Qingsheng

2010-01-01

Based on the energy transformation regularity in physical process of pressurized water reactors (PWR), PWR NPP models are established in PSASP (Power System Analysis Software Package), which are applicable for calculating the dynamic process of PWR NPP and power system transient stabilization. The power dynamic characteristics of PWR NPP is simulated and analyzed, including the PWR self-stability, self-regulation and power step responses under power regulation system. The results indicate that the PWR NPP can afford certain exterior disturbances and 10%P n step under temperature negative feedbacks. The regulate speed of PWR power can reach 5%P n /min under the power regulation system, which meets the requirement of peak regulation in Power Grid. (authors)

Ignalina NPP its environment, safety and future, prospects of the energetic, ethnic and cultural situation: expert evaluation

International Nuclear Information System (INIS)

Morkunas, Z. V.; Ciuzas, A.; Jonaitis, V.; Sutiniene, I.

1995-01-01

According to the tasks defined in the 'Atomic Energy and the Environment' program an expert evaluative survey was done for the first time in Lithuania concerning the Ignalina NPP and its consequences and perspectives according to the concept which was prepared. The results of survey analysis, done by Lithuanian experts, are presented. Investigation involved these problems: evolution of the technical state safety, use and prospects of the nuclear power plant; evaluation of the activities of governmental and social institutions in connection with the nuclear power plant; Ignalina NPP and the environment; the effect of the nuclear power plant on agricultural activities and development; evolution of the ethnic and cultural situation; conclusions and recommendations for regulations of those areas. (author). 2 refs., 11 figs

Simulator training and human factor reliability in Kozloduy NPP, Bulgaria

International Nuclear Information System (INIS)

Stoychev, Kosta

2007-01-01

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

Radiation ecological monitoring in NPP region

International Nuclear Information System (INIS)

Egorov, Yu.A.; Kazakov, S.V.

1985-01-01

The known principle of sanitary-hygienic regulation of NPP radiation effect on man and environment is analyzed. An ecological approach is required to optimize NPP relations with the environment and to regulate radioactivity of the NPP - environment system. The ecological approach envisages the development of standards of permissible concentrations of radioactive and chemical substances (as well as heat) in natural environment, taking into account their synergism, corresponding to ecologically permissible response reactions of biota to their effect. The ecological approach also comprises the sanitary-hygienic principle of radiation protection of man. Attention is paid to ecological monitoring in NPP region, comprising consideration of factors, affecting the environment, evaluation of the actual state of the environment, prediction of the environmental state, evaluation of the expected environmental state

Seismic analysis for safety related structures of 900MWe PWR NPP

International Nuclear Information System (INIS)

Liu Wei

2002-01-01

Nuclear Power Plant aseismic design becomes more and more important in China due to the fact that China is a country where earthquakes occur frequently and most of plants arc unavoidably located in seismic regions. Therefore, Chinese nuclear safety authority and organizations have worked out a series of regulations and codes related to NPP anti-seismic design taking account of local conditions. The author presents here an example of structural anti-seismic design of 90GM We PWR NPP which is comprised of: ground motion input, including the principles for ground motion determination and time history generation; soil and upper-structure modelling, presenting modeling procedures and typical models of safety related buildings such as Reactor Building, Nuclear Auxiliary Building and Fuel Building; soil-structure interaction analysis; and in-structure response analysis and floor response spectrum generation. With this example, the author intends to give an overview of Chinese practice in NPP structure anti-seismic design such as the main procedures to be followed and the codes and regulations to be respected. (author)

Safety critical FPGA-based NPP instrumentation and control systems: assessment, development and implementation

International Nuclear Information System (INIS)

Bakhmach, E. S.; Siora, A. A.; Tokarev, V. I.; Kharchenko, V. S.; Sklyar, V. V.; Andrashov, A. A.

2010-10-01

The stages of development, production, verification, licensing and implementation methods and technologies of safety critical instrumentation and control systems for nuclear power plants (NPP) based on FPGA (Field Programmable Gates Arrays) technologies are described. A life cycle model and multi-version technologies of dependability and safety assurance of FPGA-based instrumentation and control systems are discussed. An analysis of NPP instrumentation and control systems construction principles developed by Research and Production Corporation Radiy using FPGA-technologies and results of these systems implementation and operation at Ukrainian and Bulgarian NPP are presented. The RADIY TM platform has been designed and developed by Research and Production Corporation Radiy, Ukraine. The main peculiarity of the RADIY TM platform is the use of FPGA as programmable components for logic control operation. The FPGA-based RADIY TM platform used for NPP instrumentation and control systems development ensures sca lability of system functions types, volume and peculiarities (by changing quantity and quality of sensors, actuators, input/output signals and control algorithms); sca lability of dependability (safety integrity) (by changing a number of redundant channel, tiers, diagnostic and reconfiguration procedures); sca lability of diversity (by changing types, depth and method of diversity selection). (Author)

Environmental impact of the NPP Krsko

International Nuclear Information System (INIS)

Novosel, N.

1996-01-01

The Ministry of Economic Affairs has for six years now been monitoring the operation of the Krsko NPP (NEK) and its impact on the environment. A bulletin titled 'NEK - Energy and Environment' is being issued every three months. It contains information on operation of the Krsko NPP for the previous three months, a graph of duration of temperature increase of water in the Sava river (delta T) in that period, an assessment of the radiological impact of Krsko NPP on the environment through an equivalent dose cumulatively throughout the calendar year, and a short current text related to Krsko NPP. The Ministry of Economic Affairs organizes a press conference on every issue of the bulletin, as an attempt of introducing this subject to the media and to the public. This paper contains a review of information given in the NEK bulletin from 1990 to 1995 with a special emphasis on the contribution of the Krsko NPP to the artificially caused radiation on the border between the Republic of croatia and the Republic of Slovenia. (author)

NPP component maintenance and life management in Russia

International Nuclear Information System (INIS)

Tutnov, I.; Lyssakov, V.

2002-01-01

This report represents the conceptual strategies (ideas) on life management programs for nuclear power plants. Use of the optimum programs for NPP's NDE, maintenance service, operation and service life can provide the best economic benefit for the utilities. The paper presents general approaches to life management, maintenance service, and risks of operating and service life of NPPs in Russia. The report offers some optimized ways for the solution of these important tasks

R and D status for NPP life management in Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Tae Ryong [Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

2009-04-15

The economical benefits may be achieved by the plant life management (PLiM) as well as structural integrity of the critical components of NPP. Systems, structures and components (SSC) of NPP are designed to have safety margins in design stage, and being operated with operational margins. As the plant gets older and older, however, aging of SSC occurs and some of SSC may be sometimes failed due to the unexpected aging mechanisms in design stage. Most countries which have operated NPP have their own R and D programs to establish proper countermeasures against the aging and degradation of SSC, The well known program are materials reliability program (MRP) and steam generator management program (SGMP) of EPRI. In Korea, we also have our own R and D programs for the plant life management. In this paper, the present status of the R and D programs will be introduced. Long term operation of a nuclear power plant is one of the goals that the plant wants to achieve, which may be possible as long as the plant safety is maintained and the economical benefits is expected. The economical benefits may be achieved by the plant life management (PLiM) activities. Many R and D activities related to PLiM have been carried out and implemented to Korean NPP, Kori Unit 1 and Wolsong Unit 1 in particular, for the long term operation beyond their original design lives. Those activities include PLiM study, PSR, SGMP, MRP, thinned pipe management program, study on dissimilar metal welds, aging monitor etc. With the results of R and D activities, continued operation of Kori Unit 1 was successfully started from January 17, 2008 for next 10 years beyond its design life. It must be a landmark of 30 years history of nuclear power generation in Korea. Subsequently Wolsong Unit 1 is also expected to start its continued operation when the replacement of pressure tubes and feeders are completed in 2009. Many countries have plans to build new reactors or to extend the life of operating plants.

R and D status for NPP life management in Korea

International Nuclear Information System (INIS)

Kim, Tae Ryong

2009-01-01

The economical benefits may be achieved by the plant life management (PLiM) as well as structural integrity of the critical components of NPP. Systems, structures and components (SSC) of NPP are designed to have safety margins in design stage, and being operated with operational margins. As the plant gets older and older, however, aging of SSC occurs and some of SSC may be sometimes failed due to the unexpected aging mechanisms in design stage. Most countries which have operated NPP have their own R and D programs to establish proper countermeasures against the aging and degradation of SSC, The well known program are materials reliability program (MRP) and steam generator management program (SGMP) of EPRI. In Korea, we also have our own R and D programs for the plant life management. In this paper, the present status of the R and D programs will be introduced. Long term operation of a nuclear power plant is one of the goals that the plant wants to achieve, which may be possible as long as the plant safety is maintained and the economical benefits is expected. The economical benefits may be achieved by the plant life management (PLiM) activities. Many R and D activities related to PLiM have been carried out and implemented to Korean NPP, Kori Unit 1 and Wolsong Unit 1 in particular, for the long term operation beyond their original design lives. Those activities include PLiM study, PSR, SGMP, MRP, thinned pipe management program, study on dissimilar metal welds, aging monitor etc. With the results of R and D activities, continued operation of Kori Unit 1 was successfully started from January 17, 2008 for next 10 years beyond its design life. It must be a landmark of 30 years history of nuclear power generation in Korea. Subsequently Wolsong Unit 1 is also expected to start its continued operation when the replacement of pressure tubes and feeders are completed in 2009. Many countries have plans to build new reactors or to extend the life of operating plants.

NPP Design Basis Handover and Knowledge Preservation from Subcontractors, Vendors and EPC

International Nuclear Information System (INIS)

Freeland, Kent

2013-01-01

Using PLM-based Workflow for Configuration Management (CM) in the Nuclear Power Industry Advantages – some work to do! • NPP’s must adapt to using PLM-based solutions to support CM and to synchronize design changes to asset or product changes, and reduce “slipstreaming”. In the NPP world, this often appears as events that circumvent CM – for example, non-approved parts substitutions and “temporary” plant modifications that are never removed. • PLM serves as the method for unifying the application of requirements to design changes, processes and workflow. In NPP’s, requirements are generally considered only relevant to designs – not process and workflow. • PLM supports Configuration Management and Design Basis in Regulator Action Tracking for NPP’s, and application of PLM-based CM to regulator action and compliance systems. This is a poorly-understood application of CM in NPP’s, yet these elements control large parts of the NPP design basis. • Suppliers, EPC’s and Technology Vendors must also understand the role of CM, SE and PLM in construction of new standards-driven NPP designs (like EPR and Westinghouse AP-1000 NPP designs), as well as understanding the role and handling of Knowledge Systems

NPP operator support in decision making - diagnostics of the operation failures using fuzzy logic

International Nuclear Information System (INIS)

Petruzela, I.

2000-01-01

In large complex systems such as nuclear power plants (NPP) and chemical industry plants, various subsystems fulfil the needs of process control and safety. Continued operation of these systems has both economic and safety implications. Electric utilities seek continuously to improve the operation of power generating stations. The improvement in the NPP Dukovany (4 x 440 MW) is related to the introduction of the plant to frequency control, meaning that the plant is operated not only in the base load operational mode but in the load follow mode as well. To achieve the improvement of plant operation, it was necessary to provide modifications to the plant control system, plant information system and diagnostics. This chapter deals with utilisation of artificial intelligence (AI) methods in implementation of these plant modifications. (orig.)

Specific problems in Kozloduy municipality, concerning NPP operation and decommissioning

International Nuclear Information System (INIS)

Pironkova, L.

2000-01-01

The only nuclear power plant in Bulgaria, which operates for 25 years is located in Kozloduy. Kozloduy municipality is situated in the northern part of Danube plane, includes the administrative center and four villages. It is 200 km far from Sofia and 80 km from the regional center Vratza. The Kozloduy NPP operates 6 units of total capacity 3760 MW, producing more than 40% of the electricity needs in Bulgaria. Settled and recurring problems of the municipality are related to economic, geographical, demographic and administration issues. Future problems will be related to forthcoming reactor shutdown and decommissioning. This involves economic problems, possible bankruptcies of local firms servicing the NPP, decreasing budget and living standard, expected restrictions of social programs, increasing unemployment, possible changes in demographic structure of population

Seismic characterization of the NPP Krsko site

International Nuclear Information System (INIS)

Obreza, J.

2000-01-01

The goal of NPP Krsko PSA Project Update was the inclusion of plant changes (i.e. configuration/operational related) through the period January 1, 1993 till the OUTAGE99 (April 1999) into the integrated Internal/External Level 1/Level 2 NPP Krsko PSA RISK SPECTRUM model. NPP Krsko is located on seismotectonic plate. Highest earthquake was recorded in 1917 with magnitude 5.8 at a distance of 7-9 km. Site (founded) on Pliocene sediments which are as deep as several hundred meters. No surface faulting at the Krsko site has been observed and thus it is not to be expected. NPP Krsko is equipped with seismic instrumentation, which allows it to complete OBE (SSE). The seismic PSA successfully showed high seismic margin at Krsko plant. NPP Krsko seismic design is based on US regulations and standards

Experience in development and implementation of Control Room continuing training programme at Ignalina NPP

International Nuclear Information System (INIS)

Peradze, K.

2002-01-01

Based on the same SAT principles each NPP (or operating organisation) goes by its own way, which is defined by available resources, assistance, NPP operational conditions, including policy, economics and public opinion. There were several groups of factors, which are very important to provide quality of training- Time, Human Resources and material resources. We pay especial attention to simulator training. In different conditions personnel behaviour is defined by knowledge, rule or skills. It is very difficult to develop unknown to personnel scenarios. But sometimes- real events not described in plant procedures take place at Nuclear Power Plants. Therefore during NPP events analysis we pay a especial attention searching for situation when knowledge or rule defines personnel behaviour. To provide analysis and statistics of Control Room Personnel training at INPP simulator we developed 'INPP events computer data base'. (author)

The virtual digital nuclear power plant: A modern tool for supporting the lifecycle of VVER-based nuclear power units

Science.gov (United States)

Arkadov, G. V.; Zhukavin, A. P.; Kroshilin, A. E.; Parshikov, I. A.; Solov'ev, S. L.; Shishov, A. V.

2014-10-01

The article describes the "Virtual Digital VVER-Based Nuclear Power Plant" computerized system comprising a totality of verified initial data (sets of input data for a model intended for describing the behavior of nuclear power plant (NPP) systems in design and emergency modes of their operation) and a unified system of new-generation computation codes intended for carrying out coordinated computation of the variety of physical processes in the reactor core and NPP equipment. Experiments with the demonstration version of the "Virtual Digital VVER-Based NPP" computerized system has shown that it is in principle possible to set up a unified system of computation codes in a common software environment for carrying out interconnected calculations of various physical phenomena at NPPs constructed according to the standard AES-2006 project. With the full-scale version of the "Virtual Digital VVER-Based NPP" computerized system put in operation, the concerned engineering, design, construction, and operating organizations will have access to all necessary information relating to the NPP power unit project throughout its entire lifecycle. The domestically developed commercial-grade software product set to operate as an independently operating application to the project will bring about additional competitive advantages in the modern market of nuclear power technologies.

Function analysis of automatic power controller in Tianwan Nuclear Power Plant

International Nuclear Information System (INIS)

Zhou Haixiang

2006-01-01

The hardware and software design characters of the automatic power controller (APC) in Tianwan NPP are introduced. According to the analysis of the principle and function of the system, both availability and reliability of APC in Tianwan NPP are proved. The paper also supplies some methods on how to design the digital APC system. (authors)

Some problems of NPP personnel training

International Nuclear Information System (INIS)

Vajshnis, P.P.; Kumkov, L.P.; Omel'chuk, V.V.

1984-01-01

Shortcomings of NPP personnel training are discussed. Development of full-scale training systems is necessary for qualitative training operative personnel. Primary problems that should be necessarily solved for ensuring effective training NPP personnel are considered

Sensitivity Analysis of Evacuation Speed in Hypothetical NPP Accident by Earthquake

Energy Technology Data Exchange (ETDEWEB)

Kim, Sung-yeop; Lim, Ho-Gon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

Effective emergency response in emergency situation of nuclear power plant (NPP) can make consequences be different therefore it is regarded important when establishing an emergency response plan and assessing the risk of hypothetical NPP accident. Situation of emergency response can be totally changed when NPP accident caused by earthquake or tsunami is considered due to the failure of roads and buildings by the disaster. In this study evacuation speed has been focused among above various factors and reasonable evacuation speed in earthquake scenario has been investigated. Finally, sensitivity analysis of evacuation speed in hypothetical NPP accident by earthquake has been performed in this study. Evacuation scenario can be entirely different in the situation of seismic hazard and the sensitivity analysis of evacuation speed in hypothetical NPP accident by earthquake has been performed in this study. Various references were investigated and earthquake evacuation model has been developed considering that evacuees may convert their evacuation method from using a vehicle to walking when they face the difficulty of using a vehicle due to intense traffic jam, failure of buildings and roads, and etc. The population dose within 5 km / 30 km have been found to be increased in earthquake situation due to decreased evacuation speed and become 1.5 - 2 times in the severest earthquake evacuation scenario set up in this study. It is not agreed that using same emergency response model which is used for normal evacuation situations when performing level 3 probabilistic safety assessment for earthquake and tsunami event. Investigation of data and sensitivity analysis for constructing differentiated emergency response model in the event of seismic hazard has been carried out in this study.

Sensitivity Analysis of Evacuation Speed in Hypothetical NPP Accident by Earthquake

International Nuclear Information System (INIS)

Kim, Sung-yeop; Lim, Ho-Gon

2016-01-01

Effective emergency response in emergency situation of nuclear power plant (NPP) can make consequences be different therefore it is regarded important when establishing an emergency response plan and assessing the risk of hypothetical NPP accident. Situation of emergency response can be totally changed when NPP accident caused by earthquake or tsunami is considered due to the failure of roads and buildings by the disaster. In this study evacuation speed has been focused among above various factors and reasonable evacuation speed in earthquake scenario has been investigated. Finally, sensitivity analysis of evacuation speed in hypothetical NPP accident by earthquake has been performed in this study. Evacuation scenario can be entirely different in the situation of seismic hazard and the sensitivity analysis of evacuation speed in hypothetical NPP accident by earthquake has been performed in this study. Various references were investigated and earthquake evacuation model has been developed considering that evacuees may convert their evacuation method from using a vehicle to walking when they face the difficulty of using a vehicle due to intense traffic jam, failure of buildings and roads, and etc. The population dose within 5 km / 30 km have been found to be increased in earthquake situation due to decreased evacuation speed and become 1.5 - 2 times in the severest earthquake evacuation scenario set up in this study. It is not agreed that using same emergency response model which is used for normal evacuation situations when performing level 3 probabilistic safety assessment for earthquake and tsunami event. Investigation of data and sensitivity analysis for constructing differentiated emergency response model in the event of seismic hazard has been carried out in this study

Preferred external power supplies; Fuentes electricas preferentes exteriores

Energy Technology Data Exchange (ETDEWEB)

Martinez Anton, L.

2010-07-01

In June 2008 ANAV and ENDESA DISTRIBUCION (EDE) undertook a joint study of Asco NPP Preferred External Power Supplies (PEPSs) to check the number of lines or power supplies to the 110 kV substation at Asco that met the criteria defined in the power supply regulations applicable to Asco NPP and primarily to confirm compliance with IEEE 765-2006 standard. (Author).

Nuclear power complexes and economic-ecological problems of nuclear power development

International Nuclear Information System (INIS)

Dollezhal', N.A.; Bobolovich, V.N.; Emel'yanov, I.Ya.

1977-01-01

The effect of constructing NPP's at separate sites in densely populated areas on economic efficiency of nuclear power and its ecological implications has been investigated. Locating NPP's and nuclear fuel cycle plants at different sites results in large scale shipments of fresh and spent nuclear fuels and radioactive wastes. The fact increases the risk of a detrimental environmental impact, duration of the external fuel cycle, and worsens, in the end, nuclear power economics. The prudence of creating nuclear parks is discussed. The parks may be especially efficient if the program of developing NPP's with fast breeder reactors is a success. Comparative evaluations show that from economic standpoint deployment of nuclear parks in the European part of the USSR has no disadvantage before construction of separate NPP's and supporting fuel cycle facilities of equivalent capacity, even if the construction of nuclear parks runs dearer by 30% than assumed. The possibility for nuclear parks to meet a part of demand for ''off-peak'' energy production, district heating and process heat production is also shortly discussed

Startup physics tests at Temelin NPP, Unit 1

International Nuclear Information System (INIS)

Sedlacek, M.; Minarcin, M.; Toth, L.; Elko, M.; Hascik, R.

2002-01-01

The objective, scope and proceedings of the physics tests of Temelin NPP, Unit 1 physical commissioning are given in this paper. Furthermore, some results of selected physics tests are presented: reactor initial criticality test, determination of reactor power range for physics testing, measurement of control rod cluster assembly group no. 10 reactivity worth in case of limitation system LS(a) actuation, control rod cluster assembly system reactivity worth measurement with single rod cluster assembly of greatest reactivity worth stuck in fully withdrawn position, measurement of differential reactivity worth of control rod cluster assembly group no. 9, boron 'endpoint' determination and measurement of power reactivity coefficient (Authors)

Slovak Electric, plc, Mochovce Nuclear Power Plant

International Nuclear Information System (INIS)

2000-01-01

In this popular scientific brochure a brief description of history construction of Bohunice Nuclear Power Plant is presented. The chart of electricity generation in WWER 440/V-213 nuclear power plant is described. Operation and safety improvements at Mochovce NPP as well as environment protection are presented. Basic data of Mochovce NPP are included

Role of nuclear engineering in the national power complex

International Nuclear Information System (INIS)

Petros'yants, A.M.; Baturov, B.B.

1981-01-01

Role of nuclear power in power engineering and fuel-power system of the country in the whole is discussed. Economic advantages of NPP's as compared with thermal power plants for district heating (TPP) are grounded. Advisability of combined production of thermal and electric power at TPP as compared with separate heat generation at NPP for district heating and electric power generation at NPP is reported. Data on perspectives of development of nuclear engineering in the light of ''Main directions of economic and social development of the USSR in 1981-1985 and up to 1990'' are presented. It is concluded that nuclear power introduction into national economy would bring important technical, economic and social consequences. Large-scale NPP construction would result in radical revision of the industry structure in the whole fuel-power system including output and transport on the base of modern technology and recent scientific-technical achievements providing essential economic and national economic effect essentially higher labour productivity in fuel power branches of industry. Besides, nuclear engineering creates conditions for better preservation of environment, reduction of expenditures for power and fuel transport, bringing industry centres nearer to centres of energy consumption as well as pre-conditions for removing threat of the so-called ''power hunger'' [ru

75 FR 5355 - Notice of Extension of Comment Period for NUREG-1934, Nuclear Power Plant Fire Modeling...

Science.gov (United States)

2010-02-02

..., Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG), Draft Report for Comment AGENCY... 1019195), Nuclear Power Plant Fire Modeling Application Guide (NPP FIRE MAG), Draft Report for Comment... exists in both the general fire protection and the nuclear power plant (NPP) fire protection communities...

Fuel leak testing performance at NPP Jaslovske Bohunice

International Nuclear Information System (INIS)

Slugen, V.; Krnac, S.; Smiesko, I.

1995-01-01

The NPP Bohunice VVER-440 fuel leak testing experience are relatively extensive in comparison with other VVER-440 users. As the first Europe NPP was adapted Siemens (KWU) in core-sipping equipment to VVER-440 units and since this time were have done these tests also for NPP Paks (Hungary) and NPP Dukovany (Czech Republic). The occurrence of leaking fuel assemblies in NPP is in the last 5 years relatively stabilised and low. A significant difference can be observed between type V-230 (31 leaks) and type V-213 (1 leak). None of of the indicated leaking fuel assemblies has been investigated in the hot cell. Therefore cannot be confirm the effective causes of leak occurrence. Nevertheless, the fuel failure rate and the performance of leak testing in NPP Bohunice are comparable to the world standard at PWR's. 1 tab., 2 figs., 3 refs

Fuel leak testing performance at NPP Jaslovske Bohunice

Energy Technology Data Exchange (ETDEWEB)

Slugen, V; Krnac, S [Slovak Technical Univ., Bratislava (Slovakia); Smiesko, I [Nuclear Powr Plant EBO, Jaslovske Bohuce (Slovakia)

1996-12-31

The NPP Bohunice VVER-440 fuel leak testing experience are relatively extensive in comparison with other VVER-440 users. As the first Europe NPP was adapted Siemens (KWU) in core-sipping equipment to VVER-440 units and since this time were have done these tests also for NPP Paks (Hungary) and NPP Dukovany (Czech Republic). The occurrence of leaking fuel assemblies in NPP is in the last 5 years relatively stabilised and low. A significant difference can be observed between type V-230 (31 leaks) and type V-213 (1 leak). None of of the indicated leaking fuel assemblies has been investigated in the hot cell. Therefore cannot be confirm the effective causes of leak occurrence. Nevertheless, the fuel failure rate and the performance of leak testing in NPP Bohunice are comparable to the world standard at PWR`s. 1 tab., 2 figs., 3 refs.

Preparation for Ignalina NPP decommissioning

International Nuclear Information System (INIS)

Medeliene, D.

2004-01-01

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

Validation of the CORD-2 System for the Nuclear Design Calculations of the NPP Krsko Core

International Nuclear Information System (INIS)

Kromar, M.; Kurincic, B.

2016-01-01

The CORD-2 package intended for core design calculations of PWRs has be recently updated with some improved models. Since the modifications could substantially influence the obtained results, a technical validation process is required. This paper presents comparison of some calculated and measured parameters of the NPP Krsko core needed to qualify the package. Critical boron concentrations at hot full power for selected cycle burnup points and several parameters obtained during the start-up testing at the beginning of each cycle (hot zero power critical concentration, isothermal temperature coefficient and rods worth) for all 27 finished cycles of operation are considered. In addition, assembly-wise power distribution for some selected cycles is checked. Comparison has shown very good agreement of the CORD-2 calculated values with the selected measured parameter of the NPP Krsko core.(author).

IAEA activities and main achievements on human resource management and training of nuclear power plant personnel

International Nuclear Information System (INIS)

Kossilov, A.

2002-01-01

The Nuclear Power Engineering Section is responsible for implementation of the Agency's sub-programme on Engineering and Management Support for Competitive Nuclear Power. The objectives of the sub-programme is to increase Member State capabilities in utilizing the best engineering and management practices for improving NPP performance and competitiveness, optimizing plant service life and decommissioning and strengthening nuclear power infrastructure. NPES' main activities cover: Nuclear power infrastructure, Knowledge management, Personal training and qualification, Quality Management and QA, NPP life management including databases, Modern NPP control and instrumentation, and NPP performance management

Analysis of 14C level around Qinshan NPP base

International Nuclear Information System (INIS)

Huang Renjie; Liang Haiyan; Chen Qianyuan; Ni Shiying; He Jun; Zeng Guangjian; Ma Yongfu

2012-01-01

By using the method of alkaline solution absorption, the activity concentrations of Carbon-14 as well as its variation tendency in air and biological samples were analyzed. The air samples and biological samples were collected around the Qinshan nuclear power plant base (Qinshan NPP Base) in 2002 to 2009 and 2007 to 2009 respectively. The results showed that, since 2002, the annual average activity concentrations of Carbon-14 in air samples were in the range of 38.3 mBq/m 3 to 55.4 mBq/m 3 . Although the monitoring results of Xiajiawan village and Yanliucun village were comparatively higher than the reference site in Hangzhou City, the results were still at the same level. Meanwhile, monitoring results of Xiajiawan village and Yangliucun village in the summer of 2004 and 2005 are relatively high, with the peak value of 55.4 mBq/m 3 appeared in Xiajiawan village during the summer of 2005. Correspondingly the annual airborne Carbon-14 of 2004 and 2005 discharged from the Qinshan NPP 3 rd Phase were higher than normal as well, it can therefore be concluded that the activity concentration of Carbon-14 around the Qinshan NPP Base are related to the discharged source term. The activity concentration of Carbon-14 in rice and leaf vegetable samples from Xiajiawan village and Yangliucun village were slightly higher, but within the same level, than that of Hangzhou. The activity concentration of Carbon-14 in the mullet samples collected from the sea area around Qinshan NPP Base are approximately the same with the sea area of Zhoushan. (authors)

Mochovce NPP safety improvement and completion

International Nuclear Information System (INIS)

1997-01-01

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)

Corporate portal system at PAKS NPP, Hungary

International Nuclear Information System (INIS)

2009-01-01

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)

Transposition of the SQUG methodology to the Belgian NPP(nuclear power station)

International Nuclear Information System (INIS)

Detroux, P.; Aelbrecht, D.; Naisse, J.C.; Greer, J.L.

1991-01-01

The units of a Belgian Nuclear PowerStation had to be seismically reassessed after ten years of operation because the seismic requirements were upgraded from 0.1g to 0.17g free field ground acceleration. Seismic requalification of the active equipment was a critical problem as the current classical methods were too conservative and their application would have lead to unacceptable replacement or reinforcement of a lot of equipment. The approach based on the use of past experience of seismic behavior of non nuclear equipment was chosen; this methodology was developed by the Seismic Qualification Utility Group (SQUG); a group of U.S. utilities and had to be transposed to the Belgian N.P.P. This transposition is described in this paper. It affects different aspects of the methodology. First, the impact of specific requests of the Safety Authorities on the elaboration of the Safe Shutdown Equipment List (SSEL) shall be examined. Then it is explained why the tedious work of specific relay screening was avoided by taking advantage of initial design features for both Instrumentation and Control (I and C) and Electrical power distribution system; the impact on the Electrical SSEL is also described. Afterwards, it is presented how it was possible to conduct a specific existing seismic qualification at 0.1 g free field ground acceleration. Finally, the resolution of specific important problems that arose from the application of the SQUG methodology, is presented such as the definition of the grade level and the conservatism of the classical Amplified Floor Spectra (criterion 1), the calculation of the nozzle loads on mechanical equipment connected to long unbraced piping and the transfer of these loads to the anchorage. (author)

Krsko NPP Periodic Safety Review program

International Nuclear Information System (INIS)

Basic, I.; Spiler, J.; Novsak, M.

2001-01-01

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)

Innovative Approach to Implementation of FPGA-based NPP Instrumentation and Control Systems

Energy Technology Data Exchange (ETDEWEB)

Andrashov, Anton; Kharchenko, Vyacheslav; Sklyar, Volodymir [Centre for Safety Infrastructure-Oriented Research and Analysis, Kharkov (Ukraine); SIORA Alexander [Research and Production Corporation Radiy, Kirovograd (Ukraine)

2011-08-15

Advantages of application of Field Programmable Gates Arrays (FPGA) technology for implementation of Instrumentation and Control (I and C) systems for Nuclear Power Plants (NPP) are outlined. Specific features of FPGA technology in the context of cyber security threats for NPPs I and C systems are analyzed. Description of FPGA-based platform used for implementation of different safety I and C systems for NPPs is presented. Typical architecture of NPPs safety I and C system based on the platform, as well as approach to implementation of I and C systems using FPGA-based platform are discussed. Data on implementation experience of application of the platform for NPP safety I and C systems modernization projects are finalizing the paper.

Innovative approach to implementation of FPGA-based NPP instrumentation and control systems

International Nuclear Information System (INIS)

Andrashov, Anton; Kharchenko, Vyacheslav; Sklyar, Volodymir; Siora, Alexander

2011-01-01

Advantages of application of Field Programmable Gates Arrays (FPGA) technology for implementation of Instrumentation and Control (I and C) systems for Nuclear Power Plants (NPP) are outlined. Specific features of FPGA technology in the context of cyber security threats for NPPs I and C systems are analyzed. Description of FPGA-based platform used for implementation of different safety I and C systems for NPPs is presented. Typical architecture of NPPs safety I and C system based on the platform, as well as approach to implementation of I and C systems using FPGA-based platform are discussed. Data on implementation experience of application of the platform for NPP safety I and C systems modernization projects are finalizing the paper. (author)

Innovative Approach to Implementation of FPGA-based NPP Instrumentation and Control Systems

International Nuclear Information System (INIS)

Andrashov, Anton; Kharchenko, Vyacheslav; Sklyar, Volodymir; SIORA Alexander

2011-01-01

Advantages of application of Field Programmable Gates Arrays (FPGA) technology for implementation of Instrumentation and Control (I and C) systems for Nuclear Power Plants (NPP) are outlined. Specific features of FPGA technology in the context of cyber security threats for NPPs I and C systems are analyzed. Description of FPGA-based platform used for implementation of different safety I and C systems for NPPs is presented. Typical architecture of NPPs safety I and C system based on the platform, as well as approach to implementation of I and C systems using FPGA-based platform are discussed. Data on implementation experience of application of the platform for NPP safety I and C systems modernization projects are finalizing the paper

On application of the systematic approach to training in Qinshan NPP

International Nuclear Information System (INIS)

Wang Riqing

1997-01-01

The author describes the feature of systematic approach to training and introduces the situation about using the approach for training operation and maintenance personnel in Qinshan NPP. The final part of paper shows that there are still some problems worthy of serious consideration in application of the systematic approach to training in nuclear power plant

Development of Tsunami PSA method for Korean NPP site

International Nuclear Information System (INIS)

Kim, Min Kyu; Choi, In Kil; Park, Jin Hee

2010-01-01

A methodology of tsunami PSA was developed in this study. A tsunami PSA consists of tsunami hazard analysis, tsunami fragility analysis and system analysis. In the case of tsunami hazard analysis, evaluation of tsunami return period is major task. For the evaluation of tsunami return period, numerical analysis and empirical method can be applied. The application of this method was applied to a nuclear power plant, Ulchin 56 NPP, which is located in the east coast of Korean peninsula. Through this study, whole tsunami PSA working procedure was established and example calculation was performed for one of real nuclear power plant in Korea

Nuclear power plant V-1

International Nuclear Information System (INIS)

1999-01-01

In this leaflet the short history of commissioning of Bohunice V-1 NPP is reviewed (beginning of construction 24 April 1972; First controlled reactor power, Reactor Unit 1 (RU1): 27 November 1978, Reactor Unit 2 (RU2): 15 March 1980; Connection to the grid: RU1 17 December 1978, RU2 26 March 1980; Commercial operation: RU1 1 April 1980, RU2 7 January 1981. The scheme of the nuclear reactor WWER 440/V230 is depicted. The major technological equipment (primary circuit, nuclear reactor, steam generators, reactor coolant pumps, primary circuit auxiliary systems, secondary circuit, turbine generators, NPP electrical equipment, and power plant control) are described. Technical data of the Bohunice V-1 NPP are presented

External flood probabilistic safety analysis of a coastal NPP

International Nuclear Information System (INIS)

Pisharady, Ajai S.; Chakraborty, M.K.; Acharya, Sourav; Roshan, A.D.; Bishnoi, L.R.

2015-01-01

External events pose a definitive challenge to safety of NPP, solely due to their ability to induce common cause failures. Flooding incidents at Le Blayais NPP, France, Fort Calhoun NPP, USA and Fukushima Daiichi have pointed to the importance of external flooding as an important contributor to NPP risk. A methodology developed for external flood PSA of a coastal NPP vulnerable to flooding due to tsunami, cyclonic storm and intense local precipitation is presented in this paper. Different tasks for EFPSA has been identified along with general approach for completing each task

Demographic and health characteristics of the population residing within the 30-km area around the Kozloduy NPP

International Nuclear Information System (INIS)

Dimitrov, P.; Bliznakov, V.

1993-01-01

Based on detailed analysis of data on demographic and health state of the population residing within the 30-km zone around the Kozloduj NPP, an attempt was made to detect any impact of the power plant on population health under normal NPP operational conditions. The health characteristics of the population revealed no unfavorable trends. Particular attention was given to diseases of the blood and blood-forming organs, malignant new growths, complications of pregnancy, and congenital anomalies. (author)

Predisposal of Radioactive Waste from NPP 1000 MWe

International Nuclear Information System (INIS)

Suryantoro

2007-01-01

Predisposal of radioactive waste from NPP 1000 MW which was planned to be operated in 2016 has been conducted. In this study NPP applying PWR type was assumed. This assessment comprises all aspects of radioactive waste coming from NPP. One through cycle was chosen consequently no reprocessing step will be conducted. The assessment shows that technologically all radioactive waste treatment process rising from NPP operation has similarities to the existing radioactive waste process conducted by RWI which has lower scale of waste amount. (author)

Review report on the dynamical study of the main building of the Paks NPP

International Nuclear Information System (INIS)

Gatti, F.

1995-01-01

The present report deals with the review of the report 'Dynamical Study of the main building of the Paks NPP', issued by Paks NPP (Hungary) on April, 1993, within the frame of the IAEA benchmark study for the seismic analysis and testing of an existing Nuclear Power Plant (M), and on behalf of ENEL DSR/VDN Rome, in the aims of the nuclear activities of ENEL DSR/VDN (Rome). After a foreword to define the aims of the job (Chapter 1) and the identification of the scope of the work (Chapter 2), a short list of references is given (Chapter 3). In Chapter 4, the criteria followed in the review activity are listed; in Chapter 5, the contents of the Paks NPP report are summarized. In Chapter 6 the results of the review are given, while the main conclusions of the review activities are summarized in the Chapter 7. (author)

Study on regimes of nuclear power plants with WWER-type reactors

International Nuclear Information System (INIS)

Akkerman, G.; Khampel', R.; Khentshel', G.; Kertsher, F.; Lyuttsov, K.

1976-01-01

The problems are considered of optimization of nuclear fuel loading, the peculiarities of the NPP operation at decreased power, and also the problem of stability operation of NPP with WWER type reactors taking into account specific features of these reactors (partial fuel overloads, change in reactor reactivity with power changes). The two particular interconnected problems discussed are: choice of such a sequence of partial rechargings which ensures the minimum cost of the electric power generated, and increasing the reactor operating time by reducing its power output. Besides the technical and economic estimates, much attention is given to analysing the stability of NPP operation

Application of ant colony optimization in NPP classification fault location

International Nuclear Information System (INIS)

Xie Chunli; Liu Yongkuo; Xia Hong

2009-01-01

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)

Improvement of coal focus and cooling towers of COFRENTES NPP

International Nuclear Information System (INIS)

Martinez, I.; Bogh, P.

1998-01-01

Cofrentes Nuclear Power Plant is performing a improving program of its cooling towers based on the filling revamping and cooling water circuit improvement. Furthermore, and as consequence of the acquired experience on cooling towers due to the mentioned program, Cofrentes NPP has decided to follow up with this project from a different point of view based on the thermal-hydraulic optimization of the cooling process inside the towers. This program, which is going to be carried out by Cofrentes NPP, Iberinco and Energy Planning and Power Generation (EPPG) provides an improvement on the thermal profile and of the draught inside the cooling towers by improving the water distribution in the towers active area. In order to perform such a program is needed to fulfill a test program to assure a guaranteed performance gain. In this way, Iberinco is developing a test procedure which improves the results which are obtained with the present standards used commonly by the industry. As a consequence of this program, Cofrentes is expecting to obtain a gain of 5 to 8 MWe with a revenue period of 4 to 5 months, results validated in another foreigner Plant which have developed a similar program. (Author)

Operation safety at Ignalina NPP

International Nuclear Information System (INIS)

Zheltobriukh, G.

1999-01-01

An improvement of operational safety at Ignalina NPP covers: improvement of management structure and safety culture; symptom-based emergency operating procedures; staff training and full scope simulator; program of components ageing; metal inspection; improvement of fire safety. The first plan of Ignalina NPP Safety culture development for 1997 purposed to the SAR recommendation implementation was prepared and approved by the General Director

[Phylogenetic analysis of genomes of Vibrio cholerae strains isolated on the territory of Rostov region].

Science.gov (United States)

Kuleshov, K V; Markelov, M L; Dedkov, V G; Vodop'ianov, A S; Kermanov, A V; Pisanov, R V; Kruglikov, V D; Mazrukho, A B; Maleev, V V; Shipulin, G A

2013-01-01

Determination of origin of 2 Vibrio cholerae strains isolated on the territory of Rostov region by using full genome sequencing data. Toxigenic strain 2011 EL- 301 V. cholerae 01 El Tor Inaba No. 301 (ctxAB+, tcpA+) and nontoxigenic strain V. cholerae O1 Ogawa P- 18785 (ctxAB-, tcpA+) were studied. Sequencing was carried out on the MiSeq platform. Phylogenetic analysis of the genomes obtained was carried out based on comparison of conservative part of the studied and 54 previously sequenced genomes. 2011EL-301 strain genome was presented by 164 contigs with an average coverage of 100, N50 parameter was 132 kb, for strain P- 18785 - 159 contigs with a coverage of69, N50 - 83 kb. The contigs obtained for strain 2011 EL-301 were deposited in DDBJ/EMBL/GenBank databases with access code AJFN02000000, for strain P-18785 - ANHS00000000. 716 protein-coding orthologous genes were detected. Based on phylogenetic analysis strain P- 18785 belongs to PG-1 subgroup (a group of predecessor strains of the 7th pandemic). Strain 2011EL-301 belongs to groups of strains of the 7th pandemic and is included into the cluster with later isolates that are associated with cases of cholera in South Africa and cases of import of cholera to the USA from Pakistan. The data obtained allows to establish phylogenetic connections with V cholerae strains isolated earlier.

Individual protection of NPP personnel

International Nuclear Information System (INIS)

Koshcheev, V.S.; Gol'dshtejn, D.S.; Chetverikova, Z.S.

1983-01-01

Specific features of NPP personnel individual protection are considered, mainly with respect to maintenance and repair works on various type reactors. The major concern is given to the selection and application reglamentations of the individual protection system (IPS), employment of sanitary locks, the organization of individual protection under the conditions of a heating microclimate. The ways are specified to the development and introduction of the most effective IPS and improvement of the entire NPP personnel individual protection system with respect to providing the necessary protection effect for maintaining high working capability of the personnel and minimizing the IPS impact on human organism functional systems. The accumulated experience in the personnel individual protection can be applied during construction and operation of NPP's in CMEA member-countries [ru

Safety critical FPGA-based NPP instrumentation and control systems: assessment, development and implementation

Energy Technology Data Exchange (ETDEWEB)

Bakhmach, E. S.; Siora, A. A.; Tokarev, V. I. [Research and Production Corporation Radiy, 29 Geroev Stalingrada Str., Kirovograd 25006 (Ukraine); Kharchenko, V. S.; Sklyar, V. V.; Andrashov, A. A., E-mail: marketing@radiy.co [Center for Safety Infrastructure-Oriented Research and Analysis, 37 Astronomicheskaya Str., Kharkiv 61085 (Ukraine)

2010-10-15

The stages of development, production, verification, licensing and implementation methods and technologies of safety critical instrumentation and control systems for nuclear power plants (NPP) based on FPGA (Field Programmable Gates Arrays) technologies are described. A life cycle model and multi-version technologies of dependability and safety assurance of FPGA-based instrumentation and control systems are discussed. An analysis of NPP instrumentation and control systems construction principles developed by Research and Production Corporation Radiy using FPGA-technologies and results of these systems implementation and operation at Ukrainian and Bulgarian NPP are presented. The RADIY{sup TM} platform has been designed and developed by Research and Production Corporation Radiy, Ukraine. The main peculiarity of the RADIY{sup TM} platform is the use of FPGA as programmable components for logic control operation. The FPGA-based RADIY{sup TM} platform used for NPP instrumentation and control systems development ensures sca lability of system functions types, volume and peculiarities (by changing quantity and quality of sensors, actuators, input/output signals and control algorithms); sca lability of dependability (safety integrity) (by changing a number of redundant channel, tiers, diagnostic and reconfiguration procedures); sca lability of diversity (by changing types, depth and method of diversity selection). (Author)

Influence of the CVCS Modelling on Results of the Loss of Offsite Power (LOOP) Safety Analysis for NPP Krsko

International Nuclear Information System (INIS)

Bencik, V.; Bajs, T.; Debrecin, N.

2006-01-01

A Loss of Offsite Power (LOOP) transient scenario is based on a complete loss of non-emergency AC power that results in the loss of all power to the plant auxiliaries, i.e., the Reactor Coolant Pumps (RCPs), condensate pumps, etc. An actual LOOP event would cause a loss of all feedwater, a loss of forced Reactor Coolant System (RCS) flow and a reactor trip within less than 2 seconds as a result of either loss of power to the rod cluster assembly gripper coils or any RCS flow trips. For safety analysis purposes the LOOP event is conservatively modelled as a Loss of Normal Feedwater (LONF) transient with a subsequent loss of offsite power as a result of a reactor trip. The reactor trip followed by RCP trip are delayed until a low-low Steam Generator (SG) level signal is reached. This is a more conservative scenario than the LOOP event because the least amount of SG secondary side water mass available for heat removal and the increased amount of the stored energy in the primary circuit at the time of the loss of RCS flow result. The standard LOOP safety analysis is aimed to demonstrate the natural circulation capability of the RCS to remove residual and decay heat from the core aided by Auxiliary Feedwater in the secondary system. In addition to this goal the presented work is aimed to resolve the potential safety issue resulting from the influence of the Chemical and Volume Control System (CVCS) operation during LOOP event for NPP Krsko. The potential safety concern for the LOOP analysis is that the loss of instrument air system may occur thus leading to the CVCS charging and letdown flow imbalance. A net RCS inventory addition may result with water solid pressurizer condition. Water discharge through the pressurizer relief and safety valves could lead to overpressurization of the Pressurizer Relief Tank (PRT) and rupture of the PRT rupture disks. Additional concern is that pressurizer relief and safety valves may fail to properly reseat when exposed to water relief

Methods and means for improving the man-machine systems for NPP control

International Nuclear Information System (INIS)

Konstantinov, L.V.; Rakitin, I.D.

1984-01-01

Consideration is being given to the role of ''human factors'' and the ways of improving the man-machine interaction in NPP control and safety systems (CSS). Simulators and tAaining equipment on the basis of dynamic power unit models used for training and improving skill of NPP operatoAs, as well as for mastering collective actions of personnel under accidental conditions are considered in detail. The most perfect program complexes for fast NPP diagnostics and theiA pealization in the Federal Republic of Germany, Japan, Canada, the USA and other countries are described. A special attention is paid to the means and methods of videoterminal dialogue operator interaction with an object both in normal and extreme situations. It is noted that the problems of the man-machine interaction have become the subject of study only in the end of 70s after analyzing the causes of the Three-Mile-Island accident (USA). Publications dealing with the development of perspective control rooms for NPP were analyzed. It was concluded that radical changes both in equipment and principles of organizing the personnel activity will take place in the nearest future. They will be based on the progress in creating dialogue means and computers of the fourth and fifth generations as well as on engineering and psychological and technical aspects of designing

Probabilistic assessment of NPP safety under aircraft impact

International Nuclear Information System (INIS)

Birbraer, A.N.; Roleder, A.J.; Arhipov, S.B.

1999-01-01

Methodology of probabilistic assessment of NPP safety under aircraft impact is described below. The assessment is made taking into account not only the fact of aircraft fall onto the NPP building, but another casual parameters too, namely an aircraft class, velocity and mass, as well as point and angle of its impact with the building structure. This analysis can permit to justify the decrease of the required structure strength and dynamic loads on the NPP equipment. It can also be especially useful when assessing the safety of existing NPP. (author)

Professional adaptability of nuclear power plant operators

International Nuclear Information System (INIS)

He Xuhong; Huang Xiangrui

2006-01-01

The paper concerns in the results of analysis for nuclear power plant (NPP) operator job and analysis for human errors related NPP accidents. Based on the principle of ergonomics a full psychological selection system of the professional adaptability of NPP operators including cognitive ability, personality and psychological health was established. The application way and importance of the professional adaptability research are discussed. (authors)

Frequency response analysis of NPP containment with WWER-1000 type reactor

International Nuclear Information System (INIS)

Zoubkov, D.; Isaikin, A.; Shablinsky, G.

2005-01-01

Analysis of vibration load on the building structures of nuclear power plants (NPP) has come to the fore due to extension of their operational lifetime. Such analysis could be carried out if dynamic characteristics test (natural vibration frequency and natural mode) of NPP building structures is conducted in full-scale conditions. In this paper we represent methods of frequency response analysis of the generating unit 1 (RO-1) reactor compartment at Kalininskaya NPP on the basis of technogenic vibration. Main vibration sources of RO-1 are turbine-type generators, main centrifugal pumps and pipelines of power generating units 1 and 2. Vibration of RO-1 has been measured alternately at three points of RO-1 containment which is 76 m high and 47.4 m in diameter: top of the dome (76.0 m), holdout ring (70.3 m), point on the ground next to containment (0.0 m). Three components of vibration velocity have been measured simultaneously at each point: vertical Z-component, horizontal Y-component along the axis of the apparatus room and horizontal X-component across the room axis. Magnetoelectric pendulum-type vibrometers have been used for measurement. They were modernized by ad hoc multiposition amplifier card installed into the sensor body. Vibrometers were connected to the recorder by vibration protected and jam resistant cables. The results of present researches testified that dominant frequencies of X- and Y-oscillation spectra at RO-1 of Kalininskaya NPP (1.7 and 1.9 Hz correspondingly) correspond to the first vibration mode of RO-1 as a rigid construction on elastic foundation. High peaks of spectra at 16.7 and 25 Hz result from vibrations caused by main centrifugal pumps and turbine-type generators and coincide with the number of their revolutions per minute (1000 and 1500 rpm). Other peaks of spectra are related to the vibration of pipelines of primary and secondary circuits. (authors)

NPP Bohunice experience with ASSET services

Energy Technology Data Exchange (ETDEWEB)

Klimo, J [Bohunice NPP (Slovakia)

1997-12-31

The general description of Bohunice NPP ASSET experience history was given at the last annual workshop in 1995. In my short presentation I would like to pay attention to the progress in this area which was achieved at our NPP during the last year. (author).

NPP Bohunice experience with ASSET services

International Nuclear Information System (INIS)

Klimo, J.

1996-01-01

The general description of Bohunice NPP ASSET experience history was given at the last annual workshop in 1995. In my short presentation I would like to pay attention to the progress in this area which was achieved at our NPP during the last year. (author)

Seismic response analysis of Wolsung NPP structure and equipment subjected to scenario earthquakes

Energy Technology Data Exchange (ETDEWEB)

Choi, In Kil; Ahn, Seong Moon; Choun, Young Sun; Seo, Jeong Moon

2005-03-15

The standard response spectrum proposed by US NRC has been used as a design earthquake for the design of Korean nuclear power plant structures. However, it does not reflect the characteristic of seismological and geological of Korea. In this study, the seismic response analysis of Wolsung NPP structure and equipment were performed. Three types of input motions, artificial time histories that envelop the US NRC Regulatory Guide 1.60 spectrum and the probability based scenario earthquake spectra developed for the Korean NPP site and a typical near-fault earthquake recorded at thirty sites, were used as input motions. The acceleration, displacement and shear force responses of Wolsung containment structure due to the design earthquake were larger than those due to the other input earthquakes. But, considering displacement response increases abruptly as Wolsung NPP structure does nonlinear behavior, the reassessment of the seismic safety margin based on the displacement is necessary if the structure does nonlinear behavior; although it has adequate the seismic safety margin within elastic limit. Among the main safety-related devices, electrical cabinet and pump showed the large responses on the scenario earthquake which has the high frequency characteristic. This has great effects of the seismic capacity of the main devices installed inside of the building. This means that the design earthquake is not so conservative for the safety of the safety related nuclear power plant equipments.

Seismic response analysis of Wolsung NPP structure and equipment subjected to scenario earthquakes

International Nuclear Information System (INIS)

Choi, In Kil; Ahn, Seong Moon; Choun, Young Sun; Seo, Jeong Moon

2005-03-01

The standard response spectrum proposed by US NRC has been used as a design earthquake for the design of Korean nuclear power plant structures. However, it does not reflect the characteristic of seismological and geological of Korea. In this study, the seismic response analysis of Wolsung NPP structure and equipment were performed. Three types of input motions, artificial time histories that envelop the US NRC Regulatory Guide 1.60 spectrum and the probability based scenario earthquake spectra developed for the Korean NPP site and a typical near-fault earthquake recorded at thirty sites, were used as input motions. The acceleration, displacement and shear force responses of Wolsung containment structure due to the design earthquake were larger than those due to the other input earthquakes. But, considering displacement response increases abruptly as Wolsung NPP structure does nonlinear behavior, the reassessment of the seismic safety margin based on the displacement is necessary if the structure does nonlinear behavior; although it has adequate the seismic safety margin within elastic limit. Among the main safety-related devices, electrical cabinet and pump showed the large responses on the scenario earthquake which has the high frequency characteristic. This has great effects of the seismic capacity of the main devices installed inside of the building. This means that the design earthquake is not so conservative for the safety of the safety related nuclear power plant equipments

Inspection Qualification Centre in NPP 'Kozloduy'

International Nuclear Information System (INIS)

Mikhovski, M.

2000-01-01

In May 1999 according to the working plan of the IAEA project RER 4/020 and the decision of the NPP the Inspection Qualification Centre (IQC) has been established in order to provide examination services in the NPP. During year 1999 IVC (AEA Technology) in the framework of the DTI project provides consulting and technical assistance to the NPP, IQC, Bulgarian Academy of Sciences and Regulatory Authorities in setting up the IQC infrastructure. Now IQC work as an independent inspection body B type. The IQC activities for the period 1999-2000 are presented and further tasks are outlined

Operating experience of the automatic technological control system at the Kolsk NPP

International Nuclear Information System (INIS)

Volkov, A.P.; Ignatenko, E.I.; Kolomtsev, Yu.V.; Mel'nikov, E.F.; Trofimov, B.A.

1981-01-01

Briefly reviewed is operating experience of the automatic control systems of the kolsk NPP (KNPP) power units, where measuring technique of the neutron flux ''Iney'', ARM-4 power regulator, automatic turbine start-up system ATS are used. The main shortcomings of the technological process automatic control system (ACS) and ways of their removal are considered. It is noted that the KNPP ACS performs only limited start-up functions of the basic equipment and reactor power control as well as partially protection functions at instant loading drops and switch-off of the main circulating pump [ru

Metamorphosis of NPP A1, V1, V2

International Nuclear Information System (INIS)

Dobak, D.; Moncekova, M.

2005-01-01

In this book the history of construction, commissioning and exploitation of NPP A1, NPP V1 and NPP V2 in Jaslovske Bohunice is presented on documentary photos. Vicinity around of these NPPs is presented, too

Suspension of the NPP ''Zarnowiec'' erection in opinion of the Regulatory Body

International Nuclear Information System (INIS)

Jozefowicz, E.T.

1990-01-01

The author attempts to review on behalf of The Regulatory Body, the Government's decision to suspend erection of the NPP ''Zarnowiec'' for one year. The current state of the erection and abilities (under new conditions) of the investor being still legally responsible for nuclear safety of the future power plant are analysed

Nuclear power plant V-1

International Nuclear Information System (INIS)

1998-01-01

The nuclear power plant Bohunice V -1 is briefly described. This NPP consists from two reactor units. Their main time characteristics are (Reactor Unit 1, Reactor Unit 2): beginning of construction - 24 April 1972; first controlled reactor power - 27 November 1978, 15 March 1980; connection to the grid - 17 December 1978, 26 March 1980; commercial operation - 1 April 1980, 7 January 1981. This leaflet contains: NPP V-1 construction; Major technological equipment (Primary circuit: Nuclear reactor [WWER 440 V230 type reactor];Steam generator; Reactor Coolant Pumps; Primary Circuit Auxiliary Systems. Secondary circuit: Turbine generators, Nuclear power plant electrical equipment; power plant control) and technical data

Sociological investigations on Ignalina NPP and within its surroundings

International Nuclear Information System (INIS)

Chiuzhas, A.

1998-01-01

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)

Experience Practices on Decontamination Activity in NPP Decommissioning

Energy Technology Data Exchange (ETDEWEB)

Yoon, Suk Bon; Kim, Jeongju; Sohn, Wook [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

2016-10-15

Decommissioning of a nuclear power plant (NPP) involves various technical and administrative activities for a utility to terminate its license, which allows the plant site to be released from the regulatory control (site release). Decontamination activity in NPP decommissioning is one of the main technical activities to be performed during the decommissioning. The decontamination at decommissioning sites is usually performed due to several reasons such as reducing personnel dose and disposal costs, and cleanup to meet license termination requirements by using physical or chemical removal techniques proven through the previous experience practices. This paper introduces the best and worst practices for the decontamination activities collected from the decommissioning operational experiences through the implementation of nuclear decommissioning projects around the world. Review of the experiences of decontamination shows that it is important to conduct an advanced planning for optimized implementation of decontamination taking into considering site specific conditions such as operating time, reactor type, system, and so on. Also, a review of newer decontamination methods is necessary to safely and economically decommission the nuclear facility.

Ageing management database development for PWR NPP steam generator

International Nuclear Information System (INIS)

Liu Hongyun; Xu Liangjun; Xiong Changhuai; Wang Xianyuan

2005-01-01

Steam generator (SG) is one of the key safe important equipment of NPP, which is covered by NPP aging management program. Steam Generator Aging Management Dabatase (SGAMDB) is developed to provide necessary information for SG aging management. RINPO is developing SGAMDB for domestic NPP. This system contains information and data about SG design, manufacture, operation and maintenance. The information include NPP fundamental data, SG design data, SG aging mechanism, SG operation data, SG ISI data, SG maintenance data and SG evaluation interface. The system runs at the intranet of Qinshan-1 NPP with B/S mode. It can provide information inquire and fundamental analysis for NPP SG aging team and SG aging researcher's. In addition, it provides necessary information and data for SG aging analysis and evaluation, such as all pressure test process and flaws of tubes, and collects the analysis results. (authors)

Pre feasibility assesment of smart off shore NPP (ONPP) of gravity based-structure type for Indonesia

International Nuclear Information System (INIS)

Sahala M Lumbanraja; Dharu Dewi

2017-01-01

The SMART ONPP GBS-type is a small power (100 MWe) pressurized water reactor, and located at offshore site. This technology was developed based on existing SMART nuclear technology & offshore drilling technology with a gravity-based type of structure. This is a response to the post-Fukushima accident, Japan (2011), to improve the safety system, overcome the land limitations, and minimize the public resistance to NPP cases in the inland. The purpose of this paper is to assess the pre-feasibility of the implementation of GBS NPP in Indonesia both in terms of technological feasibility and regulation. The method used is literature review and continued with descriptive analysis. The result shows that SMART ONPP are worth considering because they offer improved aspects of safety, offshore tread availability, and better public acceptance. So far, this NPP can not be implemented in Indonesia because it is hampered by Government Regulation No. 2 year 2014 regarding Licensing of Nuclear Installation Safety and Security which stipulates that site is an inland location and NPP built in Indonesia should be proven. (author)

Resin intrusion into the primary circuit of NPP Jaslovske Bohunice V-1

International Nuclear Information System (INIS)

Grezdo, O.; Mraz, V.

2005-01-01

During the refueling at the first unit of Bohunice NPP in 2005 a lot of sediment was found on the upper storage rack. This sediment was identification as a filter resin. Resin was found in most of the fuel assemblies, pipes and tanks of the primary circuit and his auxiliary systems. Resin producer and WANO network was contacted in order to get information about similar events. Management of Bohunice NPP made a decision that primary circuit, fuel assemblies and auxiliary systems have to be cleaned. Subsequent cleaning extended outage by 31 days. This paper summarizes causes, existing consequences and corrective actions. Accent was put on the hydraulic characteristics of the primary circuit measurement, power distribution core monitoring and the primary circuit water quality verification (Authors)

Satellite infrared imagery for thermal plume contamination monitoring in coastal ecosystem of Cernavoda NPP

Science.gov (United States)

Zoran, M. A.; Zoran, Liviu Florin V.; Dida, Adrian I.

2017-10-01

Satellite remote sensing is an important tool for spatio-temporal analysis and surveillance of NPP environment, thermal heat waste of waters being a major concern in many coastal ecosystems involving nuclear power plants. As a test case the adopted methodology was applied for 700x2 MW Cernavoda nuclear power plant (NPP) located in the South-Eastern part of Romania, which discharges warm water affecting coastal ecology. The thermal plume signatures in the NPP hydrological system have been investigated based on TIR (Thermal Infrared) spectral bands of NOAA AVHRR, Landsat TM/ETM+/OLI, and MODIS Terra/Aqua time series satellite data during 1990-2016 period. If NOAA AVHRR data proved the general pattern and extension of the thermal plume signature in Danube river and Black Sea coastal areas, Landsat TM/ETM and MODIS data used for WST (Water Surface Temperature) change detection, mapping and monitoring provided enhanced information about the plume shape, dimension and direction of dispersion in these waters. Thermal discharge from two nuclear reactors cooling is dissipated as waste heat in Danube-Black -Sea Channel and Danube River. From time-series analysis of satellite data during period 1990-2016 was found that during the winter season thermal plume was localized to an area of a few km of NPP, and the mean temperature difference between the plume and non-plume areas was about 1.7 oC. During summer and fall, derived mean temperature difference between the plume and non-plume areas was of about 1.3°C and thermal plume area was extended up to 5- 10 km far along Danube Black Sea Channel.

Strategy for decommissioning of NPP's in Germany

International Nuclear Information System (INIS)

Rittscher, D.; Sterner, H.

2003-01-01

According to German Atomic Law, two different strategies are possible, i.e. direct dismantling and safe enclosure before dismantling. Both approaches have their advantages and disadvantages. Taking into account the site and plant specific conditions the optimal strategy can be evaluated. Both approaches have been applied in Germany in the past. The German Atomic Law and the Radiation Protection Ordinance (June 2002) were adapted recently (July 2002). Additionally, the life operation time of the German NPP's was fixed in a new law (April 2002): Orderly Termination of the Commercial Production of Nuclear Electricity. These issues have made it necessary for the power utilities to review the strategies applied. As long as the final disposal in Germany is still an open issue, the construction of local Interim Stores is necessary to be able to dismantle a NPP. The basic strategies are not excluding each other and it seems clear today, that the optimal approach is a combination of these strategies, e.g. dismantling of all auxiliary systems and leaving activated parts for a longer SE period. Within this approach the advantages of both basic strategies have been integrated in one. The EWN GmbH has developed such integrated but still different approaches for the decommissioning projects of the Kernkraftwerke Greifswald (KGR) and the Arbeitsgemeinschaft Versuchsreaktor (AVR) Juelich. It can be stated that the decommissioning of a NPP does not present technical issues of concern, but is more a project management issue, although surrounded by sometime intricate political and juridical boundary conditions. A major strategy change is to be expected only when final disposal capacities are available in the future. (authors)

Organization of monitoring of agricultural products in NPP region

International Nuclear Information System (INIS)

Panteleev, L.I.; Spirin, E.V.; Sanzharova, N.I.

1990-01-01

Problem of organizing chemical and radiation monitoring of agricultural products in NPP region is considered. Attention is paid to monitoring during NPP siting and designing, to monitoring of radioactive contamination of agricultural products under normal NPP operation, emergency situations and decommissioning

Chernobyl NPP accident: a year later

International Nuclear Information System (INIS)

Asmolov, V.G.; Borovoj, A.A.; Demin, V.F.

1988-01-01

Consideration is being given to measures on liquidation of Chernobyl accident aftereffects, conducted since August, 1986. One of the most important measures lay in construction of the ''shelter'', which must provide long-term conservation of accidental unit. Works on decontamination of reactor area and contaminated populated regions were continued. Measures on providing safety of population and its health protection were performed. An attention was paid to long-term investigations on studying delayed aftereffects of the accident, monitoring of invironment, development and introduction of measures on improving NPP safety. Prospects of further development of nuclear power engeneering and possibilities of improving its safety are considered

Calculation of NPP pipeline seismic stability

International Nuclear Information System (INIS)

Kirillov, A.P.; Ambriashvili, Yu.K.; Kaliberda, I.V.

1982-01-01

A simplified design procedure of seismic pipeline stability of NPP at WWER reactor is described. The simplified design procedure envisages during the selection and arrangement of pipeline saddle and hydraulic shock absorbers use of method of introduction of resilient mountings of very high rigidity into the calculated scheme of the pipeline and performance of calculations with step-by-step method. It is concluded that the application of the design procedure considered permits to determine strains due to seismic loads, to analyze stressed state in pipeline elements and supporting power of pipe-line saddle with provision for seismic loads to plan measures on seismic protection

Analysis of the network protection devices action connected with the Krsko NPP operation safety

International Nuclear Information System (INIS)

Omahen, P.; Struc, S.

1995-01-01

The example of failure that took place in Zagreb on 30 March, 1995, has been investigated in order to obtain appropriate answers to the unexpected electric power system (ESP) response and consecutive outage of the Krsko nuclear power plant (NPP). The analysis has been made of particular operating and stability conditions, related to the functioning of distance relays line protection. Using a consequent simulation model of the EPS (European interconnection) under specified fault condition, the research of EPS operation (relays action) and stability has been done. The appropriate simulation results have been compared to the available measured data which had been collected by the SOREL on-line data acquisition system. In the end, a practise proposal for measures to be taken with the target of achieving the foreseen and expected operation of the EPS equipment that effects operation of the Krsko NPP is given. (author)

Preliminary study of the nuclear power option in Belarus

International Nuclear Information System (INIS)

Grusha, N.M.; Kazazyan, V.T.; Malykhin, A.P.; Mikhalevich, A.A.; Yakushau, A.P.; Yaroshevich, O.I.

1999-01-01

The Republic of Belarus possesses an economy with many energy intensive branches. At the same time the share of domestic energy resources is about 15% of total energy demand. The share of the payment for primary energy resources reaches 60% or USD 2 billion of the total energy import. That is comparable with the annual state budget. In addition to that, about half of the installed capacities have reached their operation life and 90% of the units have to be retrofitted or replaced until 2010. Thus, the problem of energy supply is one of the most important ones for Belarus' economy. The nuclear power appears to be one of the possible ways for solving the energy demand problem in Belarus which has, as in case of many countries of Central and South-Eastern Europe, limited energy resources. In 1992 - 1994 the works for studying the possibility of NPP siting were recommenced and six relatively competitive sites have been chosen out from 54 possible locations for NPP siting. Parallely, works on assessment of environmental NPP effect in these sites were carried out. As concerning the reactors to be purchased and installed in the sites selected, the following options were taken into consideration: PWR of American Company WESTINGHOUSE; PWR N4 of France Company FRAMATOME; PWR KONVOI of German Company SIEMENS. Also promising are the new generation of Russian Reactor NPP, namely NPP - 91, NPP - 92 and NPP with NGWWER - 640 reactors. Preliminary assessment having in view the feasibility characteristics, safety, reliability as well as the degree of completion shows the Russian projects NPP - 92 and NGWWER - 640 as more preferably at present. Concerning the radioactive waste management, sites for storing low and medium active waste have been determined as well as regions for high active waste disposal. At present Belarus Republic disposes of a definite production, engineering and scientific potential, which can be used when the nuclear power program will be launched. Construction

New version of NPP Krsko Decommissioning program and LILW and spent fuel management

International Nuclear Information System (INIS)

Zeleznik, N.; Mele, I.; Jenko, T.; Lokner, V.; Levanat, I.; Rapic, A.

2004-01-01

According to the requirements of the bilateral agreement between Republic of Slovenia and Republic of Croatia on the legal and other obligations for Nuclear power plant (NPP) Krsko the Decommissioning program was prepared. The main purpose of the program was to estimate the overall expenses of the future decommissioning, radioactive waste and spent fuel management of the NPP Krsko in order to establish separate fund in Croatia and to correct the rate per kWh collected in the existing decommissioning fund in Slovenia. The program looked at all possible scenarios of dismantling, radioactive waste and spent fuel management and proposed the most plausible two scenarios which are technically possible and financially feasible. (author)

The Romanian experience on introduction of CANDU-600 reactor at the Cernavoda NPP

International Nuclear Information System (INIS)

Rapeanu, S.N.; Bujor, A.; Comsa, O.

1998-01-01

The Cernavoda Nuclear Power Plant (NPP) Project is a key component of the Romanian nuclear development program. Selection of the CANDU design represents a major contribution to this development, due to the technological feasibility for manufacturing of parts, components and the nuclear fuel based on the uranium resources in Romania. The Romanian nuclear development program also involves a nuclear fuel manufacturing plant, a heavy water production plant and organizations specialized in research, engineering, manufacturing and completion for systems and components. The agreement on technological transfer between Canada and Romania is supporting the Romanian involvement to the achievement of the Project, with a degree of participation that is gradually increasing from the first to the last NPP Unit. (author)

Study on human factor at NPP

International Nuclear Information System (INIS)

Nopp, I.

1984-01-01

Factors affecting the reliabilty of the reactor control by an NPP operator are considered on the base of the Czechoslovakia NPP operating experience. The reliability level of NPP operators depends on objective factors (conditions and regime of labour) determining the labour productivity and on subjective ones (psychological morale, physical and mental abilities and occupational level of personnel). Problems of the effect of physical and mental abilities and professional level on the reliability of personnel are considered to be the most important ones. The effect of individual abilities and specific features of the human body on changes in his occupational abilities can be estimated only to a certain degree

Domestic design and validation of natural circulation steam generator of China 1000 MWe PWR NPP

International Nuclear Information System (INIS)

Liu, H.Y.; Wang, X.Y.; Wu, G.; Qin, J.M.; Xiong, Ch.H.; Wang, W.; Chen, J.L.; Cheng, H.P.; Zuo, Ch.P.

2005-01-01

In order to meet the requirements of domestic design of China intending built NPP projects, Research Institute of Nuclear Power Operation (RINPO) has achieved design of 1000 MWe NPP steam generator, called RINSG-1000(means 1000MWe SG designed by RINPO), which is based on SG research ,experiments and service experience accumulated by RINPO in more 40 years. Testing validation of two steam generator key technologies, advanced moisture separate device and sludge collector, has been accomplished during the period of 2000 to 2002. This paper describes the design features of RINSG-1000, and provides some validation test results. (authors)

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

International Nuclear Information System (INIS)

Nurfarhana Ayuni Joha; Syahirah Abdul Rahman; Izhar Abu Hussin

2011-01-01

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)

Perspectives of NPP personnel training in the future?

International Nuclear Information System (INIS)

Khess, R.E.

1996-01-01

Problems of the NPP personnel education are discussed during radical reorganization of the state regulation of energy production and distribution when nuclear energetics will appears in the market conditions. Effective methods of the NPP personnel training developed by the corporation GPU Nuclear are given. Potentials of the application of simulators and computerized programs for increasing the NPP personnel education efficiency are considered

Nuclear power and the problems of its development

International Nuclear Information System (INIS)

Nevskij, V.P.

1979-01-01

The state and prospects of nuclear power in the Soviet Union are considered. Problems of NPP exploitation are discussed, as well as ways of improving the organization of timely and qualitative putting NPP into operation. The main problem of a wide programme of NPP construction is to provide NPP security, reliability and effectiveness. This can be provided by exploiting highly reliable technological equipment and taking appropriate measures during NPP designing, construction and exploitation. One of the main ways to solve these problems is to increase the automation level, to improve control and to provide a gradual transfer from the automation of separate processes to the creation of automatic all-regime NPP control systems

Financing strategy for Indonesian Nuclear Power Project

International Nuclear Information System (INIS)

Subki, I.M.; Arbie, B.; Adiwardojo; Seotrisnanto, A.Y.

1998-01-01

In anticipation of the introduction in the early 2000s of a nuclear power plant, the Government of Indonesia (GOI), through the National Atomic Energy Agency (BATAN) , has formulated a Bid Invitation Specification (BIS) in parallel with the completion of the NPP Feasibility Study. This BIS formulation assumed an open international tender for the first unit of the NPP with project financing as a conventional loan. The GOI's recent policy is to minimize government financial support for power development. This paper summarizes a financing strategy for the Indonesian NPP project to make the NPP economically viable, and provides a general discussion on project financing using a conventional approach, Build--Own-Operate (BOO) and a counter-purchase approach. Innovative approaches for financing are still being pursued in order to obtain an optimum solution for investors and owners, to fulfill the Indonesian government's requirements. (author)

IAEA activities on safety aspects of NPP ageing

International Nuclear Information System (INIS)

Pachner, J.

1998-01-01

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

Integrated ageing management of Atucha NPP

International Nuclear Information System (INIS)

Ranalli, Juan M.; Marchena, Martin H.; Zorrilla, Jorge R.; Antonaccio, Elvio E.; Brenna, Pablo; Yllanez, Daniela; Cruz, Gerardo Vera de la; Luraschi, Carlos; Sabransky, Mario

2013-01-01

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)

Integrated Ageing Management of Atucha NPP

International Nuclear Information System (INIS)

Ranalli, J.M.; Marchena, M.H.; Zorrilla, J.R.; Sabransky, M.

2012-01-01

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)

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)

Chernobyl NPP decommissioning efforts - Past, Present and Future. Decommissioning Efforts on Chernobyl NPP site - Past, Present

International Nuclear Information System (INIS)

Kuchinskiy, V.

2017-01-01

Two unique large-scale projects are underway at the moment within the Chernobyl - Exclusion zone - Shelter object transformation into ecologically safe system and the decommissioning of 3 Chernobyl NPP Units. As a result of beyond design accident in 1986 the entire territory of the industrial site and facilities located on it was heavily contaminated. Priority measures were carried out at the damaged Unit under very difficult conditions to reduce the accident consequences and works to ensure nuclear and radiation safety are continuous, and the Unit four in 1986 was transformed into the Shelter object. Currently, works at the Shelter object are in progress. Under assistance of the International Community new protective construction was built above the existing Shelter object - New Safe Confinement, which will ensure the SO Safety for the long term - within up to 100 years. The second major project is the simultaneous decommissioning of Chernobyl NPP Units 1, 2 and 3. Currently existing Chernobyl NPP decommissioning Strategy has been continuously improved starting from the Concept of 1992. Over the years the following was analyzed and taken into account: the results of numerous research and development works, international experience in decommissioning, IAEA recommendations, comments and suggestions from the governmental and regulatory bodies in the fields of nuclear energy use and radioactive waste management. In 2008 the final decommissioning strategy option for Chernobyl NPP was approved, that was deferred gradual dismantling (SAFSTOR). In accordance with this strategy, decommissioning will be carried out in 3 stages (Final Shutdown and Preservation, Safe Enclosure, Dismantling). The SAFSTOR strategy stipulates: -) the preservation of the reactor, the primary circuit and the reactor compartment equipment; -) the dismantling of the equipment external in relation to the reactor; -) the safe enclosure (under the supervision); -) the gradual dismantling of the primary

Experiences in the implementation of the Coaching project in the nuclear power plant of Laguna Verde (NPP-L V)

International Nuclear Information System (INIS)

Mendez M, H. I.

2012-10-01

This document has the purpose of to share acquired experiences during the implementation of the Coaching project focused the training of supervisors and directive personnel of the nuclear power plant of Laguna Verde (NPP-L V). Derived of the improvement areas identified by the supervisor organization of the nuclear power stations WANO (World Association Nuclear of Operators) and of the auto-evaluations realized by the expert personnel of the same power station that based on external experiences carried out through the Benchmarking (comparison with other power stations) they have reflected the necessity to activate a training process in Coaching with a practical focus toward the directive and supervisor personnel in the power station. By means of the observation of the personnel's acting so much in the control rooms like in different areas, three focus areas have been identified for the training in Coaching, these are the personnel's motivation, the organizational communication so much in vertical form as horizontal and the perception of confidence lack among directive, supervisors, operators and technicians. The plan focused in the abilities training of Coaching with practical sense was development, supported with an evaluation of 360 grades as tool of competitions development through a computer application e-Coaching. The use of application and Coaching following techniques facilitated the conformation of the practical focus, same that are of continuous use starting from the training of the supervisor and directive personnel. (Author)

Project No. 10 - Partial restoration of Ignalina NPP territory

International Nuclear Information System (INIS)

2000-01-01

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

Integral design small nuclear power plant UNITHERM

International Nuclear Information System (INIS)

Adamovich, L. A.; Grechko, G. I.; Ulasevich, V. K.; Shishkin, V. A.

1995-01-01

The need to erect expensive energy transmission lines to these places demands to use independent local energy sources. Therefore, a reasonable alternative to the plants fired fossil fuel, mostly hydrocarbon fuel, may come from the nuclear power plants (NPP) of relatively small capacity which are nonattended, shipped to the site by large-assembled modules and completely withdrawable from the site during decommissioning. Application of NPPs for power and heat supply may prove to be cost-efficient and rather positive from social and ecological point of view. UNITHERM NPP belongs to such energy sources and may be used for heat and power supply. Heat can be provided both as hot water and superheated steam. The consumers are able to specify heat/energy supply ratio. NPP design provides for independent energy supply to the consumers and the possibility to disconnect each of them without disruption of operation of the others. Thermal hydraulic diagram of UNITHERM NPP provides for the use of three interconnected, process circuits. The consumers of thermal energy (turbogenerator unit and boilers of the central heating unit) are arranged in the last circuit

Special aspects of implementing advanced fuel cycles at Kalinin NPP

International Nuclear Information System (INIS)

Tsvetkov, A.

2015-01-01

The presentation showed the experience of different TVSA modifications usage at Kalinin NPP. The strategy of 18 month fuel cycles implementation at uprated power (104%) was also presented. The transition and equilibrium fuel loadings features were discussed. The implementation of burn-up measurement installation MKS-01 was presented, in order to solve the spent nuclear fuel handling and transportation issues due to the increased fuel enrichment and heavy metal mass

Analysis of heavy radiological accidents in NPP and gamma-irradiators

Energy Technology Data Exchange (ETDEWEB)

Angelov, V [Civil Defence Administration, Sofia (Bulgaria); Semova, T; Bonchev, Ts [Sofia Univ. (Bulgaria). Fizicheski Fakultet

1996-12-31

A review of several heavy radiological accidents, their cause, character, radioactivity emission, victims and economical impact is presented in the form of uniform tables. Eleven cases of incidents in power plants and 4 cases of accidents involving powerful gamma irradiators are considered. Radiological accidents in Bulgaria, not connected with the Kozloduy NPP, are listed. The human factor has been identified as the main cause for most of the accidents. It is stressed that the probability of heavy accident increases at the time of reactor refuelling, repair or testing. Technical failures could be eliminated by improved check and diagnostics procedures. 2 tabs., 12 refs.

Analysis of heavy radiological accidents in NPP and gamma-irradiators

International Nuclear Information System (INIS)

Angelov, V.; Semova, T.; Bonchev, Ts.

1995-01-01

A review of several heavy radiological accidents, their cause, character, radioactivity emission, victims and economical impact is presented in the form of uniform tables. Eleven cases of incidents in power plants and 4 cases of accidents involving powerful gamma irradiators are considered. Radiological accidents in Bulgaria, not connected with the Kozloduy NPP, are listed. The human factor has been identified as the main cause for most of the accidents. It is stressed that the probability of heavy accident increases at the time of reactor refuelling, repair or testing. Technical failures could be eliminated by improved check and diagnostics procedures. 2 tabs., 12 refs

Reactor noise analysis applications in NPP I and C systems

Energy Technology Data Exchange (ETDEWEB)

Gloeckler, O. [International Atomic Energy Agency, Wagramer Strosse 5, A-1400 Vienna, Austria Ontario Power Generation, 230 Westney Road South, Ajax, Ont. L1S 7R3 (Canada)

2006-07-01

Reactor noise analysis techniques are used in many NPPs on a routine basis as 'inspection tools' to get information on the dynamics of reactor processes and their instrumentation in a passive, non-intrusive way. The paper discusses some of the tasks and requirements an NPP has to take to implement and to use the full advantages of reactor noise analysis techniques. Typical signal noise analysis applications developed for the monitoring of the reactor shutdown system and control system instrumentation of the Candu units of Ontario Power Generation and Bruce Power are also presented. (authors)

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

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

International Nuclear Information System (INIS)

Hossen, Muhammed Mufazzal; Kang, Sunkoo; Kim, Jonghyun

2014-01-01

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

Main principles of NPP project ecological expert investigation

International Nuclear Information System (INIS)

Dibobes, I.K.; Revina, S.K.; Glushkov, V.P.

1983-01-01

NPP project ecological expert investigation among the other objectives is to provide implementation of standards, rules and requirements as well as government decrees and international obligations of the USSR concerning the environment protection. The expert investigation takes into consideration both environment protection, regional, resources, ecological, demographic and economic aspects. The NPP siting and the local environment and resources state are estimated as well as the structure of utilization of the latter, the expected damage to the environment due to NPP construction and the measures directed towards the optimal using of natural resources. On the basis of the presented issues suggestions about NPP projects coordination with Goskomgidromet's institutions are given [ru

Slovakian-Russian partnership as a part of the supply chain for nuclear power plants and advanced Russian technology for nuclear power plants

International Nuclear Information System (INIS)

Ivanov, T.; Chernyakhovskaya, Y.

2009-01-01

The first nuclear power project in the Slovak Republic was launched in 1958 through close cooperation with the Russian nuclear industry. Since then the Slovak and Russian nuclear branches were never separated. Technical and economic performances of the NPP units constructed with participation of Russian specialists were and continue being one of the best globally. The culture of business and competence of ASE is based on about 40 years of experience in construction of 29 NPP power units abroad with 20 GW total capacity. ASE strives to present to the Customers line of NPP designs ready for implementation and well-developed network of the multi-functional alliances and JVs. Currently, large-scale NPP projects involve public-private partnership (PPP) more and more. ASE development vision is to flexibly conform to Customers' requirements and needs and to diversify in related segments of EPC-business, namely designing, manufacturing, electric power trade, etc. Systematical approach to the fostering of mutual relations under the new economic conditions and nuclear renaissance, the Slovak-Russian cooperation in NPP engineering, manufacturing and construction are once again promising and long-term oriented. (authors)

Trial operation of TVS-2 at Balakovo NPP. Analysis of results and further modernization

International Nuclear Information System (INIS)

Vasilchenko, I.; Molchanov, V.; Pavlovichev, A.; Novikov, A.; Enin, A.

2006-01-01

In this report the more detailed specifications of TVS-2 considering modifications of separate units, and also the conditions and results of its operation at Balakovo NPP on the basis of three fuel loads are presented. Implementation of TVS-2 at power units of Balakovo NPP in the fuel cycle 3x350 eff. days has been started in 2003 and the reactor core full loading at Balakovo NPP, Unit 1 has been achieved in 2005. Considering positive operational experience of TVS-2 at Unit 1 implementation of TVS-2 by full make-ups has been started at other units of Balakovo NPP. The operational results confirm the predicted essential increasement in reliability of reactor scram, possibility of implementation of new design restrictions, which enable to form the fuel loading with small neutron leakage. Besides, the favorable results on performance of transport - technological procedures enabling to reduce time of PM has been obtained. On the basis of this structure the detailed project report of a new FA modification with lengthened fuel stack has been developed, the necessary calculational and experimental justifications have been performed, materials for obtaining a license to trial operation of the first lot of such fuel assemblies beginning from 2006 are being prepared

Remanent life management of nuclear power plants

International Nuclear Information System (INIS)

Pinedo, J.; Gomez Santamaria, J.

1995-01-01

The concept of life in the nuclear power plants is very special. The main aceptions are: design life, economic life and useful life. The good management of NPP will do the prolongation of the life in the NPP. The remanent of management life summarizes certain activities in order to prolong the lifetime of the NPP. This article presents the activities of the RML program, the technological program and its benefits

Social consequences of closing the Ignalina NPP

International Nuclear Information System (INIS)

Baubinas, R.; Burneika, D.

2001-01-01

The possible social consequences of closing the Ignalina Nuclear Power Plant are studied. The social and economical situation in Visaginas and in the Utena region as a precondition for possible social consequences is shown. Also, two main groups of factors that can possibly influence the situation in the labour market are analysed. The problems of the enterprises that create working places and of the inhabitants of Visaginas whose possible behaviour can affect the situation in the labour market are discussed. Also, some proposals to neutralize the social costs of closing the Ignalina NPP are made. (author)

Environmental aspects of Greenfield NPP site in northern Finland

International Nuclear Information System (INIS)

Kopisto, L.

2015-01-01

Fennovoima will build a nuclear power plant of 1200 MW at Hanhikivi headland in Pyhaejoki, Northern Finland on the shore of the Baltic Sea. According to the target schedule the plant will produce electricity in 2024. The plant supplier is Rusatom Overseas, subsidiary of the Russian Rosatom. No industrial activity is practiced in the immediate surroundings of the site area and the headland and its surroundings are sparsely populated. The area is in its natural state. This means that all the preparatory and infrastructure works needs to be done before the construction of NPP can start. The environmental and nature conservation aspects have to be taken into consideration in planning, construction and operation of the NPP. Northern location sets some challenges to the design of the power plant. The sea area is normally covered with ice almost half of the year which has to be taken into account in the design of the power plant. But there are also advantages: in winter when the cooling water is cold the efficiency of electricity production is estimated to be exceptionally good, approximately 39 %. Since 2008, Fennovoima has carried out several environmental studies and surveys in the site area and has collected information about the nature conditions on land and in the sea area. The collected environmental data has been utilized in land use planning, environmental impact assessment procedure and in applying for conventional permits. The environmental data can also be used as baseline data. The document is composed of an abstract and the presentation slides

Regulatory approach to NPP ageing in Bulgaria

International Nuclear Information System (INIS)

Vassilev, D.

2000-01-01

In this contribution summary information of Kozloduy NPP units is presented. The nuclear legislation, regulatory approach for managing safety aspects on NPP ageing, short term programme, complex programme PRG'97 ant other aspects of ageing management are discussed

Reliability Analysis on NPP's Safety-Related Control Module with Field Data

International Nuclear Information System (INIS)

Lee, Sang Yong; Jung, Jae Hyun; Kim, Seong Hun

2006-01-01

The automatic control systems used in nuclear power plant (NPP) consists of numerous control modules that can be considered to be a network of components various complex ways. The control modules require relatively high reliability than industrial electronic products. Reliability prediction provides the rational basis of system designs and also provides the safety significance of system operations. The aim of this paper is to minimize the deficiencies of the traditional reliability prediction method calculation using the available field return data. This way is possible to do more realistic reliability assessment. SAMCHANG Enterprise Company (SEC) has established database containing high quality data at the module and component level from module maintenance in NPP. On the basis of these, this paper compares results that add failure record (field data) to Telcordia-SR-332 reliability prediction model with MIL-HDBK-217F prediction results

Soundness of Krsko Nuclear Power Plant Performance in Terms of Energy and Finance

International Nuclear Information System (INIS)

Curkovic, A.; Vrankic, K.; Magdic, M.

1998-01-01

Compared to existing conventional thermal power plants in Croatian electric power system, as well as to alternative (potential) imported coal and gas fired thermal power plants, Krsko NPP (nuclear power plant) generates electricity with lower production costs. This cost margin in favour of the Krsko NPP represents the soundness of this nuclear power plant in terms of energy and finance. (author)

Perception of tomorrow's nuclear power plant control rooms

International Nuclear Information System (INIS)

Meyer, O.R.

1986-01-01

Major development programs are upgrading today's light water reactor nuclear power plant (NPP) control rooms. These programs involve displays, control panel architecture, procedures, staffing, and training, and are supported by analytical efforts to refine the definitions of the dynamics and the functional requirements of NPP operation. These programs demonstrate that the NPP control room is the visible command/control/communications center of the complex man/machine system that operates the plant. These development programs are primarily plant specific, although the owners' groups and the Institute of Nuclear Power Operations (INPO) do provide some standardization. The Idaho National Engineering Laboratory recently completed a project to categorize control room changes and estimate the degree of change. That project, plus related studies, provides the basis for this image of the next generation of NPP control rooms. The next generation of NPP control rooms is envisioned as being dominated by three current trends: (1) application of state-of-the-art computer hardware and software; (2) use of NPP dynamic analyses to provide the basis for the control room man/machine system design; and (3) application of empirical principles of human performance

EMAS at Doel NPP

International Nuclear Information System (INIS)

Nolan, Peter; Thoelen, Els

1998-01-01

In October 1995, Doel NPP of Electrabel, Belgium opted to seek registration under the EC Eco-management and Audit Scheme (EMAS). A comprehensive environmental management system (EMS) has been introduced and implemented, encompassing all four PWRs and the supporting departments. A critical step was to seek certification from an accredited environmental auditing body against the International Standard ISO 14001. This provided the foundation for the publicly available environmental statement required by EMAS. The complications of achieving EMAS at a time when national and international standards were being re-formulated were successfully overcome and Doel NPP passed its EMAS audit in June 1997. (author)

Development of seismic safety reevaluation procedure considering the ageing of NPP facilities

Energy Technology Data Exchange (ETDEWEB)

Lee, Myoung Kue [Jeonju Univ., Cheonju (Korea, Republic of); Kim, J. M. [Cheonnam National Univ., Gwangju (Korea, Republic of); Kim, Y. S.; Cheong, S. H.; Kim, I. S.; Lee, M. G.; Kim, D. O. [Andong National Univ., Andong (Korea, Republic of); Lee, G. H. [Mokpo National Maritime Univ., Mokpo (Korea, Republic of)

2003-03-15

There are three of Nuclear Power Plants subject to the USI A-46 in Korea, including Kori No 1 and No 2 and Wolsung No 1. For the sake of resolution of the issue the possibility of adopting the GIP developed by the SQUG in USA is very high. In relation to the issue, this study addresses some technical improvements of the GIP including sloshing analysis based on multiple modes, seismic retrofit of cabinet for reduction of ICRS and modification of IRS depending on damping ratio. Dominant degradation factor and its affects NPP concrete elements are reviewed : chloride induced corrosion, carbonation of concrete elements, freezing and thawing of concrete elements, chemical and biological process, crack affect on concrete degradation. Various technical reports and papers about age-related degradation are reviewed for identification of degradation properties of NPP structures and components and degradation trend in NPP structures and components. This report summarizes numerical model for concrete degradation and development procedure of numerical models for concrete degradation. This report proposes the research necessity for performance evaluation of degraded concrete structure and selection of element for further study.

DEVELOPMENT OF A MULTIPLE-LOCUS VARIABLE NUMBER OF TANDEM REPEAT ANALYSIS (MLVA FOR HELICOBACTER PYLORI AND ITS APPLICATION TO HELICOBACTER PYLORI ISOLATES FROM ROSTOV REGION,RUSSIA

Directory of Open Access Journals (Sweden)

Sorokin VM

2012-09-01

Full Text Available Stomach infection with Helicobacter pylori (H. pylori is the second most common infectious disease of humans. The severe pathological consequences of this infection include gastric and duodenal ulcer disease, the development of gastric mucosal atrophy, gastric carcinoma, and, more rarely, malignant tumors of the lymphoma. H. pylori infections cause very high morbidity and mortality and are of particular concern in developing countries, where H. pylori prevalences as high as 90% have been reported. The population of H. pylori shows a high genomic variability among isolates. And the polymorphism of repeat-units of genomics had participated the important process of evolution. A variety of molecular typing tools have been developed to access genetic relatedness in H. pylori isolates. However, there is still no standard genotyping system of this bacterium. The MLVA (Multi-Locus of Variable number of tandem repeat Analysis method is useful for performing phylogenetic analysis and is widely used in bacteria genotyping; however, there's little application in H. pylori analysis. This article is the first application of the MLVA method to investigate H. pylori isolates in Russia. MLVA of 4 VNTR loci with high discrimination power based on 10 candidates were performed on a collection of 22 strains of H. pylori which originated from Rostov region of Russia. This method provides a starting point on which improvements to the method and comparisons to other techniques can be made.

On psichological problem of NPP operation and control

International Nuclear Information System (INIS)

Mashin, V.A.

1994-01-01

The role of psichological factor as a reserve for increasing NPP safety connected with human factor is discussed. It is emphasized that the process of NPP personnel professional training should not be restricted by formation of a certain set of knowledge, skills and experience. It is necessary to initiate ability for constant self-developing. Control for assurance of effective interaction of the whole NPP personnel is an important problem

Institutions and organisations in Russian higher education: the example of Rostov region education services market

Directory of Open Access Journals (Sweden)

Volchik Vyacheslav, V.

2015-12-01

Full Text Available The paper examines the process of transformation in institutional and organizational structures of Russian Higher Education (Rostov Region is taken as an example. Adaptive economic behavior of key actors on the Russian education services market has been studied in the context of constantly changing institutional and organizational environments. Original institutional approach in the tradition of J. Commons and J. Hodgson has been applied to analyze interconnections between institutions and organizations. The evolution of institutional and organizational structures in Russian Higher education has been divided into three stages. We distinguish between those stages taking into account the dynamics of quantitative indicators and the change in norms and standards that regulate actors’ behavior in the field. The period of 1990-2002 can be characterized by weakening of government regulation and, simultaneously, lack of financial support of Higher Education. Meanwhile, private Higher Education and paid university programmes developed rapidly during that period. These changes resulted in quantitative growth in the field on the one hand, and devaluation of Higher Education, on the other hand. It is assumed that the “bubble” in Russian Higher Education, which arose in 2002-2008, occurred to a great extent because of the expansion in extramural and lowquality full-time education aimed only at getting graduate diplomas. During the period of bubble formation and latter decline in demand on the Russian education services market, the Government strengthened norms and standards referring to regulation of Higher Education. Recent “optimization processes” of 2009-2015 resulted in reducing the number of students and lecturers, universities and their branches.

Bohunice V1 NPP upgrading programme

International Nuclear Information System (INIS)

Kerak, J.

2001-01-01

The paper describes whole process of Bohunice V1 NPP nuclear safety and operational reliability level increase which has been performed since units commissioning (1. unit in 1978, 2. unit in 1980), continued Small Reconstruction (1991 -1993) and finished Gradual Upgrading(1994 -2000). The main purpose is to last stage -Gradual upgrading of Bohunice V1 NPP. (author)

The dependence level analysis between the human actions in NPP Operation

International Nuclear Information System (INIS)

Farcasiu, M.; Nitoi, M.; Apostol, M.; Florescu, G.; Prisecaru, Ilie

2009-01-01

The Human Reliability Analysis (HRA) is an important method in Probabilistic Safety Assessment (PSA) studies and offers desirability for concrete improvement of the man - machine - organization interfaces, reliability and safety. An important step in HRA is the dependence level analysis between the human actions performed by the same person or between the actions performed by different persons, step in quantitative analysis of the human errors probabilities. The purpose of this paper is to develop a model to analyze the dependence level between human actions for Nuclear Power Plant (NPP) operation. The model estimates the conditional human error probabilities (CHEP) and joint human error probabilities (JHEP). The achieved sensitivity analyses determine human performance sensibility to systematic variations for dependence level between human actions. The human error probabilities estimated in this paper are adequate values for integration both in HRA and in PSA realized for NPP. This type of analysis helps in finding and analyzing the ways of reducing the likelihood of human errors, so that the impact of human factor to systems availability, reliability and safety can be realistically estimated. In order to demonstrate the usability of this model an analysis is performed upon the dependences between the necessary human actions in mitigating the consequences of LOCA events, particularly for the case of Cernavoda NPP. (authors)

Precautions against axial fan stall in reactor building to Tianwan NPP

International Nuclear Information System (INIS)

Liu Chunlong; Pei Junmin

2011-01-01

The paper introduces the mechanism and harm of rotating stall of axial fans, analyzes the necessity for prevention against axial fan stall in reactor building of Tianwan NPP, introduces the precautions, and then makes an assessment on anti-stall effect of flow separators. It can provide reference for model-selection or reconstruction of similar fans in power stations, and for operation and maintenance of axial fans. (authors)

Psychology of NPP operation safety

International Nuclear Information System (INIS)

Tret'yakov, V.P.

1993-01-01

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

Use of the deterministic safety analyses in support to the NPP Krsko modification

International Nuclear Information System (INIS)

Feretic, D.; Cavlina, N.; Debrecin, N.; Grgic, D.; Bajs, T.; Spalj, S.

2004-01-01

The ultimate goal of the safety analysis is to verify that Nuclear Power Plant (NPP) meets safety and operational requirements. To this aim it is necessary to demonstrate that plant safety has not been deteriorated in the case of the modifications to the plant Systems, Structures and Components (SSC) or changes to the plant procedures. In addition, safety analyses are needed in the case of reassessment of an existing plant. The reasons for reassessment may be different, e.g. due to the changes in the methodology and assumptions used in the original design, if the original design basis or acceptance criteria may no longer be adequate, if the safety analysis tools used may have been superseded by more sophisticated methods or if the original design basis may no longer be met. The operation of the NPP Krsko has experienced numerous changes from the original design for the majority of the reasons that have been mentioned before. On the other side, the application of the large best-estimate thermalhydraulic codes has evolved to the wide spread support in the operation of the NPP: compliance with the regulatory goals, support to the PSA studies, analysis of the operational transients, plant modifications studies, equipment qualification, training of the operators, preparation of the operating procedures, etc. This trend has been followed at the Faculty of Electrical Engineering Zagreb (FER) and applied to the on-going needs due to the modifications and changes at NPP Krsko. In this paper, an overview of the deterministic safety analyses performed at FER in the support to the NPP Krsko modifications and changes is presented.(author)

From the chronicle of training of Dukovany NPP staff

International Nuclear Information System (INIS)

2005-01-01

The long way the Dukovany NPP had to go before the plant staff was fully qualified and skilled is described. First the training concept was prepared, then the necessary training facilities were set up, lecturers and instructors were hired and trained, training programmes and training materials were developed, and ultimately the first training course was launched in 1979. A training NPP was constructed and a full-scope simulator of the Dukovany NPP was set up. The current status of organization of NPP staff training by the CEZ utility is highlighted. (author)

Training center of Rovenskaya NPP. The experience of creation

International Nuclear Information System (INIS)

Fedorov, O.M.; Aristov, B.N.

1991-01-01

Experience in creation of a teaching-training centre at the Rovno NPP, which uses means available at unified NPPs, at most is discussed. The centre hardware complex functions include the event filing and providing for user-friendly interface with NPP technical personnel under training. The system of personnel training at the Rovno NPP teaching-training centre gives an opportunity to analyze accidents and emergency conditions more completely and carefully. The taching analysis of failures and accidents by a NPP operators using the complex of the teaching-training centre hardware sufficiently improves knowledge of particular accidents

Human resource issues related to an expanding nuclear power programme

International Nuclear Information System (INIS)

2006-05-01

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

Determination of Safety Performance Grade of NPP Using Integrated Safety Performance Assessment (ISPA) Program

International Nuclear Information System (INIS)

Chung, Dae Wook

2011-01-01

Since the beginning of 2000, the safety regulation of nuclear power plant (NPP) has been challenged to be conducted more reasonable, effective and efficient way using risk and performance information. In the United States, USNRC established Reactor Oversight Process (ROP) in 2000 for improving the effectiveness of safety regulation of operating NPPs. The main idea of ROP is to classify the NPPs into 5 categories based on the results of safety performance assessment and to conduct graded regulatory programs according to categorization, which might be interpreted as 'Graded Regulation'. However, the classification of safety performance categories is highly comprehensive and sensitive process so that safety performance assessment program should be prepared in integrated, objective and quantitative manner. Furthermore, the results of assessment should characterize and categorize the actual level of safety performance of specific NPP, integrating all the substantial elements for assessing the safety performance. In consideration of particular regulatory environment in Korea, the integrated safety performance assessment (ISPA) program is being under development for the use in the determination of safety performance grade (SPG) of a NPP. The ISPA program consists of 6 individual assessment programs (4 quantitative and 2 qualitative) which cover the overall safety performance of NPP. Some of the assessment programs which are already implemented are used directly or modified for incorporating risk aspects. The others which are not existing regulatory programs are newly developed. Eventually, all the assessment results from individual assessment programs are produced and integrated to determine the safety performance grade of a specific NPP

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.

A way of Dukovany NPP to privatization and liberalized market

International Nuclear Information System (INIS)

Kouklik, I.

2001-01-01

This presentation describes the current situation in the Dukovany NPP with two main upcoming future phenomena - privatization of CEZ company and preparation for liberalized electricity market. Considerations about level of safety, investment costs and competitiveness of Dukovany Nuclear Power Plant in liberalization process is described together with a comparison of some safety features of the world's NPPs. Results of this comparison are used for consideration and evaluation of some require modifications effectiveness. (author)

Risk assessment of the Krsko NPP normal operation on the public in the Zagreb area

International Nuclear Information System (INIS)

Skanata, D.; Pevec, D.

1994-01-01

In the paper, a very short review of the ICRP recommendations related to effective dose limitation for the workers as well as for the public, is given. Particular attention is paid to the risk coefficients values. In the short manner, description of the applied methodology and achieved result related to the risk assessment of the Krsko NPP normal operation on the public in the Zagreb Area, are given too. The mentioned assessment was performed as an activity within the Case Study Zagreb Project developed under the Inter-Agency Programme on the Assessment and Management of Health and Environmental Risks from Energy and Other Complex Industrial Systems (UNEP, WHO, IAEA and UNIDO). Making comparison between assessment risk of the Krsko NPP normal operation and risks to which inhabitants of the City of Zagreb are normally exposed, it is concluded that living in the vicinity of such nuclear power plant as it is Krsko NPP (PWR, 664 MWe), is not so risky as risky are some everyday activities

Seismic response and fragility evaluation for an Eastern US NPP including soil-structure interaction effects

International Nuclear Information System (INIS)

Ghiocel, Dan M.; Wilson, Paul R.; Thomas, Gary G.; Stevenson, John D.

1998-01-01

The paper discusses methodological aspects involved in a probabilistic seismic soil-structure interaction (SSI) analysis for a Seismic Probabilistic Risk Assessment (SPRA) review. An example of an Eastern US nuclear power plant (NPP) is presented. The approach presented herein follows the current practice of the Individual Plant Examination for External Events (IPEEE) program in the US. The NPP is founded on a relatively soft soil deposit, and thus the SSI effects on seismic responses are significant. Probabilistic models used for the idealization of the seismic excitation and the surrounding soil deposit are described. Using a lognormal format, computed random variability effects were combined with those proposed in the SPRA methodology guidelines. Probabilistic floor response spectra and structural fragilities for different NPP buildings were computed. Structural capacities were determined following the current practice which assumes independent median safety factors for strength and inelastic absorption. Limitations of the IPEEE practice for performing SPRA are discussed and alternate procedures, more rigorous and simple to implement, are suggested

Some questions of optimization in the personnel dosimetry at NPP

International Nuclear Information System (INIS)

Liberman, A.N.; Petrov, V.I.; Bronshtejn, I.Eh.

1978-01-01

Some possible ways of optimizing the radiation monitoring of personnel of nuclear power plants (NPP) are considered. For premises within the zone of a strict operating regime, it is proposed that the intervals between periods of monitoring be shortened if the operating conditions are normal. To improve the monitoring of activity of water in the primary circuit, it is considered desirable to provide all NPP with a system of automatic radiation monitoring having input to the control panel. Where the work involves opening of primary circuit communications or deactivation of equipment and also in cases of emergency, it is proposed that, in addition to routine monitoring, gamma-spectrometric or radiochemical analysis of the isototip composition of contaminants be carried out. Because of the absence of measurable quantities of incorporated radionuclides in the vast majority of those working in the strict regime zone, it is suggested that the number of persons subject to systematic individual monitoring of internal radiation be limited

Pre-operational Study on Impact of Temelin NPP on Hydrosphere

International Nuclear Information System (INIS)

Hanslik, E.J.

1999-01-01

Beginning of the construction of Temelin Nuclear Power Plant (NPP) in south Bohemia (CR) dates back to 1986. It is planned that the first water-cooled reactor could be put into operation in 2000. A research project, funded from the national budget and carried out under supervision of the Czech Ministry of Environment, has been aimed at examining pre-operational environmental conditions (a reference level) in terms of concentrations of radioactive and non-radioactive polluting substances in components of the environment, particularly in hydrosphere, and at predicting possible impacts of future operation of Temelin NPP. Special attention paid to the hydrosphere is associated with requirements for protection of water quality in the Vltava River, which serves as water resource for Prague capital. The paper summarises selected interim results of the project, particularly those concerning per-operational environmental conditions and impacts predicted for standard operation of the plant. More detailed description of the results including possible impacts of the so called maximum project accident is presented in (1)

A Survey of a Remote Diagnosis Center for Nuclear Power Plants

International Nuclear Information System (INIS)

Choi, Yoo Rark; Lee, Jae Cheol; Kim, Jae Hee

2005-01-01

Methodologies for remote diagnosis have been developed and applied to medical care and lots of industrial fields. Modern science technologies such as a fast network, high computing power, sensing technology and advanced robot engineering make it possible to diagnose remote targets. Nuclear power plant(NPP) has highly connected network enabling systems. The systems (accumulated data analysis systems, alarm systems, main control panel, NPP database systems and so on) are connected with each other through a network. But remote diagnosis researches for a NPP have been developed individually. Efficient monitoring power, convenient management and a costcutting of the diagnosis will be provided through integration of the remote diagnosis technologies. The result of the integration can be represented as a remote diagnosis center. We propose an architecture of the remote diagnosis center for a NPP in this paper

Standardization of Nuclear Instrumentation Applied in the NPP and in other nuclear installations

International Nuclear Information System (INIS)

Kusnowo, Arlinah; Darmawati, Suzie

2002-01-01

Nuclear power plant (NPP) and other nuclear installations have been recognized as applications needing very sophisticated technologies. One of technologies used in this all nuclear facilities is nuclear instrumentation. In order that NPP and other nuclear installations be operated safely, nuclear instrumentation requires standardization from design to its operation. Internationally, standardizations of nuclear instrumentation have been issued by IEC (International Electrotechnical Commission). Formulation of standard in nuclear instrumentation in IEC is carried out by Technical Committee (TC) 45. This paper describes briefly the standardization of nuclear instrumentation applied in Indonesia as Indonesian National Standard (SNI, Standard National Indonesia), standardization of nuclear instrumentation developed by TC 45, SC 45A, and SC 45B, as well as the possibility to adopt and apply those IEC standard in Indonesia

Questions to the reactors power upgrade of the Nuclear Power Plant of Laguna Verde

International Nuclear Information System (INIS)

Salas M, B.

2014-08-01

The two reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) were subjected to power upgrade labors with the purpose of achieving 20% upgrade on the original power; these labors concluded in August 24, 2010 for the Reactor 1 and in January 16, 2011 for the Reactor 2, however in January of 2014, the NNP-L V has not received by part of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) the new Operation License to be able to work with the new power, because it does not fulfill all the necessary requirements of safety. In this work is presented and analyzed the information obtained in this respect, with data provided by the Instituto Federal de Acceso a la Informacion Publica y Proteccion de Datos (IFAI) and the Comision Federal de Electricidad (CFE) in Mexico, as well as the opinion of some workers of the NPP-L V. The Governing Board of the CFE announcement that will give special continuation to the behavior on the operation and reliability of the NPP-L V, because the frequency of not announced interruptions was increased 7 times more in the last three years. (Author)

Feature article. Fukushima Daiichi NPP accident

International Nuclear Information System (INIS)

Ekarinai, Masashi; Ake, Yutaka; Narabayashi, Tadashi

2011-01-01

This special feature article consisted of five reports and the minutes of emergency discussion meeting on Fukushima Daiichi Nuclear Power Plant (NPP) accident. Effects of the accident on future electricity supply of electric utilities and also on business development of nuclear industries were discussed. Activities of senior network team of atomic energy society of Japan (AESJ) to conduct severe accident analysis and early restoration from the accident were introduced. Circulating injection reactor cooling system and zeolite decontamination system of accumulated contaminated water was proposed. Effects of the accident on overseas reaction on nuclear development were also reported as well as personal experience of the professor in the US west coast on communications. (T. Tanaka)

Electrohydraulic system to control NPP turbines

International Nuclear Information System (INIS)

Kosyak, Yu.F.; Virchenko, M.A.; Rozhanskij, V.E.; Rokhlenko, V.Yu.; Gapunin, A.Ya.; Zhornitskaya, T.Ya.; Rasskazov, I.Eh.; Butsenko, V.N.; Brajnin, L.S.; Makarenko, N.I.

1985-01-01

Operation regimes of electrohydraulic regulation system (EHRS) of NPP turbines, designed to control the turbine in start-up and working conditions, have been decribed. In start-up regimes EHRS ensures the testing of control valves of the turbine, the turn of the turbine from zero to the nominal rotation frequency (automatic, semiautomatic and manual regulation), turbine acceleration to test safety automatic systems, gradual change in rotation frequency during generator synchronization with circuit. Under working conditions EHRS ensures the maintenance of frequency, power and vapour pressure before the turbine. A block diagram of EHRS is presented. Sensors and electronic part of EHRS are supplied with triple reservation, which ensures a high relaibility of the system

NPP Cernavoda Unit 2 Financing Completion Works

International Nuclear Information System (INIS)

Chirica, T.; Stefanescu, A.; Constantin, C.; Dobrin, M.

2002-01-01

NPP Cernavoda Unit 2 completion is the highest priority of the Romanian power sector strategy. The nuclear energy represents, through its technological features of adopted solution (a CANDU nuclear power plant) and also through technological and economical performance indicators, the best solution to fulfill the demands concerning the sustainable development and the electricity request. The guidelines of energy strategy regarding the nuclear sector development in Romania are framing in the general policy for energy system development at least costs and they are responding to requests concerning the environment and people protection. The paper presents the financing alternatives for Unit 2 completion works taking into consideration the financing market conditions. The paper presents the impact of the financing conditions on the project efficiency, as well as the facilities offered by the Romanian Government in order to support this project. (author)

Scientific management of the commissioning of the Temelin NPP

International Nuclear Information System (INIS)

Pazdera, F.; Vasa, I.; Svoboda, C.

2002-01-01

A Scientific Supervisory Group (SSG) for the commissioning of the Temelin nuclear power plant was set up by the statutory body of CEZ, a.s. (utility which holds responsibility for the start-up of the plant pursuant to Act No. 18/1997). The SSG provides support to the operator through expertise in nuclear safety assurance and nuclear power plant commissioning. Nuclear Research Institute Rez plc was appointed to this function. The article gives the definition and explains the statute of the SSG, highlights its main tasks and responsibilities, and presents the main results of activities of the SSG. The mission of the International Scientific Council for the Commissioning of the Temelin NPP is also briefly outlined. (author)

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.

Economical aspect of the decommissioning for NPP

International Nuclear Information System (INIS)

Daryoko, M.

1998-01-01

The estimated, analysed and founding of the economical aspect at decommissioning of Nuclear Power Plant (NPP) have been studied. The data that have been obtained from literature, then the calculation and analysing have been done base to the future condition. The cost for NPP decommissioning depend on the internal factor such as type, capacity and safe storage time, and the external factor such as policy, manpower and the technology preparation. The successfulness of funding, depend on the rate of inflation, discount rate of interest and the currency fluctuation. For the internal factor, the influence of the type of the reactor (BWR or PWR) to the decommissioning cost is negligible, the big reactor capacity (±1100 MW), and the safe storage between 30 to 100 years are recommended, and for the external factor, specially Indonesia, to meet the future need the ratio of decommissioning cost and capital cost will be lower than in develop countries at the present (10%). The ratio between decommissioning fund and electricity generation cost relatively very low, are more less than 1.79 % for 30 years safe storage, and discount rate of interest 3%, or more less than 0.30 % for safe storage 30 years, and discount rate of interest 6%. (author)

The reevaluation of seismic safety of existing nuclear power plant

International Nuclear Information System (INIS)

Kitagawa, Hiroshi; Tominaga, Shohei; Kumagai, Chiyoshi; Koshiba, Koremutsu; Kono, Tomonori; Agawa, Kazuyoshi; Kuwata, Kenichiro

2003-01-01

We have carried out additional geological surveys in order to enrich our database on geological faults in the vicinity of Shimane Nuclear Power Plant (NPP). Prior to additional geological surveys, given the social importance of nuclear power plants, we hypothetically assumed that almost the whole length of an area covered by surveys would be an active fault that must be considered in seismic design, and tried to reevaluate the seismic safety of the NPP by applying an input earthquake ground motion larger than the level at the design stage. As a result, we have confirmed that seismic safety of the NPP can be maintained. This paper describes the method that we employed to reevaluate the seismic safety of Shimane NPP. (author)

Investigation of interfacing NPP simulators with PSCAD software

International Nuclear Information System (INIS)

Zahedi, P.

2006-01-01

This paper demonstrates a new method of interfacing a NPP simulator with the PSCAD software so that the interaction between the plant dynamics and the grid dynamics can be studied. Through this method, data extracted from NPP simulator, as an object, will be communicated to a server running PSCAD software. This paper will illustrate the use of Remote Procedure Calls (RPC) as a distributed, client-server based application used to establish a connection between NPP simulator running on UNIX server and PSCAD running on a PC. Using this method, the called procedure need not exist in the same address space as the calling procedure. Communication protocols available in the NPP simulator are used to export data from the simulator. (author)

Summary of structural analysis and comparison with experimental results for Paks NPP

International Nuclear Information System (INIS)

Hauptenbuchner, B.; David, M.

2001-01-01

This contribution deals with the analysis and comparison of the dynamic response, calculated and measured by the explosion test in Nuclear Power Plant Paks, Hungary. Some details of the calculation model are also presented. The calculated and measured data of dynamic response are compared in selected points of the NPP Paks reactor building. Conclusions and recommendations are derived from this comparison. (author)

Nuclear power plant personnel training and its evaluation. A guidebook

International Nuclear Information System (INIS)

1996-01-01

The Guidebook will prove especially useful for, and is addressed primarily to: nuclear power operating organizations establishing or upgrading their NPP personnel training systems; regulatory personnel responsible for setting requirements and/or evaluating NPP personnel training; and organizations (within or outside the operating organization) responsible for the development, implementation and evaluation of training programmes for NPP personnel. Figs, tabs

Study of the excretion of catecholamines in the Kozloduj NPP personnel

International Nuclear Information System (INIS)

Bliznakov, V.; Topalova, M.

1990-01-01

The changes in catecholamine excretion are determined in dynamics in 9 persons from the reactor hall, having received cumulative individual doses 0.022 - 0.50 Gy and exposed to thermal, sound and psycho-emotional impact. As controls 10 workers from a thermal power plant have been studied having a similar working conditions but without ionizing radiation. The noradrenaline (NA) and adrenaline (A) excretion have been determined in urine, collected in the beginning of the shift (8-11 a.m.) and in the end of the working day (1-4 p.m.). Statistically significant increase in the values of A and NA are established in NPP personnel in the beginning of the working day; they retain increased also later. The changes are interpreted as activation of sympathico-adrenaline system - a part of developing of common adaptation syndrome, connected with the labour activity in NPP. 2 tabs

Multimedia system for the visitors' centre at the Ignalina NPP

International Nuclear Information System (INIS)

Alvers, Margareta

1999-01-01

The contents illustrated with video clips, animations, photographs, show the follwing: History of Ignalina NPP (INPP) growing; Visaginas - how the town came into being; Lake Druksiai; Development of nuclear power; Technical data of INPP; Description of INPP; Characteristic features of RBMK reactors; Reactor design; Technical parametres of RBMK-1500 reactor; Nuclear reaction and nuclear fission; Types of nuclear reactors; Circuits and systems; Radiation safety; Safety systems at the INPP; Upgrading nuclear safety at INPP following the Chernobyl accident; Safety problems at MP; Radioactive waste management in the world; RW Management at MP; Energy in Lithuania (thermal power stations, cogeneration plants, producing biogas from organic waste)

A Tsunami PSA for Nuclear Power Plants in Korea

International Nuclear Information System (INIS)

Kim, Min Kyu; Choi, In Kil; Park, Jin Hee; Seo, Kyung Suk; Seo, Jeong Moon; Yang, Joon Eon

2010-06-01

For the evaluation of safety of NPP caused by Tsunami event, probabilistic safety assessment (PSA) method was applied in this study. At first, an empirical tsunami hazard analysis performed for an evaluation of tsunami return period. A procedure for tsunami fragility methodology was established, and target equipment and structures for investigation of Tsunami Hazard assessment were selected. A several fragility calculations were performed for equipment in Nuclear Power Plant and finally accident scenario of tsunami event in NPP was presented. Finally, a system analysis performed in the case of tsunami event for an evaluation of a CDF of Ulchin 56 NPP site. For the evaluation of safety of NPP caused by Tsunami event, probabilistic safety assessment (PSA) method was applied. A procedure for tsunami fragility methodology was established, and target equipment and structures for investigation of Tsunami Hazard assessment were selected. A several fragility calculations were performed for equipment in Nuclear Power Plant and finally accident scenario of tsunami event in NPP was presented. As a result, in the case of tsunami event, functional failure is mostly governed total failure probability of facilities in NPP site

Reserves of labour content reduction in NPP construction

International Nuclear Information System (INIS)

Bekerman, R.E.

1986-01-01

Specific labour contents when constructing NPP with RBMK-1000 and WWER-1000 type reactors are presented. Factors affecting labour content of NPP construction are shown. Measures aimed at labour content decrease are suggested

Reactor plant for Belene NPP completion

International Nuclear Information System (INIS)

Dragunov, Yu. G.; Ryzhov, S. B.; Ermakov, D. N.; Repin, A. I.

2004-01-01

Construction of 'Belene' NPP was started at the end of 80-ties using project U-87 with V-320 reactor plant, general designer of this plant is OKB 'Gidropress'. At the beginning of 90-ties, on completing the considerable number of deliveries and performance of civil engineering work at the site the NPP construction was suspended. Nowadays, considering the state of affairs at the site and the work performed by Bulgarian Party on preservation of the equipment delivered, the most perspective is supposed to be implementation of the following versions in completing 'Belene' NPP: for completion of Unit 1 - reactor plant VVER-1000 on the basis of V-320 reactor with the maximum use of the delivered equipment (V-320M) having the extended service life and safety improvement; for Unit 2 - advanced reactor plant VVER-1000. For the upgraded reactor plant V-230M the basic solutions and characteristics are presented, as well as the calculated justification of strength and safety analyses, design of the reactor core and fuel cycle, instrumentation and control systems, application of the 'leak-before break' in the project and implementation of safety measures. For the modernised reactor plant V-392M the main characteristics and basic changes are presented, concerning reactor pressure vessel, steam generator, reactor coolant pump set. Design of NPP with the modernized reactor plant V-320M meets the up-to-date requirements and can be licensed for completion and operation. In the design of NPP with the advanced reactor plant the basic solutions and the equipment are used that are similar to those used in standard reactor plant V-320 and new one with VVER-1000 under construction and completion in Russia, and abroad. Compliance of reactor design with the up-to-date international requirements, considering the extended service life of the main equipment, shows its rather high potential for implementation during completion of 'Belene' NPP

Integral thermal model of severe accident dynamics of NPP with containment

International Nuclear Information System (INIS)

Arutyunyan, R.V.; Bol'shov, L.A.; Vasil'ev, A.D.; Kamennov, G.P.

1991-01-01

An analytical model of the interaction of reactor core remains with concrete during severe accidents at nuclear power plants is considered. Time dependences of side and radial concrete melting are plotted. Time dependences of containment atmosphere temperature and pressure during a severe accident at nuclear power plants are investigated analytically and numerically. The sensitivity of the results to the coefficient values in the problem is studied within the range of their concertainty. The Kaverna-1 is described. The results of modelling a severe NPP accident which have been obtained using the Kaverna-1 package are presented

Modelling the impact of Cernavoda NPP on the environment

International Nuclear Information System (INIS)

Constantin, A.-I.

2001-01-01

In connection with a stay as a visiting researcher at VTT Energy (Technical Research Center of Finland), a study was conducted related to the atmospheric dispersion and dose assessment for radioactive releases from nuclear power plants. The most important aspects of this study are described in this paper. These include: the application of the TRADOS dispersion and dose assessment model in the case of the Cernavoda NPP and the development of a special program INTEGRATION for the calculation of cloud gamma dose rate of 72 nuclides. (authors)

Role of the team of scientific and technical commissioning support (TSTCS) during Mochovce NPP unit 3 and 4 commissioning

International Nuclear Information System (INIS)

Hermansky, J.; Prachar, M.; Sedlacek, M.; Petenyi, V.

2011-01-01

The Team of Scientific and Technical Commissioning Support (TSTCS) shall provide an independent support for the Mochovce NPP 3 and 4 Commissioning Department during Mochovce Units 3 and 4 commissioning. This independent support will be in line with the Mochovce NPP 3 and 4 Directive 'Non-active tests and commissioning' and it will be carried out in form of professional and expert works focusing on supervision of fulfilment of requirements for nuclear safety observance. The TSTCS duty to provide for such services during NPP commissioning is specified by Slovak Regulatory Body legislation. The independent TSTCS will supervise; - fulfilment of requirements for nuclear safety during preparation and implementation of commissioning tests; -scientific and technical level of commissioning programmes, and reflection on nuclear safety requirements in commissioning programmes,- commissioning process and test results. Main standpoints of the Team activities for individual unit commissioning stages will be; - assesment of the selected programs of functional tests in installations having an impact on nuclear safety and evaluation of the results of these tests; - assesment of the programs of physics and power commissioning, - assesment of the unit preparedness before fuel loading start; - assesment of the unit preparedness for performing initial criticality and low power commissioning and power commissioning stages; - evaluation of the results of physics and power commissioning stages and sub-stages; - final evaluation of the results from implementing the physics and power commissioning stages. The paper also presents a short description of the Team scope activities, the Team organisation, and a procedure for issuing of standpoints to individual unit commissioning stages. (Authors)

Optimalisation of national industry participation in nuclear power plant construction

International Nuclear Information System (INIS)

Sriyana

2008-01-01

A study of national industry participation based on recent data has already been conducted. The current industry data is used to estimate the optimum level of national industry participation in nuclear power plant (NPP) construction based on the prior study. The purpose of the study is to give a figure of the optimum level of national industry participation in NPP construction. The scope of the study is the NPP construction project in related to the potency of national industry to participate in the project. The methodology used in the study are literature study, web surfing for industrial data, and on-the-spot industry survey that are potential to participate in NPP construction. In addition to that, discussion with expertise of industrial practitioner was also conducted. The study concludes that (1) based on the recent national industry capability provided and compared to prior similar study, it is estimated that the level of national industry participation in the first NPP construction with the capacity of 1000 MWe PWR is about 40%. (2) to accelerate NPP technology transfer, we need to build a small size NPP. The nuclear island will be developed by BATAN in cooperation with national industry and the non-nuclear island will be developed by national industry. Universities and other academicians should be involved to support and keep the sustainability of man power availability in developing the NPP technology. (author)

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

Hydrodynamics and sediment transport at Muria Peninsula NPP Site

International Nuclear Information System (INIS)

Heni Susiati; Berni A Subki; Harman A

2011-01-01

Coastal along the coast of the Muria Peninsula, particularly the location of the Muria NPP site candidate is a dynamic region, the interaction between physical oceanographic factors such as currents, waves and tides in the coastal sediments cause abrasion or accretion. Interactions have resulted in coastal dynamics needs to be considered in siting NPP is essential in order to plan. Capacity of hydro-oceanographic data is essential in order to plan the development of the Muria NPP. The process of selecting a safe site for hydro-oceanographic aspects carried out according to IAEA safety standards on site selection. For the evaluation stage of hydro oceanographic potential site (site survey stage), the analysis is more focused on the tidal along the northern coast, bathymetry, potential water resources and hydrologic systems in the Muria NPP siting locations, Jepara. The method used is a secondary, confirmation of field data collection and interpretation of modeling results. The results showed that the preparation for the construction of NPP need to be evaluated further to coastal conditions with respect to the increase coastal erosion in the area of prospective NPP siting. (author)

Diversity of microflora at the fourth destroyed unit of the ChNPP

International Nuclear Information System (INIS)