Company profile VUJE

International Nuclear Information System (INIS)

Anon

2007-01-01

At the present time the whole world realizes the serious need for energy for the preservation of perpetually sustainable development. A distinctive place in the life of modern society belongs to electric energy,its safe production and reliable delivery according high standards of quality. When our company was established 30 years ago, we assumed research and development challenges directly related to the safe, reliable and economical production of electric energy from nuclear power plants, as well as the elimination of potential negative influences on the environment and employees. During our existence, we have gradually expanded our activities and specializations. Our first job was ti train plant personnel. We trained specialists to meet the needs not only of (what was then) Czechoslovakia, but also of Germany and Hungary. Gradually, we also met the problems of processing and storing radioactive waste, maintaining the service-life of our equipment and deactivating and disposing of contaminated devices at the end their operating lives. Industry requirements and concerns led use to broaden our services in energy production to include renewable sources of energy. Our youngest division of activity deals with the distribution of hydro-electrical energy via the electric grid. By continually updating the specialized skills of our employees and by investing in the latest equipment, our challenges and operational issues in the energy sector. Responding to developmental trends and the requirements of our consumers, we have established a system of quality management, which complies with the ISO 9001 and 14001 standards certified by the LRQA Corporation of Great Britain. Throughout the years, our company has been consistently proving to the operators of power facilities, both in Slovakia and abroad, our viability and high, innovative potential, in recognition of this, in 2005, when we participated in the sixth EU Framework Programme in R and D, the Slovak Ministry of Education presented use with the Award for the Organization Demonstrating the Most Successful Applied Research. Achieved results and the trust of our customers commit use to permanent improvement and increasing quality in the services we provide. We are proud to contribute to Slovak's energy safety, our society's quality of life, and our energy's perpetually sustainable development

Company profile VUJE

International Nuclear Information System (INIS)

Anon

2007-01-01

At the present time the whole world realizes the serious need for energy for the preservation of perpetually sustainable development. A distinctive place in the life of modern society belongs to electric energy,its safe production and reliable delivery according high standards of quality. When our company was established 30 years ago, we assumed research and development challenges directly related to the safe, reliable and economical production of electric energy from nuclear power plants, as well as the elimination of potential negative influences on the environment and employees. During our existence, we have gradually expanded our activities and specializations. Our first job was ti train plant personnel. We trained specialists to meet the needs not only of (what was then) Czechoslovakia, but also of Germany and Hungary. Gradually, we also met the problems of processing and storing radioactive waste, maintaining the service-life of our equipment and deactivating and disposing of contaminated devices at the end their operating lives. Industry requirements and concerns led us to broaden our services in energy production to include renewable sources of energy. Our youngest division of activity deals with the distribution of hydro-electrical energy via the electric grid. By continually updating the specialized skills of our elmasil and by investing in the latest equipment, our challenges and operational issues in the energy sector. Responding to developmental trends and the requirements of our consumers, we have established a system of quality management, which complies with the ISO 9001 and 14001 standards certified by the LRQA Corporation of Great Britain. Throughout the years, our company has been consistently proving to the operators of power facilities, both in Slovakia and abroad, our viability and high, innovative potential, in recognition of this, in 2005, when we participated in the sixth EU Framework Programme in R and D, the Slovak Ministry of Education presented us with the Award for the Organization Demonstrating the Most Successful Applied Research. Achieved results and the trust of our customers commit us to permanent improvement and increasing quality in the services we provide. We are proud to contribute to Slovak's energy safety, our society's quality of life, and our energy's perpetually sustainable development

COPMA-III demonstrator using HTML and JAVA applets

International Nuclear Information System (INIS)

Hrehus, M.; Kolarik, P.

1998-01-01

Fast and reliable utilisation of the process operation documentation during the work in the control room of the nuclear power plant is an important part of present safety precautions. These days are used for this purpose in many countries information systems for control and presentation of technological procedures. This report shows an idea of people of the Information technologies division of VUJE Tmava Inc about an architecture and possibilities of implementation one of such a system (in the following COPMAIII-vuje). The basic requirements put on this system come from an experience of the project developers of the project COPMA within the scope of the program OECD HRP which are described in the report HWR-385. The developers at VUJE were trying in their design by a goal: to design an architecture of the system that would satisfy specified requirements and it would be implemented in modem information environment. To this purpose where accomplished activities on a prototype of COPMAIII-vuje that contributed to some important conclusions. It has been observed that the technology of INTRANET/INTERNET fulfils the requirements for the design and using of the system. There were proposed new modules for the architecture of COPMAIII: ''workflow manager'' and ''procedure manager''. With no doubts a most important change is in a proposal of using a database format as a format for internal procedure description. (author)

Our services

International Nuclear Information System (INIS)

2007-01-01

In this video-films services of the VUJE, a. s. are presented. The company VUJE provides reconstruction and modernization of nuclear installations, research, development and production of equipment for nuclear power plants and electric industry, development of diagnostic methods, training on simulator of reactor, increase of reactor safety, preparation of documentation about NPP for the Nuclear Regulatory Authority of the Slovak Republic, measures for radiation protection and protection of the environment as well as development and application of information technologies.

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)

Unique systems for inspection and repair of VVER steam generators

International Nuclear Information System (INIS)

Kovalyk, Adrian; Pilat, Peter; Jablonicky, Pavol

2014-01-01

During over 30 years, VUJE Trnava has developed a series of remote control manipulators for in-service inspection and maintenance of steam generator collectors. The manipulators have been widely used on WWER type reactors in Slovakia and abroad. Some of the manipulators for non-destructive testing are shown.

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

ALARA radiation protection applications at NPP A1 decommissioning using VISPLAN planning tool

International Nuclear Information System (INIS)

Slavik, O.; Kucharova, D.; Listjak, M.

2005-01-01

The SCK.CEN developed during the BR3 reactor decommissioning a graphical interfaced 3D dose assessment tool aimed at the above mentioned dose optimization problems. The tool was improved further and commercialized under the name VISIPLAN 3D ALARA planning tool. The use of VISIPLAN tool at NPP A1 decommissioning was advised by EDF within the IAEA TCP SLR/4008 project missions as a component of a 3D technological chain ensuring acquisition and evaluation of digitized information leading to ALARA optimisation of the developed decommissioning working procedures (see Fig. 1). VISIPLAN license was purchased by IAEA and granted to VUJE and NPP A1 within the IAEA TCP project SLR/4008, covering also the necessary basic and advanced training (at NPP A1 real decommissioning environment), and is currently used by VUJE analysts at NPP A1 decommissioning as an ALARA tool for intervention planning and optimisation. The VISIPLAN allows a fast dose assessment for work planned in a radioactive environment. The calculations are based on a 3D model of the work place. This PC-based tool is user friendly and calculates a detailed dose account for different work scenarios defined by the ALARA analyst, taking into account worker position, work duration and subsequent geometry and source distribution changes. The VISIPLAN methodology is described. The VISIPLAN tool was applied to several ALARA studies carried out by the VUJE within development and analysis of various Work Programs for NPP Al decommissioning tasks. The applications ranged from simpler to complex ALARA planning tasks covering simple shielding applications to selection of the most suitable order of complex working procedures. Removal of inner liners from underground reservoirs 6/1 and 6/2 as well as Dismantling of pipes and components from a (hostile) 60 m corridor are described. (authors)

AER Working Group B activities in 2010

International Nuclear Information System (INIS)

Darilek, P.

2010-01-01

Review of AER Working Group B Meeting in Modra - Harmonia, Slovakia is given. Regular meeting of Core Design Group was organized by VUJE, Inc. and held at Modra - pension Harmonia, Slovakia, April 20-22, 2010, together with Working Group A. Presented papers (see List of papers and List of participants) covered topics as follows. (Author)

International cooperation

International Nuclear Information System (INIS)

2008-01-01

In this chapter international cooperation of the Division for Radiation Safety, NPP Decommissioning and Radwaste Management of the VUJE, a. s. is presented. Very important is cooperation with the International Atomic Energy Agency. This cooperation has various forms - national and regional projects of technical cooperation, coordinated research activities, participation of our experts in preparation of the IAEA documentation etc.

Operation diagnostics of the reactor coolant pumps in the Jaslovske Bohunice nuclear power plant, CSSR

International Nuclear Information System (INIS)

Bahna, J.; Jaros, I.; Oksa, G.

1990-01-01

The state of the art of the materials basis, the diagnostics methods used, organization of data collection and processing, and some results of routine and specific investigations concerned with diagnosis of the reactor coolant pump in the Jaslovske Bohunice NPP V-1 are presented. Some information is given about the reactor coolant pump monitor developed in the VUJE. (author)

Important projects of the Division

International Nuclear Information System (INIS)

2008-01-01

In this chapter important projects of the Division for Radiation Safety, NPP Decommissioning and Radwaste Management of the VUJE, a. s. are presented. Division for Radiation Safety, NPP Decommissioning and Radwaste Management has successfully carried out variety of significant projects. The most significant projects that were realised, are implemented and possible future projects are introduced in the following part of presentation.

Scientific conference proceedings. Session 3

International Nuclear Information System (INIS)

Bartosek, V.

1985-01-01

The Radiochemical Technology session met at UJV Rez on June 7, 1985 to hear 13 papers of which 11 were incorporated in INIS. The papers inform of results attained in the field of processing liquid radioactive wastes from nuclear power plants, processing spent nuclear fuel using the fluoride process, of the separation of fission products by dicarbolide extraction, the chemistry of complex uranium compounds, etc. The cooperation of UJV with VUJE and VUCHZ is also dealt with. (E.S.)

Diagnostic systems developed in NPPRI (VUJE) Trnava Inc. for NPPs

International Nuclear Information System (INIS)

Kucharek, P.

1998-01-01

Since foundation of Nuclear Power Plant Research Institute (NPPRI) in 1977, the department of diagnostics has been dealt with problems related to the theoretical, practical and organizatory questions of operational diagnostics connected with PWR type nuclear components. This department acts directly in locality of NPP Jaslovske Bohunice, but there are performances for all NPP in Slovak or Czech Republic (Dukovany, Mochovce, and Temelin). Besides direct services and achievements for NPP there exist advisory, experts and research activities for the government and supervising authorities, too. In 1985, NPPRI began systematically construct and verify technical means for operational diagnostics of main circulating pumps (MCP) with good results, based on own rich practical experiences and contacts with organisations abroad. In recent years NPPRI as one of recognised qualified and authorised institutions in Slovak Republic has begun to develop a new generation of diagnostic systems for NPP on high technical level but with lower procuring costs in comparison with western countries products. This contribution deals with four following types of diagnostic systems which were not only developed but also delivered and installed on Slovak and Czech nuclear units: - Loose part monitoring system (LPMS), - Humidity monitoring system (HUMON), - Reactor coolant pumps monitoring system (RCPMS), - Primary circuit vibration monitoring system (VMS). Main features of new generation from middle of 1990's of these systems are described in this paper and operational experiences with them too. (author)

Introductory speeches

International Nuclear Information System (INIS)

2001-01-01

This CD is multimedia presentation of programme safety upgrading of Bohunice V1 NPP. This chapter consist of introductory commentary and 4 introductory speeches (video records): (1) Introductory speech of Vincent Pillar, Board chairman and director general of Slovak electric, Plc. (SE); (2) Introductory speech of Stefan Schmidt, director of SE - Bohunice Nuclear power plants; (3) Introductory speech of Jan Korec, Board chairman and director general of VUJE Trnava, Inc. - Engineering, Design and Research Organisation, Trnava; Introductory speech of Dietrich Kuschel, Senior vice-president of FRAMATOME ANP Project and Engineering

The most extensive reconstruction of nuclear power plant with VVER 440/V230 reactor

International Nuclear Information System (INIS)

Ferenc, M.

2000-01-01

The nuclear power plant V-1 Bohunice consists of two VVER-440 units with V-230 reactors. Unit 1 was commissioned in 1978 and Unit 2 in 1980. Large experience and knowledge from the operation of previous units with V-230 reactors were incorporated into the V-1 design, which resulted in a higher level of safety and operational reliability of these units. The Siemens company which won an international bidding process developed these basic goals for the Gradual Upgrading into the so called Basic Engineering (BE). For the implementation of the Gradual Upgrading in line with the BE, Rekon consortium was established consisting of Siemens and VUJE. The implementation of the Gradual Upgrading is scheduled for the time period of 1996 - 2000. Siemens was responsible for the upgrading strategy - based on the approved results of the basic engineering phase and the PSAR, the engineering and realization of all I and C improvements, and also for the seismic upgrade. VUJE's responsibility covered the detailed engineering and implementation of mechanical, electrical and civil part of upgrading measures as well as overall organisation and evaluation of verification tests. The consortium awarded contracts for final planning and design, installation services and commissioning to other Slovakian subcontractors in order to ensure the largest possible local content. The gradual reconstruction of the V-1 Bohunice with V230 reactors represents a comprehensive reconstruction of safety-related systems and equipment. Following its completion, the units will be operated with a safety level accepted internationally. (author)

Nonlinear 3D calculations of turbine blade impact on turbine cover

International Nuclear Information System (INIS)

Hatala, B.; Adamik, V.; Buchar, J.

2000-01-01

This paper present the approach used at the VUJE institute for the evaluation of a ruptured blade impact on the current protection cover of a SKODA 220 MW turbine. Firstly, it briefly describes experiments (Hopkinson-Davies split bar facility, Taylor tests) and numerical simulations used to obtain realistic material parameters needed for the Cowper- Symonds material model that is implemented in the code LS-DYNA3D. Then, numerical simulations, by using the code, of the ruptured blade impact on various protection barriers are presented. These simulations make it possible to find an optimal solution for a new turbine protection cover. (author)

Experiences from start-up and use of fail-safe reactor level meter with KNITU probes

International Nuclear Information System (INIS)

Badiar, S.; Sipka, J.; Vanco, P.; Slanina, Marek; Liska, L.; Gavora, D.

2001-01-01

Within the framework of the reconstruction of both V1 Bohunice units with WWER-440/V-230 reactors, the VUJE-SIEMENS consortium implemented measurement systems for coolant level monitoring in reactor pressure vessels with 1E qualification, resp. with the qualification of category 1 according to NUSS RG1.97. The solution uses KNITU 11 probes made by Russian POZIT company. In operating plants, the installation causes problems in relation to the existing technology and quality assurance system. In the phase of implementation, the most important tasks were to resolve component quality, to commission the system, and to check its performance. (Authors)

Report on the evaluation under the Act No 24/2006 of Coll. Environmental Impact Assessment Law Extension of National Radioactive Waste Repository in Mochovce for disposal low-level radioactive waste and construction of very low-level radioactive waste repository

International Nuclear Information System (INIS)

Hanusik, V.; Moravek, J.; Kusovska, Z.

2011-01-01

The report elaborated assessment of the environmental impact of extension of the National Radioactive Waste Repository in Mochovce for disposal of low and intermediate level radioactive wastes. Within this repository also the premises for very low level radioactive waste deposition should be built. The assessment report was prepared according to the Act no. 24/2006 Coll, as amended 'On the assessment of environmental impacts' Annex No. 11 upon The scope of assessment issued by the competent authority on the basis of assessment of Intent for this action. The report was prepared in VUJE, Inc. Trnava for Nuclear and Decommissioning Company, Inc. Bratislava (JAVYS).

Bohunice Simulator Data Collection Project

International Nuclear Information System (INIS)

Cillik, Ivan; Prochaska, Jan

2002-01-01

The paper describes the way and results of human reliability data analysis collected as a part of the Bohunice Simulator Data Collection Project (BSDCP), which was performed by VUJE Trnava, Inc. with funding support from the U.S. DOE, National Nuclear Security Administration. The goal of the project was to create a methodology for simulator data collection and analysis to support activities in probabilistic safety assessment (PSA) and human reliability assessment for Jaslovske Bohunice nuclear power plant consisting of two sets of twin units: two VVER 440/V-230 (V1) and two VVER 440/V-213 (V2) reactors. During the project training of V-2 control room crews was performed at VUJE-Trnava simulator. The simulator training and the data collection were done in parallel. The main goal of BSDCP was to collect suitable data of human errors under simulated conditions requiring the use of symptom-based emergency operating procedures (SBEOPs). The subjects of the data collection were scenario progress time data, operator errors, and real-time technological parameters. The paper contains three main parts. The first part presents preparatory work and semi-automatic computer-based methods used to collect data and to check technological parameters in order to find hidden errors of operators, to be able to retrace the course of each scenario for purposes of further analysis, and to document the whole training process. The first part gives also an overview of collected data scope, human error taxonomy, and state classifications for SBEOP instructions coding. The second part describes analytical work undertaken to describe time distribution necessary for execution of various kinds of instructions performed by operators according to the classification for coding of SBEOP instructions. It also presents the methods used for determination of probability distribution for different operator errors. Results from the data evaluation are presented in the last part of the paper. An overview of

Bohunice Simulator Data Collection Project

International Nuclear Information System (INIS)

Cillik, I.; Prochaska, J.

2002-01-01

The paper describes the way and results of human reliability data analysis collected as a part of the Bohunice Simulator Data Collection Project (BSDCP), which was performed by VUJE Trnava, Inc. with funding support from the U.S. DOE, National Nuclear Security Administration. The goal of the project was to create a methodology for simulator data collection and analysis to support activities in probabilistic safety assessment (PSA) and human reliability assessment for Jaslovske Bohunice nuclear power plant consisting of two sets of twin units: two VVER 440/V-230 (V1) and two VVER 440/V-213 (V2) reactors. During the project, training of V-2 control room crews was performed at VUJE Trnava simulator. The simulator training and the data collection were done in parallel. The main goal of BSDCP was to collect suitable data of human errors under simulated conditions requiring the use of symptom-based emergency operating procedures (SBEOPs). The subjects of the data collection were scenario progress time data, operator errors, and real-time technological parameters. The paper contains three main parts. The first part presents preparatory work and semi-automatic computer-based methods used to collect data and to check technological parameters in order to find hidden errors of operators, to be able to retrace the course of each scenario for purposes of further analysis, and to document the whole training process. The first part gives also an overview of collected data scope, human error taxonomy, and state classifications for SBEOP instructions coding. The second part describes analytical work undertaken to describe time distribution necessary for execution of various kinds of instructions performed by operators according to the classification for coding of SBEOP instructions. It also presents the methods used for determination of probability distribution for various operator errors. Results from the data evaluation are presented in the last part of the paper. An overview of

Training of selected categories of personnel in VUJE branch training centre

International Nuclear Information System (INIS)

Jacko, J. et al.

1983-01-01

The educational and research activity is described of the training centre which trains personnel for nuclear power plants in Czechoslovakia. Educational work includes training of personnel, the development of instructional and training aids, the assignment of tutors, curriculum development and the organization of final examinations. The results of the centre's educational work for the years 1979 to 1982 are tabulated. The research work of the centre is aimed at improving and increasing the effectiveness of the educational and training process. The spaces and equipment of the centre are described as are personnel conditions, the approach of trainees to education and the attitude of managerial staff to the centre's activities. (J.P.)

General presentation of the EC FP7 SARGEN IV project

International Nuclear Information System (INIS)

Blanc, Daniel

2012-01-01

SARGEN I V project: Innovative reactors with fast spectrum to be built in Europe. The ESNII roadmap includes: • the ASTRID SFR prototype supported by the French Government; • ALFRED LFR demonstrator; → Romania is interested to host the ALFRED prototype. • the ALLEGRO GFR prototype → A Memorandum of Understanding (MOU) has been signed in May 2010 between UJV (Czech Republic), AEKI (Hungary) and VUJE (Slovakia) to develop ALLEGRO. • the MYRRHA experimental facility supported by the Belgian government is able to: → test the LFR technology; → provide irradiation in the fast spectrum area; → test the Accelerator Driven System (ADS) technology (not retained by the GIF)

Organization structure. Main activities of the Division

International Nuclear Information System (INIS)

2008-01-01

In this chapter the organization structure as well as main activities of the Division for radiation safety, NPP decommissioning and radioactive waste management are presented. This Division of the VUJE, a.s. consists of the following sections and departments: Section for economic and technical services; Section for radiation protection of employees; Department for management of emergency situations and risk assessment; Department for implementation of nuclear power facilities decommissioning and RAW management; Department for personnel and environmental dosimetry; Department for preparation of NPP decommissioning; Department for RAW treatment technologies; Department for chemical regimes and physico-chemical analyses; Department for management of nuclear power facilities decommissioning and RAW management. Main activities of this Division are presented.

Plugging criteria for WWER SG tubes

Energy Technology Data Exchange (ETDEWEB)

Papp, L.; Wilam, M. [Vitkovice NPP Services (Switzerland); Herman, M. [Vuje, Trnava (Slovakia)

1997-12-31

At operated Czech and Slovak nuclear power plants the 80 % criteria for crack or other bulk defect depth is used for steam generator heat exchanging tubes plugging. This criteria was accepted as the recommendation of designer of WWER steam generators. Verification of this criteria was the objective of experimental program performed by Vitkovice, J.S.C., UJV Rez, J.S.C. and Vuje Trnava, J.S.C .. Within this program the following factors were studied: (1) Influence of secondary water chemistry on defects initiation and propagation, (2) Statistical evaluation of corrosion defects progression at operated SG, and (3) Determination of critical pressure for tube rupture as a function of eddy current indications. In this presentation items (2) and (3) are considered.

Plugging criteria for WWER SG tubes

Energy Technology Data Exchange (ETDEWEB)

Papp, L; Wilam, M [Vitkovice NPP Services (Switzerland); Herman, M [Vuje, Trnava (Slovakia)

1998-12-31

At operated Czech and Slovak nuclear power plants the 80 % criteria for crack or other bulk defect depth is used for steam generator heat exchanging tubes plugging. This criteria was accepted as the recommendation of designer of WWER steam generators. Verification of this criteria was the objective of experimental program performed by Vitkovice, J.S.C., UJV Rez, J.S.C. and Vuje Trnava, J.S.C .. Within this program the following factors were studied: (1) Influence of secondary water chemistry on defects initiation and propagation, (2) Statistical evaluation of corrosion defects progression at operated SG, and (3) Determination of critical pressure for tube rupture as a function of eddy current indications. In this presentation items (2) and (3) are considered.

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)

LESPRO - an expert system for the decision support in determination and suggestion of protective measures

International Nuclear Information System (INIS)

Bohunova, J.; Duranova, T.; Hatar, E.

2000-01-01

A prototype expert system for advising emergency procedures for nuclear regulatory authority has been developed. The expert system ESPRO is known as goal oriented rule-based knowledge system. The system is based on emergency procedures developed in VUJE Trnava, Inc. for use by the Emergency Response Centre (ERC) of the Slovak Nuclear Regulatory Authority (NRA). The operation interpretation module uses the knowledge base of emergency procedures for the evaluation of source term and determination and suggestion of protective measures which is represented in the form of a Petri net model. Its verification and validation was done on the basis of the results of two exercises: joint exercise of ERC staff with Slovak Army Headquarters and full scale Mochovce NPP emergency exercise with use of the Mochovce NPP simulator. (author)

Chapter 9. Personnel qualification and training

International Nuclear Information System (INIS)

2001-01-01

The overall training system and the development of projects for training of all categories of NPP V-1, NPP V-2 Bohunice, SE-VYZ and NPP Mochovce staff were the subject of Nuclear Regulatory Authority of the Slovak Republic (UJD) attention. During 2000, the following inspections were carried out on nuclear personnel training: (a) NPP Bohunice: an inspection focused on compliance with requirements for staff qualifications and compliance with the prescribed training of Bohunice plant staff ; (b) NPP Mochovce: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of NPP Mochovce staff; an inspection focused on verifying the simulator aided training; an inspection focused on checking the preparedness of NPP Mochovce operation and technical personnel for NPP Mochovce Unit 2 operation; (c) Technology for treatment and conditioning of radioactive waste Bohunice (BSC): an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of SE-VYZ staff; VUJE Trnava: verification of technical equipment and professional skills of VUJE Trnava staff and tasks arising out of the 'Authorisation on nuclear installation staff training'. Examinations of selected personnel were scheduled according to the plan of examining committee meetings. For each examined person written tests are generated by the computer from the database of test questions at the Training Centre of VUJE Trnava for individual positions - categories of selected staff of NPP V-1 and NPP V-2 Bohunice and NPP Mochovce so that the examination questions both in written and oral part equally cover individual facilities and regimes of operation of NPP. The database is continuously updated, thereby containing new questions resulting from the recent changes carried out at NPPs. A part of the examination in case of promotion to a higher position is the practical part, which is conducted under

Implementation of pre-operational version of RODOS in Slovakia

International Nuclear Information System (INIS)

Duranova, T.; Janko, K.

2000-01-01

With support of the European Commission's Echo programme ''Implementation of the Rodeos Decision Support System for Off-Site Emergency Preparation and response in the Emergency centres in Poland and the Slovak Republics' '', Rodeos was implemented in the Slovak Republic. The main objective of the project - implemented by the Consortium of Ecton and STUK, with participation of VUJE and IAE - was to accelerate the implementation of the RODOS system within national emergency preparedness arrangements in Poland and the Slovak Republic. The main elements are: procure and install the computer hardware for the RODOS; establish dedicated communication lines; install and adapt RODOS software; test and verify the operability of the whole system; develop and implement procedures for the pre-operational integration of RODOS into national emergency arrangements; develop and implement maintenance procedures; develop and implement a training programme. (author)

Implementation of pre-operational version of RODOS in Slovakia

International Nuclear Information System (INIS)

Duranova, T.

2001-01-01

With support from the European Commission's ECHO programme 'Implementation of the RODOS Decision Support System for Off-Site Emergency Preparation and response in the Emergency centres in Poland and the Slovak Republic', RODOS was implemented in the Slovak Republic. The main objective of the project which was implemented by the Consortium of ENCONET and STUK, with participation of VUJE and IAE, was to accelerate the implementation of the RODOS system within national emergency preparedness arrangements in Poland and the Slovak Republic. The main elements are: procure and install the computer hardware for the RODOS; establish dedicated communication lines; install and adapt RODOS software; test and verify the operability of the whole system; develop and implement procedures for the pre-operational integration of RODOS into national emergency arrangements; develop and implement maintenance procedures; develop and implement a training programme. (author)

Chapter No.8. Personnel qualification and training

International Nuclear Information System (INIS)

2002-01-01

The overall training system and the development projects of training the staff of all categories from NPP V-1, NPP V-2 Bohunice, SE-VYZ and NPP Mochovce were the subject of UJD's attention. During 2001 following inspections were carried out on nuclear personnel training: - PP's Bohunice: an inspection focused on compliance with requirements for staff qualifications and compliance with the prescribed training of Bohunice plant staff; - Mochovce NPP: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of NPP Mochovce staff; - SE-VYZ: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of SE-VYZ staff. Training the staff of the NPP's Bohunice: - The fundamental and periodical theoretical training as sure as the fundamental and periodical simulator training is carried out by the VUJE Training centre in Trnava. - The fundamental practical training in the workplace and training for the change work- rank is carried at Bohunice plant. Training of the staff of the NPP Mochovce: - The fundamental and periodical theoretical training is carried out by the VUJE Training centre in Trnava. The fundamental practical training in the workplace and training for the change work- rank as well as the fundamental and periodical simulator training is carried at Mochovce plant. Based on a successful passing of examination before the examining committee, UJD issues a certificate on special professional skills of selected staff members of nuclear installations for specific activity for the given type of nuclear installation and for the following positions: 1. Scientific shift manager for start up with the right of manipulation; 2. Shift supervisor; 3. Unit supervisor; 4. Primary circuit operator; 5. Secondary circuit operator; 6. Reactor physicist; 7. Scientific shift manager for start up without the right of manipulation. Examinations of

Czech fiasco with oil reserves has not deterred Slovakia

International Nuclear Information System (INIS)

Haluza, I.

2004-01-01

In order to meet its obligation to keep a 90-day emergency reserve of oil and oil products, Slovakia must purchase about 40% of the required volume of these commodities and complete storage capacity for the reserves. In addition, it must also create a system of storage management for the reserves including a regular exchange of the contents of the tanks. If it does not meet the 2008 deadline, EU structural funds will be decreased. In order to create the missing storage capacity, the Sprava statnych hmotnych rezerv (SSHR - Administration of Public Material Reserves) is considering a solution which Slovnaft, a.s. sees as a major risk for the state. Should the hundreds of millions needed for the building of new tanks not be found in the budget, the state would invite private investors to build the tanks, stated SSHR Chairman, Jan Tusim. Private investors will not endanger public control over the emergency reserves. Other countries also lease tanks. But according to information provided by its chairman, SSHR also wants to make the private investors responsible for the regular exchange of the emergency reserves that must be carried out every four to five years. Given an accurate forecast of price development on international markets, a lot of money can be made on these exchanges. Slovnaft stresses that if the state were no longer responsible for the exchange of the tanks' contents, it would be the state that was at risk not the refineries

Nuclear safety. Improvement programme

International Nuclear Information System (INIS)

2000-01-01

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

Data base EQDB - data base of the qualified equipment's for NPP

International Nuclear Information System (INIS)

Rovny, K.

2009-01-01

In the contribution, there is presented the project of the data base for qualified equipment's for nuclear power plants. The data base is operated by the 'Certification body which certified the products - the chosen equipment's for nuclear power plants', reg. No. P-028, at VUJE, Inc. Trnava. Data base will serve to the designers, the operators of the nuclear power plants and the workers from Nuclear regulatory authority of the Slovak Republic as a source of information about the state of concrete type equipment's qualification. In the first part of the contribution, there is information about the legislation and technical requirements for equipment's qualification, the way of demonstration and importance of the qualification for the operator. In the next part, there is presented the own structure of data base and the works with own data base regarding the examples of concrete equipment's. The data base will be accessible after the free registration on address WWW.EQDB.sk from 1.5.2009

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)

Round Table: Integrating radiation protection research in the EU - European Joint Programme and participation of the Slovak Republic and Czech Republic national institutions in it

International Nuclear Information System (INIS)

Duranova, T.; Bohunova, J.; Raskop, W.; Schneider, T.; Liland, A.; Andronopoulos, S.; Mustonen, R.

2014-01-01

Activities of the NERIS-TP association are described. The NERIS ICRP Workshop, held in Bratislava, Slovak Republic in February 6-8, 2012, was organized by VUJE in cooperation with ICRP aiming to provide a forum for discussion and sharing of experiences on the implementation of the ICRP Recommendations. International, European and national perspectives were presented. 88 specialists from 51 organizations from 26 countries participated in the workshop. The final Dissemination Workshop 'Strengthening the Preparedness at National and Territorial Level Using New Tools and Methods - Stakeholders Experiences', was conducted in Oslo from 22 to 24 January 2014. International organisations such as HERCA, EC DG Research, IAEA, OECD/NEA, and NGOs such as NTW (Nuclear Transparency Watch) and GMF (Group of European Municipalities with Nuclear Facilities) as well as representatives of the OPERRA project participated in the workshop and particular panels. 82 experts and stakeholders participated in the workshop, representing twenty countries. Notably, participants from Japanese organisations provided first feedback from the management of the consequences of the Fukushima accident. (authors)

Preparation of physics commissioning of Mochovce units 3 and 4

International Nuclear Information System (INIS)

Sedlacek, M.; Chrapciak, V.

2010-01-01

The Project 'Mochovce Units 3 and 4 Completion' started in 2009 and it will be finished in 2013. VUJE, Inc. is one of the five main Project contractors for the Nuclear Island and it is responsible, inter alia, for Mochovce Units 3 and 4 commissioning. The commissioning of Units 3 and 4 includes the stages of Physics Commissioning and Power Commissioning. This paper deals with the preparation of Mochovce Units 3 and 4 Physics Commissioning. In the paper there is presented a preparation of some commissioning documents, e.g. 'Quality Assurance Programme', 'Commissioning Programme', 'Stage Programme for Physics Commissioning', 'Test working programmes', 'Neutron-physics characteristics for Physics and Power Commissioning', etc. The scope of Physics Commissioning is presented by list of tests. For assessment of tests results so-called three-level acceptance criteria will be applied: realization, design and safety criteria. In the paper there are also presented computer codes, which will be used for neutron-physics characteristics calculation and the fuel loading scheme for the reactor core of Mochovce Unit 3. (Authors)

Chemical composition determination of Bohunice 1 and 2 RPVs and hardness measurements of RPVs material

International Nuclear Information System (INIS)

Kupca, L.; Brezina, M.; Beno, P.; Kniz, I.

1994-01-01

The base informations of all activities concerning the material properties recovery performed before and after annealing procedure on the first two units V-230 type in NPP V-1, are the topic of this paper. The samples of weld and base metal from both RPVs NPP V-1 were prepared by special apparatus in the very narrow gap between the outside surface of the RPV and the reactor thermal shielding in the reactor cavity, from the critical circumferential weld joint no.4. The chemical composition of the samples was analyzed in Nuclear Power Plants Research Institute (VUJE) laboratories. Except these results achieved from the analysis of the irradiated samples are presented the evaluation results of the chemical composition influence on the RPVs materials brittle fracture temperatures. All these results which served as input data for the irradiation embrittlement recovery evaluation of the both RPV NPP V-1 in Jaslovske Bohunice, are presented in the form of the trend curves for both RPVs. (author). 10 refs, 7 figs, 1 tab

On-line testing of nuclear plant temperature and pressure instrumentation and other critical plant equipment. IAEA regional workshop. Working material

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-12-31

Under European regional TC project RER/4/011, IAEA and VUJE Training centre organized a workshop on On-line Testing of Nuclear Power Plant Temperature and Pressure Instrumentation and Other Critical Plant Equipment in Trnava, Slovak Republic, from 25 to 29 May 1998. The objective of the workshop was to review the state-of-the-art in NPP instrumentation, cover typical instrumentation problems and solutions, describe technical and regulatory requirements for verifying the performance of nuclear power plant instrumentation, describe new methods developed and applied in NPPs for on-line verification and performance of instrumentation and present new techniques using existing instrumentation to identify the on-set problems in the plant electrical, mechanical and thermal hydraulic systems. Particular emphasis was placed on temperature measurements by Resistance Temperature Detectors (RTDs) and thermocouples and pressure measurements using motion-balanced and forced-balanced pressure transmitters. This proceedings includes papers presented by the invited speakers and the participants each with an abstract as wells as a summary of the Round-Table discussions Refs, figs, tabs

Main achievements of the european research project NERIS-TP

International Nuclear Information System (INIS)

Duranova, T.; Bohunova, J.; Raskop, W.; Schneider, T.; Liland, A.; Andronopoulos, S.; Mustonen, R.

2014-01-01

Activities of the NERIS-TP association are described. The NERIS ICRP Workshop, held in Bratislava, Slovak Republic in February 6-8, 2012, was organized by VUJE in cooperation with ICRP aiming to provide a forum for discussion and sharing of experiences on the implementation of the ICRP Recommendations. International, European and national perspectives were presented. 88 specialists from 51 organizations from 26 countries participated in the workshop. The final Dissemination Workshop 'Strengthening the Preparedness at National and Territorial Level Using New Tools and Methods - Stakeholders Experiences', was conducted in Oslo from 22 to 24 January 2014. International organisations such as HERCA, EC DG Research, IAEA, OECD/NEA, and NGOs such as NTW (Nuclear Transparency Watch) and GMF (Group of European Municipalities with Nuclear Facilities) as well as representatives of the OPERRA project participated in the workshop and particular panels. 82 experts and stakeholders participated in the workshop, representing twenty countries. Notably, participants from Japanese organisations provided first feedback from the management of the consequences of the Fukushima accident. (authors)

Nuclear boom - challenge for research and development

International Nuclear Information System (INIS)

Korec, M.; Liska, P.

2009-01-01

In this lecture authors present research and development in which VUJE, a. s. has participated. Authors concluded that resume as soon as possible the short-term research and development tasks for the existing SE reactors, both, operational reactors of SE and for shut-downed reactors - JAVYS. (Financing with the contribution from the state but major part from the industry). In cooperation with state institutions, regulatory authorities and investor (would-be operator) and supplier (suppliers) define and prepare tasks focused on issues of new-built Generation III reactors (Financing split between the state and industry in accordance with the characteristics of the tasks). Begin preparing tasks for resolving development problems of Generation IV reactors: - Persuade politicians abut the inevitability of state participation in the process, including financing; - Involve in the process institutions that can significantly contribute to the problems resolving (mainly on technical level, but also on organization and potentially financial level); - Prepare international cooperation agreements in this field (based on the existing agreements, preparation of new agreements); - Define technical areas of cooperation (research infrastructure, experimental and development facilities, simulation tools).

On-line testing of nuclear plant temperature and pressure instrumentation and other critical plant equipment. IAEA regional workshop. Working material

International Nuclear Information System (INIS)

1998-01-01

Under European regional TC project RER/4/011, IAEA and VUJE Training centre organized a workshop on On-line Testing of Nuclear Power Plant Temperature and Pressure Instrumentation and Other Critical Plant Equipment in Trnava, Slovak Republic, from 25 to 29 May 1998. The objective of the workshop was to review the state-of-the-art in NPP instrumentation, cover typical instrumentation problems and solutions, describe technical and regulatory requirements for verifying the performance of nuclear power plant instrumentation, describe new methods developed and applied in NPPs for on-line verification and performance of instrumentation and present new techniques using existing instrumentation to identify the on-set problems in the plant electrical, mechanical and thermal hydraulic systems. Particular emphasis was placed on temperature measurements by Resistance Temperature Detectors (RTDs) and thermocouples and pressure measurements using motion-balanced and forced-balanced pressure transmitters. This proceedings includes papers presented by the invited speakers and the participants each with an abstract as wells as a summary of the Round-Table discussions

Reactor core T-H characteristics determination in case of parallel operation of different fuel assembly types

International Nuclear Information System (INIS)

Hermansky, J.; Petenyi, V.; Zavodsky, M.

2009-01-01

The WWER-440 nuclear fuel vendor permanently improve the assortment of produced nuclear fuel assemblies for achieving better fuel cycle economy and reactor operation safety. Therefore it is necessary to have the skilled methodology and computing code for analyzing factors which affecting the accuracy of flow redistributed determination through reactor on flows through separate parts of reactor core in case of parallel operation different assembly types. Whereas the geometric parameters of new manufactured assemblies were changed recently, the calculated flows through the fuel parts of different type of assemblies are depended also on their real position in reactor core. Therefore the computing code CORFLO was developed in VUJE Trnava for carrying out stationary analyses of T-H characteristics of reactor core within 60 deg symmetry. The CORFLO code deals the area of the active core which consists of 312 fuel assemblies and 37 control assemblies. Regarding the rotational 60 deg symmetry of reactor core only 1/6 of reactor core with 59 fuel assemblies is calculated. Computing code is verified and validated at this time. Paper presents the short description of computing code CORFLO with some calculated results. (Authors)

Legislation

International Nuclear Information System (INIS)

1996-01-01

Nuclear Regulatory Authority of the Slovak Republic (NRA SR) developed a methodology and the NRA SR Chairman's Regulation that sets out a uniform administration procedure in collecting administration fees, for the purpose of applying the Act of the National council of the Slovak Republic on Administration Fees. Pursuant to the Act on Czech-Slovak technical standards, NRA SR has a function of an uneglectable participant in commenting on draft Slovak technical standards (STN). A total of 101 drafts were reviewed. The standard drafts in most cases concerned taking European standards and international standards over into the STN system, with respect to the Slovak Republic integration into the European Union. Coordination of technical standardization is assessed by the Council for Technical Standardization that is established at the Slovak Institute of Technical Standardization. The NRA SR's staff member takes part at meetings of the Council. In the third year of their existence, NRA SR started to issue their own publications that should provide legal and qualified information about peaceful use of nuclear power. NRA SR in co-operation with VUJE a.s. Trnava issued the first publication 'Selected legal documents on peaceful use of nuclear power (general binding legal regulations)'. The publication contains texts or extracts from 21 regulations

Validation and comparison of dispersion models of RTARC DSS

International Nuclear Information System (INIS)

Duran, J.; Pospisil, M.

2004-01-01

RTARC DSS (Real Time Accident Release Consequences - Decision Support System) is a computer code developed at the VUJE Trnava, Inc. (Stubna, M. et al, 1993). The code calculations include atmospheric transport and diffusion, dose assessment, evaluation and displaying of the affected zones, evaluation of the early health effects, concentration and dose rate time dependence in the selected sites etc. The simulation of the protective measures (sheltering, iodine administration) is involved. The aim of this paper is to present the process of validation of the RTARC dispersion models. RTARC includes models for calculations of release for very short (Method Monte Carlo - MEMOC), short (Gaussian Straight-Line Model) and long distances (Puff Trajectory Model - PTM). Validation of the code RTARC was performed using the results of comparisons and experiments summarized in the Table 1.: 1. Experiments and comparisons in the process of validation of the system RTARC - experiments or comparison - distance - model. Wind tunnel experiments (Universitaet der Bundeswehr, Muenchen) - Area of NPP - Method Monte Carlo. INEL (Idaho National Engineering Laboratory) - short/medium - Gaussian model and multi tracer atmospheric experiment - distances - PTM. Model Validation Kit - short distances - Gaussian model. STEP II.b 'Realistic Case Studies' - long distances - PTM. ENSEMBLE comparison - long distances - PTM (orig.)

Information about AER WG A on improvement, extension and validation of parametrized few-group libraries for VVER 440 and VVER 1000

International Nuclear Information System (INIS)

Mikolas, P.

2010-01-01

Joint AER Working Group A on 'Improvement, extension and validation of parameterized few-group libraries for WWER-440 and WWER-1000' and AER Working Group B on 'Core design' nineteenth meeting was hosted by VUJE a. s. in Modra - Harmonia (Slovakia) during the period of 20. to 22. April 2010. There were present altogether 12 participants from 8 member organizations and 9 papers were presented (8 of them in written form). Objectives of the meeting of WG A are: Issues connected with spectral calculations and few-groups libraries preparation, their accuracy and validation. Presentations were devoted to some aspects of transport and diffusion calculations and to the benchmark dealing with WWER-1000 core periphery power tilt. Tamas Parko (co-authors Istvan Pos and Sandor Patai Szabo) described in his presentation 'Application of Discontinuity factors in C-PORCA 7 code', Radoslav Zajac (co-authors Petr Darilek and Vladimir Necas) spoke about 'Fast Reactor Nodalisation in HELIOS Code', Gabriel Farkas presented 'Calculation of Spatial Weighting Functions of Ex-Core Neutron Detectors for WWER-440 Using Monte Carlo Approach' and Daniel Sprinzl (co-authors Vaclav Krysl, Pavel Mikolas and Jiri Svarny) provided a definition of a benchmark in ' 'MIDICORE' WWER-1000 core periphery power tilt benchmark proposal'. (Author)

Role of Slovakia within the IAEA Decommissioning Related Activities

International Nuclear Information System (INIS)

Michal, V.; Stubna, M.

2009-01-01

Slovakia has a long-term experience with the IAEA decommissioning related activities as a recipient of Agency assistance and then as a country offering assistance to others. Background, short 'history' and current status of Slovakian national technical cooperation (TC) projects SLR/4/008 'Robotic Technologies for Decontamination and Decommissioning of the Bohunice A1 NPP' and SLR/3/002 'Management of Radioactive Waste from the A1 Nuclear Power Plant Decommissioning' will be described in paper. The first TC project SLR/4/008 was solved by the main Slovakian counterpart, company VUJE, Inc., from 2001 to 2006. Second TC project SLR/3/002 is ongoing with extension to 2011. Thanks to the implementation of a long-term large-scale 'Project of the A1 NPP Decommissioning - Stage I' (1996-2007), financed by Slovak National Nuclear Account (decommissioning fund), as well as implementation of the IAEA TC national projects a comprehensive know-how in the field of D and D and RAW management was obtained. Moreover, technologies and facilities necessary for implementation of decommissioning and RAW management projects were developed. Thanks to this development Slovakia offers donor assistance to other countries in subjected fields through IAEA TC program. The type and scope of assistance for Armenia, Bulgaria, Egypt, Latvia, Lithuania and The Ukraine is described in the paper. The above-mentioned national projects are not only activities of Slovakia within the IAEA TC program. Regional TC project RER/3/005 'Support in Planning the Decommissioning of Nuclear Power Plants and Research Reactors' has been ongoing from 2007 with accepted extension to 2011. About nine countries from Eastern and Central Europe participate in the project (for the NPPs part) and Slovakia plays the role of LCC (Leading Country Coordinator). On the basis of suggestion of Nuclear Regulatory Authority of the Slovak Republic, VUJE is the coordinator of the regional project. Moreover, Slovakia would be the

Proceedings of the international symposium on safety related measurements in PWRs: Topic of the first meeting: 'Temperature and level measurements'

International Nuclear Information System (INIS)

2001-09-01

Numerous teams of experts from several countries deal with theme of measurement important for safety operation of WWER reactors. These special teams have a need to meet at various opportunities to change their experience. As an example I can mention meeting of experts from Russia , Germany, France and Slovakia at completion and reconstruction of Slovak NPP, at modernisation of Russian and Bulgarian NPP. Mentioned meetings have invoked an idea of participants to organise a common action aimed at measurement important for safety operation of WWER, that participants can change their experience from mentioned area at welcome environment of symposium. Therefore, at meeting of experts from Siemens, INCOR and VUJE at the end of the year 2000 participants agreed on realisation of such common action. Participants have taken orientation at all safety measurements for very deep topic. Therefore, they have decided in respect of this first meeting of symposium to give consideration to only some special measurements in particular to temperature and surface. In case of interest there is possible to take focus at other type of measurements. Slovakia has been chosen for the first meeting place on basis of economic reasons and also because a number of improvements of standard reactor temperature measuring procedures have been implemented here that over passed its frontiers. In addition the first fail-safe level measuring in reactor pressure vessel has been effectuated in Slovakia

RODOS System in the Slovak Republic - its Implementation and Adaptation

International Nuclear Information System (INIS)

Duranova, T.; Bohun, L; Metke, E.; Janko, K.

2003-01-01

With support of the European Commission's (EC) ECHO programme 'Implementation of the RODOS Decision Support System for Off-Site Emergency Preparation and response in the Emergency centres in Poland and the Slovak Republic', RODOS system version 3.13 was implemented in the Slovak Republic with main objective to accelerate the implementation of the system within national emergency preparedness arrangements. Within the ECHO project, the National Centre of RODOS was established at the Nuclear Regulatory Authority of the Slovak Republic (NRA SR). VUJE was established as technical support organization and interactive user. As a data supplier and passive user were established the Slovak Centre for Radiation Monitoring, Slovak Hydro-Meteorological Institute (SHMI), Jaslovske Bohunice and Mochovce NPP's. As RODOS could become a standard tool for emergency preparedness in the European Union and CEE region lessons learned within projects mentioned in the paper were valuable contribution to other similar international and national projects. Effective working arrangements and links have been established between some institutes having competence in various aspects of emergency preparedness and response in about 20 European countries, with Forschungszentrum Karlsruhe as main responsible institute for system development and DSSNET project co-ordination. This network contributes to the more cost-effective use of resources for the further improvement of decision support for nuclear emergencies. More importantly, it will enhance trust and confidence between people, which is essential for responding effectively and coherently to any future nuclear accident that may have implications on a European scale. (authors)

Pilot exemption of the controlled area from regulatory control at NPP A1 -lessons learned

International Nuclear Information System (INIS)

Slaninka, A.; Listjak, M.; Slavik, O.; Rau, L.

2014-01-01

The contribution includes the lessons learned within frame of the radiological characterisation of surface ground layer in the NPP A1 site of area approximately 60 m2 (9 x 7 m) that was a part of Controlled area. Aim of the characterisation was a demonstration that the area fulfils the requirements to exemption from Controlled area for purpose of decommissioning activities carry out within frame of II. stage of NPP A1 decommissioning project.The requirements on free release of materials into the environment were applied (e.g. 300 Bq/kg for single 137 Cs). Radiological characterisation was performed by two independent methods; in situ scintillation gamma spectrometry and systematic sampling in regular grid followed by gamma spectrometry analyses in accredited laboratory of VUJE, Inc. (S-219). This improved the quality of monitoring and at the same time it enabled the inter-comparison of results obtained by both mentioned independent methods.Characterised ground area was partitioned to smaller sub-areas of 4 m2. At ground layer of 20 cm it means approximately 1000 kg of ground (in compliance with requirements on reference area at even activity distribution according to government regulation No 345/2006) The results of measurements showed that under appropriate conditions (sufficiently low radiation background, on interfering external sources) also the designed in situ method is effective and reliable tool for contaminated ground layer identification. In addition the in situ method is more effective in terms of time and cost consumption on unit of monitored area. (authors)

Study on the Development of Methodology for Cost Calculations and Financial Planning of Decommissioning Operations

International Nuclear Information System (INIS)

2001-12-01

The following study deals with the development of methodology for cost calculations and financial planning of decommissioning operations. It has been carried out by EDF / FRAMATOME / VUJE / SCK-CEN in the frame of the contract B7-032/2000/291058/MAR/C2 awarded by the European Commission. This study consists of 4 parts. The first task objective is to develop a reliable and transparent methodology for cost assessment and financial planning sufficient precise but without long and in depth investigations and studies. This methodology mainly contains: Calculation methods and algorithms for the elaboration of costs items making up the whole decommissioning cost. Estimated or standard values for the parameters and for the cost factors to be used in the above-mentioned algorithms Financial mechanism to be applied as to establish a financial planning. The second part task is the provision of standard values for the different parameters and costs factors described in the above-mentioned algorithms. This provision of data is based on the own various experience acquired by the members of the working team and on existing international references (databases, publications and reports). As decommissioning operations are spreading over several dozens of years, the scope of this task the description of the financial mechanisms to be applied to the different cost items as to establish a complete financial cost. It takes into account the financial schedule issued in task 1. The scope of this task consists in bringing together in a guideline all the information collected before: algorithms, data and financial mechanisms. (A.L.B.)

Chapter 7. Radioactive wastes

International Nuclear Information System (INIS)

2000-01-01

The inspection and assessment activities of Nuclear Regulatory Authority of the Slovak Republic (UJD) focused on minimization of activity and the quantity of produced radioactive waste (RAW), and on increasing safety of waste management. The general scheme of rad-waste management in the Slovak Republic is presented. The radioactive wastes produced during the operation of NPP V-1, NPP V-2 and NPP Mochovce in 1999 are listed.Liquid RAW was treated and conditioned into a solid form at the nuclear facility Technology for treatment and conditioning of RAW. In 1999 combustible solid waste was treated at the nuclear facility Incinerator of VUJE Trnava. Produced liquid and solid RAW are stored at designed equipment at individual nuclear installations (in case of NPP V-1, NPP V-2 Bohunice and NPP Mochovce in compliance with the Regulation No. 67/1987 Coll. law).The status of free capacity of these storages as of 31.121999 is presented. Storage solidified product built the SE-VYZ was fully filled at the end of 1999. In 1999 there was a significant improvement in the process of radioactive waste management by: (A) issuing approval for commissioning the National Repository for RAW, (B) issuing approval for commissioning the Treatment and Conditioning Center for RAW, (C) having the application for approval to transport conditioned RAW to the National repository Mochovce in the final stage of evaluation. At the beginning of 2000 it is realistic to expect that RAW conditioned in the Conditioning center of RAW will start to be disposed at the National repository of RAW in Mochovce

Radiological characterisation of contaminated concretes from the object 44/20 of NPP A1

International Nuclear Information System (INIS)

Slavik, O.; Listjak, M.; Pely, I.; Soos, F.

2005-01-01

Results of radiological characterisation of contaminated concretes from object 44/20 of the NPP A-1 Jaslovske Bohunice are summarized in this work. These works were carried out in VUJE in the laboratory of environmental dosimetry in 2004 and partially in 2005. The main results of radiological characterisation can be summarised as follow: (1) Contamination of concretes is in all cases surficial, it reaches up to 5-10 mm, the dominant contaminant is 137 Cs; (2) The spawn concrete is mostly contaminated only from one side (one being adjacent to the ceiling concrete), crucial part of them is even on this side contaminated in very low level complying with free release level; (3) The ceiling concrete blocks are contaminated mostly on one side, only (the inner side of shafts), their decontamination will require removing of about 5 mm thick surface layer. (4) The floor concrete is covered by heavily contaminated dust 137 CS, 100-500 Bq/g), originating from sorting of the wet RAW .Its decontamination will require removing of 10 mm thick surface concrete layer; (5) The core samples taken from the whole depth profile of the ceiling concrete show also only surface contamination, samples prepared from the deeper layers have not demonstrated any contamination in these layers. Control measurements of deeper concrete layers, however, went on with negative results also in year 2005; (6) The relative content for 90 Sr in these concretes is in average about 8%, for 241 Am determined by gamma-spectrometry is 0.4% and for 239 , 240 Pu determined radiochemically is 0.33% in comparison with the content of 137 Cs. (authors)

External hazards analysis approach to level 1 PSA of Mochovce NPP - Slovakia

International Nuclear Information System (INIS)

Stojka, Tibor

2000-01-01

Analyses of external events had been first time performed at the design stage of the Mochovce NPP showing sufficiently low contribution of external hazards to core damage frequency. But, based on IAEA document 'Safety problems of WWER-440/213 NPPs and the categorization' (IAEA-EBP-WWER-03, 1996), the need of new reassessment arose due to discrepancy of some origin recommendations in compare with present IAEA ones. Mochovce NPP Nuclear Safety Improvements Program elaborated at the same time included the IAEA recommendations and following improvements were proposed to perform in context of external events. 1. Seismic project and new locality seismic evaluation This safety improvement includes also some 'on site' technical improvements in seismic stability of structures and equipment. 2. Unit specific analyses of extreme meteorologic conditions. This safety improvement focuses on impact of feasible extreme conditions on NPP systems caused by rain, snow and hail storms, frost, winds, low and high temperatures. 3. Analyses of external hazards caused by humans. In this safety improvement were specified: feasible sources of explosions; analyses of hydrogen, gas and propane-calor gas depots; air crash risk. The results of these implemented safety improvements were considered in the PSA study. The External hazards analysis is also part of Level 1 PSA Mochovce NPP performed by PSA Department of VUJE Trnava Inc., Engineering, Design and Research Organization, Slovakia. Some partial analyses are performed in cooperation with following companies DS and S - SAIC, USA and Geophysical Institute Academy of Science, Slovakia Relko, Slovakia. Basic documents are: NUREG/CR-2300 'PRA Procedures Guide - A Guide to the Performance of Probabilistic Risk Assessments for Nuclear Power Plants' and IAEA SS No. 50-P-7 'Treatment of External Hazards in PSA for NPPs. The external hazards analysis consists of following parts: 1. Geography and plant locality; 2. Nearby industry; 3. Extreme

Chapter 9. Personnel qualification and training

International Nuclear Information System (INIS)

2000-01-01

In 1999 the Nuclear Regulatory Authority of the Slovak Republic (UJD) focused on the overall training system and on developing programmes for individual categories for NPP V-1 Bohunice, NPP V-2 Bohunice, NPP Mochovce and SE-VYZ. The fundamental theoretical and periodical training for both Bohunice and Mochovce NPPs personnel, simulator training for NPP Bohunice, and periodical simulator training for Bohunice personnel is carried out by the VUJE Training center in Trnava, whereas the simulator training and periodical training for NPP Mochovce is carried at Mochovce plant. Based on a successful passing of examination before the examining committee, UJD issues, a certificate on special professional skills of selected staff of nuclear installations for specific activity for the given type of nuclear installation and for the following positions: (a)Shift manager for scientific start up with the right of manipulation; (b) Shift supervisor; (c) Unit supervisor; (d) Primary circuit operator; (e) Secondary circuit operator; (f) Reactor physicist; (g) Shift manager for scientific start up without the right of manipulation. Examination of selected personnel is described. Last year the examining committee held twelve session for oral theoretical examination. The number of licenses issued in 1999 and the total number of valid licenses is given.Conclusions from inspections carried out by UJD and inspections and tests carried out by the NPP operators in 1999, as well as results from operation and start up of nuclear units confirm that the standard of professional skills of the staff at nuclear installations a high standard of operational safety is being achieved on a permanent basis. Increasing the qualification of UJD staff was done in a form of training and courses scheduled in the plan of training for the staff for 1999. These training, composed of specialized qualification study, functional study, as well as study aimed at maintaining qualification. Training courses organized

Chemické úlohy se školními měřicími systémy: motivační orientace žáků v badatelsky orientovaných úlohách

Directory of Open Access Journals (Sweden)

Petr Šmejkal

2016-07-01

Questionnaire (MSLQ a (ii Intrinsic Motivation Inventory (IMI. Dotazníky byly statisticky zpracovány – analýzou úrovně reliability (Cronbachovo alfa, analýzou rozptylu (jednoprůchodová ANOVA a shlukovou analýzou. Výsledky ukázaly, že většina žáků byla již před laboratorní prací dostatečně motivována, jejich motivace se po realizaci cvičení ještě zvýšila. Studované aktivity byly hodnoceny nadprůměrně, zvláště pak ty, které se vztahovaly bezprostředně k lidskému tělu (účinnost antacid či medializovaným tématům (plynová chromatografie – methanolová aféra. Analýza rozptylu pak ukázala, že ze sledovatelných faktorů ovlivňující motivační orientace žáků je převážně škola, kterou žák navštěvuje, a potažmo učitel chemie. Naopak, minimálně ovlivňuje motivační orientace pohlaví či realizovaná aktivita. Práce na aktivitách a se školními měřicími systémy žáky ve většině bavila a celkově lze říci, že žáci jsou nakloněni implementaci měřicích systémů do výuky, které tak mají ve výuce přírodních věd nepochybně své místo.

Monitoring of arched sched ground layer

International Nuclear Information System (INIS)

Listjak, M.; Slaninka, A.; Rau, L.; Pajersky, P.

2015-01-01

Arched Shed was a part of controlled area of NPP A1 site in Jaslovske Bohunice (Slovakia). It had been used for temporary storage of loose radioactive waste (RAW) which has been characterized within the BIDSF project C13, Characterisation of Loose Radioactive Waste'. Stored RAW has been treated and sorted within the project ',Realization of the 2 nd stage of Decommissioning Project of NPP A1'. Area of Arched Shed represents approximately 270 m 2 (45 m x 6 m). Ground layer of the AS consists mostly of soil with solid elements (stones and gravel). The aim of monitoring was to remove the contaminated soil up to 1 m below ground level. Requirement for detail monitoring of the Arched Shed ground layer resulted from conclusions of the BIDSF project C13 which has proved that massic activity 137 Cs of soil was up to few thousands Bq·kg -1 in underground layer. Dominant easy to measure radionuclide in the soil is 137 Cs which has been used as a key radionuclide for methodology of in-situ soil monitoring. Following methods has been applied during characterization: dose rate survey, sampling from defined ground layer followed by laboratory gamma spectrometry analysis by the accredited testing laboratory of radiation dosimetry VUJE (S-219) and in-situ scintillation gamma spectrometry by 1.5''x1.5'' LaBr detector. Massic activity of the remaining soil (not excavated) comply the criteria for free release into the environment (Government Regulation of Slovak Republic 345/2006 Coll.). Area was filled up by non-contaminated soil up to the ground level of surroundings. Afterward the area was covered with geotextile and concrete panels and nowadays it is ready for further usage within the NPP A1 decommissioning project as a place for treatment, conditioning and disposal of contaminated soil and concrete. (authors)

Chapter 8: Quality assurance

International Nuclear Information System (INIS)

2001-01-01

The main efforts of Nuclear Regulatory Authority of the Slovak Republic (UJD) have been focused on inspection of quality assurance programmes of Slovak Power Stations, plc. and its daughter companies at Bohunice and Mochovce. Two quality assurance inspections in the area of periodical in service inspections (V-2 units) and tests of selected equipment (NPP V-2 units) and operation control (V-1 units) has been performed at NPPs Bohunice. One violation of decree on quality assurance of selected equipment has been found in the area of documentation archiving. The inspection concerning the implementation of quality assurance programme for operation of NPP Mochovce in the area of operation control has been performed focused on safety aspects of operation, operational procedures, control of operational events and feedback from operational experience. The results of this inspection were positive. Inspection of implementation of quality assurance programme for operation of radioactive waste repository (RU RAW) at the Mochovce location has been performed focused on receiving of containers, with radioactive wastes, containers handling, radiation monitoring, activities of documentation control and radiation protection at the repository site. No serious deficiencies have been found out. Also one inspection of experimental nuclear installations of VUJE Trnava at Jaslovske Bohunice site has been performed focused on procurement control, quality audits, documentation and quality records control when performing activities at experimental nuclear installations. The activity on development of internal quality assurance system continued. The implementation of this system will assure quality and effective fulfilment enlarged tasks of UJD with limited resources for its activity. The analyses of possible use of existing internal administrative control documentation as a basis for future quality system procedures was performed in co-operation with an external specialised organisation. The

OECD-IAEA Paks Fuel Project. Final Report

International Nuclear Information System (INIS)

2010-05-01

provided financial support to the operating agent (Hungarian Academy of Sciences KFKI Atomic Energy Research Institute (AEKI)) and reviewed the progress of the project within the framework of Technical Cooperation Project, RER9076, on Strengthening Safety and Reliability of Fuel and Material in Nuclear Power Plants. Thirty organizations from sixteen countries participated in the project. The following participants performed analyses of the event using numerical models based on a common database: AEKI (Hungary), SUEZ - TRACTEBEL ENGINEERING, BME NTI (Hungary), (Belgium), GRS (Germany), NRC (United States of America), IRSN (France), VEIKI (Hungary), IVS (Slovakia), VTT (Finland), KI (Russian Federation), VUJE (Slovakia). The main results of calculations are summarized in the present report

Chapter No.6. Radioactive waste (RAW)

International Nuclear Information System (INIS)

2002-01-01

UJD SR supervises all phases of radioactive waste management at nuclear installations and final phases of institutional radioactive waste management. Total concentrates generation and minimisation trends during recent period (for NPP V1, NPP V2 Bohunice and NPP Mochovce) as well as increasing of their conditioning are presented. So nearly 8000 m3 of concentrates were stored at the end of year 2001, representing 75.5% of storage capacity at Bohunice site. Total amount of solid waste stored at VVER NPPs reached 3500 m3 at December 2001. The solid waste storage capacity of NPP V1 Bohunice is spent. NPP A1 Bohunice with a heterogeneous reactor using natural uranium, moderated by heavy water and cooled by CO 2 had been in operation for 4 years. It was finally shut down in February 1977 after an accident (INES level 4). Main activities in 2001 were focused on an increasing of radwaste management safety by the waste solidification or storage improvement, especially in the case of inorganic spent fuel coolant. The total solid radwaste inventory in 2001 (including filters) represents cca 700 m3 of soft and pre-pressed not sorted waste, 700 m3 of sorted waste, more then 1 000 t of scrap and next 260 m3 of scrap in drums. The total volume of contaminated soils and concrete is more than 7200 m3. The volume of solid radwaste depends on the extent of dismantling works and following treatment, conditioning and disposal. The total volume is also increased by products of bituminization and cementation facilities in drums stored before conditioning at NPP A1 Bohunice site. The facilities focused only on treatment of radwaste from NPP A1 decommissioning are operated by the same operator as a part of this decommissioned nuclear installation. Experimental and research treatment plants are operated by VUJE. A facility for the treatment and conditioning of operational liquid radwaste from NPP Mochovce is under preparation and a start of construction is foreseen in 2004. The nuclear

Final Treatment Center Project for Liquid and Wet Radioactive Waste in Slovakia

International Nuclear Information System (INIS)

Kravarik, K.; Stubna, M.; Pekar, A.; Krajc, T.; Zatkulak, M.; Holicka, Z.; Slezak, M.

2006-01-01

The Final Treatment Center (FTC) for Mochovce nuclear power plant (NPP) is designed for treatment and final conditioning of radioactive liquid and wet waste produced from plant operation. Mochovce NNP uses a Russian VVER-440 type reactor. Treated wastes comprise radioactive concentrates, spent resin and sludge. VUJE Inc. as an experienced company in field of treatment of radioactive waste in Slovakia has been chosen as main contractor for technological part of FTC. This paper describes the capacity, flow chart, overall waste flow and parameters of the main components in the FTC. The initial project was submitted for approval to the Slovak Electric plc. in 2003. The design and manufacture of main components were performed in 2004 and 2005. FTC construction work started early in 2004. Initial non-radioactive testing of the system is planned for summer 2006 and then radioactive tests are to be followed. A one-year trial operation of facility is planned for completion in 2007. SE - VYZ will be operates the FTC during trial operation and after its completion. SE - VYZ is subsidiary company of Slovak Electric plc. and it is responsible for treatment with radioactive waste and spent fuel in the Slovak republic. SE - VYZ has, besides of other significant experience with operation of Jaslovske Bohunice Treatment Centre. The overall capacity of the FTC is 870 m 3 /year of concentrates and 40 m 3 /year of spent resin and sludge. Bituminization and cementation were provided as main technologies for treatment of these wastes. Treatment of concentrate is performed by bituminization. Concentrate and bitumen are metered into a thin film evaporator with rotating wiping blades. Surplus water is evaporated and concentrate salts are embedded in bitumen. Bitumen product is discharged into 200 l steel drums. Spent resin and sludge are decanted, dried and mixed with bitumen. These mixtures are also discharged into 200 l steel drums. Drums are moved along bituminization line on a roller

Chapter No.11. Public information

International Nuclear Information System (INIS)

2002-01-01

pursuant to Act No 211/2000 of Coll. was published on UJD web site (www.ujd.gov.sk). From January 2001, 56 requests were registered asking for the information (by phone, e-mail, letter or personally). One written request from Greenpeace was not satisfied since the information is a matter of business secret. The matter is in the proceeding of the Supreme Court of the Slovak Republic. The Slovak press agencies, daily newspapers and electronic media were provided with 63 contributions on domestic and foreign UJD activities. UJD, together with SUJB, issues the expert journal 'Bezpecnost jadrovej energetiky (Nuclear Sector Safety)'. Two important articles on UJD legislative activities and on informing the public were published in monthly 'Verejna sprava (Public Administration)'. Contributions on supervisory activity and on UJD international co-operation are published regularly in 'Spravodajstvo SE (SE Information Service)', company journals 'Mochovce' and 'Bohunice'. Domestic and foreign UJD activities were presented in 5 issues of 'Bulletin Slovenskej nuklearnej spolocnosti (Slovak Nuclear Society Bulletin)'. This year, the report on nuclear facilities safety and on handling with spent nuclear fuel and radioactive waste in the Slovak Republic was published in European Nuclear Society journal 'Nuclear Europe Worldscan No 7-8/2001'. Several important contributions were published in journal 'Energia (Energy)'. Contributions on UJD tasks and mission in the Slovak Republic were published in 'Energia almanach (Energy Almanac 2001/2002)' and in 'Euro Nuclear'. Three contributions on domestic and foreign UJD activities were prepared for the world information Agency NucNet. Slovak-English additional information document on UJD was elaborated and issued for the public in December 2001. The 2001 Yearbook on UJD activities and on nuclear facilities safety in the Slovak Republic was prepared and issued in Slovak and English version. Four press conferences took place in 2001 in UJD followed

Chapter 12. Public information

International Nuclear Information System (INIS)

2001-01-01

'Nuclear Power Engineering Safety' running substantial articles from major UJD activities. The double issues 7/8 and 11/12 (2000) included safety analyses - NPP V-1 Bohunice and NPP Mochovce units safety assessment. The monthly 'Verejna sprava' (Public Administration) ran in 2000 two substantial articles on UJD legislative and state law activities. Contributions on UJD regulatory activity and international co-operation appear on a regular basis in 'Spravodajstvo SE, a.s.' (SE, a.s., Newsletter) and in-house journals 'Mochovce' and 'Bohunice'. UJD domestic and foreign activities were published in 5 issues in 'Slovak Nuclear Society (SNUS) Bulletin'. A report on the safety of nuclear installations and the management of spent nuclear fuel and radioactive wastes in the Slovak Republic in the journal 'Nuclear Europe Worldscan' No. 7-8/2000 was also published the year 2000. A number of substantial articles were published in the magazine Energia. A contribution on UJD's mission and tasks in the Slovak Republic was published in 'Energia Almanach' 2000/2001. Six contributions focused on UJD's domestic and foreign activities were prepared for the world information agency NucNet. A Slovak-English information material on UJD (12/2000) was prepared and published for the public. Also the Slovak-English 1999 Annual Report on the results of UJD activity and nuclear installation safety in the Slovak Republic was prepared and published. In 2000, four press conferences were held at UJD, with follow-up appearances by UJD management in television and radio. UJD executives made five appearances in television and gave six interviews and seven relevant interviews for Slovak Radio and magazines and dailies, respectively. In 2000, two video-clips were produced for the public, namely on the 'UJD tasks and mission' and 'emergency planning'. A highly successful press conference on Slovakia's NPP safety was arranged by UJD on the occasion of the visit to Slovakia by the OECD/ Nuclear Energy Agency

Enlarged Halden programme group meeting on high burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects and man-machine systems research. Volume II

International Nuclear Information System (INIS)

1999-01-01

Academy of Sciences, KFKI Atomic Energy Research Institute, the N.V. KEMA, the Netherlands, the Russian Research Centre 'Kurchatov Institute', the Slovakian VUJE - Nuclear Power Plant Research Institute, and from USA: the ABB Combustion Engineering Inc., the Electric Power Research Institute (EPRI), and the General Electric Co. The right to utilise information originating from the research work of the Halden Project is limited to persons and undertakings specifically given this right by one of these Project member organisations. The activities in the area of fuel and materials performance are based on extensive in-reactor measurements. The programmes are expanding in the areas of fuel performance at extended burn-ups, waterside corrosion and material testing in general. Development of in-core instruments is an important activity in support of the experimental programmes. The research programme at the Halden Project addresses the research needs of the nuclear industry in connection with introduction of digital I and C systems in NPPs. The programme provides information supporting design and licensing of upgraded, computer-based control room systems, and demonstrates the benefits of such systems through validation experiments in Halden's experimental research facility, HAMMLAB and pilot installations in NPPs. The Enlarged Halden Programme Group Meeting at Loen, Norway, was arranged to provide an opportunity to present results of work carried out at Halden and within participating organisations, and to encourage comments and impulses related to future Halden Project work. This HPR-351 relates to the fuel and materials part of the meeting and is divided in two volumes, HPR-351 Volume I and HPR-351 Volume II. The corresponding collection of papers in the man-machine area are given in one volume, HPR-352 Volume I. The overall programme of the Loen Enlarged Meeting covering the Fuel and Materials Research is given in the following pages. The papers with denomination HWR have

Chapter 4. Assessment and inspection of nuclear installations

International Nuclear Information System (INIS)

2001-01-01

develop protocols in which the findings from these inspections are specified. This protocol also contains orders and measures imposed by UJD to correct the shortcomings found. Qualifications and examinations of nuclear safety inspectors are assured in accordance with an internal guideline of UJD. Inspectors take part not only in training courses and other technical meetings organised by the IAEA, but also in some special training courses organised in co-operation with nuclear safety regulators from European countries, USA, Canada and Japan. In next part of this chapter there are presented in details the assessment activity as well as the inspection activity of UJD on the NPP V-1 Bohunice, NPP V-2 Bohunice, NPP Mochovce, NPP A-1 Bohunice, Interim spent fuel storage Bohunice, Technology for treatment and conditioning of radioactive waste Bohunice, National Radioactive Waste Repository Mochovce, Nuclear facilities of VUJE Trnava, Statistical data on assessment and inspection activity of UJD

Design and Function of a Brain Scanner for Clinical Use; Etude d'un Appareil de Scintigraphy du Cerveau - Son Role Clinique; Ustrojstvo i funktsiya pribora dlya skennirovaniya mozga i ego klinicheskoe ispol'zovanie; Diseffo y Funcion de un Aparato de Exploracion del Cerebro para Uso Clinico

Energy Technology Data Exchange (ETDEWEB)

Paul, W.; Morley, T. P. [Department of Pathological Chemistry and Department of Surgery, University Of Toronto (Canada)

1964-10-15

predstavljajutsja v vide asimetrogammagramm i razdel'nyh levogo i pravogo fotograficheskih dvuhrazmernyh izobrazhenij. Impul'sy ot kazhdogo detektora podajutsja na kontur usilitel'-diskriminator i zatem na differencial'nyj kontur, kotoryj pechataet levuju ili pravuju otmetki s cel'ju pokaza preobladanija koncentracii radioaktivnosti sleva ili sprava. Impul'sy ot kazhdogo kontura usiljtel'-diskriminator podajutsja takzhe na pereschetnye ustrojstva, kotorye v svoju ochered' vozbuzhdajut lampy, ustanovlennye v svetonepronicaemom pomeshhenii. Dve lampy, intensivnost' sveta kotooyh poedstavljaet soboj Funkciju aktivnosti, izmerennoj sootvetstvujushhimi detektorami, montirujutsja na obshhej podstavke, peredvigaemoj s pomoshh'ju dvigatelej Sel'sina v sisteme detektora sinhronno s generatorami Sel'sina, tem samym davaja vozmozhnost' primenjat' ustanovlennuju na rasstojanii registrirujushhuju ustanovku. Cilindricheskie linzy fokusirujut lampovye istochniki na plenku, pri jetom registracija kak sprava, tak i sleva osushhestvljaetsja odnovremenno na rentgenovskoj plenke razmerom 28 ch 36 sm. Hotja operator mozhet ustanovit' sootvetstvujushhuju predvaritel'no opredelennuju velichinu srednej sily toka lampy v shirokom diapazone skorosti scheta, operatoru predostavljaetsja bol'shaja svoboda v svjazi s nalichiem v kassete treh plenok, kazhdaja iz kotoryh obespechivaet optimal'nuju kontrastnost' v razlichnom diapazone skorosti scheta. Pacientam vvodilis' 350 mkjuri joda-131 s syvorotochnym al'buminom cheloveka posle predvaritel'noj obrabotki rastvorom Ljugolja. Skennirovanie osushhestvljalos' cherez 24 - 72 chasa. Obychno bylo dostatochno poluchenija odnoj skennogrammy. U nekotoryh pacientov skennogrammy snimalis' povtorno v peredne-zadnem napravlenii. V period s sentjabrja 1961 goda po nojabr' 1962 goda u 653 pacientov bylo snjato 789sken- nogramm. U 109 pacientov iz jetogo chisla diagnoz podtverdilsja, u 88 pacientov byli obnaruzheny opuholi. Byla ustanovlena lokalizacija 23 iz 30 glioblastom i