WorldWideScience

Sample records for atomovych elektrarni mochovce

  1. Mochovce site

    International Nuclear Information System (INIS)

    1997-01-01

    In Mochovce site the construction of four units of WWER 440 NPP with V-213 type of reactor is being carried out. The financing of Mochovce units completion was resolved in April 1996. The completion work commenced at the construction site under leadership of SKODA Prague, the general supplier. The completion work on building part and tests of constructional electric distributions and lightning constructors started. The revisions in technological part were finished, and final protocols from revisions are the basis for starting of completion work. The assembly of transport container anchorage,ventilation system in hermetic areas and hermetic coverage of pools for stored spent nuclear fuel is being carried out. The pre-completion tests of instrumentation and control of ventilation systems, individual dosimetric control in medical station, and tests of nuclear programme according to commissioning and assembling work schedule at the equipment for physical protection of the NPP area started. Inspection activities at Mochovce were performed in accordance with inspection plan for 1996. Evaluation of routine inspections was performed by means of quarterly protocols. Main findings from the inspections performed in Mochovce were in the following areas: (a) deficiencies in the knowledge of the respective regulation and conditions from the Resolution of the state regulatory body, concerning selected employees; (b) training of the selected employees; (c) aim of the measures imposes by inspectors is to eliminate deficiencies in preparation of programmes for pre-completion and completion testing. NRA SR assessment activities at Mochovce NPP were focused mainly on approving and inspecting of design modification to approving programmes for pre-completion and completion testing of system s and equipment and on approving quality assurance programmes. The suggestions of international missions, which reviewed Mochovce safety in the years, were taken into consideration in the programme

  2. Mochovce NPP simulator

    International Nuclear Information System (INIS)

    Ziakova, M.

    1998-01-01

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

  3. Mochovce waste treatment centre

    International Nuclear Information System (INIS)

    Sedliak, D.; Endrody, J.

    2000-01-01

    The first unit of the Mochovce NPP (WWER 440 MW) was put in a test operation in October 1998. The second unit with the same power output was put in the test operation in March 2000. The Nuclear Regulatory Authority of the Slovak Republic in its Decision No. 318/98 of 28 October 1998, by which an agreement with the operation of the Unit 1 of the Mochovce. Nuclear Power Plant was issued, requires to start the construction of the Liquid Radioactive Waste Treatment Centre until January 2004. The subject of this presentation is a system description of the Liquid Radioactive Waste (LRW) management in the Mochovce NPP. The initial part is dedicated to a short description of the radioactive waste management legislation requirements. Then the presentation continues with an information about the LRW production in the Mochovce NPP, LRW sources, chemical and radiochemical attributes, description of storage. The presentation also provides real values of its production in a comparison with the design data. The LRW production minimization principles are also mentioned there. Another part deals with the basic requirements for the technology proposal of the liquid RW treatment, especially concerning the acceptance criteria at the Republic RW Repository Mochovce. The final part is devoted to a short description of the investment procedure principles - design preparation levels and a proposed construction schedule of the centre. (authors)

  4. National Radwaste Repository Mochovce

    International Nuclear Information System (INIS)

    2000-01-01

    In this leaflet the National Radioactive Waste Repository in Mochovce (Repository) is described. The Mochovce National Radioactive Waste Repository is a surface multi-barrier type storage facility for solid and treated solidified radioactive wastes generated from the Slovak Republic nuclear power plants operation and decommissioning, research institutes, laboratories and hospitals. The Repository comprises a system of single- and double-row storage boxes. The first double-row is enclosed by a steel-structure building. The 18 x 6 x 5.5 m storage boxes are made of reinforced concrete. The wall thickness is 600 mm. Two-double-rows, i.e. 80 storage boxes were built as part of Stage I (1 row = 20 storage boxes). Each storage box has a storage capacity of 90 fibre concrete containers of 3.1 m 3 volume. The total storage capacity is 7200 containers with the overall storage volume of 22320 m 3

  5. The seismic reassessment Mochovce NPP

    International Nuclear Information System (INIS)

    Baumeister, P.

    2004-01-01

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

  6. Safety culture at Mochovce NPP

    International Nuclear Information System (INIS)

    Markus, Jozef; Feik, Karol

    2002-01-01

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

  7. National radioactive wasterRepository Mochovce

    International Nuclear Information System (INIS)

    2000-01-01

    In this leaflet the scheme of the Mochovce National radioactive waste repository for the Slovak Republic is presented. The National radioactive waste repository in Mochovce is a surface type storage facility. It is intended for final disposal of solid and solidified low and intermediate radioactive waste produced during the operation of nuclear power plants and institutions located within the territory of the Slovak Republic. The Repository site is situated about 2 km northwest to the Mochovce NPP

  8. Safety upgrading program in NPP Mochovce

    International Nuclear Information System (INIS)

    Baumeister, P.

    1999-01-01

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

  9. Slovak Electric, plc, Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    2000-01-01

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

  10. Performance assessment of Mochovce repository

    Energy Technology Data Exchange (ETDEWEB)

    Mrskova, A; Hanusik, V [Dept. of Accident Management and Risk Assessment, Vyskumny Ustav Jadrovych Elektrarni, Trnava (Slovakia)

    2000-07-01

    The near-surface disposal site at Mochovce is designed for low-level and intermediate level radioactive waste. It is a vault-type concrete structure housing the reinforced concrete containers as the final waste packages. This paper shortly presents the long-term safety analysis methods applied for the post-closure phase of the repository. The main aim of paper is description of the philosophy of analysis, development of the scenarios, their modeling and comparing of the results of normal evolution scenario, alternative scenario and intruders scenario for some radionuclides. (author)

  11. Performance assessment of Mochovce repository

    International Nuclear Information System (INIS)

    Mrskova, A.; Hanusik, V.

    2000-01-01

    The near-surface disposal site at Mochovce is designed for low-level and intermediate level radioactive waste. It is a vault-type concrete structure housing the reinforced concrete containers as the final waste packages. This paper shortly presents the long-term safety analysis methods applied for the post-closure phase of the repository. The main aim of paper is description of the philosophy of analysis, development of the scenarios, their modeling and comparing of the results of normal evolution scenario, alternative scenario and intruders scenario for some radionuclides. (author)

  12. Mochovce Unit 3 and 4 Completion

    International Nuclear Information System (INIS)

    Aquilanti, G.

    2007-01-01

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

  13. NPP Mochovce nuclear safety enhancement program

    International Nuclear Information System (INIS)

    Cech, J.; Baumester, P.

    1997-01-01

    Nuclear power plant Mochovce is currently under construction and an extensive nuclear safety enhancement programme is under way. The upgrading and modifications are based on IAEA documents and on those of the Nuclear Regulatory Authority of the Slovak Republic. Based on a contract concluded with Riskaudit from the CEC, safety examinations of the Mochovce design were performed. An extensive list of technical specifications of safety measures is given. (M.D.)

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

    International Nuclear Information System (INIS)

    Bodorik, K.

    1999-01-01

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

  15. Recent history of Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    Holy, R.

    1999-01-01

    Mochovce Nuclear Power Plant has been an open project involving a wide international co-operation of numerous organisations of countries stretching from the Atlantic coast up to the Urals that make it a truly European project. The units at Mochovce are the later V-213 type of Soviet-designed WWER-440 reactors. They therefore incorporate a number of improvements over the earlier V-230 type. There are four units at Mochovce site: unit 1 has been in operation since summer 1998, unit 2 is currently in the stage of commissioning tests and scheduled for operation by the end of this year, and unit 3 and 4 are still waiting for the final governmental decision about their completion, currently 40% and 30% completed respectively. Beginning in 1981, the construction works were stopped in early 90's due to the decision on replacement of the original I and C system, as well as lack of funding afterwards. Slovenske elektrarne, a.s. have been working to resuscitate the project focusing initially on completion of the units 1 and 2 with assistance of western companies. one month later the governmental guarantees were given for loans and Slovenske elektrarne signed loan agreements to finance the project completion, as well as construction completion agreements with contractors. (Author)

  16. Regulatory requirements for demonstration of the achieved safety level at the Mochovce NPP before commissioning

    International Nuclear Information System (INIS)

    Lipar, M.

    1997-01-01

    A review of regulatory requirements for demonstration of the achieved safety level at the Mochovce NPP before commissioning is given. It contains licensing steps in Slovakia during commissioning; Status and methodology of Mochovce safety analysis report; Mochovce NPP safety enhancement program; Regulatory body policy towards Mochovce NPP safety enhancement; Recent development in Mochovce pre-operational safety enhancement program review and assessment process; Licensing steps in Slovakia during commissioning

  17. Mochovce NPP safety improvement and completion

    International Nuclear Information System (INIS)

    1997-01-01

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

  18. NPP Mochovce units 1 and 2 diagnostic systems

    International Nuclear Information System (INIS)

    Heidenreich, S.

    1997-01-01

    In this paper the diagnostic systems (leak detection monitoring, vibration monitoring, lose parts monitoring, fatigue monitoring) of NPP Mochovce units 1 and 2 are presented. All of the designed diagnostic systems are personal computer based systems

  19. The confirmation audit in Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Andlova, Z.

    2004-01-01

    Mochovce NPP, as the first plant of the Slovenske elektrarne, a. s., has obtained certificate for the environmental management system (EMS) in September 2002, which was established according to the standard STN ISO 14 001:1996. The Audit EMS was executed by the Det Norske Veritas. Mochovce NPP has obtained the EMS Certificate after compliance of process requests and it is valid for three years. After expire of this period the certification process must be repeated. (author)

  20. Pavol Rusko brings up Mochovce again

    International Nuclear Information System (INIS)

    Janoska, J.

    2003-01-01

    Minister of Economy of the Slovak Republic Pavol Rusko would like to see the power plant in Mochovce finished. Press agency SITA quoted his statement that in case of privatisation of Slovenske elektrarne (SE), a.s., Bratislava investor should be searched that would be willing to complete the third and fourth blocks of the nuclear power plant. Last week a tender for sale of a 49-percent stake in SE was repeatedly launched when a privatisation advertisement was published in local and international press. Through a resolution announced last summer the cabinet allowed other companies to participate in the tender (as a reaction interest shown by Czech CEZ). CEZ would be interested in all areas of SE and not only in its conventional part as the other prospects. It is well possible that the number of prospects interested in nuclear energy may increase. Boss of SE, Miroslav Rapsik shares this view and last week announced that there would be probably at least two or three prospects that may be interested in SE as a whole. Amongst them some Russian companies. General Manager and Chairman of Board of Directors, Jaroslav Mil does not wasn't to speculate on under what conditions CEZ may agree with completing of Mochovce. He adds that building any source of nuclear power anywhere in Europe is very difficult without a clear support of wide political spectrum of the specific country. And he needs another assurance: that the cabinet would guarantee that it would eliminate all political pressure from side of the European Union.' In regards to a semi-finished source, according to J. Mil, it made a difference whether this was offered free or with all the fixed costs. 'First we have to see the figures,' he adds. Works on the third and fourth block were stopped in 1992 due to lack of funds. Based on the advise of privatisation advisor the semi-finished blocks were taken out of the privatisation. According to latest analysis the finalization would cost up to 43 billion Sk (1.04 billion

  1. Mochovce power plant units 3 and 4

    International Nuclear Information System (INIS)

    Cuba, J.

    2003-01-01

    The report gives the basic technical data and history of the construction of the units 3 and 4 of the Mochovce NPP.The current status of the units completion according to the original plan is: civil part - 70%; mechanical part - 30%; electric and IC equipment - 1%. Strategic plan for the preservation of the units 3 and 4 has been developed in accordance with TECDOC-1110. In implementation of the plan preservation activities are performed for the components located and built-in on the site and in storehouses. Preservation with dryers and protective coatings is applied. The factors of possible component degradation are determined. Ventilation components are used for improving the climate conditions in the primary part of the reactor building. Temperature and humidity measurements are done and temperature control is set. Special pre-service inspections beyond the basic scope of preservation and protection works are conducted of steam generator and reactor pressure vessel. The implementation of the design data protection and enhancement is discussed. The feasibility study of units 3 and 4 completion funding has been developed in 2002

  2. Fiddle at financing of Mochovce NPP

    International Nuclear Information System (INIS)

    Beer, G.

    2003-01-01

    Slovak police found out and documented racket in financing of third and fourth block of Mochovce NPP. Damage should be 144 millions Slovak crowns. Investigator consequently accused twenty-three Slovaks from foundation, trump up and supporting of criminal group and deception. Two persons are suggested to be taken to custody. Skoda Praha, which was general supplier of construction for 1,5 billions Slovak crowns, in 2001 allowed to create a connection to let the finances between Slovenske elektrarne, a.s., Bratislava as investor and Skoda as subcontractor to be paid through three mediator companies. Companies got authorization to balance the relationship among all interested subjects. Confused network of 118 treaties was created. They invoiced reward from money current based on these treaties. Reward represented up to 70 per cent of transferred resources in some cases. According to Minister of Domestic Affairs Vladimir Palko it will be necessary to find out where is actually the money. For the time being nobody from NPP is among accused. (Author)

  3. The commission of independent experts has labeled Mochovce as safe

    International Nuclear Information System (INIS)

    Grujbar, V.

    1998-01-01

    An independent commission of experts, appointed by IAEA, said that it did not find any faults concerning the integrity of the pressure vessel of the reactor in first block of the NPP Mochovce. The commission, comprising experts from the U.S.A., Belgium, Finland, Germany and Russia, was given the same documents as the Austrian mission, appointed by the office of the Austrian Chancellor, in May. The Austrian experts then expressed two serious concerns about the security of the first block in Mochovce.The experts of the IAEA agreed that the real condition of Mochovce is a lot better that shown in the technical documentation and they did not find any faults. IAEA was in this case, for the first time, an arbiter solving an international dispute about security of a NPP

  4. Development and implementation of symptom based EOP for Mochovce NPP

    International Nuclear Information System (INIS)

    Zold, T.

    1999-01-01

    In this lecture the history and problems concerning the development and implementation of symptom based emergency operating procedures at the Mochovce NPP are reviewed. In order to increase the safety of nuclear installations and their operation at Mochovce a new programme of Safety measures has been worked out, the core of which are the safety rules administratively labeled as OP-02 introducing the symptom - oriented Emergency operating procedures. Following the selection of partners by the Slovenske Elektrarne power Company a contract was signed with US Westinghouse to work out symptom - based EOPs for the Mochovce power plant to be certified by a letter of approval by Westinghouse in November 1998. Subsequent phases of whole programme for development of EOPs were divided as follows: Phase 1 - Preparation phase; Phase 2 - Emergency operating guideline development and Phase 3 - Emergency operating procedures development and validation

  5. Polish media and public opinion on NPP Mochovce commissioning

    International Nuclear Information System (INIS)

    Latek, Stanislaw

    1999-01-01

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

  6. Radioactive waste handling at the Mochovce NPP, 1998-2008

    International Nuclear Information System (INIS)

    Vasickova, Gabriela

    2009-01-01

    The radioactive waste management system at the Mochovce NPP is described. The system addresses technical aspects as well as administrative provisions related to radioactive waste generated within the controlled area, from the waste generation phase to waste sorting, packaging, storage, recording, measurement, and transportation to the Bohunice waste processing facility or transfer to the Mochovce liquid radioactive waste treatment facility. The article also addresses conditions for release from the controlled area to the environment for radioactive waste which can be exempt from the institutional administrative control system or released to the environment on the basis of a valid permission issued by the relevant regulatory authority

  7. Press travel to the Mochovce power plant in Slovakia

    International Nuclear Information System (INIS)

    1998-07-01

    This press dossier gives, first, a general presentation of the Mochovce power plant of the republic of Slovakia (history, technical characteristics, safety aspects, technical particularities of VVER 440/213 reactors (safety analysis, recent improvements), financing of the modernization project). Then, the activities of the Framatome group in central and eastern Europe are presented (partnerships, cooperation agreements and contracts). (J.S.)

  8. 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)

  9. Fire protection at the Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Molnarova, Zuzana; Zeman, Peter

    2009-01-01

    A succinct account is given of current situation in fire prevention at the Mochovce NPP and of past fire events. The fact is stressed that no fire ever occurred at any technological facility of the plant since the startup of the reactor units. Steps required to improve fire safety at a nuclear power plant are highlighted. (orig.)

  10. EDF Contribution to the Mochovce completion and safety upgrading project

    International Nuclear Information System (INIS)

    Norvez, G.

    1997-01-01

    The challenge that SE a.s. took up in April 1996 to start Mochovce units 1 and 2 within a very demanding time frame and in satisfactory conditions is on the way to being wined. EMO managed to put in place an organisation able to ensure the continuity of the design and construction works and to integrate the requirements of modern safety. EDF is proud and happy to contribute to this effort by making available its expertise and experience in building and operating nuclear power plants. The success of Mochovce will not only contribute to the Slovak electricity needs coverage, but will be the first demonstration of a soviet design nuclear power plant brought to international safety standards. (author)

  11. EGP contribution to Mochovce completion, safety enhancement and operation

    International Nuclear Information System (INIS)

    Letko, A.; Matula, P.

    2000-01-01

    The Re-Evaluation Programme of Mochovce NPP was created in 1995 as an integral part of the completion of the Unit 1 and Unit 2. This program analyzed the general fulfillment of the principle of nuclear safety in the NPP Mochovce project. The analysis has required new corrections of the project, so that the project met the higher safety requirements when starting production. 87 safety measures represent the 'Program'. The basis for their creation were the international missions from 1992 to 1995 which defined. The final safety aim was represented by 'The Technical Specification of the Safety Measures' supported by The Nuclear Power Plant Research Institute and recommended by The Nuclear Regulatory Authority of the Slovak Republic. The technical specification served as a qualified base for the next steps in the pre-project, project and realization stages. (author)

  12. Status of the seismic upgrading programme at Mochovce NPP

    International Nuclear Information System (INIS)

    Zajicek, T.; Dolnik, R.; Stevko, M.

    2001-01-01

    The paper provides an overview of the seismic characterisation of the Mochovce site in Slovakia. Particularly, emphasis is given to differences between the original siting and design procedures and the re-evaluation approach, much more based on the data from the micro-earthquake monitoring system installed at the site. Details are also provided for the seismic monitoring of the buildings, as confirmation of the design assumptions. (author)

  13. Slovenske elektrarne, a.s., Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    1998-01-01

    In this booklet the uranium atom nucleus fission as well as electricity generation in a nuclear power plant (primary circuit, reactor, reactor pressure vessel, fuel assembly, control rod and reactor power control) are explained. Scheme of electricity generation in nuclear power plant and Cross-section of Mochovce Nuclear Power Plant unit are included. In next part a reactor scram, refuelling of fuel, instrumentation and control system as well as principles of nuclear safety and safety improvements are are described

  14. Review of accident analyses performed at Mochovce NPP

    International Nuclear Information System (INIS)

    Siko, D.

    2000-01-01

    In this paper the review of accident analysis performed in NPP Mochovce V-1 is presented. The scope of these safety measures was defined and development in the T SSM for NPP Mochovce Nuclear Safety Improvements Report' issued in July 1995. The main objectives of these safety measures were the followings: (a) to establish the criteria for selection and classification of accidental events, as well as defining the list of initiating events to be analysed. Accident classification to the individual groups must be performed in accordance with RG 1.70 and IAEA recommendations 'Guidelines for Accidental Analysis of WWER NPP' (IAEA-EBR-WWER-01) to select boundary cases to be calculated from the scope of initiating events; (b ) to elaborate the accident analysis methodology that also includes acceptance criteria for their result evaluation, initial and boundary conditions, assumption related with the application of the single failure criteria, requirements on the analysis quality, used computer codes, as well as NPP models and input data for the accident analysis; (c) to perform the accident analysis for the Pre-operational Safety Report (POSAR); (d) to provide a synthetic report addressing the validity range of codes models and correlations, the assessment against relevant tests results, the evidence of the user qualification, the modernisation and nodding scheme for the plant and the justification of used computer codes. Analyses results showed that all acceptance criteria were met with satisfactory margin and design of the NPP Mochovce is accurate. (author)

  15. Slovak power stations, Nuclear Power Plants Mochovce (Annual report 1997)

    International Nuclear Information System (INIS)

    1998-01-01

    A brief account of activities carried out by the Nuclear power plants Mochovce in 1997 is presented. These activities are reported under the headings: (1) Director's foreword; (2) Power plant management; (3) Highlights of 1997; (4) Capital construction; (5) Nuclear safety; (6) Radiation safety; (7) Work safety and health protection at work; (9) Fire protection; (10) Units upgrading - safety measures; (11) Maintenance; (12) Operation; (13) Environmental impacts of operations; (14) List of balances; (15) Human sources; (16) International co-operation; (17) Public relations

  16. Feasibility study for NPP Mochovce Units 3 and 4 completion

    International Nuclear Information System (INIS)

    Tomik, L.; Chakraborty, S.; Hoffelner, W.; Stoian, A.

    2004-01-01

    The system dynamic approach presented in this study by modelling the behaviour of Slovak market on the basis of system dynamic model (Forrester model), enables real mix in the extend of 12 years and helps understanding of the market limits. In addition this tool can be used for sensitivity calculations depending on many parameters to develop possible trends in the economic development of the Slovak Republic. If both nuclear power options are maintained then it becomes obvious that electric excess energy is produced and could be exported. This export option remains for the situation that a strong growth of the gross national product is assumed without any increase in energy efficiency. Between these extremes is the scenario that Bohunice 1, 2 off is balanced by Mochovce 3, 4 on and increasing demand this will lead to more moderate but still not negligible potential of CO 2 increase. Switching off Bohunice 1, 2 and not switching on Mochovce 3, 4 leads to energy need which must be counterbalanced either by investments in other power plants or by import energy. As far as domestic production is concerned even assuming 50 % CHP production leads to partly remarkable additional CO 2 -production which might infringe on a long term basis with the Kyoto goals. Assuming additional CO 2 -emissions from increasing traffic real problems can be expected in such a case. To maintain national nuclear capabilities in Slovakia is very important for today and for future of nuclear energy option in enlarged European Union. (authors)

  17. Completion of Mochovce 1 and 2 nuclear power plant project

    International Nuclear Information System (INIS)

    Valach, J.

    2000-01-01

    Commissioning of the Mochovce Nuclear Power Plant unit 2 fully completed the Mochovce unit 1 and 2 project. The power plant construction passed through a complicated evolution since early 80's. The genesis started with the change of the plant location due to a seismic resistance requirement raised by the former Czechoslovak Atomic Energy Commission, change of the design and contractor of the Instrumentation and Control system in early 90's, halt of construction in 1993 till 1996 due to a lack of funding, as well as a series of international reviews of safety aspects. All the obstacles had been overcome in the end, and completion works were re-started in 1996. Looking back to the unit 1 and 2 completion project, I would like to highlight some aspects of the project, particularly the level of safety, technical and organisational conditions, and terms of funding. The most important argument for completion of the plant was that VVER 440/213 reactor units were distinguished with very high level of passive safety, even overcoming Western-type PWR's in some aspects. The replacement of the original I and C system was another important contribution to the initial level of safety. International safety reviews performed at Mochovce NPP between 1990 and 1995 (Siemens, EdF, IAEA, RlSKAUDIT) confirmed the high level of safety of VVER 440/213 reactors, however, pointed out at some safety issues which had not been dealt with in the design. Those included e.g. the 'external risks', primary-to-secondary leaks, qualification of pressurizer safety valves, and others. It is necessary to stress that the Safety Improvement Programme defined for Mochovce NPP to comply with international standards did not become the most important part of the completion project due to external pressures, but based on natural requirements on nuclear power plant safety level generally accepted in 90's. The good example could be the seismic resistance of the plant which, though designed as seismic resistant

  18. Natural and artificial radioactivity in the area of the Mochovce regional radioactive waste store

    International Nuclear Information System (INIS)

    Bezak, J.; Daniel, J.; Moravek, J.

    2000-01-01

    The results of monitoring of natural and artificial radioactivity in the area of the Mochovce regional radioactive waste store before commission are presented. The concentrations of uranium, thorium, potassium, and cesium, as well as radon volume activity were measured

  19. Actual status of project Mochovce NPP units 3 and 4 completion

    International Nuclear Information System (INIS)

    Niznan, S.

    2005-01-01

    In this presentation author deals with actual status of project Mochovce NPP units 3 and 4 completion. Present state of Mochovce NPP, Units 3 and 4 enables real assumption to completion. It is expected that such supplier companies can be used which are experienced in field of nuclear projects. Based on budget of 2002, it seems that completion costs of 45 billions SKK are real. These figures were confirmed by study performed by TRACTEBEL in 2004. Based on experience from Bohunice NPP completion as well as from Mochovce NPP, Units 1 and 2 completion and if decision milestone and project start up deadlines will be observed according to modified preliminary schedule of Mochovce NPP Units 3 and 4 completion, it seems as real that Unit 3 will be completed till 06/2011 and Unit 4 - till 12/2011.

  20. Mochovce Nuclear Power Plant. How was it? Starting of the first block by the eyes of participants in the construction operation

    International Nuclear Information System (INIS)

    Blaha, M.; Bucha, T.

    2008-01-01

    This book is published at 10 th anniversary of commissioning of Mochovce NPP. It consists of two parts: Part I. Story completion of the first block Mochovce nuclear power plant. Part II. Interviews with interested politicians and managers of Mochovce NPP.

  1. Summary revaluation of energetic start-up of the unit 1 of nuclear power plant Mochovce

    International Nuclear Information System (INIS)

    Sarvaic, I.; Miskolci, M.

    1998-01-01

    The document contents stage revaluation of energetic start-up of the unit 1 of nuclear power plant Mochovce. Test results of the stage of energetic start-up are summarized in the document, valuation of important systems and block devices as well as fulfilling the operation limits and conditions has been performed. On that base conclusions and recommendations for start-up the unit 2 and for commercial operation of the unit 1 are elaborated. The valuation has been elaborated by a scientific management for start-up nuclear power plant Mochovce of nuclear safety of nuclear power facilities. Scientific management for start-up of nuclear power plant Mochovce performed continuous valuation of individual power levels after ending of each individual level and it gave its valuation to energy power level with recommendations and conditions for further start-up process and operation. Scientific management finished its activity at the unit 1 of nuclear power plant Mochovce according to a statute of scientific management for start-up after successful completion of conclusive block run. Scientific management group was founded in February 1998 at nuclear power plant Mochovce. Its members are experts from Slovak, Czech, Russian and French organizations which are participating in power plant completion. Members are listed in a supplement No. 2

  2. Computerized information system of the Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Holik, V.

    1986-01-01

    The computer-based information system for the Mochovce nuclear power plant has a hierarchic structure which incorporates SM 1804 microcomputers and SM 1420 minicomputers. With regard to operation it is divided into two levels: the information system at the level of power plant units and the information system t the level of the whole power plant. The information system of a unit provides the collection of information on the technological equipment of each unit for the operative control of the unit and documentation on unit operation. Each unit has its own independent computer information system. The actual nucleus of each unit information system consists of two computer complexes based on SM 1420 twin computers, mutually substitutional. The power plant level information system provides the processing and output of information for personnel in the central control room of the power plant and for other managerial staff. It uses preprocessed information from the unit information systems and direct information from non-unit installations and from dosimetric control rooms of the power plant units. This information system is also based on a computer complex with two SM 1420 computers. (Z.M.)

  3. Completion of Units 3 and 4 at Mochovce NPP

    International Nuclear Information System (INIS)

    Aquilanti, G.

    2009-01-01

    After the completion of a feasibility study, SE/ENEL decided to complete Mochovce Nuclear Power Plant Units 3 and 4 in April 2007. In July 2008, after a revision of the Basic Design that led to the inclusion of additional safety improvements, the European Commission issued a positive viewpoint on the decision. In August 2008 the Slovak Nuclear Regulatory Authority issued a permit for 'modification of a construction project prior to its completion', approving the Basic Design modifications: the kick-off of site activities was on November 2008. In December 2008, SE initiated the Environmental Impact Assessment (EIA) procedure aimed at obtaining the Operational License by submitting the EIA intent to the Ministry of Environment. A multi contractual strategy was adopted for the completion works: the total number of foreseen contracts is about 250 (90 main and additional 160 minor). In the following the present status of the project is presented: in particular, the Project Management system implemented by SE/ENEL is described and the progress of the engineering, fabrication and construction activities is analyzed. (author)

  4. Health state of population in vicinity of the Mochovce nuclear power plant. Epidemiologic study

    International Nuclear Information System (INIS)

    Celko, M.; Durov, M.; Letkovicova, M.; Holy, R.; Sedliak, D.; Zrubec, M.; Kristufek, P.; Machata, M.; Prikazsky, V.; Rehak, R.; Stehlikova, B.; Vladar, M.

    1999-01-01

    Results of epidemiologic study of health state of population in vicinity of the Mochovce nuclear power plant (Slovak Republic) are presented. This report is reported under the headings: (1) Introduction; (2) Basic information about Mochovce NPP; (3) Assessment of population exposition by environmental factors; (4) Basic conceptions and principles of epidemiologic study; (5) Demography and health state of population; (6) Characterisation of databases and data; (7) Description of demographic and health indicators; (8) Calculation of demographic and health indicators in vicinity of the Mochovce NPP and in control areas; (9) Calculated indicators; (10) Statistical methods and evaluation of calculated indicators; (11) Summary and conclusions; (12) References; Appendixes: Literature review of similar epidemiologic studies; Quantities and units in radiation protection; Definitions of indicators calculation - specification of method

  5. 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)

  6. Current situation of the project of 3. and 4. block of nuclear power plant Mochovce

    International Nuclear Information System (INIS)

    Suchy, L.

    2006-01-01

    The contribution shows the basic information about the crucial milestone of 3. building and the current situation of the project of 3. and 4. block of the nuclear power plant Mochovce. Contribution also shows what activities were realized and what material in area of designation of the technical and safety standard of the project was elaborated in the past, the main activities planned for 2006 have been described, support for Feasibility Study elaborated by ENEL and description of the integrated management system. The basic thesis crucial for the next steps on the project of 3. and 4. block of Nuclear Power Plant Mochovce is presented in the conclusion

  7. Preparation phase of Mochovce NPP unit 3 and 4 construction completion

    International Nuclear Information System (INIS)

    Cillik, I.; Tvaroska, V.; Liska, P.; Ziman, V.

    2005-01-01

    In this presentation authors deal with preparation phase of Mochovce NPP unit 3 and 4 construction completion. The preparation phase of the Mochovce unit 3 and 4 construction completion gives following main outputs: (a) Detail Safety Concept gives definitive complex safety and technical improvement of MO34, more precise analysis of the total cost of construction completion, a list of potential suppliers and construction completion time schedule; (b) Appendices of Basic Design Documentation and Preliminary SAR serves as basic documentation for UJD SR decision making according to Law No. 541 for start of Realization Phase; (c) The Preparation Phase represents effective tool for start of MO34 construction completion Realization Phase.

  8. Summary revaluation of cold testing of the first block of nuclear power plant Mochovce

    International Nuclear Information System (INIS)

    Miskolci, M.; Sarvaic, I.

    1998-01-01

    The document contents summary revaluation of the stage of cold testing of the first unit of nuclear power plant Mochovce. The valuation is processed in individual systems with safety significance. The process and results of system testing and their conclusions for the block readiness for active testing are summarized in the document. The valuation has been elaborated by a scientific management for start-up of nuclear power plant Mochovce as an independent conductor assistance for activation check from the nuclear safety point of view. The valuation of the activation results of systems in the first unit of nuclear power plant was processed as of 15.3.1998

  9. Evaluation of power commissioning of the Mochovce Unit 1 demonstration run

    International Nuclear Information System (INIS)

    Sarvaic, I.; Miskolci, M.

    1998-01-01

    The document contains evaluation of the 144 hour demonstration run of the Mochovce Unit 1. In the document, the courses and results of additional tests in this phase of power commissioning are summarized, evaluation of the performance of important systems and equipment of the unit is carried out, as well as of the compliance with Limits and Conditions in the course of the demonstration run. On this basis, conclusions are drawn and recommendations given for the unit to by ready for trial operation. The evaluation was developed by the scientific management of the Mochovce commissioning providing an independent support for the operators for supervising the commissioning tasks from the point of nuclear safety

  10. Summary revaluation of cold testing of the first block of nuclear power plant Mochovce; Suhrnne zhodnotenie neaktivneho vyskusania 1. bloku jadrovej elektrarne Mochovce

    Energy Technology Data Exchange (ETDEWEB)

    Miskolci, M; Sarvaic, I [Nuclear Power Plants Research Institute Trnava, Inc., Okruzna 5, 918 64 Trnava (Slovakia)

    1998-04-03

    The document contents summary revaluation of the stage of cold testing of the first unit of nuclear power plant Mochovce. The valuation is processed in individual systems with safety significance. The process and results of system testing and their conclusions for the block readiness for active testing are summarized in the document. The valuation has been elaborated by a scientific management for start-up of nuclear power plant Mochovce as an independent conductor assistance for activation check from the nuclear safety point of view. The valuation of the activation results of systems in the first unit of nuclear power plant was processed as of 15.3.1998 61 figs., 44 tabs., `Translation to english is available from OMEGA INFO, Vysehradska 33, SK-84215 Bratislava, Slovak Republic, E-Mail: kuruc at fns.uniba.sk`

  11. Mochovce NPP experience in the certification and the use of full scope simulator

    International Nuclear Information System (INIS)

    Krenicky, L.

    1999-01-01

    The paper presents some of the Mochovce NPP experience in the full-scope simulator certification process, simulator training programs development, implementation and evaluation, the use of simulator in the all-plant emergency exercises as well as the experience in validation of plant operational procedures.(author)

  12. Implementation of computer codes for performance assessment of the Republic repository of LLW/ILW Mochovce

    International Nuclear Information System (INIS)

    Hanusik, V.; Kopcani, I.; Gedeon, M.

    2000-01-01

    This paper describes selection and adaptation of computer codes required to assess the effects of radionuclide release from Mochovce Radioactive Waste Disposal Facility. The paper also demonstrates how these codes can be integrated into performance assessment methodology. The considered codes include DUST-MS for source term release, MODFLOW for ground-water flow and BS for transport through biosphere and dose assessment. (author)

  13. 'HSE protection through safe work'. Mochovce NPP is the holder of ISO 14001:2004 and CSN OHSAS 18001 certificates

    International Nuclear Information System (INIS)

    Molnarova, Zuzana; Torda, Anton

    2009-01-01

    The article provides information on the safety of the Mochovce NPP related to occupational health and safety and environmental protection. The facility has earned EN ISO 140001 and OHSAS 18001 certificates. (orig.)

  14. Theoretical parameter histories of dynamic tests during power commissioning of Mochovce units power level up to 100 % Nnom

    International Nuclear Information System (INIS)

    Jagrik, J.; Mraz, M.; Rapant, M.; Stefanovic, P.; Kotasek, J.; Gieci, A.; Macko, J.; Mosny, J.

    1998-01-01

    Theoretical histories of selected parameters for dynamic tests carried out in the course of power commissioning of the Mochovce Unit 1 at the power level 100% N nom are shown in the report. The expected histories given were developed based on calculations performed by means of simulator in Nuclear Power Plants Research Institute Trnava, Inc., simulator in EGU Praha and simulator at the Mochovce plant, as well as based on similar tests at both Bohunice and Dukovany plants

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  17. Evaluation of power commissioning of the Mochovce Unit 1 power level up to 100 % Nnom

    International Nuclear Information System (INIS)

    Sarvaic, I.; Mickolci, M.

    1998-01-01

    The document contains an evaluation of the power phase of power commissioning of the Mochovce Unit 1 in the phase up to the power level of 100 % N nom .In the document, the courses and results of tests in this phase of power commissioning are summarized, evaluation of the performance of important systems and equipment of the unit is carried out, and the compliance with Limits and Conditions in the course of the phase is assessed. On this basis, conclusions are drawn and recommendations for the unit to be ready for subsequent phases of the power commissioning. The evaluation was developed by the scientific management of the Mochovce commissioning providing an independent support for the operators for supervising the commissioning tasks from the point of nuclear safety

  18. Further experience in simulation of rod drop experiments in the Loviisa and Mochovce reactors

    International Nuclear Information System (INIS)

    Siltanen, P.; Kaloinen, E.; Tanskanen, A.; Mattila, R.

    2001-01-01

    Simulations of reactor scram experiments using the 3-dimensional kinetics code HEXTRAN have been updated for the initial cores of Loviisa-1 and 2 Mochovce-1 and have been extended to burned cores of Loviisa-1. In these simulations, the entire experiment is simulated dynamically, including the behaviour of the core, the signal of the ionization chamber, and the inverse point kinetics of the reactivity meter. The predicted output of the reactivity meter is compared with the output observed during the experiment (Authors)

  19. Mathematical Analysis of Malfunctions Caused by Seepage Water to the Republic Radioactive Waste Dump in Mochovce

    Directory of Open Access Journals (Sweden)

    Jozef Kuzma

    2007-01-01

    Full Text Available The storage of radioactive waste and the problem of assuring the low and medium radioactive waste is an actual interdisciplinary problem. An important factor influencing on a complex approach to solving these problems is also a creation of suitable technical conditions for its long-term storage. In this article we mathematically analyze an influence of the break covering and its effect on the long-term stability and reliable serviceability of the Republic radioactive waste dump in Mochovce.

  20. Start. Slovak power stations, Nuclear Power Plants Mochovce (Annual report 1998)

    International Nuclear Information System (INIS)

    1999-01-01

    A brief account of activities carried out by the Nuclear power plants Mochovce in 1998 is presented. These activities are reported under the headings: (1) Director's foreword; (2) Power plant management; (3) Highlights of 1998; (4) Quality system; (5) Electricity and heat generation; Maintenance; Capital construction; (6) Radiation safety; Environmental impacts of operations; (7) List of balances; Human resources; (8) International co-operation; Public relations

  1. Some experience from seismic check-ups of components of Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Masopust, R.

    1987-01-01

    The first Czechoslovak nuclear power plant with the so-called partial anti-seismic design will be built in Mochovce. The evaluation of seismic resistance is prescribed only for equipment and systems which secure the safe reactor shutdown, the withdrawal of residual heat and prevent uncontrolled release of radioactivity into the environment. The following variants were compared in the calculation analysis of the primary loop of the WWER-440 reactor for the Mochovce nuclear power plant: the seismically unsecured loop of a usual design for WWER-440 nuclear power plants, the loop provided with mechanical or hydraulic dampers and the loop provided with viscose shock absorbers. The tests showed that technically most suitable is the use of viscose shock absorbers which do not completely block the movement of the system during the earthquake but absorb it intensively. The viscose shock absorbers are also much cheaper than the dampers. Briefly described is experience with the experimental evaluation of the seismic resistance of components of the Mochovce nuclear power plant. Great difficulty was encountered by the non-existence in Czechoslovakia of a seismic table allowing simultaneous excitation in the vertical and horizontal directions. (Z.M.). 18 refs

  2. 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)

  3. Commissioning of Mochovce 1 - Important achievement of the world's nuclear industry

    International Nuclear Information System (INIS)

    Holy, Robert; Petrech, Rastislav

    1999-01-01

    The nuclear power industry has been recently perceived by the general public as a specific industrial branch stretching its activities far beyond the conventional industrial standard. Similarly, the stage of testing and commissioning of a nuclear power plant is perceived as a specific stage in the plant life-cycle. This is a complicated process not only in technical terms, but in the context of nowadays, it is also one of the key periods in terms of public relations and public acceptance. The stage of commissioning unit 1 of Mochovce Nuclear Power Plant evoked a real communication media war between defenders and opponents of the nuclear industry started early in 1998 in Slovakia, as well as in other, mostly neighbouring countries. It should be noted, however, that the Mochovce plant has never been a technical problem as confirmed a number of international regulatory missions and audits, even though its construction was stopped in early 90's. The result of the war between the opponents and 'nuclear experts' was more or less clear to a thinking human being - a compromise could have been the only result. The compromise which is in fact a victory of the side of technical development, and loss of those lobbying for a nuclear-reactor-free central Europe. This article brings a review of events that accompanied commissioning activities of Mochovce NPP unit I which were important in terms of public relations

  4. 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

  5. Jevgenij V. Doc: We do not want to build a monument at Mochovce

    International Nuclear Information System (INIS)

    Janoska, J.

    2004-01-01

    In this paper the interview with the General Manager of Inter RAO JES - Jevgenij V. Doc is published. Inter RAO JES applies for the privatisation of Slovenske elektrarne (Slovak Electric - SE). According to the General Manager of Inter RAO JES, the company does not need a foreign partner to provide financial support after the privatisation of SE, but rather it requires a political support. Plans about Bohunice NPP and of completion of the Mochovce NPP as well as of privatisation of the SE by the Inter RAO JES are presented

  6. Participation of Skoda Praha a.s. in completion of NPP Mochovce

    International Nuclear Information System (INIS)

    Poukar, F.

    1997-01-01

    The history of the construction of the Mochovce nuclear power plant is briefly described. In 1995, after obtaining promises of loans from Czech banks the Slovak government decided that the completion of the mechanical and electrical parts of units 1 and 2 would be placed with Skoda Praha in the position of general supplier; Skoda together with Siemens and Framatome would also be charged with implementing the safety measures necessary to reach European standards. Evaluation of safety studies and risk audits, and elaboration of safety measures are now under way. (M.D.)

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

    International Nuclear Information System (INIS)

    Farkas, G.; Hascik, J.; Lueley, J.; Vrban, B.; Petriska, M.; Slugen, V.; Urban, P.

    2011-01-01

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

  8. Seismic re-evaluation of Mochovce nuclear power plant. Seismic reevaluation of civil structures

    International Nuclear Information System (INIS)

    Podrouzek, P.

    1997-01-01

    In this contribution, an overview of seismic design procedures used for reassessment of seismic safety of civil structures at the Mochovce NPP in Slovak Republic presented. As an introduction, the objectives, history, and current status of seismic design of the NPP have been explained. General philosophy of design methods, seismic classification of buildings, seismic data, calculation methods, assumptions on structural behavior under seismic loading and reliability assessment were described in detail in the subsequent section. Examples of calculation models used for dynamic calculations of seismic response are given in the last section. (author)

  9. Experience with drilling and blasting work during construction of Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Mraz, M.; Vojta, A.; Podel, R.

    1986-01-01

    The results are discussed of four years of investigating the technical and economic parameters of drilling and blasting equipment employed on the building site of the Mochovce nuclear power plant. The technical and operating characteristics are given of tested breaking and drilling sets manufactured by various foreign companies. The final choice was based on output, hard currency prices, power demand, operating reliability and number of personnel required for operation. The optimal set consists of two Hausherr HBM 70 drilling systems (holes with a diameter of 130 to 150 mm) and two ROC 601-02 Atlas Copco machines (auxiliary work, breaking foundation holes for nuclear reactors). (J.C.)

  10. Ejected control rod and rods drop measurements during Mochovce startup physical tests

    International Nuclear Information System (INIS)

    Minarcin, Miroslav; Elko, Marek

    1998-01-01

    Paper deals with measurements of asymmetric reactivity insertion into the reactor core that were carried out during physical startup tests of Mochovce Unit 1 in June 1998. Control rods worth measurements with one and two rods s tucked in upper limit and worth measurement of one control rod from group 6 'ejected' from the reactor core are discussed. During the experiments neutron flux was measured by four ionisation chambers (three of them were placed symmetrically around the reactor core). Results of measurements and influence of asymmetric reactivity influence on ionisation chambers response are presented in the paper. (Authors)

  11. Transport structures and water reservoir for the Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Farkas, J.; Klacansky, T.

    1986-01-01

    The projects are described which were implemented by Doprastav Bratislava within the preparation of the site for the Mochovce nuclear power plant. This includes a railway siding in a length of 11.2 kilometres which includes a railway bridge, two other bridges and the reconstruction of the Kalna nad Vahom railway terminal. Also reconstructed or newly built were road communications in a total length of 23.3 km. The said project included the construction of a road flyover over the railway track and the construction of five other smaller bridges. In order to provide the utility water supply to the Mochovce nuclear power plant, a large reservoir is being built at Velke Kozmalovce. The reservoir will have a total capacity of 2.6 mill. m 3 of water, of this the effective capacity will be 2.1 mill. m 3 on a flooded area of some 90 ha. Part of the reservoir will be a small hydro-power plant, the reservoir will also be used for irrigation on the fields of the neighbouring farms. (Z.M.)

  12. Completion of the VVER 440/213 NPP Mochovce incorporation enhanced safety features

    International Nuclear Information System (INIS)

    Charbonneau, S.; Eckert, G.

    1996-01-01

    The cooperation between the western countries and the countries of ex-eastern block in the field of nuclear safety is recent and still limited. The main reasons for this situation are limited or non existent capabilities of these countries for financing as well as non acceptable legal conditions concerning the third party nuclear liability in this part of Europe. Nevertheless, Framatome and Siemens associated in the consortium named EUCOM, have signed in April 1996 the contract of about 100 million US dollars with Slovak electricity company (SLOVENSKE ELEKTRARNE-SE) for upgrading the Units 1 and 2 of Mochovce Nuclear Power Plant according to the western safety standards. This is the first important project involving west-european companies in the modernisation of Russian type of pressurized water reactor (VVER 440/213). The consortium will cooperate with other partners involved in the project: Slovak, Czech and Russian. The financing of the project will be provided mainly form Slovak and Czech sources. The safety upgrading will be financed through French and German buyer credits. French company Electricite de France (EDF) will be the consultant for SE. The safety upgrading measures have been elaborated taking into account the recommendation of Vienna International Atomic Energy Agency (IAEA) and the evaluation of the safety realised by RISKAUDIT, the common organization of German and French safety authorities (GSR and IPSN). Hence all guaranties have been taken to fulfil the western safety criteria for Nuclear Power Plant Mochovce. (author)

  13. Health state of population in the locality of the Mochovce nuclear power plant after four years of operation

    International Nuclear Information System (INIS)

    Letkovicova, M.; Letkovicova, H.; Letkovic, M.

    2002-01-01

    The Mochovce NPP was put into the operation in 1998. Authors monitor the health state of the population in its vicinity since 1993. The authors recorded this health state also in before-operational safety report of Mochovce NPP. The authors show in the presentation the evaluation of nine years, five before putting of Mochovce NPP into the operation and four during its operation. The aim of the authors is to evaluate the state of chosen health indicators in individual villages in whole monitored region and to try to found out the differences between of their size before and after putting the Mochovce NPP into the operation. Authors used the methods of so-called population epidemiology, where they evaluate the health risks by the system of multidimensional mathematical-statistical methods, by using of the theory of fuzzy sets. The Mochovce region belongs for the long period to the regions with very unfavourable health state. Its very general comparison with one year all Slovak values of the relevant indicators in 2000 are following: more newborn on thousand inhabitants (in 12 per cent) (consequence of wholly older population), higher general mortality of population (in 11 per cent), higher premature mortality of population (in 17 per cent), higher mortality from selected causes, thus malignant tumours of digestive tract (in 20 per cent), higher mortality from malignant tumours of lungs (in 25 per cent), higher mortality from malignant tumours of leukaemia (in 25 per cent). However the authors found out very positive findings in the evaluation of the trends: in the case of fifteen most serious health indicators in the vicinity of Mochovce NPP authors state also mathematically visible influence on the surroundings, which is registerable only in positive meaning. There are created the demonstrable clusters of the villages with low general, also premature women mortality. This locality was far off the industrial and cultural centres, there were always historically higher

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

    International Nuclear Information System (INIS)

    Anon

    2007-09-01

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

  15. Level 1 PSA study of Mochovce unit 1 NPP (SM AA 10 and 08)

    International Nuclear Information System (INIS)

    Cillik, I.

    1997-01-01

    This paper presents genesis of Level 1 PSA project preparation for all operational modes of Mochovce NPP unit 1 including the description of its' main objectives, scope and working method. The PSA study which includes full power (FPSA) as well as shutdown and low power conditions (SPSA) Level 1 PSA has to support the nuclear safety improvements of the unit. They evaluate the basic design and the benefits of all improvements, which were found necessary to be incorporated before the start-up of the unit. The study includes internal events (transients and under-loss of coolant accident, LOCAs), internal hazards as fires and floods and selected external hazards as earthquake, influence of external industry, extreme meteorological conditions and aircraft crash.The PSA (both FPSA and SPSA) models is developed using the RISK SPECTRUM PSA code. (author)

  16. Advanced breaking technology on the Mochovce nuclear power plant building site

    International Nuclear Information System (INIS)

    Mraz, M.; Podel, R.; Vojta, A.

    1982-01-01

    Observing the given deadlines of the construction of the Mochovce nuclear power plant and the required volumes of breaking to the total value of 6.2 million m 3 of rock, the required output was derived for the 7th five year plan to the value of 200,000 m 3 per month, i.e., 10,000 m 3 per day and 700 m 3 per hour. The basic task is to build a flat building site with an area of 2,300 by 700 m 2 which requires the removal of a masiff of rocks rising to a height of 37 m, and by compacting the mined rock to build heaps to a height of 20 m. The rocks were disintegrated by blasting. Surface blasting was used for mining faces and ribs. POLONIT 2 or PERMON DAP 1 were mainly used for blasting (ammonium nitrate explosives). The Danubit 1 detonator was used in holes flooded with water. For drilling a combination was used of drilling machines HBM 70 Hausherr with a drilling diameter of 130 to 155 mm and Ingersol Rand ECM 350 with a drilling diameter of 80 mm. The compressors used are Atlas Copco XRHS 350 Dd and PTS 900 Dd. As the optimal combination of machines for the removal of disengaged material for the daily output of 15,000 m 3 the combination was used of 6 excavators with a shovel volume of 2.5 m 3 ORENSTEIN-KOPPEL RH 25 with 12 Kockum 445 trucks and 18 ORENSTEIN-KOPPEL RH 40 excavators with a shovel volume of 4 m 3 and a total of 64 Caterpillar 769 C, Belaz 548 A, Tatra T 200 and T 138 S1 trucks. The planned targets are being fulfilled and the work performed up to now on the Mochovce site equals 2.5 million m 3 of excavated and removed rock. (B.S.)

  17. Review of selected contributions of the conference 'Integrated quality management systems in completion of units 3 and 4 Mochovce'

    International Nuclear Information System (INIS)

    2009-04-01

    There were 14 contributions presented of the conference focused on the integrated quality management systems in completion EMO34. Contributions were focused both on theoretical problems from the project management area and on the applications in practice in management systems implementation in accordance with the standards: STN EN ISO 9001:2000, STN EN ISO 14 001:2005, and OHSAS 18 001:1999 at the completion of the Nuclear Power Plant Mochovce of units 3 and 4

  18. Radiation exposure of the population from 222Rn and other natural radionuclides around Mochovce nuclear power plant, Slovakia

    International Nuclear Information System (INIS)

    Bulko, Martin; Holy, Karol; Mullerova, Monika; Bohm, Radoslav; Pohronska, Zofia; Hola, Olga

    2017-01-01

    In this article, the effective dose to the population from natural sources of ionizing radiation in the vicinity of Mochovce nuclear power plant in Slovakia is presented. All major contributions to the effective dose were taken into account, including the contributions from gamma radiation of soil and rocks, cosmic radiation, and indoor and outdoor radon and thoron. On the basis of recent indoor radon measurements in Slovak cities and publicly available data about radon concentration in the soil air, a roughly linear relationship was found between these variables. Consequently, the annual effective dose from indoor radon and thoron was conservatively estimated. For the area of interest, a map of conservatively estimated potential effective doses was created. For the villages in the vicinity of Mochovce, the conservatively estimated effective dose to the population from natural sources ranged from 5.4 to 14.6 mSv, which is four orders of magnitude higher than the contribution of radioactive discharges from Mochovce nuclear power plant. (authors)

  19. The nuclear regulatory authority of the Slovak Republic and start-up of the Mochovce NPP

    International Nuclear Information System (INIS)

    Seliga, Mojmir

    1999-01-01

    The important aspect is testing if the nuclear energy in the Slovak Republic is due to obligatory rules acceptable and its operation is regulated by the state through the independent institution - The Nuclear Regulatory Authority of the Slovak Republic (UJD). UJD considers the whole area of public relations an essential component of its activity. UJD intends to serve the public true, systematic, qualified, understandable and independent information regarding nuclear safety of nuclear power plants, as well as regarding methods and results of UJD work. Generally, public information is considered as significant contribution to the creation of confidence into the regulatory work. The public relations are understood as attempts to establish, keep and improve UJD-s good relations to its neighbours through purposeful informing. An Information centre at the offices of UJD was built and opened in October 1995 with IAEA Director General as the first visitor. NPP Mochovee is an example of international co-operation in achieving internationally acceptable safety standards. Companies from France, Germany, USA, Russian Federation, Czech Republic and Slovakia and last, but not least also the IAEA participated significantly on increasing the safety level of this NPP. We have been fully aware of the importance of good communication with press, TV and radio broadcasting in this pre-operation and operation period about nuclear safety, nuclear standard and other nuclear aspects commissioning of the NPP Mochovce in the UJD. The information policy of the UJD was in this period focused on the preparation an actual press releases for general and specialised news- paper and national press agencies. Very important were the frequent presentations the requirement safety stages of the NPP Mochovce inIV and radio broadcasting by headquarters of the UJD. UJD as the state authority provides information related to its competence, namely information on safety of operation of nuclear installations

  20. Advanced breaking technology on the Mochovce nuclear power plant building site

    Energy Technology Data Exchange (ETDEWEB)

    Mraz, M; Podel, R; Vojta, A [Vyskumny Ustav Inzinierskych Stavieb, Bratislava (Czechoslovakia)

    1982-10-01

    Observing the given deadlines of the construction of the Mochovce nuclear power plant and the required volumes of breaking to the total value of 6.2 million m/sup 3/ of rock, the required output was derived for the 7th five year plan to the value of 200,000 m/sup 3/ per month, i.e., 10,000 m/sup 3/ per day and 700 m/sup 3/ per hour. The basic task is to build a flat building site with an area of 2,300 by 700 m/sup 2/ which requires the removal of a masiff of rocks rising to a height of 37 m, and by compacting the mined rock to build heaps to a height of 20 m. The rocks were disintegrated by blasting. Surface blasting was used for mining faces and ribs. POLONIT 2 or PERMON DAP 1 were mainly used for blasting (ammonium nitrate explosives). The Danubit 1 detonator was used in holes flooded with water. For drilling a combination was used of drilling machines HBM 70 Hausherr with a drilling diameter of 130 to 155 mm and Ingersol Rand ECM 350 with a drilling diameter of 80 mm. The compressors used are Atlas Copco XRHS 350 Dd and PTS 900 Dd. As the optimal combination of machines for the removal of disengaged material for the daily output of 15,000 m/sup 3/ the combination was used of 6 excavators with a shovel volume of 2.5 m/sup 3/ ORENSTEIN-KOPPEL RH 25 with 12 Kockum 445 trucks and 18 ORENSTEIN-KOPPEL RH 40 excavators with a shovel volume of 4 m/sup 3/ and a total of 64 Caterpillar 769 C, Belaz 548 A, Tatra T 200 and T 138 S1 trucks. The planned targets are being fulfilled and the work performed up to now on the Mochovce site equals 2.5 million m/sup 3/ of excavated and removed rock.

  1. Participation of SKODA JS in the construction of the Temelin and Mochovce nuclear power plants

    International Nuclear Information System (INIS)

    Svec, A.; Zach, J.; Ruzicka, P.

    2000-01-01

    SKODA JS is the traditional manufacturer of WWER type reactor equipment and also supplier of the primary circuits and of equipment for the transport, refuelling and storage of fuel for Ver type nuclear power plants built in the Czech and Slovak Republics. The paper deals with activities of the company SKODA JS at two power plants whose reactor units are close to completion, viz. the Mochovce NPP in the Slovak Republic (4 x Ver 440 MW; unit 1 was put in operation in 1998, unit 2 is in the stage of commissioning, units 3 and 4 are not to be completed) and the Temelin NPP in the Czech Republic (2 x Ver 1000 MW, commissioning of units 1 and 2 is expected in 2001 and 2002, respectively). The scope of supplies to the two nuclear power plants (detailed design, delivery of equipment, installation, commissioning) and the course of construction from SKODA JS's viewpoint are described. The most important design changes and improvements made during the construction are highlighted. (author)

  2. Mochovce NPP safety measures evaluation from point of view of operational safety enhancement

    International Nuclear Information System (INIS)

    Cillik, I.; Vrtik, L.

    2000-01-01

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

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

    International Nuclear Information System (INIS)

    Cillik, I.; Vrtik, L.

    2001-01-01

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

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

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  5. Hydrobiological survey of some surface waters in the area of Mochovce nuclear power plant and their saprobiological assessment

    International Nuclear Information System (INIS)

    Kovacik, L.

    1987-01-01

    The results are presented of a hydrobiological study of three flows and one retention reservoir in the surroundings of the Mochovce nuclear power plant (Western Slovakia) performed in June 1982 and May 1983. The research was aimed at obtaining necessary information on the species composition of the algal flora (include blue-green algae) and selected groups of invertebrate hydrofauna (Sarcodina, Rotatoria, Cladocera, Copepoda, Oligochaeta and Chironomidae) in this territory. Natural waters were classified on the basis of the species composition of water organisms according to saprobiological criteria. (author). 4 refs

  6. Current situation of the project finishing of the building of 3 and 4 block of the nuclear power plant Mochovce

    International Nuclear Information System (INIS)

    Niznan, S.

    2005-01-01

    In the contribution there is the basic information mentioned about history of building and the current situation at the finishing of the building of 3 and 4 block of the Nuclear Power Plant Mochovce with the use of project digitization. Further on the contribution shows what kinds of supporting material has been elaborated, what kind of decisions have been issued to the finishing of the building, way of financing and also the assumption of investment return under the defined conditions. An orientation time schedule of the finishing of the building and the crucial steps for its security are presented in the conclusion

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

    International Nuclear Information System (INIS)

    Ocenas, M.

    2009-01-01

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

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

    International Nuclear Information System (INIS)

    Rjeznikov, Iu.V.; Lifshitz, E.V.; Kouznetsov, M.V.; Antropov, V. N.; Doulepov, U. N.; Suchanek, M.

    1997-01-01

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

  9. Analysis of the methodical component of core power density field calculation error on the basis of Mochovce-1 commissioning tests

    International Nuclear Information System (INIS)

    Brik, A.

    2009-01-01

    In the first decade of June 2008, during the power commissioning of the reactor at the Mochovce NPP unit 1, the experiment with reducing the thermal power of core almost to the balance-of-plant (BOP) needs was performed. After the reactor has operated for seven hours at low power (about 200 220 MW (thermal)), its power was increased (at a rate of about 0.25% of N nom /min) to the initial level, close to 107% (1471 MW). During the experiment, core parameters, which were subsequently used for comparing the measured data with the results of experiment simulation calculations, were recorded in the reactor in-core monitoring system database. Calculated and measured levels of critical concentrations of boric acid were compared, along with power density distributions by fuel elements and assemblies obtained both by the KRUIZ in-core monitoring system and on the basis of calculations simulating reactor operation in accordance with the given core power variation schedule. The final stage consisted of assessing the methodical component of power density micro- and macro-fields calculation error in the core of Mochovce-1 reactor operating with varying load. (author)

  10. Analysis of the methodical component of core power density field calculation error on the basis of Mochovce-1 commissioning tests

    International Nuclear Information System (INIS)

    Brik, A.

    2009-01-01

    In the first decade of June 2008, during the power commissioning of the reactor at Mochovce NPP unit 1, the experiment with reducing the thermal power of core almost to the balance-of-plant needs was performed. After the reactor has operated for seven hours at low power (about 200 220 MW (thermal)), its power was increased (at a rate of about 0.25% of N nom /min) to the initial level, close to 107% (1471 MW). During the experiment, core parameters, which were subsequently used for comparing the measured data with the results of experiment simulation calculations, were recorded in the reactor in-core monitoring system's database. Calculated and measured levels of critical concentrations of boric acid were compared, along with power density distributions by fuel elements and assemblies obtained both by the KRUIZ in-core monitoring system and on the basis of calculations simulating reactor operation in accordance with the given core power variation schedule. The final stage consisted of assessing the methodical component of power density micro- and macro-fields' calculation error in the core of Mochovce-1 reactor operating with varying load. (Authors)

  11. Experience gained during commissioning and trial operation of Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    GaL, P.; Adamica, T.; Marosik, V.; Rehak, A.

    2000-01-01

    In this paper authors describe the experience gained during commissioning and trial operation of Mochovce NPP (EMO). The first year of EMO operation from the point of view of safety and reliability was successful. Evidently we were challenged with certain problems characteristic to this stage of operation which resulted in automatic reactor shutdown. There were 11 automatic shutdowns in 1998 by action of the quick emergency protection AO-1 and two manual shutdowns by the AO-1 key. In 1999, there were 6 automatic shutdowns by action of the quick emergency protection AO-1. Three of them was connected to the falsely activated binary signal of MCP switch of, in two cases the reason came out from the turbo-generator (TG) cooling water system. Very positive trend in the operation of both units shows the fact that during all commissioning period of the second unit there were only three automatic reactor shutdowns by the signal AO-1. All these actions were done in frame of commissioning tests. All causes which activated the automatic unit shutdowns were found out and rectified, the overall tuning of the cooling water system is on the process now. The solution of this problem is possible only power commissioning, and in the stage of the trial operation had no direct impacts on the nuclear, radiation, or technical safety respectively. In 1998 two events according to the INES scale after second unit commissioning because of two unit links of the cooling water system. The operational events during the commissioning tests, start-up tests, physical commissioning, were ranked the category 1 ('Action of SIS U040 p po <8,34 MPa at the system 2 and 3' and 'Breaching the L and C'). In 1999 only events occurred that were ranked in the category safety insignificant events and lower (category 0, or off the scale respectively). In the frame of the safety culture principles adopted, such as critical attitude, exact and careful approach, and communication, these problems were given the

  12. Ecological impacts and damage - comparison of selected components for nuclear and conventional power plants (example of Mochovce nuclear power plant)

    International Nuclear Information System (INIS)

    Bucek, M.

    1984-01-01

    A comparison is given of ecological damage for the nuclear power plant in Mochovce and a conventional power plant with the same power. Ecological effects and damage are divided into three groups: comparable damage, ecological damage caused only by conventional power plants and ecological damage caused only by nuclear power plants. In the first group the factors compared are land requisition, consumption of utility water and air consumption. In the second group are enumerated losses of crops (cereals, sugar beet, potatoes, oleaginous plants) and losses caused by increased disease rate owing to polluted environment by conventional power plants. In the third group health hazards are assessed linked with ionizing radiation. Also considered are vent stack escapes. (E.S.)

  13. Requirements and possible upgrading concept for the WWER-440/213: Mochovce NPP structures under seismic conditions

    International Nuclear Information System (INIS)

    Freiman, M.

    1993-01-01

    The Mochovce-Nuclear Power Plant is one of the WWER-440/213 plants which has been designed against earthquake. Nevertheless, the design earthquake has not been assessed adequately to the seismic hazard at the site. A new seismic design shall include an increased seismic input and assure an acceptable standard of safety. This contribution is related to some design aspects of civil structures for this nearly finished plant, such as: existing design and its margins with regard to the employed codes; requirements for a new design concept; effects to be expected by an increased design earthquake; applicable design methods; use of inelastic design spectra, behavior factors and capacity design; feasible upgrading measures. (author)

  14. The design preparation for radiation monitoring system in the frame of completion NPP Mochovce Units 3 and 4

    International Nuclear Information System (INIS)

    Sevecka, S.; Slavik, O.; Kapisovsky, V.

    2009-01-01

    In 1985 a Basic Design of Radiation Monitoring System (RMS) has been elaborated for Mochovce NPP unit 3 and 4 construction. Due to construction interruption in the following years this design solution became obsolete. A new solution of RMS have been developed with conception following that of original Basic Design accommodating also safety measures implemented in RMS of NPP EMO units 1 and 2, and based on modem instrumentation and computer technique. Following the updating of Basic Design documentation the preparation of elaboration of RMS detailed design was carried on. In the frame of this preparation a review of possible suppliers of instrumentation satisfying the conception of radiation monitoring system and the extension of required deliveries has been made. Also criteria on RMS suppliers selection have been determined. The types of monitoring systems and equipment, as well as their quantities, have been specified based on updated Basic Design requirements and production profiles and possibilities of potential suppliers. The required parameters of measurements (including measurement geometry) have been evaluated, as well as requirements of legislation and requirements of proposed RMS architecture. (authors)

  15. Human reliability analysis approach to level 1 PSA - shutdown and low power operation of Mochovce NPP, Unit 1, Slovakia

    International Nuclear Information System (INIS)

    Stojka, Tibor; Holy, Jaroslav

    2003-01-01

    The paper presents general approach, used methods and form of documentation of the results as have been applied within the Human Reliability Analysis (HRA) task of the shutdown and low power PSA (SPSA) study for Mochovce nuclear power plant, Unit 1, Slovakia. The paper describes main goals of the HRA task within the SPSA project, applied methods and data sources. Basic steps of the HRA task and human errors (HE) classification are also specified in its first part. The main part of the paper deals with pre-initiator human errors, human-induced initiators and response to initiator human errors. Since the expert judgment method (SLIM) was used for the last type of human errors probability assessment, also related activities are described including preparation works (performance shaping factors (PSFs) selection, development of PSF classification tables, preparation of aid tools for interview with plant experts), qualitative analysis (sources of information and basic steps) and quantitative analysis itself (human errors classification for final quantification including criteria used for the classification, description of structure of the spreadsheet used for quantification and treatment with dependencies). The last part of the paper describes form of documentation of the final results and provides some findings. (author)

  16. Results of physics start-up tests of Mochovce and Bohunice units with 2-nd generation Gd fuel (average enrichment 4.87 %)

    International Nuclear Information System (INIS)

    Polakovic, F.

    2015-01-01

    There are presented main features of the fuel and the list of experimental neutron-physical characteristics measured during physics start-up tests.All together there were carried out 14 physics start-ups at Bohunice and Mochovce Units with the new type of fuel. Differences between theoretical and experimental neutron-physical characteristics were statistically processed and compared with the tests acceptance criteria. There are summarized results of reactor physics start-ups with 2-nd generation Gd fuel usage [ru

  17. The experience from operation of electronic personal dosimetry system at Dukovany, Temelin and Mochovce NPPs after repair of Siemens dosemeters eliminating false doses

    International Nuclear Information System (INIS)

    Malysak, J.; Kocvara, S.; Jurochova, B.; Zelenka, Z.; Schacherl, M.; Zrubec, M.; Kaiser, H.

    2003-01-01

    This presentation summarizes the operational experience of the Electronic Personal Dosimetry Systems installed at Dukovany, Temelin and Mochovce NPPs. The system consists of three basic parts: Electronic personal dosemeters (EPD); Physical layer (HW); Logical layer (SW). Number of false doses before and after correction is presented. This presentation has demonstrated the possibilities of SEOD system and the possibility of easy dose comparison between the individual NPPs after introducing this electronic dosimetry system. Basically, the results of film and electronic dosimetry systems are according to our findings nearly identical. Electronic dosemeter sensitivity to interfering electromagnetic fields is a problem which is easily re-movable. In addition, if we know this problem, these false doses in the SEOD system can be easily revealed (e.g. by investigation of histograms) and repaired

  18. Eco information 4. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within April 2014

    International Nuclear Information System (INIS)

    2014-05-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within February 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 1.011 GBq of tritium (1.011 for the period January - April 2014 (0.36% of AL)) and summary of gamma-radionuclides 0.479 GBq (0.944 GBq for the period January - April 2014 (24.21% of AL)). The radioactive effluents into hydrosphere within April 2014 for FS KRAO were: 62 kBq of 90 Sr (62 kBq for the period January - March 2014 (0.003% of AL)), 0.003 kBq of summary alpha (0.003% of AL) and 1847 kBq of 14 C (1847 kBq for the period January - March 2014). The radioactive effluents into hydrosphere within April 2014 for RU RAO were: 0.568 MBq of tritium (4.544 MBq for the period January - April 2014 (0.024% of AL)); 0.004 MBq of 137 Cs (0.033 MBq for the period January - April 2014 (0.145% of AL)); 0.119 MBq of 90 Sr - the value of the quarterly (0.119 MBq for the period January - March 2014 (0.049% of AL)); 0.008 MBq of 60 Co (0.031 MBq for the period January - April 2014 (0.138% of AL)); 0.005 MBq of 239 Pu (0.005 MBq for the period January - March (0.892% of AL)). Volume of liquid effluents in April 2014 was 227 m 3 (186 m 3 for the period January - April 2014). The radioactive effluents into atmosphere within April 2014 for FS KRAO were: 0.0005 MBq of gamma radionuclides (0.0018 MBq for the period January - April 2014, that is 0.0023% of annually limit (AL)); 0.022 MBq of alpha radionuclides (0.022 MBq for the period January - March (0.0022% of AL)), and 0.149 MBq of 89 Sr and 90 Sr - the value of the quarterly (0.149 MBq for the period January - March 2014 (0.0075% of AL)).

  19. Eco information 10. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within October 2014

    International Nuclear Information System (INIS)

    2014-11-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within October 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.512 GBq of tritium (8.464 GBq for the period January - October 2014 (2.82% of AL)) and summary of gamma-radionuclides 0.147 GBq (2.904 GBq for the period January - October 2014 (64.13% of AL)). The radioactive effluents into hydrosphere within July - September 2014 for FS KRAO were: 60 kBq of 90 Sr (489 kBq for the period January - September), 0.003 kBq of summary alpha (0.030 kBq of annually value) and 1920 kBq of 14 C for the period July - September (39367 kBq of annually value). The radioactive effluents into hydrosphere within October 2014 for RU RAO were: 0 MBq of tritium (13.064 MBq for the period January - October 2014 (0.069% of AL)); 0 MBq of 137 Cs in October 2014 (0.092 MBq for the period January - August 2014 (0.404% of AL)); 0.128 MBq of 90 Sr - the value within July - September 2014 (0.324 MBq for the period January - September 2014 (0.13% of AL)); 0 MBq of 60 Co in October 2014 (0.093 MBq for the period January - October 2014 (0.415% of AL)); 0.006 MBq of 239 Pu (0.016 MBq for the period April - June 2014 (2.86% of AL)). Volume of liquid effluents in October 2014 was 0 m 3 (5221 m 3 for the period January - October 2014). The radioactive effluents into atmosphere within October 2014 for FS KRAO were: 0.0007 MBq of gamma radionuclides (0.0055 MBq for the period January - October 2014, that is 0.0068% of annually limit (AL)); 0.025 kBq of alpha radionuclides within July - September 2014 (0.071 kBq for the period July - September 2014 (0.0071% of AL)), and 0.161 kBq of 89 Sr and 90 Sr - the value within July - September 2014 (0.465 kBq for the period January

  20. Eco information 2. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within February 2014

    International Nuclear Information System (INIS)

    2014-03-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within February 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.0000 GBq of tritium (9.0000 for the period January - February 2014 (0.00% of AL)) and summary of gamma-radionuclides 0.0000 GBq (0.0000 GBq for the period January - February 2014 (0.00% of AL)). The radioactive effluents into hydrosphere within February 2014 for FS KRAO were: 0.000 kBq of 90 Sr (0.000% of AL)), 0.000 kBq of summary alpha (0.000% of AL) and 0.000 kBq of 14 C (0.000% of AL). The radioactive effluents into hydrosphere within February 2014 for RU RAO were: 2.272 MBq of tritium (3.976 MBq for the period January - February 2014 (0.021% of AL)); 0.017 MBq of 137 Cs (0.029 MBq for the period January - February 2014 (0.127% of AL)); 0.00 MBq of 90 Sr - the value of the quarterly (0.00 MBq for the period January - March 2013 (0.000% of AL)); 0.014 MBq of 60 Co (0.023 MBq for the period January - February 2014 (0.103% of AL)); 0.000 of 239 Pu (0.000 MBq for the period January - March 2014 (0.000% of AL)). Volume of liquid effluents in February 2014 was 908 m 3 (1589 m 3 for the period January - February 2014). The radioactive effluents into atmosphere within February 2014 for FS KRAO were: 0.0002 MBq of gamma radionuclides (0.0007 MBq for the period January - February 2014, that is 0.0009% of annually limit (AL)); 0.000 MBq of alpha radionuclides (0.000 MBq for the period January - March 2014 (0.000% of AL)), and 0.000 MBq of 89 Sr and 90 Sr - the value of the quarterly (0.000 MBq for the period January - March 2014 (0.000% of AL)).

  1. Eco information 3. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within March 2014

    International Nuclear Information System (INIS)

    2014-04-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within March 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.056 GBq of tritium (0.056 for the period January - March 2014 (0.2% of AL)) and summary of gamma-radionuclides 0.465 GBq (0.465 GBq for the period January - March 2014 (11.92% of AL)). The radioactive effluents into hydrosphere within January - March 2014 for FS KRAO were: 0.000 kBq of 90 Sr (0.000% of AL)), 0.000 kBq of summary alpha (0.000% of AL) and 0.000 kBq of 14 C (0.000% of AL). The radioactive effluents into hydrosphere within March 2014 for RU RAO were: 0.000 MBq of tritium (3.976 MBq for the period January - March 2014 (0.021% of AL)); 0.000 MBq of 137 Cs (0.029 MBq for the period January - March 2014 (0.127% of AL)); 0.00 MBq of 90 Sr - the value of the quarterly (0.00 MBq for the period January - March 2014 (0.000% of AL)); 0.000 MBq of 60 Co (0.023 MBq for the period January - March 2014 (0.103% of AL)); 0.000 MBq of 239 Pu (0.000 MBq for the period January - March 2014 (0.000% of AL)). Volume of liquid effluents in March 2014 was 0 m 3 (1589 m 3 for the period January - March 2014). The radioactive effluents into atmosphere within March 2014 for FS KRAO were: 0.0006 MBq of gamma radionuclides (0.0013 MBq for the period January - March 2014, that is 0.0016% of annually limit (AL)); 0.00 MBq of alpha radionuclides (0.000 MBq for the period January - March 2014 (0.000% of AL)), and 0.000 MBq of 89 Sr and 90 Sr - the value of the quarterly (0.000 MBq for the period January - March 2014 (0.000% of AL)).

  2. Eco information 1. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within January 2014

    International Nuclear Information System (INIS)

    2014-02-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within January 2014 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.0000 GBq of tritium (0.0000 GBq for the period January - January 2014 (0.000% of AL)) and summary of gamma-radionuclides 0.0000 GBq (0.0000 GBq for the period January - January 2014 (0.000% of AL)). The radioactive effluents into hydrosphere within January 2014 for FS KRAO were: 1,704 kBq of 90 Sr (0.009% of AL)), 0.012 kBq of summary alpha (0.053% of AL) and 0.000 kBq of 14 C (0.000% of AL). The radioactive effluents into hydrosphere within January 2014 for RU RAO were: 0.009 MBq of tritium (1.704 MBq for the period January - January 2014 (1.704% of AL)); 0.012 MBq of 137 Cs (0.012 MBq for the period January - January 2014 (0.053% of AL)); 0.000 MBq of 90 Sr - the value of the quarterly (0.000 MBq for the period January - January 2014 (0.000% of AL)); 0.009 MBq of 60 Co (0.009 MBq for the period January - January 2014 (0.04% of AL)); 0.000 MBq of 239 Pu (0.000 MBq for the period January - January 2014 (0.000% of AL)). Volume of liquid effluents in January 2014 was 681 m 3 (4681m 3 for the period January - January 2014). The radioactive effluents into atmosphere within January 2014 for FS KRAO were: 0.0005 MBq of gamma radionuclides (0.0005 MBq for the period January - January 2014, that is 0.0006% of annually limit (AL)); 0.000 MBq of alpha radionuclides (0.000 MBq for the period January - January 2014 (0.000% of AL)), and 0.000 MBq of 89 Sr and 90 Sr - the value of the quarterly (0.000 MBq for the period January - January 2014 (0.000% of AL)).

  3. Eco information 4. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within April 2016

    International Nuclear Information System (INIS)

    2016-05-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within April 2016 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.642 GBq of tritium (0.649 GBq for the period January - April 2016 (0.213% of AL)) and summary of gamma-radionuclides 0.000 GBq (0.000 GBq for the period January - April 2016 (0.0% of AL)). The radioactive effluents into hydrosphere within January - January 2016 for FS KRAO were: 0 kBq of 90 Sr (0 kBq for the period January - March 2016), 0.024 kBq of summary alpha (0.024 kBq of annually value) and 10.817 kBq of 14 C for the period January - March 2016 (01.817 kBq of annually value). The radioactive effluents into hydrosphere within April 2016 for RU RAO were: 0.000 MBq of tritium (2.840 MBq for the period January - April 2016 (0.015% of AL)); 0.000 MBq of 137 Cs in April 2016 (0.026 MBq for the period January - April 2016 (0.114% of AL)); 0.248 MBq of 90 Sr - the value within January - March 2016 (0.248 MBq for the period January - April 2016 (0.102% of AL)); 0.000 MBq of 60 Co in April 2016 (0.018 MBq for the period January - April 2016 (0.080% of AL)); 0.009 MBq of 239 Pu (0.009 MBq for the period January - March 2016 (1.607% of AL)). Volume of liquid effluents in January 2016 was 0 m 3 (1135 m 3 for the period January - April 2016). The radioactive effluents into atmosphere within April 2016 for FS KRAO were: 0.0010 MBq of gamma radionuclides (0.0041 MBq for the period January - April 2016, that is 0.0039% of annually limit (AL)); 0.027 kBq of alpha radionuclides within January - March 2016 (0.027 kBq for the period January - March 2016 (0.0027% of AL)), and 0.179 kBq of 89 Sr and 90 Sr - the value within January - March 2016 (0.179 kBq for the period January - March

  4. Eco information 2 Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, Locality of Mochovce, within February 2016

    International Nuclear Information System (INIS)

    2016-03-01

    In this leaflet the results of monitoring of radioactive gaseous and liquid effluents into the Hron River as well as of radiation monitoring of Mochovce Liquid RAW Final Treatment Facility (FS KRAO) and Mochovce Radioactive Waste Repository (RU RAO) are presented. The radioactive effluents into hydrosphere within February 2016 for the radioactive effluents into hydrosphere within for FS KRAO were: 0.007 GBq of tritium (0.000 GBq for the period January - February 2016 (0.02% of AL)) and summary of gamma-radionuclides 0.215 GBq (0.215 GBq for the period January - February 2016 (5.51% of AL)). The radioactive effluents into hydrosphere within January - March 2016 for FS KRAO were: 0 kBq of 90 Sr (0 kBq for the period January - March 2016), 0 kBq of summary alpha (0 kBq of annually value) and 0 kBq of 14 C for the period January - March 2016 (0 kBq of annually value). The radioactive effluents into hydrosphere within January 2016 for RU RAO were: 2.272 MBq of tritium (2.272 MBq for the period January - March 2016 (0.012% of AL)); 0.018 MBq of 137 Cs in February 2016 (0.018 MBq for the period January - March 2016 (0.079% of AL)); 0.000 MBq of 90 Sr - the value within January - March 2016 (0.000 MBq for the period January - March 2016 (0.000% of AL)); 0.013 MBq of 60 Co in February 2016 (0.013 MBq for the period January - March 2016 (0.058% of AL)); 0.000 MBq of 239 Pu (0.000 MBq for the period January - March 2016 (0.00% of AL)). Volume of liquid effluents in February 2016 was 908 m 3 (908 m 3 for the period January - February 2016). . The radioactive effluents into atmosphere within February 2016 for FS KRAO were: 0.0009 MBq of gamma radionuclides (0.002 MBq for the period January - February 2016, that is 0.0025% of annually limit (AL)); 0.000 kBq of alpha radionuclides within January - March 2016 (0.000 kBq for the period January - March 2016 (0.000% of AL)), and 0.000 kBq of 89 Sr and 90 Sr - the value within January - March 2016 (0.000 kBq for the period January

  5. Unit 1 and Unit 2 Nuclear Power Plant Mochovce construction finishing from primary contractor of technological part. Skoda Praha a. s. point of view

    International Nuclear Information System (INIS)

    Horky, F.

    2000-01-01

    In this paper the history of delivery of technological part for NPP V-1 Mochovce as well as of reconstruction and safety improvements by the Skoda Praha a.s. is presented. Primary contractor of technological part Skoda Praha together with its final suppliers proved ability to realize under hard conditions such a complicated work what was indisputedly Units 1 and 2 finishing. Company proved capability to conform itself flexibly in the course of work to requirements of customer for realization of safety measures which means that Units 1 and 2 fully satisfy international standards. By fulfilment of primary contractor of technology obligations and above all by takeover of complex responsibility for both Units putting in operation including responsibility for 'past' Skoda Praha put away one of basic problems which occurred in decision making to whom will be assigned construction finishing contract. These facts fully qualify Skoda Praha to be selected for possible Units 3 and 4 construction finishing as one of chief construction finishing participant

  6. Contribution of Mochovce Units completion

    International Nuclear Information System (INIS)

    Burdova, J.

    2013-01-01

    In spite of the on-going economic crisis in Europe, Slovakia is still showing economic growth. Slovenske elektrarne belong to the key companies within the Slovak economy. Not only because of its position in the electricity market, basis for the operation of companies and homes, but also because of its influence on the social and economic development of the country. (author)

  7. 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).

  8. 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; Sprava o hodnoteni v zmysle zakona NR SR c.24/2006 o posudzovani vplyvov na ZP. Rozsirenie RU RAO v Mochovciach pre ukladanie NSAO a vybudovanie uloziska pre VNAO

    Energy Technology Data Exchange (ETDEWEB)

    Hanusik, V; Moravek, J; Kusovska, Z [VUJE, a.s., 91864 Trnava (Slovakia)

    2011-11-30

    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).

  9. NPP Mochovce - a project of extraordinay significance

    International Nuclear Information System (INIS)

    Chwolik, I.; Debru, M.

    2000-01-01

    In this paper and in this presentation the reactor safety upgrading of two blocks of the NPP V-1 Bohunice, some results of participation on safety upgrading by the German-French consortium EUCOM (Framatome and Siemens-KWU) are presented. (author)

  10. Slovak Electric, plc, Mochovce Nuclear Power Plant

    International Nuclear Information System (INIS)

    1999-01-01

    In this popular scientific brochure a brief description of construction scheme of Bohunice Nuclear Power Plant is presented. Electricity generation in a nuclear power plant is described. Instrumentation and control system as well as nuclear safety principles applied on the NPP are presented

  11. Safety measures for NPP Mochovce - Skoda contribution

    International Nuclear Information System (INIS)

    Svec, P.

    1997-01-01

    Brief technical descriptions are given of the following issues involved in safety measures: reactor pressure vessel embrittlement and its monitoring; non-destructive testing; integrity of the steam generator primary collector; integrity of steam generator heat exchanging tubes; distribution of feedwater in the steam generator; the hazard of plugging water collectors located on the steam generator room floor; steam generator level control valves; primary circuit venting under emergency conditions; diagnostic systems installed in the primary circuit; monitoring of reactor pressure vessel head leaks; severity of containment leaks; turbine missiles; seismic design; procedures for normal operation; and operation limits and conditions. (M.D.)

  12. Staranje cevi uparjalnikov v Jedrski elektrarni Krško: Aging of tubes in the Krško nuclear power plant's steam generators:

    OpenAIRE

    Androjna, Ferdo; Cizelj, Leon

    2000-01-01

    The paper reviews the domestic efforts devoted to the safe and reliable operation of the Krško nuclear power plant (NPP) at full power, close to the design limit of the steam generators (18% of plugged tubes) for a full decade. This includes an overview of the recent status and history of the degradation processes, discussion of repair criteria, defining the acceptable size of defects and selected results from safety analyses supporting the operation of degraded steam generator (SG) tubes. It...

  13. Should the service life of nuclear power plants be limited for technical reasons?; Mela by byt provozni zivotnost jaderne elektrarny z technickych duvodu omezena?

    Energy Technology Data Exchange (ETDEWEB)

    Schomer, E

    1995-03-01

    German nuclear power plant operating licenses take into account the fact that the design lifetime of the facilities is 40 years. The technological lifetime, however, is governed by actual ageing processes and operational burden. The service life of nuclear power plants can be extended by replacement of the steam generator and by repair or replacement of the reactor pressure vessel or parts thereof. Attention is also paid to the reactor protection systems. (J.B.). 8 figs.

  14. Slovenske elektrarne, Mochovce nuclear power plant. Safety strategy

    International Nuclear Information System (INIS)

    1999-01-01

    In this leaflet the Management's declaration is presented. This declaration contains: operation management and quality assurance, plant commissioning, maintenance and repairs, reactor physics, radiation protection, surveillance programmes, events analyses and experience feed-back, accident management procedures and training, emergency planning and preparedness review of safety performance, human resources, and personnel responsibility

  15. Public Discussion about Completion of Mochovce Units 3 and 4

    International Nuclear Information System (INIS)

    Anon

    2014-01-01

    After the introduction of the Nuclear Regulatory Authority (NRA) reopened NRA, the participants familiarised themselves with the history of M.I.5 (1980-2008), with the decisions of the NRA issued in 2008, with the law-suit and the judgement of the Supreme Court of the Slovak Republic, with the course of the procedure after the judgement, and with the comments, proposals and suggestions of the procedure participants delivered to the Authority within the specified period. The public hearing of the comments was followed by technical comments of the procedure participants focused on events at one unit that can affect the neighbouring unit, containment concept, seismic threat and accidents with fuel melting, which were fully answered by the competent persons. The hearing ended with a discussion.

  16. The common project for completion of Bubbler Condenser Qualification (Bohunice, Mochovce, Dukovany and Paks NPPs)

    International Nuclear Information System (INIS)

    Jaroslav, H.; Pavol, B.

    2003-01-01

    Described is the common project for completion of bubbler condenser qualification for nuclear power plants in Bohunice, Mochovice, Dukovany and Paks. Functionality of the bubbler condenser was elaborated during the simulation of the main steam line brake, medium break and small break LOCA. On this basis the appropriate operation of bubbler condenser containment under accident conditions can be positively confirmed

  17. The Slovak nuclear regulatory authority and start-up of the Mochovce NPP

    International Nuclear Information System (INIS)

    Seliga, M.; Micankova, J.

    2000-01-01

    A major element of providing information is the demonstration that the area of nuclear energy uses has its binding rules in the Slovak Republic and the observance thereof is controlled by the state through an independent institution Slovak Nuclear Regulatory Authority (UJD). As early as 1995 were laid on the UJD the foundations of the concept of broadly keeping the public informed on UJD activity and the safety of nuclear installations by opening the UJD Information Centre that provides by its activity communications with the public and mass media, which is instrumental in creating in the public a favourable picture of the independent state nuclear regulation. Clear communication policy is the key to credibility and is based on perceptions which give ride to varying levels of confidence. It has been consistently found in opinion research that credibility is the single most powerful persuasive force. Public communication programmes are the principal currency for the Regulatory Authority to inform the public on issues like costs, benefit requirements and risks

  18. Simulation of rod drop experiments in the initial cores of Loviisa and Mochovce

    International Nuclear Information System (INIS)

    Kaloinen, E.; Kyrki-Rajamaeki, R.; Wasastjerna, F.

    1999-01-01

    Interpretation of rod drop measurements during startup tests of the Loviisa reactors has earlier been studied with two-dimensional core calculations using a spatial prompt jump approximation. In these calculations the prediction for the reactivity meter reading was lower than the measured values by 25%. Another approach to solve the problem is simulation of the rod drop experiment with dynamic core calculations coupled with out of core calculations to estimate the response of ex-core ionization chambers for the reactivity meter. This report described the calculations performed with the three-dimensional dynamic code HEXTRAN for prediction of the reactivity meter readings in rod drop experiments in initial cores of the WWER-440 reactors. (Authors)

  19. Vulnerability of steam generator super-emergency feeding. Super-emergency feedwater system for the Mochovce NPP steam-generators

    International Nuclear Information System (INIS)

    Hlasova, M.; Jary, A.

    1997-01-01

    The following major requirements and criteria fulfillment concerned the super-emergency feedwater system (SEFW) system were proposed: to provide sufficient water amount for accident conditions, inclusive seismicity, even during required SEFW system operation for the time period of 72 hours; to analyse ensuring of residual heat removal in case of a station black-out; to state criteria for water supply by the SEFW system into the steam generators (SGs); to simplify the existing connection scheme inclusive decreasing the number of valves, which are in series; to analyse and provide the system protection against a common cause failure, which the SEFW system did not provide in some parts (possibilities of three systems failure due to flooding; vulnerability of all tanks by the operation building fall in case of a seismic event; vulnerability of all tanks due to extreme climatic conditions; vulnerability of all tanks during new seismic loading and consequent mutual endangering; the possibility of three systems failure due to common routing in the vicinity of high; energy media on the +14,7 m floor in the intermediate machinery building and due to inconsistent electrical valves secured power supply systems); to analyse temperature increase impact on the number of uses and lifetime of SGs; to perform a change of SEFW system pipelines routing layout outside the dangerous area of the +14,7 m floor in the intermediate machinery building with high energy media; checking the thanks autonomy. There were performed analyses of selected transient operation modes. The analyses had the following objectives: necessary flowrate of the SEFW in case of the primary side stabilised temperature of 140 C till 72 hours of the process duration; sufficient capacity of one subsystem for the supply of sufficient water amount; sufficient water reserve in the tanks at given conditions; and other. Accident situations were evaluated using an analysis and three characteristic operation modes were selected, out of them each covers a group of ana-logical processes: operating mode with feedwater loss; operating mode with station black-out; operating mode during an earthquake

  20. Větrné podmínky pro malé větrné elektrárny

    Czech Academy of Sciences Publication Activity Database

    Hanslian, David

    -, červen (2012), - ISSN 1801-4399 R&D Projects: GA AV ČR(CZ) KJB300420905 Institutional support: RVO:68378289 Keywords : wind energy * small wind turbines * wind speed * wind conditions * wind power production Subject RIV: DG - Athmosphere Sciences, Meteorology http:// oze .tzb-info.cz/vetrna-energie/8358-vetrne-podminky-pro-male-vetrne-elektrarny

  1. Safety provisions for steam generator in Mochovce nuclear power plant. BO CI 04 Integrity of primary collectors of VVER 440 steam generators

    International Nuclear Information System (INIS)

    Cikryt, F.; Bednarek, L.; Matocha, K.; Vejvoda, S.

    1997-01-01

    This paper dealt with the identification of possible damaging mechanism of the collector of the WWER 440 steam generator, cracking of primary collectors, corrosion damage of the protective coat of the primary collector circumferential weld, cracking of breathing space in the region of blinding effect by corrosion and strain, leaking of disassembling joint of the primary collector lid and with the integrity of heat exchanging tubes

  2. Quality provision within the preparation of the finishing of the building of 3. and 4. block of the Nuclear Power Plant Mochovce

    International Nuclear Information System (INIS)

    Kompan, L.

    2007-01-01

    The contribution defines within the mentioned project the basic documentation of quality management system, relation between the launching programme, phase programmes and quality plans, relations between documentation of quality provision and documentation of the project quality provision. Moreover it describes the organisation structure of the plant Slovak Power Plants MO34 and the organisation scheme of the project team and principles of communication between teams on the working level

  3. Appraisal of the correspondence of the safety improvement measures proposed for the Mochovce NPP with respect to the ones outlined in the TEO for the Juragua NPP

    International Nuclear Information System (INIS)

    Pereira Hernandez, Guillermo

    1996-01-01

    The work accomplished consisted in determining the correspondence or relationship between the safety improvement measures of the outlined for both plants as well as a preliminary analysis from which were determined. The measures which a deeper analysis is recommended to evaluate theirs possible addition to the group it is recommended to deepen with a view to take into considerations aspects of interest that in them are outlined and which could serve to enhance the approach or the linkage of the measures outlined in the TEO

  4. Slovak National Prize for Quality 2004

    International Nuclear Information System (INIS)

    Steflik, Marian

    2009-01-01

    Competition for the Slovak National Prize for Quality is a milestone in the history of the Mochovce NPP. The Mochovce NPP won the prize in 2004. The article describes in detail the preparatory efforts including not only technological issues but also various administrative challenges. The impacts of this achievement on the plant's subsequent development are also highlighted. (orig.)

  5. We should use nuclear power plants as good as possible

    International Nuclear Information System (INIS)

    Kaplanova, J.

    2004-01-01

    In this paper visit of Austrian journalist Christian Hunger (redactor of the Austrian broadcast OE1) on the Jaslovske Bohunice NPP and Mochovce NPP is described. Upgrade of the Jaslovske Bohunice NPP and finishing of a building of the Mochovce NPP as well as shut-down of the first and second blocks of the Jaslovske Bohunice NPP are discussed

  6. Part II. Chapter VII. Lack of knowledge has generated misconceptions about WWER in Western Europe

    International Nuclear Information System (INIS)

    Bucha, T.

    2008-01-01

    In this interview Mr. Giancarlo Aquilanti (Project Director Mochovce NPP, Unit-3 and Unit-4, the Slovenske elektrarne, a. s., a member of ENEL) evaluates reactor safety in Mochovce NPP. Perspectives of development of nuclear energy in the Slovak Republic and Italia are discussed.

  7. Radwaste treatment and disposal

    International Nuclear Information System (INIS)

    Ehn, L.; Breza, M.; Pekar, A.

    2000-01-01

    In this lecture is given the basic information, that is concerning on the RAW treatment and long term disposal of the treated RAW in repository at Mochovce. Then here is given the basic technical and technological information, that is concerning bituminization, plant, the vitrification unit, center for the RAW-treatment (BSC) and repository at Mochovce. (authors)

  8. Part I. Chapter IV. Coldness is coming from Wienna

    International Nuclear Information System (INIS)

    Blaha, M.

    2008-01-01

    In this chapter author reviewed a political pressure of Austrian government and Austrian legislative assembly on Slovakia before fuel assembly insertion and commissioning of the Unit-1 of the Mochovce NPP. Mission of Walkdown II is described.

  9. Future strategy of SE

    International Nuclear Information System (INIS)

    Arcelli, M.

    2006-01-01

    In this presentation author (General Director of Slovenske elektrarne, a. s.) presents structure and investment plans of SE. The feasibility study of construction of the blocks 3 and 4 of the Mochovce NPP is presented

  10. National Report

    International Nuclear Information System (INIS)

    Lipar, M.

    2001-01-01

    Power production in Slovak Republic is presented. The safety at the NPPs Bohunice V-1, V-2 and Mochovce is discussed. The events - Automatic Reactor Scram at Bohunice 1 and Power Reduction - Home Load at Bohunice 2 due to short circuit in the external grid on 22 May 2001 and Manual Reactor Scram at Mochovce 2 NPP due to Loss of Offsite Power on 30 May 2001 are described

  11. Ukraine is nuclear Great Power

    International Nuclear Information System (INIS)

    Svolik, S.

    2005-01-01

    In this paper the interview with Mr. Jaroslav Holubec - the Director of the Mochovce NPP is published. MR. Jaroslav Holubec with Mr. Stefan Niznan - the Director of the 3 r d and 4 th blocks of the Mochovce NPP - took part in opening commissioning of blocks on the Rovno NPP and Khmelnitskaya NPP, both with installed reactors 1,000 MW. Development of nuclear energetics in the Ukraine is discussed. The share of nuclear energy on the production of the Ukraine constitutes 42 %

  12. Irradiation temperature measurement of the reactor pressure vessel surveillance specimen in the programmes of radiation degradation monitoring

    International Nuclear Information System (INIS)

    Kupca, L.; Stanc, S.; Simor, S.

    2001-01-01

    The information's about the special system of irradiation temperature measurement, used for reactor pressure vessel surveillance specimen, which are placed in reactor thermal shielding canals are presented in the paper. The system was designed and realized in the frame of Extended Surveillance Specimen Programme for NPP V-2 Jaslovske Bohunice and Modern Surveillance Specimen Programme for NPP Mochovce. Base design aspects, technical parameters of realization and results of measurement on the two units in Bohunice and Mochovce NPPs are presented too. (Authors)

  13. SE-VYZ - Decommissioning of Nuclear Installations, Radioactive Waste and Spent Fuel Management

    International Nuclear Information System (INIS)

    Anon

    2004-01-01

    In this presentations processes of radioactive waste treatment in the Bohunice Radioactive Waste Processing Center (SE-VYZ), Jaslovske Bohunice are presented. Decommissioning of the A-1 NPP is also presented. Disposal of conditioned radioactive waste in fibre concrete containers (FCC) are transported to Mochovce from Jaslovske Bohunice by the transport truck where are reposited in the National radioactive waste repository Mochovce. The Interim spent fuel storage facility (ISFSF) is included into this presentation

  14. VUJE capabilities for participation in the development of Slovak power sector

    International Nuclear Information System (INIS)

    Liska, P.

    2004-01-01

    In this presentation author deals with VUJE Trnava, Inc. capabilities for participation in the development of Slovak power sector. It is concluded that VUJE supports the completion of Mochovce units 3 and 4 as the most effective option; VUJE calls of the Slovak government to revive negotiations on a revision of a commitment to close V1 units Bohunice NPP in 2006 or 2008 respectively; VUJE is prepared to be an important participant in supply system for Mochovce NPP Units 3 and 4

  15. The biggest investment in the history of Slovakia

    International Nuclear Information System (INIS)

    Anon

    2009-01-01

    On 11 June 2009 the General Director and Chairman of the Board of Directors of Slovenske elektrarne Paolo Ruzzini and the Prime Minister of the Slovak Republic Robert Fico announced the signature of contracts with the main suppliers for the completion of units 3 and 4 of Mochovce Nuclear Power Plant. Planned investment of Eur 2.775 billion by 2013 for the Mochovce completion is an important commitment for us and especially in this time, such investment can mitigate the impact of global slowdown in economic growth which impacts Slovakia but also other economies of the world. (author)

  16. Safety of nuclear installations in Slovakia

    International Nuclear Information System (INIS)

    1998-01-01

    In this part next aspects are described: (1) Site selection (Legislation related to site selection; Meeting criteria at Bohunice and Mochovce sites; International agreements); (2) Design preparation and construction (Designing and construction-relevant legislation; Nuclear installation project preparation of nuclear installation at Mochovce site); (3) Operation (Operator licensing procedure; Operation limits and conditions; Maintenance testing and control documentation for management and operation; Technical support of operation; Analysis of events at nuclear installations and Radioactive waste production); (4) Planned safety upgrading activities at nuclear installations

  17. Slovenske elektrarne and the environment

    International Nuclear Information System (INIS)

    Mihaly, B.

    2003-01-01

    In this paper the environmental impact from Slovenske elektrarne is reviewed. The Mochovce Nuclear Power Plant has obtained as the first plant in the Slovak Republic - the International certificate in environmental management according the norm ISO 14001:1996 for production and supply of electric energy from NPP. The Certification was awarded by the certification company Det Norske Veritas Slovensko according to the Dutch accreditation the Raad voor Accredative. Mochovce NPP has obtained the Certificate after compliance of process requests and it is active for three years. After expiration of this period the certification process must be repeated

  18. Safety improvement programme of WWER 440/230 units in Jaslovske Bohunice

    International Nuclear Information System (INIS)

    Tomek, J.

    2000-01-01

    A brief overview is given of the power sources in Slovakia which include 6 operational reactor units (4 at Jaslovske Bohunice and 2 at Mochovce) and 2 units under construction (at Mochovce). The efforts undertaken in the past 10 years and aimed at upgrading the nuclear safety of the two older (V-230 Soviet type) units at Bohunice are highlighted. The relevant regulatory decisions are dealt with and the measures already carried out are listed. Also characterized are several IAEA international safety assessment missions and safety-aimed meetings which took place in 1998 and 1999 and are of concern to the older Bohunice units. (A.K.)

  19. Training of personnel

    International Nuclear Information System (INIS)

    1997-01-01

    Selected staffs (in the area of NPPs) are examined by the State Examining Committee established by Nuclear Regulatory Authority of the Slovak Republic (NRA SR's) chairman. The committee consists of representatives of NRA SR , Bohunice NPPs, Mochovce NPP, Research Institute of Nuclear Energy and experts from the Faculty of Electrical Engineering and Information Technology of the Slovak Technical University. The review of selected personnel of NPP V-1, V-2 and Mochovce NPP which passed exams in 1996 is given. NRA SR paid attention to the upgrading training process of individual categories of staff for V-1, V-2 and Mochovce NPPs, simulator training and training with computerized simulation system according to the United criteria of nuclear installation personnel training that started in 1992. During the year, an inspection was performed focused on examination of technical equipment of the simulator of Mochovce NPP, professional eligibility and overall preparation of simulator training including simulator software. Throughout the year launching works continued at the simulator with the deadline of commissioning to trial use operation in the first half of 1997

  20. Can Slovakia secure reliable electricity supply without nuclear?

    International Nuclear Information System (INIS)

    Pnacek, I.

    2004-01-01

    In this presentation author deals with structure of electricity production in the Slovak republic in 2006 and perspectives of electricity supply up to 2020 year. Decommissioning of Unit 1 and Unit 2 of the Bohunice NPP and completion of Unit 3 and 4 of the Mochovce NPP are discussed

  1. Case law

    International Nuclear Information System (INIS)

    2015-01-01

    This section treats of the two following case laws: Slovak Republic: Further developments in cases related to the challenge by Greenpeace Slovakia to the Mochovce nuclear power plant; United States: Judgment of the Nuclear Regulatory Commission denying requests from petitioners to suspend final reactor licensing decisions pending the issuance of a final determination of reasonable assurance of permanent disposal of spent fuel

  2. Part II. Chapter I. Nobody will build the nuclear power cheaper than we finish it under construction

    International Nuclear Information System (INIS)

    Bucha, T.

    2008-01-01

    This is an interview with Mr. Sergej Kozlik (vice-prime minister of the Slovak Government from October 11, 1993 up to March 15, 1994 and from December 12, 1994 up to October 30, 1998 and finance minister from December 13, 1994 up to January 14, 1998) who is remembering about financing of construction of the Mochovce NPP.

  3. Review of selected contributions of the conference 'Suppliers and requirements for quality provision'

    International Nuclear Information System (INIS)

    2007-03-01

    There were 12 contributions presented at the conference focused on the requirements of the standard ISO 9001:2000 for supplies of services and products, especially from the point of view of supplies for nuclear power plants. Two contributions were focused in the issue of quality assurance of finishing of the building of 3. and 4. block of the Nuclear Power Plant Mochovce

  4. Annual Report 2007 VUJE

    International Nuclear Information System (INIS)

    Anon

    2008-01-01

    VUJE foundation is closely connected with the history of Bohunice nuclear power plant. The team of research and development employees in Bohunice nuclear power plant formed the basis for foundation of the Vyskumny ustav jadrovych elektrarni (Nuclear Power Plant Research Institute - hereinafter referred to as VUJE or Company). Institute started its operations on January 1, 1977 as a concern company of Slovenske energeticke podniky (Slovak Power Enterprises). One year later VUJE became an independent organization controlled directly by the Federal Ministry of Fuels and Power. Excellent results were the impulse for the federal government to accredit VUJE in 1983 to lead the scientific commissioning of all nuclear power plants in Czechoslovakia. In 1983 started VUJE the branch education and training centre, which was in the next year equipped with a full-range simulator of WWER 440/213 reaktor unit. This centre gradually achieved international recognition. The international Atomic Energy Agency in Vienna also carried out training courses here. VUJE moved its headquarters to Trnava in 1985, however multiple experimental facilities, development workshops and some laboratories stayed in the area of nuclear power plants in Jaslovske Bohunice. At the end of the eighties VUJE counted 759 employees and gained an important position not only in Czechoslovakia, but also within international nuclear power industry. Important changes in the whole society in 1989 also influenced the future in the institute. Management developed a new organizational model of VUJE and step-by- step also the institute's strategy and line of business. Company retained its focus and was transformed in to a state company. In the following privatisation the joint-stock company established by the institute's employees bought the state research institute. The institute was transformed into a private joint-stock company Vyskumny ustav jadrovych elektrarni Trnava, a.s as of November f 1, 1994. A The

  5. Annual report 2006 VUJE

    International Nuclear Information System (INIS)

    Anon

    2006-01-01

    VUJE foundation is closely connected with the history of Bohunice nuclear power plant. The team of research and development employees in Bohunice nuclear power plant formed the basis for foundation of the Vyskumny ustav jadrovych elektrarni (Nuclear Power Plant Research Institute - hereinafter referred to as VUJE or Company). Institute started its operations on January 1, 1977 as a concern company of Slovenske energeticke podniky (Slovak Power Enterprises). One year later VUJE became an independent organization controlled directly by the Federal Ministry of Fuels and Power. Excellent results were the impulse for the federal government to accredit VUJE in 1983 to lead the scientific commissioning of all nuclear power plants in Czechoslovakia. In 1983 started VUJE the branch education and training centre, which was in the next year equipped with a full-range simulator of WWER 440/213 reaktor unit. This centre gradually achieved international recognition. The international Atomic Energy Agency in Vienna also carried out training courses here. VUJE moved its headquarters to Trnava in 1985, however multiple experimental facilities, development workshops and some laboratories stayed in the area of nuclear power plants in Jaslovske Bohunice. At the end of the eighties VUJE counted 759 employees and gained an important position not only in Czechoslovakia, but also within international nuclear power industry. Important changes in the whole society in 1989 also influenced the future in the institute. Management developed a new organizational model of VUJE and step-by- step also the institute's strategy and line of business. Company retained its focus and was transformed in to a state company. In the following privatisation the joint-stock company established by the institute's employees bought the state research institute. The institute was transformed into a private joint-stock company Vyskumny ustav jadrovych elektrarni Trnava, a.s as of November f 1, 1994. A The

  6. Lighting up Prague

    Energy Technology Data Exchange (ETDEWEB)

    Moss, M.

    1998-12-31

    After almost half a century under the shadow of communism, the Czech Republic is set firm on a path of radical economic reform aimed at restoring its ranking among the most developed states in the world. Through a 145 million pound investment in the independent Czech heat and power producer: Elektrarny Opatovice (EOP), National Power is applying lessons learned during the privatisation of the UK electricity industry to capitalise on the new spirit of liberalisation sweeping through the nation which stands at the very centre of Europe. The National Power Office in Prague is staffed by three men who, together with other specialists from National Power, are in daily contract with their EOP counterparts to share knowledge and best practice in areas ranging from operational maintenance to find management strategies. In a two-way process, EOP is providing National Power with first-hand knowledge of large district heating schemes with efficiencies of up to 90%. EOP operates the coal-fired Opatovice power station supplying 360 MW of electricity and 750 MW of heat. 6 photos.

  7. 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)

  8. Final treatment of liquid radioactive wastes

    International Nuclear Information System (INIS)

    Svolik, S.

    2004-01-01

    Final treatment of liquid radioactive wastes which are produced by 1 st and 2 nd bloc of the Mochovce NPP, prepares the NPP in its natural range. The purpose of the equipment is liquidation of wastes, which are formed at production. Wastes are warehoused in the building of active auxiliary plants in the present time, where are reservoirs in which they are deposited. Because they are already feeling and in 2006 year they should be filled definitely, it is necessary to treat them in that manner, so as they may be liquidated. Therefore the Board of directors of the Slovenske elektrarne has disposed about construction of final treatment of liquid radioactive wastes in the Mochovce NPP. Because of transport the wastes have to be treated in the locality of power plant. Technically, the final treatment of the wastes will be interconnected with building of active operation by bridges. These bridges will transport the wastes for treatment into processing centre

  9. Protection of WWER type primary loops against extreme effects

    International Nuclear Information System (INIS)

    Podrouzek, J.; Rejent, B.

    1985-01-01

    Dynamic analyses of the WWER-440 primary loops for the Mochovce nuclear power plant showed that the unprotected primary loop is very soft with a first eigenfrequency of 0.38 Hz. Protection with amortisseurs and viscous shock absorbers was compared and the viscous shock absorber in all cases proved to be more suitable. GERB viscous absorbers will be installed at the Mochovce nuclear power plant. First calculations of the dynamic resistance of the WWER-1000 primary loops for the Temelin nuclear power plant to extreme events were also made. It was shown that the unprotected primary loop is rather soft with a first eigenfrequency of 0.9 Hz, or 0.6 Hz at the pressurizer branch. It will therefore be necessary to protect the primary loops with viscous shock absorbers. (Z.M.)

  10. 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)

  11. Backfitting of Nuclear Power Plant Bohunice V1 in Slovakia

    International Nuclear Information System (INIS)

    Ferenc, M.

    1999-01-01

    Nuclear power plants in the Slovak Republic generate almost 55 % of electricity. The operating organization and the Nuclear Regulatory Authority of the Slovak Republic pay a great attention to safe and reliable operation of four units with VVER 440 reactors at Bohunices site and one in Mochovce side. Engineering and design organizations in cooperation with well known international companies prepare evaluation of safety conditions, safety analyses and projects for the implementation of modifications to upgrade the nuclear safety of the units in operation. A gradual safety upgrading (reconstruction) of the V-1 Bohunice plant has been in progress, a modernization of the V-2 Bohunice plant is being prepared. Simultaneously the commissioning of Unit 2 at the Mochovce plant is being implemented.(author)

  12. Monitoring of covering model of the National radioactive waste repository

    International Nuclear Information System (INIS)

    Jezikova, M.

    2009-01-01

    The subject of this rigorous report is justification of cover model building at radioactive waste repository in Mochovce as a very important engineering barrier preventing significant release of radioactive substances into the environment and providing protection against ionizing radiation. This rigorous report includes a theoretical part, which describes radioactive waste characterization, radioactive waste management and summary of the preliminary activities prior to the building cover model, particularly involving the selection of appropriate variables and parameters and creation of monitoring plan during the long term monitoring for evaluation of this barrier in order to ensure minimization of any leak of radioactive substances from RAW. The next part includes evaluation of the values of parameters and variables to build cover model of RAW in Mochovce during 2006-2008 (author)

  13. Present state of the design and realization of regional radioactive waste depositories and waste acceptance criteria for disposal. Soucasny stav reseni a realizace regionalnich ulozist RA odpadu a kriteria prijatelnosti techto odpadu k ukladani

    Energy Technology Data Exchange (ETDEWEB)

    Kortus, J [Chemoprojekt, Prague (Czechoslovakia)

    1988-06-01

    Surface type regional depositories for radioactive wastes from nuclear power plants are described in detail. The depository of the Mochovce nuclear power plant is located near the plant, that of the Dukovany nuclear power plant is directly on the premises of the plant. Particular attention is paid to the design of the monolithic reinforced concrete pits, draining of rainwater from their surface, draining of seeping rainwater from the pit environment by means of a double drainage system, and insulation of the pits against water. The construction of the Mochovce depository started in 1987; some experience gained from this activity is presented. The radioactive waste acceptance criteria for depositories of this kind, based on safety analysis, are given. (author). 2 figs.

  14. Present state of the design and realization of regional radioactive waste depositories and waste acceptance criteria for disposal

    International Nuclear Information System (INIS)

    Kortus, J.

    1988-01-01

    Surface type regional depositories for radioactive wastes from nuclear power plants are described in detail. The depository of the Mochovce nuclear power plant is located near the plant, that of the Dukovany nuclear power plant is directly on the premises of the plant. Particular attention is paid to the design of the monolithic reinforced concrete pits, draining of rainwater from their surface, draining of seeping rainwater from the pit environment by means of a double drainage system, and insulation of the pits against water. The construction of the Mochovce depository started in 1987; some experience gained from this activity is presented. The radioactive waste acceptance criteria for depositories of this kind, based on safety analysis, are given. (author). 2 figs

  15. Case law

    International Nuclear Information System (INIS)

    2014-01-01

    This section of the Bulletin brings together the texts of the following case laws: Canada: - Judgment of the Federal Court of Canada sending back to a joint review panel for reconsideration the environmental assessment of a proposed new nuclear power plant in Ontario. France : - Conseil d'etat, 24 March 2014 (Request No. 358882); - Conseil d'etat, 24 March 2014 (Request No. 362001). Slovak Republic: - Further developments in cases related to the challenge by Greenpeace Slovakia to the Mochovce nuclear power plant; - Developments in relation to the disclosure of information concerning the Mochovce nuclear power plant. United States: - Initial Decision of the Atomic Safety and Licensing Board Ruling in Favour of Nuclear Innovation North America, LLC (NINA) Regarding Foreign Ownership, Control or Domination

  16. Transport of radioactive wastes

    International Nuclear Information System (INIS)

    Stuller, C.

    2003-01-01

    In this article author describes the system of transport and processing of radioactive wastes from nuclear power of Slovenske elektrarne, plc. It is realized the assurance of transport of liquid and solid radioactive wastes to processing links from places of their formation, or of preliminary storage and consistent transports of treated radioactive wastes fixed in cement matrix of fibre-concrete container into Rebublic storage of radioactive wastes in Mochovce

  17. Nuclear installations in Slovakia accords to the convention definition

    International Nuclear Information System (INIS)

    1998-01-01

    In this part the nuclear power plants Bohunice - Units V-1 and V-2 and NPP Mochovce (description of units, safety reports and safety improvement programs) are described. Description of Bohunice A-1, history and current status of the NPP A-1 and NPP decommissioning program are included. In next parts interim spent fuel storage, technologies of Raw processing and treatment, and treated and solid Raw storage sites are described

  18. Radwaste Treatment Centre Jaslovske Bohunice

    International Nuclear Information System (INIS)

    2000-01-01

    In this leaflet the Bohunice Radwaste Treatment Centre (BSC RAO) is presented. BSC RAO is designed to process and treat liquid and solid radwaste, arising from the NPP A-1 decommissioning, from NPPs V-1, V-2, and Mochovce operations, as well as institutional radwaste of diverse institutional (hospitals, research institutes) in the Slovak Republic. Transport, sorting, incineration, compacting, concentration and cementation of radwaste as well as monitoring of emission are described

  19. Personnel Training

    International Nuclear Information System (INIS)

    Tokar, M.

    2012-01-01

    The professional training of employees for Units 3 and 4 of the Mochovce Power Plant is approaching finals. At the beginning, in particular the main control room operators were trained, later all the other employees needed for power plant commissioning and operation. In June, the second phase of the project will start; it will be focused on the new equipment of the Units under commissioning. (author)

  20. International Youth Nuclear Congress 2000. Film

    International Nuclear Information System (INIS)

    OST Film Production Studio; YDRNS Information Technology Services, Ltd.

    2001-01-01

    This CD-ROM contains 28 minutes 30 seconds of video-film about programme of International Youth Nuclear Congress 2000 (IYNC 2000). There is documentary video-film about IYNC 2000, also presented are: the Opening panel of the IYNC 2000, every day work of IYNC 2000, Congress people; the fun run; Entertainment excursion in Bratislava, about excursion in Mochovce NPP as well as in IAEA

  1. Advantages of viscodampers for NPPs upgrading

    International Nuclear Information System (INIS)

    Reinsch, K.H.; Schwahn, K.J.; Podrouzek, J.

    1993-01-01

    Viscodampers GERB are the ideal components for seismic upgrading of flexible pipework systems of the existing operating NPPs, of WWER-440 type, namely in primary reactor part. There are cheap, maintenance-free, simple and their installation minimizes the support forces to the structures. The quoted attests are enclosed in this paper. The references for application on Bohunice NPP upgrading are positive, and they are used in Mochovce and Temelin NPP as well

  2. PRIMAVERA - the experience of the utilization at the completion MO34

    International Nuclear Information System (INIS)

    Porubsky, S.

    2009-01-01

    Today, it is not possible to provide the required quality of neither the process nor the project's outputs without suitable software management support. It is necessary to remember, that the software management support of the big projects is necessary, not just sufficient condition for successful implementation of the project. The following contribution describes the experience with the software support setting for completion project of units 3. and 4. of NPP Mochovce

  3. Enel Graduates in Slovakia

    International Nuclear Information System (INIS)

    Galvani, L

    2009-01-01

    Enel constructs two reactors of second generation in Mochovce. Commissioning is expected at the end of 2013, a few months after Italy returns to nuclear. The power plant relies on the support of the public in the country, free way to adopted safety requirements from Brussels. So did inform assigned redactor Laura Galvagni in the edition of the most read Italian economic daily Il Sole 24 Ore on 24 November 2009. (author)

  4. Surveillance of WWER-440 fuel performance

    International Nuclear Information System (INIS)

    Simko, J.; Urban, P.

    1999-01-01

    In this lecture next problems of surveillance of WWER-440 fuel performance are presented: surveillance of WWER-440 fuel performance at Mochovce NPP; basic data of WWER-440 reactor; in-core reactor measuring system 'SVRK'; basic level of SVRK; information output of basic level of SVRK; surveillance of fuel performance; table of permissible operation conditions of the reactor; limitation of the unit 1 power at the beginning of the operation; cyclic changes of power; future perspectives

  5. Investigation and analysis of SSI effects in seismic response of NPPs EMO and EBO

    International Nuclear Information System (INIS)

    Juhasova, E.

    1996-01-01

    This progress report outlines and describes the analysis and investigations of soil-structure interaction effects in seismic response of Bohunice and Mochovce nuclear power plants. The work carries out consists of theoretical-numerical analysis of soil-structure interaction and the description of the experimental results obtained so far. Investigations were performed for different soil conditions and recommendations were elaborated as to prepare and use long-term monitoring of vibration activity at the Bohunice NPP site

  6. Part I. Remembering No. 2 (Ladislav Loerinc). EMO joint venture, joint-stock company - really completely useless organ?

    International Nuclear Information System (INIS)

    Blaha, M.

    2008-01-01

    In this chapter author reviewed the story of the EMO joint venture, joint-stock company, between Slovenske elektrarne, a. s. and EdF. EMO joint venture, joint-stock company, was established to complete the Mochovce nuclear power plant. EMO joint venture, joint-stock company was closed after one year of work. History of EMO joint venture, joint-stock company, was described by its former general manager Mr. Ladislav Loerinc.

  7. SE-VYZ

    International Nuclear Information System (INIS)

    Anon

    2004-01-01

    On this CD compact disc 6 video-films (A-1 NPP; Bituminization; Cementation; Pressing; The Interim spent fuel storage facility; Transport into the National radioactive waste repository Mochovce; Ignition; and Vitrification). In these films process of radioactive waste treatment in the Bohunice Radioactive Waste Processing Center (SE-VYZ) is presented. 2 presentations about radioactive wastes treatment in the SE-VYZ are included

  8. Living near a nuclear power station

    International Nuclear Information System (INIS)

    Marcan, P.; Slovak, K.

    2007-01-01

    The need to expand nuclear power and its advantages are discussed publicly nearly each week. According to politicians and the nuclear lobby investing tens of billions Sk at Mochovce will bring Slovakia the often cited 'independence and energy self-sufficiency'. It will also mean profit for Slovenske elektrarne and the company's shareholders - the state and Italian company, Enel. In addition to the lively discussion on the pros and cons of nuclear energy, TREND was also interested in the living conditions around the concrete and strictly guarded, potentially dangerous plants and in the opinion of the people most affected by Mochovce and Jaslovske Bohunice on expansion of the existing and the building of new nuclear power plants. The construction of nuclear powers stations in these regions was not only about new jobs. The state 'prescribed' iodine pills and did not allow any construction in the region and, in the case of Mochovce, ordered the complete demolition of a village. The only thing that remained from Mochovce village was the church. 'And when it was found that the power plant would not reach it, it was even given a new roof. Former inhabitants, especially the older ones that had problems accepting the evacuation, used to visit it often,' explained Jan Foldy, the head of the local municipality in Kalna nad Hronom. After many years, life in the neighbouring villages is not bad. Their budgets are overflowing and so they can afford to spoil their inhabitants with free cable TV and high standard sport facilities, which should partly compensate for the fact that the people are living so close to a nuclear facility. (authors)

  9. Radiochemical speciation of strontium and cesium in soils and influence of the zeolite on its migration

    International Nuclear Information System (INIS)

    Cipakova, A.

    1998-01-01

    The dissertation deals with sorption and desorption characteristics of two significant radionuclides Sr-85 and Cs-137 in selected soil samples as well as from around of NPP Bohunice and NPP Mochovce which were examined. The dissertation consists from next chapters: (1) Introduction; (2) Present state of knowledge; (3) Materials and methods; (4) Results and discussion; (5) Conclusions; (6) Particular conclusions for the realisation in practice and for next development of the science

  10. Determination of thermal reactivity coefficients for the first fuel loading of MO34

    International Nuclear Information System (INIS)

    Lueley, J.; Vrban, B.; Farkas, G.; Hascik, J.; Hinca, R.; Petriska, M.; Slugen, V.

    2012-01-01

    The article introduces determination of thermal reactivity coefficients, especially summarized (isothermal) and moderator (density) reactivity coefficients between 200 grad C and 260 grad C with 2 grad C step, - in compliance with the assignment - for the first fuel loading into the RC of NP Mochovce units using 2 nd generation fuel during the start-up using calculation code MCNP5 1.60. (authors)

  11. 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

  12. Safety of nuclear power plants in Slovak Republic in the context of integration into the European Union

    International Nuclear Information System (INIS)

    Pillar, V.

    2001-01-01

    A review of the construction and operation of nuclear power plants in Slovak Republic which belong within Slovenske Elektrarne is made. Since 1993 with the applying of the Least Cost Planning Methods and Financial Feasibility Analysis the optimal variant, considering construction completion of the two units at Mochovce NPP, has been adopted and a project for safety enhancement has been implemented. Some changes have been made in siting project in order to meet the seismic requirements, following by change of the control system design and supplier. The most important result of the safety enhancement program, important not only for NPP Mochovce, but also for all NPPs of WWER 440/213 type, is the fact, that operability of containment with passive bubbler-condenser system for pressure suppression and its acceptability from safety point of view, has been fully confirmed. Results of safety enhancement program have been re-evaluated not only by International Atomic Energy Agency, but also by other international authorities and professional organisations with positive result. Especially significant is the conclusion of RISKAUDIT, which has carried out repeated evaluation of safety level of NPP Mochovce based on PHARE project and which is accepted by European Commission. A similar approach for enhancing the safety has been applied for the NPP V-1 units at Jaslovske Bohunice

  13. Enel waiting for the state to act first

    International Nuclear Information System (INIS)

    Anon

    2005-01-01

    Enel will only answer the basic question whether Slovenske elektrarne will complete the reactors 3 and 4 in nuclear power plant in Mochovce next year. Initial analyses made by Enel indicate that the completion of Mochovce would cost over 60 billions Sk (1,54 billions EUR). Since National Property Fund has approved the strategic investment plan two more conditions have to be met before Enel can acquire Slovenske elektrarne. The first condition is that a part of the company assets has to taken over by state owned joint stock company GovCo. This regards reactor V-1 in nuclear power plant Jaslovske Bohunice that should be made ready for closure by end of 2008, damaged reactor A-1, nuclear equipment decommissioning and disposal unit VYZ and hydroelectric power plant in Gabcikovo. The other condition that still has to be fulfilled is passing of a new act on disposal of nuclear power generating equipment. The new act should distribute the fund's resources amongst the individual nuclear energy sources. M. Arcelli (regional manager of Enel for Slovakia) stresses that the money nuclear power station in Mochovce and V-2 earned and will earn during their time in operation will have to remain in the fund to cover their later liquidation i.e. should not be used on liquidation of reactors V-1 or A-1. (authors)

  14. Assessment of spent WWER-440 fuel performance under long-term storage conditions

    Energy Technology Data Exchange (ETDEWEB)

    Kupca, L [VUJE Inc. (Slovakia)

    2012-07-01

    In the Slovak Republic are under operation 6 units (4 in the Jaslovske Bohunice site, and 2 in the Mochovce), 2 units are under construction in Mochovce site. All units are WWER-440 type. The fresh fuel is imported from the Russian Federation. The spent fuel assemblies are stored in wet conditions in Bohunice Interim Storage Spent Fuel Facility (SFIS). By 15 July 2008, there were 8413 assemblies in SFIS. The objectives are: 1) Wet AR storage of spent fuel from the NPP Bohunice and Mochovce: Surveillance of conditions for spent fuel storage in the at-reactor (AR) storage pools of both NPP's (characteristics of pool water, corrosion product data); Visual control of storage pool components; Evaluation of storage conditions with respect to long-term stability (corrosion of fuel cladding, structural materials); 2) Wet SFIS storage at Bohunice: Measurement of spent fuel conditions during the long-term wet storage, activity data in the storage casks and amount of crud; Surveillance program for SFIS structural materials.

  15. Quality assurance

    International Nuclear Information System (INIS)

    1996-01-01

    The main efforts of Nuclear Regulatory Authority of the Slovak Republic (NRA SR) was focused on support of quality assurance programmes development at responsible organizations Bohunice V-1 and V-v and Mochovce NPPs and their inspection. Development of the level two documentation of a partial quality assurance programme for NPP operation continued at Mochovce NPP. Most of documentation has been submitted to NRA SR for comments and approval. NRA SR invited a mission of French experts to Mochovce NPP to review preparation and performance of internal audits that would be beneficial for improvement in this kind activities at the NPP. Bohunice NPP continued in development of a partial quality assurance programme for operation. The Quality Assurance Programme submitted to NRA SR for approval. Based on a request of Bohunice NPPs, NRA SR consulted the draft quality assurance programme developed by Siemens for stage of the 'Basic Design' of V-1 NPP upgrading. The programme had not been submitted for approval to NRA SR prior to completion of works by Siemens. Based on an internal audit that had been performed, corrective measures were proposed to meet requirements on review and approval of suppliers quality assurance programmes. Requirements related to the quality assurance at nuclear installations were prepared to be incorporated into principles of a act on peaceful use of nuclear power in Slovak Republic

  16. The conference hybrid control room

    International Nuclear Information System (INIS)

    Gieci, A.; Caucik, J.; Macko, J.

    2008-01-01

    An original concept of a hybrid control room was developed for the Mochovce-3 and Mochovce-4 reactor units which are under construction. The basic idea underlying the concept is that the control room should be a main working place for the operators (reactor operator and turbine operator) and for the shift supervisor, designed as a comprehensive unit desk shaped so that all members of the control room crew are in a face-to-face contact constantly. The main desk consists of three clearly identified areas serving the operators and the unit supervisor as their main working places. A soft control system is installed at the main working places. A separate safety-related working place, designed as a panel with classical instrumentations at the conference hybrid control room, is provided in case of abnormal conditions or emergency situation. Principles of ergonomics and cognitive engineering were taken into account when designing the new conference hybrid control room for the Mochovce-3 and -4 reactor units. The sizes, propositions, shapes and disposition of the equipment at the control room have been created and verified by using virtual reality tools. (orig.)

  17. 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

  18. 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

  19. Rad-waste treatment

    International Nuclear Information System (INIS)

    1996-01-01

    The spent fuel coming from Slovak NPPs have partially been transported to the former Soviet Union, and a part of it is stored in an interim spent fuel wet storage. In compliance with the worldwide practices, further medium-term possibilities of storing in dry storages are under preparation. Disposal of a spent fuel and other high-level active wastes in a deep geological formation repository is the final solution. At present, there are geological investigations of possible sites in progress in Slovakia. Mochovce repository is a factory for a final disposal of compacted low and intermediate level radioactive wastes coming from the Slovak NPPs. This is a near-surface facility of a construction similar to the one used for disposal of radioactive wastes in France, Spain, Japan, Czech Republic, U.S.A, etc. Quality of the design, construction and functioning of the Mochovce's repository was assessed by an international team of experts within a special IAEA programme (WATRP). Having familiarized with the final report of the IAEA mission, Nuclear Regulatory Authority of the Slovak Republic (NRA SR) issued its position early in 1995, in which NRA SR required additional adjustment of the repository itself. Based on the NRA SR's position, Mochovce NPP invited experts from a number of institutions in September 1995 to discuss the NRA SR's requirements. Following was recommended by the experts: (1) to perform a complementary engineering-geological investigation on the site, (2) to use geophysical methods to verify existence of geological faults. In the next part a radioactive wastes that were treated at radioactive waste treatment lines in 1995 are listed. In 1995, the Chief Inspector of NRA SR issued an instruction that radioactive waste department should start inspections of radioactive waste treatment right in hospitals, research institutes and industries. Therefore, a total of 14 such workplaces were incorporated into a plan of inspections in 1995

  20. Evaluation of doses during the handling and transport of radioactive wastes containers

    International Nuclear Information System (INIS)

    Kubik, I.; Kusovska, Z.; Hanusik, V.; Mrskova, A.; Kapisovsky, V.

    2000-01-01

    Radioactive waste products from the nuclear power plants (NPPs) must be isolated from contact with people for very long period of time. Low and intermediate-level waste will be disposed of in Slovakia in specially licensed Regional disposal facility which is located near the NPP Mochovce site. Radioactive waste accumulated in the Jaslovsk. Bohunice site, during the decommissioning process of the NPP A-1 and arising from the NPP V-1 and NPP V-2 operation, will be processed and shipped in standard concrete containers to the Mochovce Regional disposal facility. The treatment centre was build at the NPP Jaslovsk? Bohunice site which is in the trial operation now. It is supposed that radioactive waste containers will be transported by train from the treatment centre Jaslovsk? Bohunice to the site of Radioactive Waste Repository at Mochovce and by truck in the area of repository. To estimate the occupational radiation exposure during the transport the calculations of dose rates from the containers are necessary. The national regulations allow low level of radiation to emanate from the casks and containers. The maximum permissible volume radioactivity of wastes inside the container is limited in such a way that irradiation level should not exceed 2 mGy/h for the contact irradiation level and 0,1 mGy/h at 2-meter distance. MicroShield code was used to analyse shielding and assessing exposure from gamma radiation of containers to people. A radioactive source was conservatively modelled by homogenous mixture of radionuclides with concrete. Standard rectangular volume source and shield geometry is used in model calculations. The activities of the personnel during the transport and storage of containers are analysed and results of the evaluation of external dose rates and effective doses are described. (author)

  1. Slovenske elektrarne has fulfilled the plan of electric power production at 101 %

    International Nuclear Information System (INIS)

    Anon

    2004-01-01

    Slovenske elektrarne, a. s., produced in 2003 year the electric power in capacity 26,047.6 GWh, whereby they fulfilled business plan at 101 %. In compare with the last year it is a reduction in production by 1,397.3 GWh. The biggest share of production - till 68.6 % of overall production of the Slovenske elektrarne, was provided by nuclear sources. Nuclear power plants fulfilled business plan at 104 %, when Jaslovske Bohunice NPP has produced 11,625 GWh and Mochovce NPP 6,238 GWh. The share of other power plants on the electricity production is presented

  2. Design works organization during the IandC system upgrading on an operating VVER power plant from the general designer's standpoint

    International Nuclear Information System (INIS)

    Krepel, V.

    1997-01-01

    Two replacements of nuclear power plant instrumentation and control systems have already been implemented according to the project design of Energoprojekt: at the Mochovce WWER-440 and the Temelin WWER-1000 plants. In the present contribution the design problems encountered during the replacement are described, the causes of the problems are discussed, and a policy of organizing project design work for an instrumentation and control system replacement at an operating WWER power plant is established such as would avoid these problems. (A.K.)

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

    International Nuclear Information System (INIS)

    Kupca, Ludovik

    2006-01-01

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

  4. Excerpts from the introductory statement by IAEA Director General. IAEA Board of Governors, Vienna, 25 November 1998

    International Nuclear Information System (INIS)

    ElBaradei, M.

    1998-01-01

    The document contains excerpts from the Introductory Statement made by the Director General of the IAEA at the IAEA Board of Governors on 25 November 1998. The following aspects from the Agency's activity are presented: inspections in Iraq in relation to its clandestine nuclear programme, conclusion of Additional Protocols to safeguards agreements, the strengthened safeguards system, Agency's involvement in safeguards verification in the Democratic People's Republic of Korea (DPRK), safety review at the Mochovce nuclear power plant in Slovakia, and the year 2000 (Y2K) computer system problems in the Agency's Member States

  5. Education and training of experts for the nuclear power sector at the Faculty of Electrical Engineering and Information Technologies, Slovak University of Technology in Bratislava

    International Nuclear Information System (INIS)

    Lipka, J.; Slugen, V.; Miglierini, M.; Necas, V.; Hascik, J.; Pavlovic, M.

    2003-01-01

    The Faculty of Electrical Engineering and Information Technologies, Slovak University of Technology in Bratislava has been training experts for the nuclear sector for over 40 years now. Current status and trends in nuclear education within the faculty's educational system, encompassing BSc, MSc and PhD studies, are highlighted. Dedicated training courses in the safety aspects of operation of the nuclear power installations are also organized for NPP staff. Periodical training is also provided to supervising physicists at the Jaslovske Bohunice and Mochovce nuclear power plants. Major international projects aimed at nuclear knowledge management and preservation are highlighted and the ENEN - European Nuclear Education Network project is described. (P.A.)

  6. 3. General principles of assessing seismic resistance of technological equipment of nuclear power plants

    International Nuclear Information System (INIS)

    1983-01-01

    The evaluation of the seismic resistance of technological equipment is performed by computation, experimental trial, possibly by combining both methods. Existing and prepared standards in the field of seismic resistance of nuclear power plants are mentioned. Accelerograms and response spectra of design-basis earhtquake and maximum credible earthquake serve as the basic data for evaluating seismic resistance. The nuclear power plant in Mochovce will be the first Czechoslovak nuclear power plant with so-called partially seismic design. The problem of dynamic interaction of technological equipment and nuclear power plant systems with a bearing structure is discussed. (E.F.)

  7. 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

  8. The Slovaks support completion of MO34

    International Nuclear Information System (INIS)

    Holy, R.

    2007-01-01

    This year (2007) in March a reputable international agency GfK conducted a poll, which was focused primarily on the questions relating to the presence and future of nuclear energy sector in Slovakia as well as brand awareness of Slovenske elektrarne. It results from the poll that 2/3 of Slovak population is not against the completion of Units 3 and 4 of Mochovce NPP (EMO34), and this relates to as much as 87 % of the asked in the region within a 10 km distance from EMO! (author)

  9. Construction history and construction management

    International Nuclear Information System (INIS)

    Agh, S.

    1999-01-01

    The process of pre-design and design preparation of the Mochovce NPP as well as the construction history of the plant is highlighted, including the financing aspect and problems arising from changes in the technological and other conditions of start-up of the reactor units. The results of international audits performed to improve the level of nuclear safety and implementation of the measures suggested are also described. The milestones of the whole construction process and start-up process, the control and quality system, and the methods of control and management of the complex construction project are outlined. (author)

  10. Nuclear Research Institute Rez view

    International Nuclear Information System (INIS)

    Biza, K.; Pazdera, F.; Vasa, I.; Zdarek, J.

    2004-01-01

    In this presentation author deals with the present state and perspectives of nuclear energy in the Czech Republic and in the Slovak Republic. It is concluded that lifetime extension and finalization of Mochovce NPP Units 3 and 4 is the cheapest solution for base load production of electricity and is in line with the European union energy challenges: - decrease of carbon dioxide emissions; dependence on energy sources from politically unstable regions; decrease import dependence on energy sources. Nuclear energy is one of important sources for long term sustainability in energy. GEN IV is successful with meet the new requirements after 2025. We should participate on this long term development effort

  11. Nuclear safety in Slovak Republic. Safety analysis reports for WWER 440 reactors

    International Nuclear Information System (INIS)

    Rohar, S.

    1999-01-01

    Implementation of nuclear power program is connected to establishment of regulatory body for safe regulation of siting, construction, operation and decommissioning of nuclear installations. Licensing being one of the most important regulatory surveillance activity is based on independent regulatory review and assessment of information on nuclear safety for particular nuclear facility. Documents required to be submitted to the regulatory body by the licensee in Slovakia for the review and assessment usually named Safety Analysis Report (SAR) are presented in detail in this paper. Current status of Safety Analysis Reports for Bohunice V-1, Bohunice V-2 and Mochovce NPP is shown

  12. Hot functional test chemistry - long term experience

    International Nuclear Information System (INIS)

    Vonkova, K.; Kysela, J.; Marcinsky, M.; Martykan, M.

    2010-01-01

    Primary circuit materials undergo general corrosion in high temperature, deoxygenated, neutral or mildly alkaline solutions to form thin oxide films. These oxide layers (films) serve as protective film and mitigate the further corrosion of primary materials. Inner chromium-rich oxide layer has low cation diffusion coefficients and thus control iron and nickel transport from the metal surface to the outer layer and their dissolution into the coolant. Much less corrosion products are generated by the compact, integral and stable oxide (passivation) layer. For the latest Czech and Slovak stations commissioned (Temelin and Mochovce) a modified Hot Functional Test (HFT) chemistry was developed in the NRI Rez. Chromium rich surface layer formatted due to modified HTF chemistry ensures lower corrosion rates and radiation field formation and thus also mitigates crud formation during operation. This procedure was also designed to prepare the commissioned unit for the further proper water chemistry practise. Mochovce 1 (SK) was the first station commissioned using these recommendations in 1998. Mochovce 2 (1999) and Temelin 1 and 2 (CZ - 2000 and 2002) were subsequently commissioned using these guidelines too. The main principles of the controlled primary water chemistry applied during the hot functional tests are reviewed and importance of the water chemistry, technological and other relevant parameters is stressed regarding to the quality of the passive layer formed on the primary system surfaces. Samples from Mochovce indicated that duplex oxide layers up to 20 μm thick were produced, which were mainly magnetite substituted with nickel and chromium (e.g. 60-65% Fe, 18-28% Cr, 9-12% Ni, <1% Mn and 1-2% Si on a stainless steel primary circuit sample). Long term operation experience from both nuclear power plants are discussed in this paper. Radiation field, occupational radiation exposure and corrosion layers evolution during the first c. ten years of operation are

  13. Internal flooding analyses results of Slovak NPPs

    International Nuclear Information System (INIS)

    Sopira, Vladimir

    2000-01-01

    The assessment of the flood risk was the objective of the internal flooding analysis for NPPs Bohunice V1, V2 and Mochovce. All important flooding sources were identified. The rooms containing safety important components were analyzed from the point of view of: Integrity of flood boundaries; Capability for drainage; Flood signalisation; Flood localization and liquidation; Vulnerability of safety system component. The redundancies of safety systems are located mostly separately and no flood can endanger more than single train. It can be concluded that NPPs with WWER-440 are very safe against the flooding initiating event

  14. Excerpts from the introductory statement by IAEA Director General. IAEA Board of Governors, Vienna, 8 June 1998

    International Nuclear Information System (INIS)

    ElBaradei, M.

    1998-01-01

    The document contains excerpts from the Introductory Statement made by the Director General of the IAEA at the IAEA Board of Governors on 8 June 1998. The following aspects from the Agency's activity are presented: nuclear testing, technical co-operation, programme and budget, safeguards, safeguards implementation report, Agency's involvement in safeguards verification in the Democratic People's Republic of Korea (DPRK), Agency's inspections in Iraq in relation to its clandestine nuclear programme, security of material, measures to strengthen international co-operation in nuclear, radiation and waste safety, study of the radiological situation at the atolls of Mururoa and Fangataufa, and Agency's role in safety assessment of the Mochovce nuclear power plant

  15. Radioactive waste and the back part of fuel cycle of nuclear installations in Slovakia

    International Nuclear Information System (INIS)

    Koprda, V.

    2004-01-01

    This article is devoted to radioactive waste (RAW) management, an integrated system starting with collection and sorting of RAW through its storage, treatment, conditioning, handling and transport up to its disposal. Some notes will touch also the near surface depository of low level and intermediate level radioactive waste in Mochovce, and the long-term storage of waste improper for such type of disposal, and also some words will be addressed to the development and research of a deep geological depository for disposal spent fuel from nuclear power plant and long-lived radioactive waste. (author)

  16. Containment leak-tightness enhancement at VVER 440 NPPs

    International Nuclear Information System (INIS)

    Prandorfy, M.

    2001-01-01

    The hermetic compartments of VVER 440 NPPs fulfil the function of the containment used at NPPs all over the word. The purpose of the containment is to protect the NPP personal against radioactive impact as well as to prevent radioactive leakage to the environment during a lost of coolant accident. Leak-tightness enhancement in NPPs with VVER 440/213 and VVER 440/230 reactors is an important safety issue. New procedures, measures and methods were adopted at NPPs in Mochovce, J. Bohunice, Dukovany and Paks for leak identification and sealing works performed by VUEZ Levice. (authors)

  17. Analysis of radioactivity increase of rad waste filled in fibre-reinforced concrete container regarding external exposure of workers

    International Nuclear Information System (INIS)

    Baratova, D.; Hrncir, T.; Necas, V.

    2012-01-01

    The paper deals with the assessment of the external radiation exposure of workers performing the individual tasks associated with disposal of the fibre-reinforced concrete containers in the National Radioactive Waste Repository in Mochovce. Models for fibre-reinforced concrete containers with maximum activity allowable for transport and for fibre-reinforced concrete containers contained radionuclides at the common level of activity concentration were created in order to analyze the option of fibre-reinforced concrete containers radioactivity increase. Calculations of individual effective doses have been carried out for three workers who work in the control area of the waste disposal facility dosimetrist, assistant and crane worker. (Authors)

  18. Seismic effects on technological equipment and systems of nuclear power plants

    International Nuclear Information System (INIS)

    Masopust, R.; Pecinka, L.; Podrouzek, J.

    1983-01-01

    A survey is given of problems related to the construction of nuclear power plants with regard to seismic resistance. Sei--smic resistance of technological equipment is evaluated by experimental trials, calculation or the combination of both. Existing and future standards are given for the given field. The Czechoslovak situation is discussed as related to the construction of the Mochovce nuclear power plant. Procedures for testing seismic resistance, types of tests and methods of simulating seismic excitation are described. Antiseismic measures together with structural elements for limiting the seismic effects on technological equipment and nuclear power plant systems are summed up on the basis of foreign experience. (E.F.)

  19. Rapid separation and determination of 107Pd in radioactive waste produced during NPP A-1 decommissioning

    International Nuclear Information System (INIS)

    Boris Andris; Miroslav Prazsky; Ferdinand Sebesta

    2015-01-01

    Procedure for 107 Pd determination in radioactive wastes coming from decommissioning of NPP A-1 is proposed and verified. 107 Pd was separated and purified by Pd precipitation with dimethylglyoxime (DMG) and/or ferric hydroxide precipitation. 107 Pd yield was determined gravimetrically by weighing the Pd(DMG) 2 precipitate. 107 Pd counting was performed using liquid scintillation counter (LSC-TDCR) and scintillation cocktail Hionic Fluor. In all analyzed samples the determined activities of 107 Pd were lower than MDA. Nevertheless such analyses permit the decision concerning the storage of solidified wastes in the Mochovce regional repository. (author)

  20. Containment leak-tightness enhancement at VVER 440 NPPs

    International Nuclear Information System (INIS)

    Prandorfy, M.

    2000-01-01

    The hermetic compartments of WWER 440 NPPs fulfil the function of the containment used at NPPs all over the world. The purpose of the containment is to protect the NPP personnel against radioactive impact as well as to prevent radioactive leakage to the. environ ent during a lost of coolant accident. Leak-tightness enhancement in NPPs with WWER 440/213 and WWER 440/230 reactors is an important safety issue. New procedures, measures and methods were adopted at NPPs in Mochovce, Jaslovske Bohunice, Dukovany and PAKS for leak identification and sealing works performed by VUEZ Levice. (authors)

  1. The use of ion exchange chromatography methods for the determination of {sup 93}Zr in the samples of radioactive wastes; Vyuzitie metod ionovymennej chromatografie pre stanovenie {sup 93}Zr vo vzorkach radioaktivnych odpadov

    Energy Technology Data Exchange (ETDEWEB)

    Gardonova, V; Dulanska, S; Remenec, B; Matel, L [Univerzita Komenskeho v Bratislave, Prirodovedecka fakulta, Katedra jadrovej chemie, 84215 Bratislava (Slovakia)

    2012-04-25

    A simple and rapid method of preconcentration, separation and purification of {sup 93}Zr based on the methods of ion exchange chromatography with ion exchangers made by Eichrom Technologies, Inc. was developed. Multi-stage method of {sup 93}Zr separation proved to be suitable for the analysis of samples highly contaminated with radioactive waste in a relatively short time and with a high decontamination factor. The use and effectiveness of the method was successfully tested by analysis of heterogeneous waste from Mochovce nuclear power plant, which belongs to the most complex matrixes of radiochemical analysis. (authors)

  2. Eastern Europe

    International Nuclear Information System (INIS)

    Baret, J.P.; Corcuff, A.; Jousten, M.; Cherie, J.B.; Gorge, X.; Augustin, X.; Belime, F.

    1999-01-01

    By its economical and political impact, nuclear energy has an important contribution the countries of Eastern Europe that goes beyond simple energy source. The most important challenge is to gain a safety culture. Improvements have been noted but the reactors safety must stay a priority of the international cooperation in Eastern Europe. The plan for the completion and improvement of Mochovce nuclear plant is described, the situation of Chernobyl and how to make the sarcophagus in safe is discussed, the experience of a french P.M.E. ( small and medium size firm) called Corys Tess that has chosen to position itself on the Eastern Europe nuclear market is related. (N.C.)

  3. 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

  4. The Modernization Program and Power Up-rate at NPP V2 Jaslovske Bohunice, Slovak Republic

    International Nuclear Information System (INIS)

    Reznik, Vladivoj; Krajmer, Imrich

    2010-01-01

    Slovenske Elektrarne, a.s. is a second largest utility company in the Central and Eastern Europe that owns an optimal production portfolio comprised of nuclear, thermal and hydroelectric power plants. There are two nuclear power plants Bohunice and Mochovce both operate with two units and another two units Mochovce 3 and 4 are currently under construction. Electricity at Nuclear power plant Bohunice V2 is generated by two 440 MW units that had gradually been connected to the power network over the period between 1984 and 1985. In the construction of the nuclear power plant V2 the concept of pressurized water reactors was adopted and the Soviet-era design WWER 440 used. The upgrading of Nuclear Power Plant Bohunice V2 is based on three main points: Modernization, Power up-rate, and Ageing monitoring program. The main targets of the modernization project were: Increasing of the Nuclear Safety and of the Nuclear operational reliability, and Seismic improvement. This modernization program is in full compliance with IAEA requirements and with the decisions from the Nuclear Regulatory Agency of the Slovak Republic (UJD) and achievement of the probabilistic safety criteria in accordance with IAEA recommendations. Except that is ensured a safe, reliable, economical and effective electricity and heat generation. Achieved results are based for further prolongation of the operation life time up to 60 years. (authors)

  5. Case Law

    International Nuclear Information System (INIS)

    2014-01-01

    This section treats of the following case laws sorted by country: 1 - Germany: Federal Administrative Court confirms the judgments of the Higher Administrative Court of the Land Hesse: The shutdown of nuclear power plant Biblis blocks A and B based on a 'moratorium' imposed by the Government was unlawful; List of lawsuits in the nuclear field. 2 - Slovak Republic: Further developments in cases related to the challenge by Greenpeace Slovakia to the Mochovce nuclear power plant; Developments in relation to the disclosure of information concerning the Mochovce nuclear power plant. 3 - United States: Judgment of the Nuclear Regulatory Commission resuming the licensing process for the Department of Energy's construction authorisation application for the Yucca Mountain high-level radioactive waste repository; Judgment of the Licensing Board in favour of Shaw AREVA MOX Services regarding the material control and accounting system at the proposed MOX Facility; Dismissal by US District Court Judge of lawsuit brought by US military personnel against Tokyo Electric Power Company (TEPCO) in connection with the Fukushima Daiichi nuclear power plant accident

  6. There's no Nuclear Future without the Young

    International Nuclear Information System (INIS)

    Petrech, R.; Holy, R.

    2002-01-01

    Construction of Mochovce NPP started in 1981 - i.e. more than 20 years ago, however it was halted in early 90's after velvet Revolution in former Czechoslovakia. When the (I and C) system was decided in 1989 to be replaced with a state-of-the-art system of Siemens, and it was implemented in early 1990-1, the utility lacked money for further works and building works had to be halted. We were consequently thrown in difficult public and expert debates about the nuclear future: do we really need it? Nuclear is looking for new ways to persuade the public about the need to keep nuclear as a part of the world energy mix. For experts it is clear. It has already been indicated in the Green Book - a report about the future electricity demand coverage by diverse sources made out for the EC. The role of the young people is indispensable in this process. Information campaigns are focused mostly on youngsters from the very young age whose opinions are being formed. Only a long-lasting systematic work with the youth can bring better public opinion. About 95 % of Mochovce NPP visitors are students (mostly primary and secondary schools) - that is important.(author)

  7. Activities of the Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear facilities in the Slovak Republic in 1994

    International Nuclear Information System (INIS)

    1995-01-01

    The report summarizes activities of the Nuclear Regulatory Authority of the Slovak Republic (NRA SR) in 1994 and briefly presents results of the national expert supervision over nuclear safety facilities in the SR in 1994. In 1994, the NRA SR have performed a national supervision of following organizations: SE, a.s. - Jaslovske Bohunice Nuclear Power Plant (V-1 Nuclear Power Plant (V-1 NPP), V-2 Nuclear Power Plant (V-2 NPP), A-1 Nuclear Power Plant (A-1 NPP)); Mochovce Nuclear Power Plant; Radioactive waste repository, Mochovce); Organizations providing a specialized training of NPP personnel; Organizations providing specific deliveries and activities for the nuclear power industry; Organizations having an owner of nuclear materials; Organizations providing activities related to import of radioactive sources; Organizations using radioactive sources. Organization structure of the NRA SR is explained. In the presented Chapter 1 - Safety of nuclear power plants in the Slovak Republic - safety aspects of the Slovak NPPs are reported. The next activities are reported: nuclear materials and safeguards; radioactive waste; emergency planning and NRA SR's control and crisis centre; international activities to improve the national surveillance quality; other activities

  8. 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

  9. Chapter No.5. Nuclear materials and physical protection of nuclear installations

    International Nuclear Information System (INIS)

    2002-01-01

    The State System of Accounting for and Control of Nuclear Material (SSAC) is based on requirements resulting from the Safeguards Agreement between the Government of the Slovak Republic and the IAEA. UJD performs this activity according to the 'Atomic Act' and relevant decree. The purpose of the SSAC is also to prevent unauthorised use of nuclear materials, to detect loses of nuclear materials and provide information that could lead to the recovery of missing material. The main part of nuclear materials under jurisdiction of the Slovak Republic is located at NPP Jaslovske Bohunice, NPP Mochovce and at interim storage in Jaslovske Bohunice. Even though that there are located more then 99% of nuclear materials in these nuclear facilities, there are not any significant problems with their accountancy and control due to very simply identification of accountancy units - fuel assemblies, and due to stability of legal subjects responsible for operation and for keeping of information continuity, which is necessary for fulfilling requirements of the Agreement. The nuclear material located outside nuclear facilities is a special category. There are 81 such subjects of different types and orientations on the territory of the Slovak Republic. These subjects use mainly depleted uranium as a shielding and small quantity of natural uranium, low enrichment uranium and thorium for experimental purposes and education. Frequent changes of these subjects, their transformations into the other subjects, extinction and very high fluctuation of employees causes loss of information about nuclear materials and creates problems with fulfilling requirements resulting from the Agreement. In 2001, the UJD carried out 51 inspections of nuclear materials, of which 31 inspections were performed at nuclear installations in co-operation with the IAEA inspectors. No discrepancies concerning the management of nuclear materials were found out during inspections and safeguards goals in year 2001 were

  10. Blasting jobs on the building site of the Temelin nuclear power plant

    International Nuclear Information System (INIS)

    Voda, J.; Podel, R.

    1984-01-01

    The problems are discussed of the preparation and implementation on the Temelin nuclear power plant building site of blasting, the volume of drilling and the choice of the drill hammer - all based on experience gained during the construction of the Mochovce nuclear power plant. The amount of explosives used on the Temelin site will be 1400 t. The use of mechanical charging may shorten the preparation of the site by 20 to 30%. Explosive emulsion slurries are being developed from home raw materials whose application will reduce the volume of drilling by 15%. The method of controlled breaking secures adequate quality of peripheral walls and bottom chink but special explosives will have to be used. Seismic effects are discussed of blasting on dwellings, agricultural and industrial buildings in the vicinity of the site, on-site buildings, underground mains and special structures of the nuclear power plant. (E.S.)

  11. Nuclear materials

    International Nuclear Information System (INIS)

    1996-01-01

    In 1998, Nuclear Regulatory Authority of the Slovak Republic (NRA SR) performed 38 inspections, 25 of them were performed in co-operation with IAEA inspectors. There is no fresh nuclear fuel at Bohunice A-1 NPP at present. Fresh fuel of Bohunice V-1 and V-2 NPPs is inspected in the fresh fuel storage.There are 327 fresh fuel assemblies in Mochovce NPP fresh fuel storage. In addition to that, are also 71 small users of nuclear materials in Slovakia. In most cases they use: covers made of depleted uranium for non-destructive works, detection of level in production plants, covers for therapeutical sources at medical facilities. In. 1995, NRA SR issued 4 new licences for nuclear material withdrawal. In the next part manipulation with nuclear materials, spent fuel stores and illegal trafficking in nuclear materials are reported

  12. Calculation of external exposure during transport and disposal of radioactive waste arisen from dismantling of steam generator

    International Nuclear Information System (INIS)

    Hornacek, M.; Necas, V.

    2014-01-01

    The dismantling of large components (reactor pressure vessel, reactor internals, steam generator) represents complex of processes involving preparation, dismantling, waste treatment and conditioning, transport and final disposal. To optimise all of these activities in accordance with the ALARA principle the prediction of the exposure of workers is an essential prerequisite. The paper deals with the calculation of external exposure of workers during transport and final disposal of heat exchange tubes of steam generator used in Slovak nuclear power plant V1 in Jaslovske Bohunice. The type of waste packages, the calculation models of truck and National Radioactive Waste Repository in Mochovce are presented. The detailed methodology of radioactive waste disposal is showed and the degree of influence of time decay (0, 5 and 10 years) on the radiological conditions during transport and disposal is studied. All of the results do not exceed the limits given in Slovak and international regulatory documents. (authors)

  13. Proceedings of the 9th NUSIM 2000 Conference. Joint Slovak, Czech and German Seminar on Nuclear Power

    International Nuclear Information System (INIS)

    2000-01-01

    Scientific conference deals with problems of reactor safety upgrading, mainly of two blocks of the NPP V-1 Bohunice as well as decomissioning of the NPP A-1 Bohunice. Other problems of the nuclear engineering were discussed. Totally, 201 participants from the Slovak Republic, Czech Republic and Germany and from other countries took part in the conference. The Conference included the following sessions: (i): Survey on the situation of nuclear power in the partner countries; (ii) Mochovce design safety enhacement and operational experience; (iii) Bohunice V-1 safety upgrading and operational experience; (iv) Decomissioning, spent fuel and radwaste management; (v) Young Generation Presentation. Proceedings contains thirty one papers dealing with the scope of INIS

  14. 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

  15. Optimization of determination of 126Sn by ion exchange chromatography method (presentation)

    International Nuclear Information System (INIS)

    Pasteka, L.; Dulanska, S.

    2013-01-01

    The aim of the work is to optimize the uptake of tin on anion exchange resins and application of this knowledge for the analysis of samples of radioactive waste from the device of Jaslovske Bohunice and Mochovce in determining of 126 Sn. First to be optimized a method for the separation of tin on ion exchange sorbent Anion Exchange Resin (1-X8, Chloride Form) from Eichrom Technologies. Model sample was prepared in 7 mol dm -3 HCl, because in that environment a sorbent effectively captures the tin, which is bounded complexly with chloride anions as SnCl 6 2- . The radiochemical separation yield was monitored by gamma spectrometric measurements on high purity germanium detector HPGe (E = 391 keV) by adding isotope 113 Sn to each model solution. The method of tin separation was optimized on model samples.

  16. Support calculations for management of PRISE leakage accidents

    Energy Technology Data Exchange (ETDEWEB)

    Matejovic, P.; Vranka, L. [Nuclear Power Plants Research Inst. Vuje, Trnava (Slovakia)

    1997-12-31

    Accidents involving primary-to-secondary leakage (PRISE) caused by rupture of one or a few tubes are well known design basis events in both, western and VVER NPPs. Operating experience and in-service inspections of VVER-440 units have demonstrated also the potential for large PRISE leaks in the case of the steam generator (SG) primary collector cover lift-up (Rovno NPP). Without performing any countermeasure for limitation of SG collector cover lift-up, a full opening results in PRISE leak with an equivalent diameter 107 mm. Although this accident was not considered in the original design, this event is usually analysed as DBA too. Different means are available for detection and mitigation of PRISE leakage in NPPs currently in operation (J.Bohunice V-1 and V-2) or under construction (Mochovce) in Slovakia. 8 refs.

  17. Project investigation and analysis of soil-structure interaction effects in seismic response of NPPs EBO, EMO, Slovakia. Final report

    International Nuclear Information System (INIS)

    Juhasova, E.

    1999-01-01

    The work described in this report was devoted to investigation of expected seismic response of the structures of WWER-440/213 type NPPs, namely Mochovce and Bohunice. Special attention was devoted to the properties of subsoil materials and the transfer of seismic waves from the bedrock to the foundation structures. Theoretical background was elaborated and discussed for wave propagation of surface waves. Alternative procedure was derived for non-linear media accounting for complex modulus theory. Material characteristics of subsoils were investigated for both NPPs. The obtained results were used as a basis for forecasting and calculation of expected seismic response when the time history records from Paks explosion were used an input. It was pointed out that the used procedure, together with previous calculation of subsoil transfer characteristics completed well the comparison with experimental results

  18. Further development of the Dynamic Control Assemblies Worth Measurement Method for Advanced Reactivity Computers

    International Nuclear Information System (INIS)

    Petenyi, V.; Strmensky, C.; Jagrik, J.; Minarcin, M.; Sarvaic, I.

    2005-01-01

    The dynamic control assemblies worth measurement technique is a quick method for validation of predicted control assemblies worth. The dynamic control assemblies worth measurement utilize space-time corrections for the measured out of core ionization chamber readings calculated by DYN 3D computer code. The space-time correction arising from the prompt neutron density redistribution in the measured ionization chamber reading can be directly applied in the advanced reactivity computer. The second correction concerning the difference of spatial distribution of delayed neutrons can be calculated by simulation the measurement procedure by dynamic version of the DYN 3D code. In the paper some results of dynamic control assemblies worth measurement applied for NPP Mochovce are presented (Authors)

  19. Chemical mode control in nuclear power plant decommissioning during operation of technologies in individual radioactive waste processing plants

    International Nuclear Information System (INIS)

    Horvath, J.; Dugovic, L.

    1999-01-01

    Sewage treatment of nuclear power plant decommissioning is performed by system of sewage concentration in evaporator with formation of condensed rest, it means radioactive waste concentrate and breeding steam. During sewage treatment plant operation department of chemical mode performs chemical and radiochemical analysis of sewage set for treatment, chemical and radiochemical analysis of breeding steam condensate which is after final cleaning on ionization filter and fulfilling the limiting conditions released to environment; chemical and radiochemical analysis of heating steam condensate which is also after fulfilling the limiting conditions released to environment. Condensed radioactive concentrate is stored in stainless tanks and later converted into easy transportable and chemically stable matrix from the long term storage point of view in republic storage Mochovce. The article also refer to bituminous plant, vitrification plant, swimming pool decontamination plant of long term storage and operation of waste processing plant Bohunice

  20. VUJE Trnava, Inc. - Engineering, Design and Research Organisation

    International Nuclear Information System (INIS)

    2001-01-01

    This CD is multimedia presentation of programme safety upgrading of Bohunice V1 NPP. This chapter contains information about VUJE: It consists of next parts: (1) From VUJE history (1977-2001); (2) Human resources (Development of staff; Structure of employees 1999); (3) VUJE activities: (Diagnostics; Nuclear safety; Radiation safety; Commissioning and operation; Personnel training; Information technology; Electric grids; Conventional power); (4) Significant projects of VUJE are presented: Gradual reconstruction with safety upgrading of the V1 Bohunice nuclear power plant; Modernization of the V2 Bohunice NPP; Completion of the Republic Repository of Radioactive Wastes in Mochovce; Decommissioning of the A1 NPP Bohunice; Development of simulators; Physical and power commissioning of NPPs; Construction of high voltage line Varin - Sucany

  1. Automated systems for control of technological processes at nuclear power plants and their use in putting the plant into operation

    International Nuclear Information System (INIS)

    Majtan, L.

    1987-01-01

    The systems of testing and control of technological processes in WWER-440 units in nuclear power plants which have so far been constructed in Czechoslovakia have been based on the conceptual principles and hardware used in the USSR. For the Mochovce nuclear power plant an automated process control system is to be introduced which proceeds from experiences gained with new Czechoslovak conventional power plants with 200 MW units. The control system consists of two levels: unit control and the control of the whole power plant the unit control consists of the DERIS-900 decentralized control system and the SM 1804 microcomputer and SM 1420 minicomputer based information and control system. A data processing system based on the SM 52/11.M1 minicomputer system will be used for power plant start-up and commissioning. (Z.M.). 2 figs., 4 refs

  2. Slovak Electric, plc, Environment report 1998

    International Nuclear Information System (INIS)

    1999-01-01

    A brief account of activities in environment protection carried out by the Slovenske Elektrarne, a.s. in 1998 is presented. These activities are reported under the headings: (1) The address of general director; (2) Conception of environmental protection in joint stock company SE, a.s.; (3) Air protection; (4) Water management; (5) Waste management; (6) Environmental management system in joint stock company Slovenske Elektrarne, a.s.; (7) Finances spent to protection and setting of environment; (8) Vojany power plant(SE-EVO); (9) Novaky power plant (SE-ENO); (10) Kosice power plant (SE-TEKO); (11) Trencin water power stations (SE-VET); (12) Dobsina water power stations (SE-VED); (13) Bohunice nuclear power plant (SE-EBO); (14) Mochovce nuclear power plant (SE-EMO); (15) Bratislava transmission system plant (SE-PS); (16) Bohunice radioactive waste treatment and conditioning centre

  3. A potention of renewable energy sources in Slovakia in term of production of electricity

    Directory of Open Access Journals (Sweden)

    Štefan Kuzevič

    2005-11-01

    Full Text Available Electro-energetics of Slovak Republic is in this time in state of re-structuralization consequent from responsibilities which SR has with integration to the EU and on the other hand with actual status of production capacities of fossil fuels using in heat power stations and heat stations also the utilization of nuclear energy in nuclear power stations Jaslovské Bohunice and Mochovce. Paradoxically slim representation in production capacities have renewable energy sources, while only one relevant one is utilization of water in small hydro power stations. According to fact, that to the year 2010, the share of renewable sources of energy using in comparing with electric energy has to achieve 21,7% (direction of EU 77/2001. It is necessary to evaluate possibilities of utilization and to specify potential of utilization from technical and economical aspect.

  4. Fuel assembly outlet temperature profile influence on core by-pass flow and power distribution determination in WWER -440 reactors

    International Nuclear Information System (INIS)

    Petenyi, V.; Klucarova, K.; Remis, J.

    2003-01-01

    The in core instrumentation of the WWER-440 reactors consists of the thermocouple system and the system of self powered detectors (SPD). The thermocouple systems are positioned about 50 cm above the fuel bundle upper flow-mixing grid. The usual assumption is that, the coolant is well mixed in the Tc location, i.e. the temperature is constant through the flow cross-section area. The present evaluations by using the FLUENT 5.5.14 code reveal that, this assumption is not fulfilled. There exists a temperature profile that depends on fuel assembly geometry and on inner power profile of the fuel assembly. The paper presents the estimation of this effect and its influence on the core power distribution and the core by-pass flow determination. Comparison with measurements in Mochovce NPP will also be a part of this presentation (Authors)

  5. Turbine disintegration debris

    International Nuclear Information System (INIS)

    Holecek, M.; Martinec, P.; Malotin, V.; Peleska, P.; Voldrich, J.

    1997-01-01

    The determination, evaluation and analysis of possible unacceptable consequences of the disintegration turbine (turbo-set) missiles is a part of the wide conceived project put by the company Nuclear Power Plant Mochovce (NPPM), the Slovak Republic. The aim of the project is to take measures reducing the probability of striking a target of safety importance in NPPM by a turbine (turbo-set) missile below the prescribed limit of 10 -6 per turbine year. Following the IAEA Safety Guides, all potential events leading to the generation of a missile are to be analysed. It is necessary to evaluate the probability of unacceptable consequences of such missiles and analyse each event whose probability is not acceptable low. This complex problem thus carries especially: complex analysis of fragment generation; evaluation of the probability of unacceptable events; location of strike zones of possible turbine missiles; assessment the possibility of the turbo-set casing penetration; and projection of additional design requirements if necessary

  6. Increasing of leak-tightness of hermetic zone and other important components in NPPs

    International Nuclear Information System (INIS)

    Murani, J.

    2001-01-01

    The performed by VUEZ resealing works in the hermetic compartments/containment of WWER 440 and WWER 1000 NPPs in Slovakia (Jaslovske Bohunice V-1 NPP, Jaslovske Bohunice V-2 NPP, Mochovce NPP), the Czech Republic (Dukovany NPP, Temelin NPP) and Hungary (Pask NPP) are presented. The leakage rate from hermetic compartments at individual NPP reactor units are shown.The VUEZ activities in field of resealing of weld joints in pools and tanks in the Jaslovske Bohunice V-1 NPP and innovation of the seal of reactor pit protective hood (kolpak) are described. The principle of operation and practical experience of the SMU-V system implemented in the Jaslovske Bohunice V-1 NPP (WWER 440 - V 230) for NPP primary circuit leakage monitoring are also given

  7. Nuclear energetics as environmentally affable source - present and and future

    International Nuclear Information System (INIS)

    Suchomel, J.

    2002-01-01

    In this paper the situation in nuclear energetics in the world in 2000 year is presented. Climatic changes initiated by burning of the fossil fuels an influence of nuclear energetics are discussed. Author informs that European Union and U.S.A. supports developing of nuclear energetics. Nuclear phobia from radiation risk of some inhabitants is compared with risks of other man activities. Possibilities of the electricity production by alternative sources are compared. Liability of the Slovak Republic for decommissioning of two reactor of the V-1 Jaslovske Bohunice NPP in 2006 and 2008, which is compared with the Program of safety improvement of these reactors are discussed. Author and Slovak Nuclear Society accept gladly the suggestion of government of the Slovak Republic that they reassess this liability. The best alternative for decommissioned Jaslovske Bohunice NPP will be the completion of the 3 rd and 4 th blocks of the Mochovce NPP

  8. Technical support and emergency centre

    International Nuclear Information System (INIS)

    Bohun, L.; Kapisovsk y, M.

    1997-01-01

    This paper presents technical support and emergency management center which will be on two places: Mochovce NPP Emergency Centre (Technical support center and Support working center) and Reserve Emergency Centre in Levice (Reserve emergency center and Environmental Evaluation Center). The main aims of the emergency management centers are: the management and coordination of all persons and organisations; provision of the all information needed to evaluation of the accident and its mitigation; continuous evaluation of the potential or real radiological consequences; taking measure for an early notification of the governmental bodies and the organizations, warning and protection of the public; and other aims. In the next part the data for technical support and emergency centre are discussed

  9. Behaviour of Aluminosilicate Inorganic Matrix Sial During and After Solidification of Radioactive Sludge And Radioactive Spent Resins and Their Mixtures

    International Nuclear Information System (INIS)

    Lichvar, P.; Rozloznik, M.; Sekely, S.

    2013-01-01

    SIAL matrix is the product of inorganic compounds by polycondensation. The inorganic SIAL matrix was subject of study from the atomic level to the level of technological application. Infrared spectroscopy measurement and X-ray analysis confirmed that SIAL matrix is mostly formed by amorphous phase. This satisfies the required criteria for disposal of immobilized radioactive waste of appropriate properties into surface repository (Slovak and Czech Republic). First of all, leaching of radioactive nuclide Cs-137 and compressive strength of the final product were found. Various remotely operated devices have been designed, manufactured and successfully used for the radioactive sludge and sludge/resins mixture solidification at the Nuclear power plant (NPP) A-1, V-2 in Jaslovske Bohunice, at Mochovce NPP (Slovak Republic), at Dukovany NPP and at Temelin NPP (Czech Republic). The SIAL matrix was approved for waste package for sludge/resins mixture by the Slovak and Czech Nuclear Regulatory Authorities. (author)

  10. Treatment and conditioning of solid and liquid raw

    International Nuclear Information System (INIS)

    Jakubec, R.

    2015-01-01

    Jadrova a vyradovacia spolocnost, a.s. (JAVYS) implements activities within the processes of treatment and conditioning of radioactive waste (RAW) at two nuclear facilities, one of them located in Bohunice - Technologies for treatment and conditioning of RAW. This nuclear facility includes: Bohunice RAW treatment centre, bituminization lines, waste water purification station and technologies for sorting, fragmentation and decontamination of metallic RAW. The Bohunice RAW treatment centre (BRTC) in Bohunice processes and conditions liquid and solid radioactive waste produced during the A1 NPP and V1 NPP decommissioning, waste from the operation of V2 NPP in Bohunice as well as from the operation of NPP EMO 1,2 in Mochovce. The BRTC includes the following technological facilities: sorting, high-pressure compaction, incineration, concentration and cementation. Treatment of radioactive wastes in the BRTC is described. (authors)

  11. Support calculations for management of PRISE leakage accidents

    Energy Technology Data Exchange (ETDEWEB)

    Matejovic, P; Vranka, L [Nuclear Power Plants Research Inst. Vuje, Trnava (Slovakia)

    1998-12-31

    Accidents involving primary-to-secondary leakage (PRISE) caused by rupture of one or a few tubes are well known design basis events in both, western and VVER NPPs. Operating experience and in-service inspections of VVER-440 units have demonstrated also the potential for large PRISE leaks in the case of the steam generator (SG) primary collector cover lift-up (Rovno NPP). Without performing any countermeasure for limitation of SG collector cover lift-up, a full opening results in PRISE leak with an equivalent diameter 107 mm. Although this accident was not considered in the original design, this event is usually analysed as DBA too. Different means are available for detection and mitigation of PRISE leakage in NPPs currently in operation (J.Bohunice V-1 and V-2) or under construction (Mochovce) in Slovakia. 8 refs.

  12. Review of selected contributions of the conference 'Project control in quality management systems'

    International Nuclear Information System (INIS)

    2008-04-01

    There were 12 contributions presented of the conference focused on the project management in quality management systems. Contributions were focused both on theoretical problems from the project management area and on the applications in practice in management systems implementation in accordance with the standards: STN EN ISO 9001:2000, STN EN ISO 14 001:2005, and OHSAS 18 001:1999. One contribution was focused on the project management in the project of preparation of finishing of the building of the Nuclear Power Plant Mochovce of 3. and 4. block and one contribution was focused on the amendment of the Atomic Act or on the preparation of the new Atomic Act with regard to duty of transposition of the Directive of the Council 2006/117/Euratom on control and supervision of the overseas transportations of radioactive waste and nuclear fuel burnt-up into legislation of the Slovak Republic

  13. Chapter 15. Attachments

    International Nuclear Information System (INIS)

    2001-01-01

    In this chapter used abbreviations and radiation safety of NPPs in Slovak Republic are presented. Results of monitoring of NPP Bohunice V-1 and V-2 as well as NPP Mochovce are presented. A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic in 2000 is presented. The collective dose is one of the fundamental indicators to assess the level of nuclear safety and safety culture. This is the total dose of both external and internal exposure of the whole of the body measured with a personal dosimeter and a calculated internal exposure over a certain period of time. Measured doses to the utility personnel, the staff of supplier organisations and official working visits are included

  14. Behaviour of Aluminosilicate Inorganic Matrix Sial During and After Solidification of Radioactive Sludge And Radioactive Spent Resins and Their Mixtures

    Energy Technology Data Exchange (ETDEWEB)

    Lichvar, P.; Rozloznik, M.; Sekely, S. [Amec Nuclear Slovakia, 919 31 Jaslovske Bohunice (Slovakia)

    2013-09-15

    SIAL matrix is the product of inorganic compounds by polycondensation. The inorganic SIAL matrix was subject of study from the atomic level to the level of technological application. Infrared spectroscopy measurement and X-ray analysis confirmed that SIAL matrix is mostly formed by amorphous phase. This satisfies the required criteria for disposal of immobilized radioactive waste of appropriate properties into surface repository (Slovak and Czech Republic). First of all, leaching of radioactive nuclide Cs-137 and compressive strength of the final product were found. Various remotely operated devices have been designed, manufactured and successfully used for the radioactive sludge and sludge/resins mixture solidification at the Nuclear power plant (NPP) A-1, V-2 in Jaslovske Bohunice, at Mochovce NPP (Slovak Republic), at Dukovany NPP and at Temelin NPP (Czech Republic). The SIAL matrix was approved for waste package for sludge/resins mixture by the Slovak and Czech Nuclear Regulatory Authorities. (author)

  15. Results and discussion

    International Nuclear Information System (INIS)

    1998-01-01

    The author deals with the experimental study of sorption, desorption and vertical migration of radionuclides in Sr-85 and Cs-137 in selected soil samples from around of NPP Bohunice and NPP Mochovce and other localities of the Slovakia. The influence of different materials [concurrent ions (K + , Ca 2+ , NH 4 + , pH), organic matter (peat) and zeolite, humidity] on kinetic of sorption and desorption of strontium and cesium as well as distribution coefficient (K D ) and transfer coefficients in followed samples of soils were followed. Obtained adsorption isotherm are presented and discussed. Using the Tessiere's sequential extraction analysis a gross variability in binding of radionuclides on soils was found. The obtained results were processed with the correlation analysis and the compartment model

  16. Mathematical simulation of gas pressure in fibre-reinforced concrete container at radiation and biological decomposition of cellulose, bituminized and concrete radwastes

    International Nuclear Information System (INIS)

    Kuruc, J.; Kvito, P.

    2005-01-01

    Fibre-reinforced concrete container (FRCC) are used for long-time repository of radioactive wastes. Low- and middle-active radwastes from operation of the NPPs V-1, V-2 Jaslovske Bohunice, Mochovce NPP and from decommissioned NPP A-1 (Jaslovske Bohunice) are treated in the plant SE-VYZ in Jaslovske Bohunice and after immobilisation are deposited in National Radwaste Repository Mochovce (RU RAO). After filling of the RU RAO, FRCC will be stored during 300 years. During this time the integrity of the FRCC must be guaranteed. By the influence of autoradiolysis of the cellulose and bituminized radwastes as well as in cement grout the gases are formed, mainly the hydrogen, methane and carbon dioxide. In the case of presence of available water (a w ≥ 0.63) and in presence of microbes and moulds at appropriate conditions the biological decomposition of cellulose materials may proceed with formation of H 2 , CH 4 a CO 2 . With increasing of developed gases may increase pressure in FRCC, that may initiate the loss of integrity of the FRCC with following endangering of radiation safety of the RU RAO, respectively of the territory over the repository.Authors developed the new mathematical model of pressure of gases in FRCC and in deposited barrels with cellulose and bituminized radwastes. The mathematical model is based on biological decomposition of cellulose materials as well as on radiation decomposition of cellulose, bitumen and concrete. In this mathematical model the diffusion through the walls of FRCC is the main process responsible for decreasing of the pressure. This model was developed in two basic variants: (1) Mathematical model of gas pressure in FRCC as function of dose; (2) Mathematical model of gas pressure in FRCC as function of mass of cellulose

  17. Report of influence on environment 2006

    International Nuclear Information System (INIS)

    2007-01-01

    The joint stock company Jadrova a vyradovacia spolocnost, a. s. (JAVYS) has established in the Slovak power engineering industry just recently. According to transaction documents about privatisation of the joint stock company Slovenske elektrarne, a. s. (SE), on 6-th July 2005 there was established state-owned organisation GovCo from which VYZ plants and V1 power plant were separated. Since 1-st April 2006, the company GovCo assumed responsibility for JE V1 plant, decommissioning of nuclear facilities in Slovakia, processing, treatment and storage of radioactive waste and care for spent nuclear fuel. Seat of the company changed to operation from Jaslovske Bohunice and, on 7-th August, also the company's name changed to Jadrova vyradovacia spolocnost, a.s.. Since March 2007, the company's name is Jadrova a vyradovacia spolocnost, a. s. Starting position of the company in the Slovak power engineering sector developed from achieved results of long- term operation of plants of the company SE, a. s. - VYZ and EBO V1. Apart from operation of currently only one block of V1 nuclear power plant, the company carries out the first phase of the A1 nuclear power plant decommissioning project, operates radioactive waste processing centre in Bohunice (Bohunicke spracovatelske centrum radioaktivnych odpadov), bitumen and vitrification line of radioactive waste processing and fragmentation plant for metal radioactive waste. Currently, new facility - final processing of liquid radioactive waste in Mochovce is being put into operation. This chain is crowned by safe storage of processed low and medium-active waste in Republic's Repository of Radioactive Waste (Republikove ulozisko RAO) in Mochovce. The company also operates spent nuclear fuel in-process store in Jaslovske Bohunice, which is resistant to seismic activity and compacted. This Report contains the results of monitoring of the environment in JAVYS, a.s. in 2006

  18. Chapter 12. Public information

    International Nuclear Information System (INIS)

    2000-01-01

    In 1999 there were 83 contributions on both national and foreign activities of the Nuclear Regulatory Authority of the Slovak Republic (UJD) send to the Press agencies of Slovakia, dailies and electronic media. UJD, together with State Office for Nuclear Safety of the Czech Republic, is a publisher of a professional journal 'Safety of Nuclear Energy', which publishes principal articles about main activities of UJD. The double issue 3/4 (1999) was dedicated to the process of start up of Unit 1 of Mochovce. In 'Public administration' there were 2 principal articles published in 1999 on legislative activities of UJD. Contributions about the regulatory activities and the international co-operation of UJD are regularly published in the 'SE Newsletter', and in company journals of 'Mochovce' and 'Bohunice'. National and foreign activities of UJD were published in 3 issues of 'Bulletin of the Slovak Nuclear Society (SNUS)'. This year also the report on safety of nuclear installations of SR was published in the journal of 'European Nuclear Society - Nuclear Europe Worldscan'. For the world information agency, NucNet, there were 4 contributions prepared focusing on both national and foreign activity of UJD. Information material on INES was was prepared and published for the public. In 1999 there were 4 press conferences held at UJD with a follow up presentation of the management of UJD on television and in the radio broadcasting. Officials of UJD had 7 presentations on television and gave 6 interviews for Slovak Radio Broadcasting and for magazines and daily 5 significant interviews. In 1999 a vide-clip was produced for public purposes on the SWISSSLOVAK project. In Bern, Switzerland a very successful press conference was held with the participation of the UJD chairman. The UJD 3 Bulletins prepared and published on national and foreign activities of UJD

  19. RAMOS - the radiation monitoring system of the Umweltforschungsinstitut Global 2000

    International Nuclear Information System (INIS)

    Exler, M.; Schmittner, W.

    2001-01-01

    The radiation early warning system RAMOS (radiation monitoring system) measures the radioactivity of the areas surrounding nuclear technical facilities (at present, around the Nuclear Power Plants Dukovany and Mochovce). Measurements are taken with Gamma-radiation devices of the type RS 03/X by the firm BITT- Technology. These devices are measuring equipment of the type Proportion-count tube with a detection range of 10 nSv/h to 10 Sv/h. The measuring stations consist of this Gamma measuring equipment, a personal computer with modem, back-up electricity devices and meteorological measuring devices. Six such measuring stations surrounding the facility comprise a complete measuring ring. The values are measured each minute. Considering the normal fluctuation in radiation measurements due to geology and weather conditions and the average background radiation, a certain alarm threshold is defined (on all stations this threshold is under 230 nSv/h). If this threshold is breached, immediately the data is transmitted through telephone lines and is received by the central office. Because of the short reaction time and low threshold, valuable time is gained for an emergency response by government agencies and the population. Official warning of the government agencies occurs after fulfilling the commendation of the Austrian Radiation Protection Commission. In the continued measurements from the end of 1994 to 2000 at NPP Dukovany and continuous measurements from NPP Mochovce from mid-1999 to the end of 2000, there was not a detection of dangerous levels of radiation were released into the atmosphere. After close examination of the measured data, different types of fluctuations could be observed - such as during the day-time period and short-term peaks after rain-fall. Detailed knowledge about trends in these fluctuations, allows an easier continual evaluation of a potential accident. The measured data is given to the public in graphic form every month via the Internet

  20. Effect of temperature on structural quality of the cement paste and high-strength concrete with silica fume

    International Nuclear Information System (INIS)

    Janotka, Ivan; Nuernbergerova, Terezia

    2005-01-01

    Experimental investigation conducted to study the thermo-mechanical properties of concrete at Temelin (Czech Republic), Mochovce (Slovakia), and Penly (France) nuclear power plants reveals structural integrity degradation between 100 and 200 deg C due to both a loss of water bound in hydrated cement minerals and subsequently air void formation. Test results indicate changes in strength, average pore radius and calculated permeability coefficients for Mochovce specimens exposed to temperatures up to 400 deg C. It demonstrates that the permeability coefficient measured on the basis of pore sizes using mercury intrusion porosimetry is suitable technique for the evaluation of concrete quality. It confirms that strength and permeability coefficient are equivalent structural quality variables of concrete. At 400 deg C gel-like hydration products are decomposed, at 600 deg C Ca(OH) 2 is dehydroxylated, and CaCO 3 dissociation to CaO and CO 2 accompanied with the re-crystallisation of non-binding phases from hydrated cement under re-combustion are dominant processes between 600 and 800 deg C. This stage of concrete is characterised by the collapse of its structural integrity, revealing residual compressive strength. This paper reports high-strength concrete behaviour subjected to temperatures up to 200 deg C. In accordance with previous results, research studies of structure-property relation show the changes in strength, dynamic modulus of elasticity, strain-stress behaviour, and shrinkage-induced deformations influenced by a hydrate phase decomposition. Volume reduction of the hydrate phase due to the loss of bound water mass is the cause of air void formation, and pore structure coarsening. The main attention is herein devoted to the evaluation of utility property decrease of high-strength concrete and microstructure degradation of the cement paste with the same composition than that in concrete when attacked by elevated temperatures

  1. Regulation of radioactive waste management

    International Nuclear Information System (INIS)

    2002-01-01

    This bulletin contains information about activities of the Nuclear Regulatory Authority of the Slovak Republic (UJD). In this leaflet the regulation of radioactive waste management of the UJD are presented. Radioactive waste (RAW) is the gaseous, liquid or solid material that contains or is contaminated with radionuclides at concentrations or activities greater than clearance levels and for which no use is foreseen. The classification of radioactive waste on the basis of type and activity level is: - transition waste; - short lived low and intermediate level waste (LlLW-SL); - long lived low and intermediate level waste (LlLW-LL); - high level waste. Waste management (in accordance with Act 130/98 Coll.) involves collection, sorting, treatment, conditioning, transport and disposal of radioactive waste originated by nuclear facilities and conditioning, transport to repository and disposal of other radioactive waste (originated during medical, research and industrial use of radioactive sources). The final goal of radioactive waste management is RAW isolation using a system of engineered and natural barriers to protect population and environment. Nuclear Regulatory Authority of the Slovak Republic regulates radioactive waste management in accordance with Act 130/98 Coll. Inspectors regularly inspect and evaluate how the requirements for nuclear safety at nuclear facilities are fulfilled. On the basis of safety documentation evaluation, UJD issued permission for operation of four radioactive waste management facilities. Nuclear facility 'Technologies for treatment and conditioning contains bituminization plants and Bohunice conditioning centre with sorting, fragmentation, evaporation, incineration, supercompaction and cementation. Final product is waste package (Fibre reinforced container with solidified waste) acceptable for near surface repository in Mochovce. Republic repository in Mochovce is built for disposal of short lived low and intermediate level waste. Next

  2. Regulatory Aspect of Periodic Safety Review Performed in Nuclear Power Plants in the Slovak Republic

    International Nuclear Information System (INIS)

    Baszo, Z.

    2010-01-01

    The paper deals with the regulatory aspect of Nuclear Power Plant (NPP) Periodic Safety Review (PSR) as a part of license renewal process in the Slovak Republic. It summarizes the history of activities similar to PSR performed in the past for NPPs operated in the Slovak Republic. Furthermore, it describes both the requirements involved in the current Slovak legislation to be met by licensee in the Slovak Republic in this field and the procedures concerning the PSR as well. The objective and rules of PSR to be performed for NPPs in the Slovak Republic were derived from the internationally accepted International Atomic Energy Agency (IAEA) document and have been implemented into national legislation. PSR of two twin units located in Bohunice NPP and Mochovce NPP, respectively, has been initiated in the Slovak Republic based on evaluation of each area to be reviewed (safety factors) using recent methodology and practice. Other significant factors, such as ageing, modifications of NPP and the safe operation for a specified future period, have to be assessed in the frame of PSR. Report on performed PSR outlines the results of review for each area, the corrective plan, which considering mutual relations between assessed areas specifies the issues to be solved with the aim to eliminate shortcomings identified in the frame of PSR and to adopt safety improvements. The findings from PSR in the evaluated areas also serve as a source of information for updating of all documents to be attached to the written application of licensee for renewal of a nuclear power plant operating license. The presented procedure describes how the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) has reviewed the documents submitted during PSR. Based on results of submitted documents evaluation and licensee application for license renewal the license for next 10 years operation has been issued for Bohunice NPP. At present, similar procedure for Mochovce NPP unit 1 and 2 is underway.(author).

  3. Low level radioactive waste disposal

    International Nuclear Information System (INIS)

    Balaz, J.; Chren, O.

    2015-01-01

    The Mochovce National Radwaste Repository is a near surface multi-barrier disposal facility for disposal of processed low and very low level radioactive wastes (radwastes) resulting from the operation and decommissioning of nuclear facilities situated in the territory of the Slovak Republic and from research institutes, laboratories, hospitals and other institutions (institutional RAW) which are in compliance with the acceptance criteria. The basic safety requirement of the Repository is to avoid a radioactive release to the environment during its operation and institutional inspection. This commitment is covered by the protection barrier system. The method of solution designed and implemented at the Repository construction complies with the latest knowledge and practice of the repository developments all over the world and meets requirements for the safe radwaste disposal with minimum environmental consequences. All wastes are solidified and have to meet the acceptance criteria before disposal into the Repository. They are processed and treated at the Bohunice RAW Treatment Centre and Liquid RAW Final Treatment Facility at Mochovce. The disposal facility for low level radwastes consists of two double-rows of reinforced concrete vaults with total capacity 7 200 fibre reinforced concrete containers (FCCs) with RAW. One double-row contains 40 The operation of the Repository was started in year 2001 and after ten years, in 2011 was conducted the periodic assessment of nuclear safety with positive results. Till the end of year 2014 was disposed to the Repository 11 514 m 3 RAW. The analysis of total RAW production from operation and decommissioning of all nuclear installation in SR, which has been carried out in frame of the BIDSF project C9.1, has showed that the total volume estimation of conditioned waste is 108 thousand m 3 of which 45.5 % are low level waste (LLW) and 54,5 % very low level waste (VLLW). On the base of this fact there is the need to build 7

  4. Design, implementation and licensing of improvement measures

    International Nuclear Information System (INIS)

    Rousset, P.

    2000-01-01

    Modifications are designed to contribute to improve the level of safety, and the level of performance of the plants. The successful implementation of a modification depends on the quality of the design and particularly the good fitting of the modification in the existing design, on the perfect consistency of the licensing approach and on the good management of the project constraints and interfaces. Over the last ten years, FRAMATOME has accumulated a large and varied experience in these activities, as shown in the few examples briefly described in the presentation. Within the Mochovce completion project, FRAMATOME has been in charge of the basic design or implementation of about twenty safety measures. This involved establishing efficient partnerships with design organizations and suppliers in the Slovak Republic, Czech Republic, and Russia. A similar approach is used in the frame of the Kozloduy 5-6 modernization program, where the basic engineering contract is conducted since 1998 and the main contract under discussion. From the very beginning of the TACIS program FRAMATOME has been involved in projects dealing with the design of reactor safety systems. For example, an extensive work aiming at developing a methodology for accident analysis in VVER reactor was initiated in 1993, in collaboration with Siemens, Kurchatov Institute and OKB Gidropress. This methodology was recently used successfully in a new project with the objective to evaluate the possible modification of reactor protection signals of some Russian reactors. Within the PHARE program, a complete analysis of the primary to secondary leakage risk was conducted for Paks nuclear power plant. This involved the writing and validation of the relevant emergency procedure, specification of the leak detection system, study of an improved design of the collector cover, and recommendation of some systems modifications. A last example is the study of the modifications of main steam lines performed in the frame

  5. What Enel and Rusko will not find in the privatization documents

    International Nuclear Information System (INIS)

    Janoska, J.

    2004-01-01

    about it publicly as yet - was that the banks included in the loan contract a clause that the loans were not to be used for the completion of units at the Mochovce nuclear power station. The contract also contains a clause that allows early repayment of the loan in the event that completion work on Mochovce units is begun

  6. Slovenske elektrarne and the environment

    International Nuclear Information System (INIS)

    Balaz, J.

    2003-01-01

    At the end of 2002 Mochovce NPP as the first Slovak energy operation got the international certificate of environmental managership according to norm ISO 14 001:1996 on production and electric energy supply from nuclear power plant praised by reputable testimonial company Det Norske Veritas. Slovenske elektrarne, a.s. management has intention to pass a certification process in all of its operations in this and following year. Certification presentation is one of the results of project of Environmental policy of SE, a.s. as it was specified by company executive in 2000. This project comes out from Environmental protection conception of SE from 1997. The basic condition of success of whole project is total orientation of Slovak electric energetic on energy production with minimal environmental load. It means the maximal exploitation of water and nuclear production of electric energy at the expense of technologies based on energy raw materials incineration. In 2002, of totally produced 32 805 MWh of electric energy almost two thirds were produced by nuclear power plants, almost one fifth by water power plants and 16% by thermal power plants. Thanks to this electricity production structure it is sharply possible to cut back the emission capacity produced by thermal power plants

  7. Rapid nuclear reaction

    International Nuclear Information System (INIS)

    Marcan, P.; Beer, G.

    2008-01-01

    Whereas the completion of blocks 3 and 4 in Mochovce were subject to some discussion, the building of a new unit at Jaslovske Bohunice has remained unnoticed. Not even environmentalists objected. And so far the plans to build a new power plant seem to have been approved without any major discussion about whether Slovakia really needs or does not need a new nuclear power unit. Political statements about a possible future shortage of electricity were enough. The plans of private companies to build their own power plants or the possibility of decreasing the use of energy by savings were disregarded. But a clear answer to the question whether this new power unit will generate electricity for export to other countries has not yet been given. But by the end of this year the government wants to decide whether the new power plant which will cost an estimated 100 billion Slovak crowns (3.3 billions EUR) will be built from public funds in tandem with a private investor or fully financed by private capital. The name of the private investor should become known by the end of this year. (authors)

  8. Fire protection measures

    International Nuclear Information System (INIS)

    Bittner

    1997-01-01

    The presentation could only show a very brief overview of the analysis results of a wide study of the existing fire protection situation at Mochovce. As far not already done the next steps will be the selection of the final suppliers of the different measures, the detailed design and the implementation of the measures. As part of the further assistance in fire protection EUCOM will perform compliance checks of the DD and implementation and assist EMO for raising problems. Especially during the implementation of the measures the belonging quality checks have a high priority. Assuming that the implementation of measures will be in accordance with with the study results and the relevant basic design requirements it can be stated that safety level concerning fire protection will be in accordance with international requirement like IAEA 50 SG D2. The next step of our work will be the delta analysis for 2 unit and the relevant basic design as far as there are differences to unit 1. (author)

  9. 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)

  10. Chapter No.4. Safety analyses

    International Nuclear Information System (INIS)

    2002-01-01

    In 2001 the activity in the field of safety analyses was focused on verification of the safety analyses reports for NPP V-2 Bohunice and NPP Mochovce concerning the new profiled fuel and probabilistic safety assessment study for NPP Mochovce. The calculation safety analyses were performed and expert reviews for the internal UJD needs were elaborated. An important part of work was performed also in solving of scientific and technical tasks appointed within bilateral projects of co-operation between UJD and its international partnership organisations as well as within international projects ordered and financed by the European Commission. All these activities served as an independent support for UJD in its deterministic and probabilistic safety assessment of nuclear installations. A special attention was paid to a review of probabilistic safety assessment study of level 1 for NPP Mochovce. The probabilistic safety analysis of NPP related to the full power operation was elaborated in the study and a contribution of the technical and operational improvements to the risk decreasing was quantified. A core damage frequency of the reactor was calculated and the dominant initiating events and accident sequences with the major contribution to the risk were determined. The target of the review was to determine the acceptance of the sources of input information, assumptions, models, data, analyses and obtained results, so that the probabilistic model could give a real picture of the NPP. The review of the study was performed in co-operation of UJD with the IAEA (IPSART mission) as well as with other external organisations, which were not involved in the elaboration of the reviewed document and probabilistic model of NPP. The review was made in accordance with the IAEA guidelines and methodical documents of UJD and US NRC. In the field of calculation safety analyses the UJD activity was focused on the analysis of an operational event, analyses of the selected accident scenarios

  11. Quality assurance programme of Temelin nuclear power plant

    International Nuclear Information System (INIS)

    Eybl, J.; Nowak, O.

    1988-01-01

    The fundamental principle of the system of quality assurance in Czechoslovak nuclear power is quality assurance at all stages of the construction and operation of nuclear power plants and the grading fo measures taken, this in dependence on the impact on nuclear safety of the respective nuclear installation or its part. The system has been made fully operational during the construction of nuclear power plants in Temelin and Mochovce. State surveillance is executed by the Czechoslovak Atomic Energy Commission, and the Czech and Slovak Offices for Work Safety. Briefly discussed are the tasks of the building subcontractor of the Temelin nuclear power plant with regard to the programme of quality assurance as well as the results of the solution of the respective research tasks. The programme of quality assurance classifies the selected sections of the structure of a nuclear power plant into three safety categories. No part of the structure is classified into the first category, the second category includes, e.g., the reactor building, cooling tanks and diesel generator units, the third includes the reactor building and the building of auxiliary workshops. Attention is also paid to the problems of the qualification of personnel and to inspection activity. (Z.M.). 12 refs

  12. Feasibility studies for decommissioning

    International Nuclear Information System (INIS)

    Hladky, E.

    2000-01-01

    In this presentation author deals with planning of decommission of the NPPs A1, V1 and V2 Bohunice and Mochovce. It was concluded that: Used model for decommissioning parameters assessment has been suitable for elaboration of initial decommissioning plans (feasibility studies); Basic assessment of main decommissioning parameters and basic comparison of various decommissioning options have been possible; Improvement of the model and corresponding software is desirable and works on software improvement began one year ago; V1-NPP initial decommissioning plan should be actualized, because initial decommissioning plan does not correspond by its content and structure to requirements of Act No. 130/98 and Nuclear Regulatory Authority Degree No. 246/99; Strategy of radioactive wastes treatment and conditioning together with technical provisions at Jaslovske Bohunice site was changed in comparison with the assumptions in 1991-92; Considered V1 NPP decommissioning options are necessary to be re-evaluated in accordance with latest development of knowledge and approaches to NPP decommissioning in the world; Specific unit costs are substantially and differentially changed in comparison with the assumptions in 1991-92; Necessity to take into account technical changes resulted from V1 NPP reconstruction. (author)

  13. Nuclear safety in Slovak Republic. Status of safety improvements

    International Nuclear Information System (INIS)

    Toth, A.

    1999-01-01

    Status of the safety improvements at Bohunice V-1 units concerning WWER-440/V-230 design upgrading were as follows: supplementing of steam generator super-emergency feed water system; higher capacity of emergency core cooling system; supplementing of automatic links between primary and secondary circuit systems; higher level of secondary system automation. The goal of the modernization program for Bohunice V-1 units WWER-440/V-230 was to increase nuclear safety to the level of the proposals and IAEA recommendations and to reach probability goals of the reactor concerning active zone damage, leak of radioactive materials, failures of safety systems and damage shields. Upgrading program for Mochovce NPP - WWER-440/V-213 is concerned with improving the integrity of the reactor pressure vessel, steam generators 'leak before break' methods applied for the NPP, instrumentation and control of safety systems, diagnostic systems, replacement of in-core monitoring system, emergency analyses, pressurizers safety relief valves, hydrogen removal system, seismic evaluations, non-destructive testing, fire protection. Implementation of quality assurance has a special role in improvement of operational safety activities as well as safety management and safety culture, radiation protection, decommissioning and waste management and training. The Year 2000 problem is mentioned as well

  14. WWER-1000 unit reliability problems from the point of view of the main supplier of technological equipment

    International Nuclear Information System (INIS)

    Bursa, V.; Holousova, M.; Turnik, S.

    1990-01-01

    At Skoda Works in Plzen, data from the period of construction of nuclear power plants are processed on an ICL DRS 300 computer. The database systems DBASE II and DATAFLEX are available for creating reliability information systems. The information system that is being developed for WWER-1000 units is tested at the WWER-440 units of the Dukovany and Mochovce nuclear power plants. Activities in the field of evaluation of structure reliability of WWER-1000 nuclear power plants are aimed at two major goals, viz., developing a methodology for testing the reliability of the whole unit and its subsystems, and performing reliability analysis and calculations of reliability indices of the secondary circuit of a WWER-1000 nuclear power plant. The reason for the latter concern is the fact that in 1984-1986, secondary circuits contributed 46% to failures of Czechoslovak WWER-440 nuclear power plants. According to existing analyses, the time fluctuations of reliability indices obey no rule that could be employed for inferring indices expected in steady-state operating conditions from indices established in the starting stage of operation. (Z.M.). 10 refs

  15. Specification of technical means for implementation of supervisory algorithms of the status of a nuclear reactor and of the main coolant pump of a NPP

    International Nuclear Information System (INIS)

    Jirsa, P.

    2000-11-01

    Inclusion into the programming of inputs of the supervisory algorithm (data collection from the monitoring system, transmission of diagnostic output fro other system and transmission of technological data), of the supervisory process proper based on the data obtained (data analysis) and of the output (presentation of the results to the operator, communication with the master and archiving systems, etc.) requires knowledge of the format of the data transmitted, their availability, communication network protocols, operating system, etc. Hence, the environment for which the algorithm will be developed should be specified, roughly at least. The following topics are addressed: Description of technical means of Czech nuclear power plants (Dukovany, Temelin, Mochovce), and Proposal for technical means to implement the monitoring algorithm (Requirements related to the monitoring systems, Identification of the reference system, Parameters of the selected system). Since no domestic manufacturer of HW for monitoring and diagnostic systems exists, a novel system of the Brueel and Kjaer company for on-line diagnosis and monitoring, COMPASS, was selected as a model model system for the implementation of the supervisory algorithms. (P.A.)

  16. Geological aspects of radioactive waste disposal

    International Nuclear Information System (INIS)

    Kobera, P.

    1985-01-01

    Geological formations suitable for burying various types of radioactive wastes are characterized applying criteria for the evaluation and selection of geological formations for building disposal sites for radioactive wastes issued in IAEA technical recommendations. They are surface disposal sites, disposal sites in medium depths and deep disposal sites. Attention is focused on geological formations usable for injecting self-hardening mixtures into cracks prepared by hydraulic decomposition and for injecting liquid radioactive wastes into permeable rocks. Briefly outlined are current trends of the disposal of radioactive wastes in Czechoslovakia and the possibilities are assessed from the geological point of view of building disposal sites for radioactive wastes on the sites of Czechoslovak nuclear power plants at Jaslovske Bohunice, Mochovce, Dukovany, Temelin, Holice (eastern Bohemia), Blahoutovice (northern Moravia) and Zehna (eastern Slovakia). It is stated that in order to design an optimal method of the burial of radioactive waste it will be necessary to improve knowledge of geological conditions in the potential disposal sites at the said nuclear plants. There is usually no detailed knowledge of geological and hydrological conditions at greater depths than 100 m. (Z.M.)

  17. Licensing of new fuel for Slovak NPPs

    International Nuclear Information System (INIS)

    Melicharek, M.; Mikulas, B.

    2011-01-01

    With the hope of achieving a six year fuel cycle and to allow for further power uprates a new type of fuel was licensed for NPP Mochovce Unit 1 (EMO1). Slovenske elektrarne, a.s. introduced the idea for the new fuel type to the regulatory authority in the middle of 2010. That's when the first draft of EMO safety report was made. This was the actual start of the licensing process. In case of new fuel regulator has several requirements like extended start up and power test; introducing a fuel behavior monitoring plan; using two independent methods to determine coolant flow though the active zone. In this paper the following issues have been discussed: 1) Engineering and safety reserve factors; 2)Fuel limits; 3) Uncertainties decrease in measurement of coolant flow through the reactor; 4) Determination of heating on fuel assembly; 5) Storage pool issues; 6) Emergency planning; 7) Monitoring of several fuel parameters (K qmax , K rmax , K v .K k and bypass)monitored during campaign

  18. Case law

    International Nuclear Information System (INIS)

    2013-01-01

    This section reports on 7 case laws from 4 countries: - France: Conseil d'Etat decision, 28 June 2013, refusing to suspend operation of the Fessenheim nuclear power plant; - Slovak Republic: New developments including the Supreme Court's judgment in a matter involving Greenpeace Slovakia's claims regarding the Mochovce nuclear power plant; New developments in the matter involving Greenpeace's demands for information under the Freedom of Information Act; - Switzerland: Judgment of the Federal Supreme Court in the matter of the Departement federal de l'environnement, des transports, de l'energie et de la communication (DETEC) against Ursula Balmer-Schafroth and others on consideration of admissibility of a request to withdraw the operating licence for the Muehleberg nuclear power plant; - United States: Judgment of the Court of Appeals for the District of Columbia Circuit granting petition for writ of mandamus ordering US Nuclear Regulatory Commission (NRC) to resume Yucca Mountain licensing; Judgment of the Court of Appeals for the Second Circuit invalidating two Vermont statutes as preempted by the Atomic Energy Act; Judgment of the NRC on transferring Shieldalloy site to New Jersey's jurisdiction

  19. Diagnostic and monitoring systems produced in Vuje, Okruzna 5, 918 64 Trnava, Slovak Republic

    International Nuclear Information System (INIS)

    Oksa, G.; Bahna, J.; Murin, V.; Kucharek, P.; Smutny, S.

    1996-01-01

    Based on the 20 years experience in on-line vibration diagnostics of mechanical components in the primary circuit of nuclear power plant PWR WWER-440, Vuje, Okruzna 5, 918 64 Trnava produces its own diagnostic and monitoring systems since 1990. The variety of diagnostic systems includes: loose part monitoring system (LPMS), monitoring system of main circulating pumps (MCPMS), vibration monitoring system (LVMS), leakage monitoring system (LMS). The emphasis in the hardware solution is put on the design modularity and versatility so that many subcomponents (circuit boards) are common or highly similar for all systems. Using exclusively digital data for processing enhances the reliability of the measurements and allows the easy data transportation from one computer to another (e.g., for more sophisticated analysis). Trends in the software development follow the similar path as for the hardware solution - namely, the modularity and versatility of software is the imperative goal. The modern operating systems also incorporate the ability of network communication, which is crucial for the integration of stand-alone diagnostic systems into nuclear power plants information system. So far a number of systems have been successfully installed: 6 LPMSs (Jaslovske Bohunice, Dukovany), 4 MCPMs (Jaslovske Bohunice) and 2 LVMSs (Jaslovske Bohunice), all systems operate in PWR WWER-440 environment. Another diagnostic systems are under construction: 2 LPMSs (Temelin, PWR WWER-1000), 2 MCMSs (Mochovce - PWR WWER-440) and 2 LMSs (Jaslovske Bohunice). (author). 1 fig

  20. 50 Years of nuclear power plants in Slovakia

    International Nuclear Information System (INIS)

    Dobak, D.; Moncekova, M.; Pritrsky, R.

    2007-01-01

    The publication was prepared to celebration of semi-centennial anniversary of nuclear power plants in Slovakia and presents a free sequel of book '40 years of nuclear power plants in Slovakia'. It contains memories of the observers that are valuable and merits spreading theirs ideas. There are photos in the publication that up to now were not disclosed and that have a unique value not due to their age only. At the same time, the publication expresses an admiration, regard and acknowledgement to all who joined their life with nuclear power. This book contains the following headings: (1) Speech, Lubomir Jahnatek (Minister of Economy of the Slovak Republic); (2) Speech, Jozef Valach; (3) Speech, Paolo Ruzzini; (4) Historic aspects of A1 NPP; (5) Historic Aspects of V1 NPP; (6) Historic Aspects of V2 NPP; (7) A remembrance to Mochovce; (8) Historic Aspects of VYZ; (9) Nuclear power as an integral part of the Slovak power engineering; (10) Under control of supervision; (12) The state health regulation performance in nuclear installations; (13) JAVYS in the Slovak energy sector

  1. Radioactivity in the environment

    International Nuclear Information System (INIS)

    2006-01-01

    In this report different aspects of the radioactivity in the environment of the Slovak Republic for the period of 2004 - 2006 years are reported. This report is published only on the Enviroportal.sk. The following aspects of the radioactivity in the environment are reviewed there: Electricity production in nuclear power plants and their consumption; Natural sources of ionisation radiation; Man-made sources of ionisation radiation; Safety of exploitation of the nuclear power plants on the territory of the Slovak Republic; International Nuclear Event Scale; Basic information about influence of radiation on health of population and about evaluation methods; Influence of physical risk factors (including of ionisation radiation) in the working environment on formation of occupation diseases; Collective doses of occupation in NPPs; Health state of population in the locality of the NPP Mochovce; Food contamination by ionisation radiation; Radiation monitoring network; Legislative directives about population health protection against ionisation radiation action; Decommissioning of the NPP Jaslovske Bohunice (EBO V-1); Conception of the back fuel cycle and treatment of spent fuels and high-level radioactive wastes; Project of territorial-economic development of the Trnava region after decommissioning of the Jaslovske Bohunice NPP

  2. Radiation protection and monitoring

    International Nuclear Information System (INIS)

    Bruecher, L.; Langmueller, G.; Tuerschmann, G.

    1997-01-01

    The safety, the quality and efficiency of the radiological monitoring systems for block one and two of the NPP Mochovce, designed and delivered by the general designer, should be increased by EUCOM Siemens. Modern, accident resistant and/or more powerful monitoring systems have been designed by Siemens will be added to the existing systems. To achieve this radiation measuring units will be installed inside the hermetic zone, in the reactor hall, at the stack, at the release water system and in the environment in the vicinity of the NPP. The presentation, the storage distribution and the processing of all measuring results also will be optimised by installing a modern high-performance computer system, the so-called Central Radiological Computer System 'CRCS', featuring a high availability. The components will be installed in the relevant control rooms all over the plant. With this computer system it is easy to control the radiation level inside and outside the NPP during normal operation and during and after an accident. Special programs, developed by Siemens support the staff by interpreting the consequences of radioactive releases into the environment and by initiating protection procedures during and after an accident. All functions of the system are available for emergency protection drills and training the staff interruption of the normal control procedure. For the personal protection a digital personal dosimetry system completely considering with the requirements of ICRP 60 and several contamination monitors will be installed. (authors)

  3. Approach to the safety culture in the Slovak Republic

    International Nuclear Information System (INIS)

    Kuchta, L.; Sladek, V.

    2002-01-01

    The Nuclear Regulatory Authority of the Slovak Republic was established on January 1st, 1993, after division of former Czech and Slovak Federation Republic to two independent states - Czech Republic and Slovak Republic. As there were inherited four units on the site Jaslovske Bohunice and Interim Spent Fuel Storage on the same site under operation and four units under construction on site Mochovce it was necessary to keep on regulatory activities from very beginning of regulatory authority existence. The new regulator has been all time co-operating closely with IAEA and countries with developed nuclear power to cover all nuclear safety related areas including the safety culture. It is, however, to be said, that the issue of safety culture begun to be an object of considerations of Czechoslovak NPPs as early as in 1986 after issue of IAEA INSAG 1. Since that time the NPPs try to enforce the safety culture principles as a part of nuclear safety into their daily work in consensus with an utility Slovenske elektrarne, nuclear power plants and Nuclear Regulatory Authority. A purpose of the article is to provide an overview on safety culture practices at nuclear installations in the Slovak Republic. (author)

  4. 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)

  5. VUEZ. Annual report 2007

    International Nuclear Information System (INIS)

    2008-01-01

    A brief account of activities carried out by the Vyskumny ustav energetickych zariadeni, a.s. (VUEZ) in 2008 is presented. These activities are reported under the headings: (1) Introductory address by the Chairman of the Board of Directors; (2) Company profile; (3) Portfolio of products and service 2007; (4) Quality management system; (5) Organisational Structure; (6) Human resources; (7) Financial statements and auditor's report; (8) Basic and contact data; (9) Contact data. The year 2007 was arduous and, with regard to contracts and projects performed and related profits, also successful for VUEZ, a.s. On the domestic market, our principal customers have bee companies such as Slovenske elektrarne - Enel, Bratislava, in its locations of Jaslovske Bohunice and Mochovce, Jadrova vyradovacia spolocnost, Jaslovske Bohunice, and Vodohospodarska vystavba, Bratislava. Equally important customers for our company have been operators of foreign nuclear power plants, namely CEZ, a.s. (Czech Republic) and the Paks NPP (Hungary). In the course of 2007, negotiations and offer proceedings were initiated with WWER nuclear power plants in Ukraine and Russia

  6. Chapter 2. The production units

    International Nuclear Information System (INIS)

    1998-01-01

    In the second chapter of this CD ROM the production units of the Slovak Electric, Plc. (Slovenske elektrarne, a.s.), are presented. It consist of next paragraphs: (1) Nuclear power plants (A-1 Nuclear Power Plant (History, Technological scheme, basic data are presented); V-1, V-2 Bohunice Nuclear Power Plant (History 1972-1985, technological scheme; nuclear safety, radiation protection, heat supply, international co-operation and basic data are presented); Mochovce Nuclear Power Plant (History 1980-1998, technological scheme, construction completion, milestones of commissioning, safety and environmental protection as well as basic data are included). (2) Conventional sources of energy (Vojany fossil power plant (History 1959-1992, Technological units of power plant, Impact of operation on the environment, Plant of Vojany FPP Renewal and Reconstruction, Basic data are listed), Novaky fossil power plant (History 1949-1998, Technological scheme, current investment construction, basic data, Handlova heating plant). Kosice Combined Heat Power Plant (History 1960-1995, technological scheme, State metrology centre, acredited chemical laboratory, basic data). (3) Hydroelectric power plants (Trencin HPPs: Cierny Vah pumped storage HPP, Liptovska Mara HPP, Orava HPP, Sucany HPP, Miksova HPP, Nosice HPP, Velke Kozmalovce HPP, Gabcikovo HPP, Dubnica HPP, Nove Mesto n/V HPP, Madunice HPP, Kralova HPP) and Dobsina HPPs: (Dobsina HPP, Ruzin HPP, Domasa HPP, small HPPs) are presented

  7. Radioactive waste disposal in Slovakia: Current practice and development

    International Nuclear Information System (INIS)

    Salzer, P.; Hanusik, V.; Ehn, L.

    2002-01-01

    The paper describes activities concerning the disposal of radioactive waste in the Slovak Republic. For disposal of the low and intermediate short-lived radioactive waste, the National radioactive waste repository Mochovce (near surface type) was put into operation in 1999. History and approaches to repository development, siting and construction are briefly described. Recent activities regarding the repository are concerning on the safety re-assessment and re-derivation of coherent waste acceptance criteria, studies of repository covering and possible enlargement. In the second part, attention is given to the Slovak deep geological repository development programme, which has been under way since 1996. Most of the results were obtained from the siting part of the programme, where four localities (six sites) were identified as prospective for next investigation. The paper also gives an overview on next two routes of deep repository development programme: studies resulted later in performance assessment and general activities, i.e. design studies, analysis of legislative and infrastructure conditions, planning and evaluation of works. (author)

  8. Hydrological balancing as applied to shallow ground disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Kobera, P.; Dlouhy, Z.

    1984-02-01

    Shallow ground repositories are suitable disposal means for low and intermediate level radioactive wastes which offer an adequate form of containment of relatively short-lived radionuclides. The majority of safety related problems are connected with occurrence of water at the site. These problems include water accumulation in the disposal modules, high water table, hydrogeological complexity, water erosion, etc. In this context a simple technique is proposed for water balancing in the region of interest which would be relatively inexpensive and could supply large amounts of pertinent information. In the paper several balancing techniques based on water and/or energy balance methods are discussed. The results of a static evaluation of long term water balance averages are presented for the regions of planned shallow ground repositories near Dukovany and Mochovce in the CSSR. Hydrological processes and elements taking part in different hydrological cycles are treated from the dynamical point of view. The calculation methods for application of the kinematic approach are briefly touched. The results may be acquired at relatively low costs

  9. Activities of Nuclear Regulatory Authority and safety of nuclear facilities in the Slovak Republic in 1993

    International Nuclear Information System (INIS)

    1994-04-01

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (NRA SR) in 1993 is presented. These activities are reported under the headings: (1) Introduction; (2) Regulatory activities at nuclear power plants units in operation; (2.1) Nuclear power plant SEP-EBO V-1; (4) Selected operation events and safety assessment in NPP SEP-EBO V-1; (2.2) Safety assessment of NPP SEP-EBO V-2; (3) Results of regulatory activities at the decommissioning of NPP A-1; (4) Regulatory activities at units under construction SEP-EMO - NPP Mochovce; (5) Further regulatory activities. (5.1) Preparation of designated personnel; (5.2) Inspection and accountancy of nuclear material; (5.3) Security provisions; (5.4) Accounted items and double use items; (5.5) Problem of radioactive wastes; (6.1) International co-operation activities of NRA; (6.2) Emergency planning; (6.3) International activities for quality enhancement of national supervision; (7) Conclusion [sk

  10. A successful approach for the implementation of symptom-based emergency operating procedures for VVER reactors

    International Nuclear Information System (INIS)

    Lhoest, V.; Prior, R.; Pascal, G.

    2000-01-01

    The paper provides an overview of the organization, the progress and the results of the various Emergence Operating Procedure (EOP) development programs for VVER type reactors conducted by Westinghouse so far. The detailed working process is presented through the solutions to some major plant issues. The EOPs have been developed for the Temelin, Dukovany, Bohunice, Mochovce and Paks VVER nuclear power plants. The procedures are developed in working teams of experts from the utility and Westinghouse. The completion of the programs constitute an indication of the overall success of this approach. This is further reinforced by the general acceptance of the new procedures by the plant personnel, together with the good results obtained so far from procedure testing. This is also confirmed by a new PSA-level 1 analysis for Dukovany plant, which shows a significant improvement in the overall plant safety. This means a 20% reduction in the Core Damage Frequency due to the introduction of the new EOPs. The fact that some modifications have been implemented to the plants to solve design weaknesses identified in the course of this programs also constitute a positive result

  11. VUEZ. Annual report 2005

    International Nuclear Information System (INIS)

    2006-01-01

    A brief account of activities carried out by the Vyskumny ustav energetickych zariadeni, a.s. (VUEZ) in 2005 is presented. These activities are reported under the headings: (1) Introductory address by the Chairman of the Board of Directors; (2) On the company; (3) Basic data; (4) Product portfolio and customer services; (5) Quality management system; (6) Human resources; (7) Economic data; (7) Adving, s.r.o.; (8) Basic data and company management; (9) Line of business; (10) Activities performed in the past year; (11) Economic data; (12) Contact persons and addresses. In 2005, a number of important events took place in VUEZ. On the home market, our main business partner was SE a.s. Company. The key works were performed at SE nuclear power plant sites in Jaslovske Bohunice and Mochovce. A considerable volume of works co-ordinated by our company was executed also for Vodohospodarska vystavba Bratislava at the Gabcikovo Dam. On the foreign market, VUEZ kept on carrying out ongoing projects of preparation for the Jaslovske Bohunice V1 NPP decommissioning in co-operation with a consortium of foreign companies. In the field of experimental research, another project was launched in co-operation with IRSN Paris. As to leak tightness improvement of hermetic compartments and integrated leakage rate tests in nuclear power plants, works were continued in foreign plants such as the Dukovany NPP, Czech Republic, and the Paks NPP, Hungary

  12. Bohunice NPPs - Part of the Slovak's economy (sustainable) development

    International Nuclear Information System (INIS)

    Dobak, Dobroslav

    2001-01-01

    Of the total consumption of electricity in Slovakia, 42% was generated in nuclear power plant units in 1999. Slovakia operates 6 units with a WWER 440 nuclear reactors, 4 of them are at Bohunice site and 2 at Mochovce. The Nuclear Regulatory Authority of SR is not the only regulatory body controlling nuclear activity. Both - the system of nuclear activities regulation in Slovakia as well as the approach to Nuclear Safety enhancement of the operator were positively judged by IAEA and WENRA. In 1993 -Slovakia has accepted the commitments of the UN Convention on Climate Changes, including a reduction of greenhouse gases to 1990 levels by the year 2000. Moreover, as an internal target Slovakia has set the reaching of the ,'Toronto Objective', i.e. 20% reduction in CO x emissions through the year 2005 as compared to 1988. Taking into account the actual situation as well as natural conditions for some renewable sources utilisation, the target won't be reached without nuclear energy. The nuclear energy is free of emissions, does not burn oxygen, and with the share of production in Slovakia will remain significant contributor. To the environment protection it contributes also by replacing fossil heat plants with heat delivery for the region. In case of radiological wastes the environment protection is ensured by very strict system of control, evidence, treatment and repository. To conclude, Bohunice NPPs were, are and will remain very important part of the Slovak's economy, creating conditions for its (sustainable) development

  13. 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

  14. Safety analyses of the electrical systems on VVER NPP

    International Nuclear Information System (INIS)

    Andel, J.

    2004-01-01

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

  15. VVER operational experience - effect of preconditioning and primary water chemistry on radioactivity build-up

    International Nuclear Information System (INIS)

    Zmitko, M.; Kysela, J.; Dudjakova, K.; Martykan, M.; Janesik, J.; Hanus, V.; Marcinsky, P.

    2004-01-01

    The primary coolant technology approaches currently used in VVER units are reviewed and compared with those used in PWR units. Standard and modified water chemistries differing in boron-potassium control are discussed. Preparation of the VVER Primary Water Chemistry Guidelines in the Czech Republic is noted. Operational experience of some VVER units, operated in the Czech Republic and Slovakia, in the field of the primary water chemistry, and radioactivity transport and build-up are presented. In Mochovce and Temelin units, a surface preconditioning (passivation) procedure has been applied during hot functional tests. The main principles of the controlled primary water chemistry applied during the hot functional tests are reviewed and importance of the water chemistry, technological and other relevant parameters is stressed regarding to the quality of the passive layer formed on the primary system surfaces. The first operational experience obtained in the course of beginning of these units operation is presented mainly with respect to the corrosion products coolant and surface activities. Effect of the initial passivation performed during hot functional tests and the primary water chemistry on corrosion products radioactivity level and radiation situation is discussed. (author)

  16. Diagnostic and monitoring systems produced in Vuje, Okruzna 5, 918 64 Trnava, Slovak Republic

    Energy Technology Data Exchange (ETDEWEB)

    Oksa, G; Bahna, J; Murin, V; Kucharek, P; Smutny, S [Vyskumny Ustav Jadrovych Elektrarni, Trnava (Slovakia)

    1997-12-31

    Based on the 20 years experience in on-line vibration diagnostics of mechanical components in the primary circuit of nuclear power plant PWR WWER-440, Vuje, Okruzna 5, 918 64 Trnava produces its own diagnostic and monitoring systems since 1990. The variety of diagnostic systems includes: loose part monitoring system (LPMS), monitoring system of main circulating pumps (MCPMS), vibration monitoring system (LVMS), leakage monitoring system (LMS). The emphasis in the hardware solution is put on the design modularity and versatility so that many subcomponents (circuit boards) are common or highly similar for all systems. Using exclusively digital data for processing enhances the reliability of the measurements and allows the easy data transportation from one computer to another (e.g., for more sophisticated analysis). Trends in the software development follow the similar path as for the hardware solution - namely, the modularity and versatility of software is the imperative goal. The modern operating systems also incorporate the ability of network communication, which is crucial for the integration of stand-alone diagnostic systems into nuclear power plants information system. So far a number of systems have been successfully installed: 6 LPMSs (Jaslovske Bohunice, Dukovany), 4 MCPMs (Jaslovske Bohunice) and 2 LVMSs (Jaslovske Bohunice), all systems operate in PWR WWER-440 environment. Another diagnostic systems are under construction: 2 LPMSs (Temelin, PWR WWER-1000), 2 MCMSs (Mochovce - PWR WWER-440) and 2 LMSs (Jaslovske Bohunice). (author). 1 fig.

  17. VUJE's experience in the field of thermal-hydraulic behaviour of WWER

    International Nuclear Information System (INIS)

    Klepach, J.

    1995-01-01

    The thermal-hydraulic behavior (THB) of NPP coolant system and its consequences to nuclear safety of WWER reactors in previous Czechoslovakia has been studied in the VUJE (Nuclear Power Plants Research Institute, Trnava, SK). The institute takes part in the development and verification of its own (SLAP, LENKA, PUMKO, SICHTA, TRACO etc.) and international (DYNAMIKA5) codes for thermal-hydraulic analysis. The verification efforts are concentrated on the WWER specific features such as horizontal steam generators, control and safety system functioning, etc. The whole range of NPP accident analyses is covered by the VUJe staff. The author outlined briefly the WWER specific features as design and implemented improvements in Bohunice V-1 and Mochovce V-1 (WWER 230 model). The pros and cons of the WWER design compared against western type PWR are described. It is believed that although the WWERs are designed under the rules and standards of 1960s, their safety and operational performance can be improved to acceptable level by thorough analysis and appropriate measures. 5 figs

  18. Separation of radionuclides using host-guest materials

    International Nuclear Information System (INIS)

    Drabova, V.

    2014-01-01

    This thesis is focused on the development of complex procedure with using commercially available sorbents to separate anthropogenic actinides 237 Np, 241 Am, 238 Pu and 239 , 240 Pu and their determination in the liquid radioactive wastes by using alpha spectrometry. Abilities of using commercially available sorbent AnaLig(R)Pu-02 gel from IBC Advanced Technologies, Inc. were tested, this product belongs to host-guest materials based on molecular recognition technology. This material is capable of selectively capturing actinides in oxidation state IV. To adjust the oxidation state of 238 Pu and 239 , 240 Pu was used NaNO 2 . Pu(IV) forms in the medium of nitric acid complexes, [Np(NO 3 ) 6 ] - , which are captured on the column. For the second monitored radionuclide, neptunium is typical valence V, Np(V) in the concentrated nitric acid produces strong complexes, [Np(NO 3 ) 6 ] - , which are capable of the sorption on the column of AnaLig(R)Pu-02 gel. The most common state of americium in aqueous solutions is III. Whereas in this oxidation state, americium do not form complexes in 8 mol·dm -3 nitric acid is the result of the flow-through. On the base of experimental obtained results, solution of 0.1 mol·dm -3 NH 4 I in 9 mol·dm -3 HCl was selected for elution of plutonium. Neptunium was eluted from the column using 9 mol·dm -3 of HCl with addition of 0.5 cm 3 TiCl 3 . Optimizing conditions for the separation procedure was performed by using model solution of radioactive waste which was prepared according to the chemical composition of radioactive concentrate from NPP Mochovce and NPP Bohunice. The effect of the concentration of Fe 3+ , the effect of the concentration of the HCl, the effect of the concentration of the solution of NH 4 I and the effect of the volume of this solution to the yields of 238 Pu were studied. And also was studied the effect of 9 mol·dm -3 of HCl and the effect of volume of 15 % TiCl 3 to the yields of 237 Np. Sorbent DGA(R) Resin from

  19. Statement of participants at the International Conference on Can Slovakia secure energy supply and sustainable development without nuclear?

    International Nuclear Information System (INIS)

    Mikus, T.; Suchomel, J.

    2004-01-01

    The participants at the Conference called on decision makers both in the European Union (EU) and in Slovakia to provide fair treatment to nuclear power compared with other energy sources, especially with renewable, without prejudice to nuclear safety. This implies ensuring equality in terms of economics, tax, and accounting for externalities. The participants called on the Slovak government to initiate studies that compare the full life-cycle costs, impacts and risks, across the spectrum of energy sources and uses. They should also internalize the external costs. The participants called for a debate on the Slovak energy needs, taking into account the environmental impact of all potential sources of energy and the costs of providing electricity from those sources, and in addition a rational and objective analysis of the security of supply of those sources. It is necessary to have a range of sources for electricity generation that are cost effective and reliable, and respect the environment. The Slovak economy cannot withstand a sudden loss of its guaranteed energy supply. The participants believe that the major government role is setting overall policy for the economy, energy and the environment, with an adequate base in legislation and institutional competence. The Slovak government should have clear strategies for achieving self-sufficient energy-policy goals with reserve power and for meeting climate-change and air-quality goals. The Conference concluded that the nuclear option should remain open in Slovakia, as part of a balanced energy mix, in line with developments abroad and the EU Green Paper from 2000; the alternative is Slovak's failure to secure an affordable energy supply for its citizens. The participants supported the completion of Mochovce 3, 4, complying with enhanced safety requirements, as the most effective option. In Slovenske elektrarne, a.s. (SE) privatization, the government should insist on as large an involvement of Slovak firms in the

  20. Atoms in Slovakia

    International Nuclear Information System (INIS)

    Danis, D.; Feik, K.; Florek, M.; Kmosena, J.; Chrapan, J.; Morovic, M.; Slugen, V.; Seliga, M.; Valovic, J.

    2006-01-01

    In this book the history of development of using of nuclear energy in the Slovak Republic as well as in the Czechoslovakia (before 1993 year) is presented. The aim of the book is to preserve the memory of the period when the creation and development of nuclear physics, technology, nuclear medicine, radioecology and energetics in Slovakia occurred - as witnessed by people who experienced this period and to adapt it to future generations. The Editorial board of the SNUS collected the views of 60 contributors and distinguished workers - Slovakian experts in nuclear science, education and technology. Calling upon a wide spectrum of experts ensured an objective historical description of the period. A huge amount of subjective views on recent decades were collected and supported by a wealth of photographic documentation. This created a synthesised reflection on the history of the 'atoms' in Slovakia. The book contains 15 tables, 192 black and white and 119 colour pictures from around the world and from places involved in the compilation of the study and with the study of atomic science in Slovakia. The main chapters are as follows: Atoms in the world, Atoms in Slovakia, Atoms in the educational system, Atoms in health services (Radiology, Nuclear medicine, Radiation protection, the Cyclotron centre of the Slovak Republic), Radioecology, Other applications of irradiation, Nuclear energetics (Electric energy in the second half of the 20 th century, NPP Bohunice, NPP Mochovce, the back-end of Nuclear energetics, Big names in Nuclear energetics in Slovakia), Chronology and an Appendix entitled 'Slovak companies in nuclear energetics'

  1. Monopolist requires totally liberalization

    International Nuclear Information System (INIS)

    Janoska, J.

    2003-01-01

    Slovenske elektrarne (SE), a.s, Bratislava in present time operates some sources, which would be off at normal conditions. It was caused by high electricity price on European markets. It is possible to sell 1 MWh for 12 thousands Slovak crowns abroad in last months. It is also advantageous to initialise thermal sources for power plant, where variable expenses are higher - from 1200 to 1300 Slovak crowns per MWh. SE are mainly trying to sell most of electricity on domestic market because returnability of dominant nuclear power plants was projected for this market. Utilizing capacities profit via domestic market covers fixed costs of power plants. Besides, power plant can demand regulated price 1272 Slovak crowns per 1 MWh. SE sources have capacity of 6800 MW, but maximal daily load uses for example in December approximately 4000 MW. Overflows are more higher in the summer - load dropped to 2200 MW in the beginning of September in last year. It is noted in issue that price increase in Europe is noticed. Price of primary power electricity will remain at liquid markets at 28 Euro (1176 Slovak crowns) in the following year prices fluctuate from 38 to 40 Euro (to 1700 Slovak crowns) per 1 MW at load peaks. Price increase is caused by lack of sources - it does not keep up to satisfy demand increase. Sources are gradually laid up and no new sources are built. Production capacities will decrease also in SE - by laying up of two 440 MW blocks of Bohunice NPP V-1. Price increase trend will continue according to SE businessmen till it is advantageous to build new source. Present price trend can be accelerated by decision about completing of Mochovce NPP 3-4

  2. VUJE experience with cementation of liquid and wet radioactive waste

    International Nuclear Information System (INIS)

    Kravarik, Kamil; Holicka, Zuzana; Pekar, Anton; Zatkulak, Milan

    2011-01-01

    Liquid and wet LLW generated during operation as well as decommissioning of NPPs is treated with different methods and fixed in a suitable fixation matrix so that a final product meets required criteria for its disposal in a final repository. Cementation is an important process used for fixation of liquid and wet radioactive waste such as concentrate, spent resins and sludge. Active cement grout is also used for fixation of low level solid radioactive waste loaded in final packing containers. VUJE Inc. has been engaged in research of cementation for long. The laboratory for analyzing radioactive waste properties, prescription of cementation formulation and estimation of final cement product properties has been established. Experimental, semi-production cementation plant has been built to optimize operation parameters of cementation. VUJE experience with cementation of liquid and wet LLW is described in the presented paper. VUJE has assisted in commissioning of Jaslovske Bohunice Treatment Centre. Cement formulations for treatment of concentrate, spent resins and sludge have been developed. Research studies on the stability of a final concrete packaging container for disposal in repository have been performed. Gained experience has been further utilized for design and manufacture of several cementation plants for treatment of various liquid and wet LLW. Their main technological and technical parameters as well as characterization of treated waste are described in the paper. Applications include the Mochovce Final Treatment Centre, Movable Cementation Facility utilizing in-drum mixing for treatment of sludge, Cementation Facility for treatment of tritiated water in Latvia and Cementation Facility for fixation of liquid and solid institutional radioactive waste in Bulgaria, which utilizes lost stirrer mixer. (author)

  3. Seismicity as dynamic load of pipes and fittings

    International Nuclear Information System (INIS)

    Rejent, B.

    1984-01-01

    The load is discussed of pipe systems and fittings for nuclear power plants which may result from earthquakes, etc. Modifications of the equation of motion are discussed which may be solved using the response spectrum method or the method of direct numerical integration. A mathematical description of both methods is given. The seismic resistance of fittings, pumps, etc., is experimentally determined by loking for their eigenfrequencies and monitoring the response of equipment to resonance oscillations. The principle is described of uniaxial hydraulic and mechanical shock absorbers and a viscous damper. The presented computation method was used for evaluating the primary circuit (Sigma Modrany) and rods for the remote control of fittings (Sigma Hodonin) supplied for the Mochovce nuclear power plant. Variants were compared of seismic protection of the primary circuit by hydraulic and mechanical shock absorbers with viscous dampers and of circuits without any protection. The unprotected system oscillates in the first harmonic, the system with shock absorbers keeps the deflections within the range of the shock absorber function (to 2 mm), and the system using viscous dampers oscillates approximately according to the first waveform with a deflection of around 11 mm. A diagram and a dynamic model are presented of a rod for the remote control of fittings. Figure shows the computation model and the response of this rod in individual time moments, both affected and not affected by play in the dilatation joint. Table shows the effect of play in the dilatation joint on deformation maxima and on rod bend stress from a symmetric load of 8g. (E.S.)

  4. What were we like in 2008

    International Nuclear Information System (INIS)

    Hroch, A.

    2009-01-01

    Slovenske elektrarne, a. s. (SE) entered the year 2008 with a determination to achieve the best possible profit from power production. During the process of production optimization were taken into account external conditions, which were mentioned in the last issue. The result is SE supply reaching 22 251 GWh. Very satisfactory for us is the fact that high fulfillments by nuclear power plants have exceeded the expectations. Bohunice V1 NPP up to 103%, Bohunice V2 NPP up to 104,5% and Mochovce NPP up to 102, 9%. Nonfulfillment of hydroelectric and thermal power plants is a result of objective reasons- as for thermal power plants due to market conditions and in case of hydroelectric power plants this has been a result of hydrological reasons. Just a few words to a crisis that appeared in January 2009. When we look back, we have to divide the issue into two periods (crises). The first one is an economic crisis the consequences of which were apparent already in December, where the providers of supporting services among industrial customers were unable to guarantee those services (the service is activated by reduction of consumption and since then there was no sale of their products, they cut off their production, i.e. power production, and as a consequence, no reserve for Ss remained.) Missing supporting services have been purchased by a transmission system provider on both daily and monthly basis. There was a demand for SRV, TRV30MIN, + TRV3MIN+, however, there were no extreme values. (author)

  5. Fast and effective determination of strontium-90 in high volumes water samples

    International Nuclear Information System (INIS)

    Basarabova, B.; Dulanska, S.

    2014-01-01

    A simple and fast method was developed for determination of 90 Sr in high volumes of water samples from vicinity of nuclear power facilities. Samples were taken from the environment near Nuclear Power Plants in Jaslovske Bohunice and Mochovce in Slovakia. For determination of 90 Sr was used solid phase extraction using commercial sorbent Analig R Sr-01 from company IBC Advanced Technologies, Inc.. Determination of 90 Sr was performed with dilute solution of HNO 3 (1.5-2 M) and also tested in base medium with NaOH. For elution of 90 Sr was used eluent EDTA with pH in range 8-9. To achieve fast determination, automation was applied, which brings significant reduction of separation time. Concentration of water samples with evaporation was not necessary. Separation was performed immediately after filtration of analyzed samples. The aim of this study was development of less expensive, time unlimited and energy saving method for determination of 90 Sr in comparison with conventional methods. Separation time for fast-flow with volume of 10 dm 3 of water samples was 3.5 hours (flow-rate approximately 3.2 dm 3 / 1 hour). Radiochemical strontium yield was traced by using radionuclide 85 Sr. Samples were measured with HPGe detector (High-purity Germanium detector) at energy E φ = 514 keV. By using Analig R Sr-01 yields in range 72 - 96 % were achieved. Separation based on solid phase extraction using Analig R Sr-01 employing utilization of automation offers new, fast and effective method for determination of 90 Sr in water matrix. After ingrowth of yttrium samples were measured by Liquid Scintillation Spectrometer Packard Tricarb 2900 TR with software Quanta Smart. (authors)

  6. Stress Tests and Vulnerability Assessment

    International Nuclear Information System (INIS)

    Wallner, A.; Lorenz, P.

    2012-01-01

    After the accident in Fukushima, nuclear safety as topic in anti-nuclear work has gained importance within the Joint Project countries. Therefore, nuclear safety and in particular the activities of the European stress tests were chosen to be the main focus of the Joint Project 2011/2012 as well as the common theme of the national projects. This brochure describes: A) Vulnerability Assessment A critical review of the EU Nuclear Stress Tests in Bulgaria, Hungary, Romania and Ukraine is presented in chapter 1. The review details the main weaknesses identified within the stress tests. Important shortcomings not mentioned in the stress tests reports are also discussed. These evaluations do not claim to be exhaustive, but the findings contribute to a more comprehensive understanding of safety and risk of nuclear power plants in Europe. B) Transparency of the stress tests In chapter 2 the experience of the Joint Project NGOs concerning transparency of the stress tests is presented. The information is not meant to be an evaluation of the transparency of the stress tests in general – such an evaluation is not possible within the scope of this brochure. The evaluation aims to show activities concerning stress tests and how they were conceived by the JP NGOs. Some recommendations for improvement are given. C) Safety focus Within the main topic “nuclear safety” of the Joint Project 2011/2012 the NGOs of each JP country selected a special safety relevant topic, which is/was of particular interest in their country: Bulgaria: The short story of Belene NPP – The victory – Key points of the campaign against the nuclear power plant Romania: Risks of the CANDU reactor design Czech Republic: Results of the conference “Power Plant Load Testing: Safety Inspection or Propaganda?“ Slovakia: Safety deficits of the NPP Mochovce These safety relevant issues are discussed in separate sections within the brochure at hand. (author)

  7. Structural seismic upgrading of NPPs in Czech and Slovak republics

    Energy Technology Data Exchange (ETDEWEB)

    David, M [DAVID Consulting, Engineering and Design Office, Prague (Czech Republic)

    1997-03-01

    Several Nuclear Power Plants of the VVER type has been constructed during the past years in former Czechoslovak Republic. Some of them has been already put in operation and some of them are under construction. Nuclear Power Plants V1(2 units of VVER 440/230), V2(2 units of VVER 440/213) in Slovak and NPP Dukovany (4 units of VVER 440/213) in Czech republic are in operation. NPP Mochovce (4 units of VVER 440/213) in Slovak and NPP Temelin (4 units reduced now to 2 units VVER 1000) have been already almost completed, but still under construction. All above cited NPPs have not been either explicitly designed against earthquake or the design against earthquake or its input data must be upgraded to be compatible with present requirements. The upgrading of seismic input as well the seismic upgrading of all structures and technological equipments for so many NPPs has involved a lot of comprehensive work in Czech as well as in Slovak republics. The upgrading cannot be completed in a short time and as a rule the seismic upgrading has been usually performed in several steps, beginning with the most important arrangements against seismic hazard. The basic principles and requirements for seismic upgrading has been defined in accordance with the international and particularly with the IAEA recommendations. About the requirements for seismic upgrading of NPPs in Czech and Slovak republics will be reported in other contribution. This contribution is dealing with the problems of seismic upgrading of NNPs civil engineering structures. The aim of this contribution is to point out some specific problems connected firstly with very complicated concept of Versa structures and secondly with the difficult task to increase the structural capacity to the required seismic level. (J.P.N.)

  8. Status and development of deep geological repository in Slovak republic from geological point of view

    Directory of Open Access Journals (Sweden)

    Jozef Franzen

    2007-01-01

    Full Text Available During the operation of Slovak NPPs, production of approximately 2,300 metric tons of spent fuel expressed as heavy metal (18,654 spent fuel assemblies is expected. In addition, about 5000 metric tons of radioactive waste unfit for near surface repository at Mochovce and destined for a deep geological disposal. The safe and long-term solution of back-end fuel cycle is so highly required.One of the most favorable solutions is Deep Geological Repository (DGR. The site for a DGR, along with repository design and the engineered barrier system must ensure long-term safety of the disposal system.A preliminary set of site-selection criteria for a DGR was proposed in Slovakia, based on worldwide experience and consistent with IAEA recommendations. Main groups of criteria are: 1 geological and tectonic stability of prospective sites; 2 appropriate characteristics of host rock (lithological homogeneity, suitable hydrogeological and geochemical conditions, favourable geotechnical setting, absence of mineral resources, etc.; 3 conflict of interests (natural resources, natural and cultural heritage, protected resources of thermal waters, etc..Based on the previous geological investigations, three distinct areas (five localities were determined as the most prospective sites for construction of a DGR so far. Three of them are built by granitoids rock (Tribeč Mts., Veporske vrchy Mts. and Stolicke vrchy Mts., other consist of sedimentary rock formations (Cerova vrchovina Upland and Rimavska kotlina Basin. Objective for the next investigation stage is to perform more detailed geological characterization of the prospective sites.

  9. VUEZ. Annual report 2003

    International Nuclear Information System (INIS)

    2005-01-01

    A brief account of activities carried out by the Vyskumny ustav energetickych zariadeni, a.s. (VUEZ) in 2003 is presented. These activities are reported under the headings: (1) Introductory address by the Chairman of the Board of Directors; (2) Mission and vision; (3) Basic data; (4) Product portfolio and customer services; (5) VUEZ - Quality mark; (6) Economic data; (7) Auditor's certificate; (8) Contact persons and addresses. In 2003, a number of important events took place in VUEZ. From the standpoint of international activities, a significant event was VUEZ involvement in the process or the preparation for the V-1 NPP decommissioning. VUEZ company became a subcontractor to the Consultant to the Project Management Unit who is an international Consortium consisting of Iberdrola Ingenieria Y Consultoria S.A., Electricite de France, Empresarios Agrupados Intemacional S.A. and Soluziona Ingenierfa S.A. In the field of experimental research, activities within the research and development project with IRSN Paris were successfully continuing. As to increasing the leak-tightness of NPP hermetic compartments, relevant works were executed at the Dukovany and Paks NPPs. For a business partner from Hungary, a project was initiated related to the manufacture and delivery of air locks. Predominant VUEZ capacities concentrated on Slovenske elektrarne, a.s. (SE) a.s. Company in the Jaslovske Bohunice and Mochovce sites. In addition to major sealing works and periodical integrated leakage rate tests at individual reactor units, VUEZ participated also in the upgrading of the V-2 NPP. Design work was implemented through ADVING, a daughter company of VUEZ; erection and installation works within the project were performed by relevant VUEZ departments during refuelling outages at the V-2 NPP

  10. VUEZ. Annual report 2006

    International Nuclear Information System (INIS)

    2007-01-01

    A brief account of activities carried out by the Vyskumny ustav energetickych zariadeni, a.s. (VUEZ) in 2006 is presented. These activities are reported under the headings: (1) Introductory address by the Chairman of the Board of Directors; (2) Company profile; (3) Organisational structure; (4) Portfolio of products and services in 2006; (5) Quality management system; (6) Human resources; (7) Financial statements and auditor's report; (8) Auditor's certificate; (9) Basic and contact data. The year 2006 was a year of changes in the Slovak energy sector what, in a certain degree, became evident also in the related sphere of supplies. In the course of the year, Slovenske elektrarne a.s. Company was divided into two entities and its proprietary structure was changed. At the same time, the number of capital investment projects was reduced and the related procedure of procurement was changed. VUEZ, as a supplier to the energy sector, had to promptly respond to the changes. That was why in the first half of 2006, the organisational structure of VUEZ was modified. In the course of the year, also the structure of customers on the domestic market was partly changed. To stable partners such as Slovenske elektrarne (and its successors after the company splitting), another important partner was added - Vodohospodarska vystavba s.p. Bratislava. As to Slovenske elektrarne, our supplies were oriented mainly on nuclear reactor units in the Jaslovske Bohunice and Mochovce NPPs. At the end of the year, a joint convention was agreed and concluded on application of the results of the joint research at third parties. In the preparation for the decommissioning of the Jaslovske Bohunice V1 NPP, VUEZ continued its participation in on-going projects of an international consortium of companies. Similarly important were the customers such as CEZ a.s., Czech Republic (in particular its Dukovany NPP), and the Paks NPP (Hungary)

  11. Review of decommissioning, spent fuel and radwaste management in Slovakia

    International Nuclear Information System (INIS)

    Jamrich, J.

    2000-01-01

    Two nuclear power plants with two WWER reactors are currently under operation in Jaslovske Bohunice and NPP A-1 is under decommissioning on the same site. At the second nuclear site in the Slovak Republic in Mochovce third nuclear power plant with two units is in operation. In accordance with the basic Slovak legislation (Act on Peaceful Utilisation of Nuclear Energy) defining the responsibilities, roles and authorities for all organisations involved in the decommissioning of nuclear installations Nuclear Regulatory Authority requires submission of conceptual decommissioning plans by the licensee. The term 'decommissioning' is used to describe the set of actions to be taken at the end of the useful life of a facility, in order to retire the facility from service while, simultaneously, ensuring proper protection of the workers, the general public and the environment. This set of activities is in principle comprised of planning and organisation of decommissioning inclusive strategy development, post-operational activities, implementation of decommissioning (physical and radiological characterisation, decontamination, dismantling and demolition, waste and spent fuel management), radiological, aspects, completion of decommissioning as well as ensuring of funding for these activities. Responsibility for nuclear installations decommissioning, radwaste and spent fuel, management in Slovakia is with a subsidiary of Slovak Electric called Nuclear Installations Decommissioning Radwaste and Spent Fuel Management (acronym SE VYZ), established on January 1, 1996. This paper provides description of an approach to planning of the NPP A-1 and NPPs with WWER reactors decommissioning, realisation of treatment, conditioning and disposal of radwaste, as well as spent fuel management in Slovakia. It takes into account that detail papers on all these issues will follow later during this meeting. (author)

  12. Structural seismic upgrading of NPPs in Czech and Slovak republics

    International Nuclear Information System (INIS)

    David, M.

    1997-01-01

    Several Nuclear Power Plants of the VVER type has been constructed during the past years in former Czechoslovak Republic. Some of them has been already put in operation and some of them are under construction. Nuclear Power Plants V1(2 units of VVER 440/230), V2(2 units of VVER 440/213) in Slovak and NPP Dukovany (4 units of VVER 440/213) in Czech republic are in operation. NPP Mochovce (4 units of VVER 440/213) in Slovak and NPP Temelin (4 units reduced now to 2 units VVER 1000) have been already almost completed, but still under construction. All above cited NPPs have not been either explicitly designed against earthquake or the design against earthquake or its input data must be upgraded to be compatible with present requirements. The upgrading of seismic input as well the seismic upgrading of all structures and technological equipments for so many NPPs has involved a lot of comprehensive work in Czech as well as in Slovak republics. The upgrading cannot be completed in a short time and as a rule the seismic upgrading has been usually performed in several steps, beginning with the most important arrangements against seismic hazard. The basic principles and requirements for seismic upgrading has been defined in accordance with the international and particularly with the IAEA recommendations. About the requirements for seismic upgrading of NPPs in Czech and Slovak republics will be reported in other contribution. This contribution is dealing with the problems of seismic upgrading of NNPs civil engineering structures. The aim of this contribution is to point out some specific problems connected firstly with very complicated concept of Versa structures and secondly with the difficult task to increase the structural capacity to the required seismic level. (J.P.N.)

  13. Stress Tests and Vulnerability Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Wallner, A. [Austrian Institute of Ecology, Vienna (Austria); Lorenz, P. [ed.; Becker, O. [eds.; Weber, U. [Austrian Institute of Ecology, Vienna (Austria)

    2012-07-01

    After the accident in Fukushima, nuclear safety as topic in anti-nuclear work has gained importance within the Joint Project countries. Therefore, nuclear safety and in particular the activities of the European stress tests were chosen to be the main focus of the Joint Project 2011/2012 as well as the common theme of the national projects. This brochure describes: A) Vulnerability Assessment A critical review of the EU Nuclear Stress Tests in Bulgaria, Hungary, Romania and Ukraine is presented in chapter 1. The review details the main weaknesses identified within the stress tests. Important shortcomings not mentioned in the stress tests reports are also discussed. These evaluations do not claim to be exhaustive, but the findings contribute to a more comprehensive understanding of safety and risk of nuclear power plants in Europe. B) Transparency of the stress tests In chapter 2 the experience of the Joint Project NGOs concerning transparency of the stress tests is presented. The information is not meant to be an evaluation of the transparency of the stress tests in general – such an evaluation is not possible within the scope of this brochure. The evaluation aims to show activities concerning stress tests and how they were conceived by the JP NGOs. Some recommendations for improvement are given. C) Safety focus Within the main topic “nuclear safety” of the Joint Project 2011/2012 the NGOs of each JP country selected a special safety relevant topic, which is/was of particular interest in their country: Bulgaria: The short story of Belene NPP – The victory – Key points of the campaign against the nuclear power plant Romania: Risks of the CANDU reactor design Czech Republic: Results of the conference “Power Plant Load Testing: Safety Inspection or Propaganda?“ Slovakia: Safety deficits of the NPP Mochovce These safety relevant issues are discussed in separate sections within the brochure at hand. (author)

  14. Case law

    International Nuclear Information System (INIS)

    2015-01-01

    This section treats of the following case laws: 1 - Canada: Decision of the Canadian Federal Court of Appeal overturning a decision to send back for reconsideration an environmental assessment of a proposed new nuclear power plant in Ontario; 2 - France: Council of State decision, 28 November 2014, Federation 'Reseau sortir du nucleaire' (Nuclear Phase-Out network) and others vs. Electricite de France (EDF), Request No. 367013 for the annulment of: - The resolution of the French Nuclear Safety Authority (ASN) dated 4 July 2011 specifying additional regulations for Electricite de France (EDF) designed to strengthen the reactor basemat of reactor No. 1 in the Fessenheim nuclear power plant, and - The resolution of ASN dated 19 December 2012 approving the start of work on reinforcing the reactor basemat in accordance with the dossier submitted by EDF; 3 - Germany: Judgment of the European Court of Justice on the nuclear fuel tax; 4 - India: Judgment of the High Court of Kerala in a public interest litigation challenging the constitutional validity of the Civil Liability for Nuclear Damage Act, 2010; 5 - Japan - District court decisions on lawsuits related to the restart of Sendai NPP and Takahama NPP; 6 - Poland: Decision of the Masovian Voivod concerning the legality of the resolution on holding a local referendum in the Commune of Rozan regarding a new radioactive waste repository; Certain provisions of the Regulation of the Minister of Health of 18 February 2011 on the conditions for safe use of ionising radiation for all types of medical exposure have been declared unconstitutional by a judgment pronounced by the Constitutional Tribunal; 7 - Slovak Republic: Developments in relation to the disclosure of information concerning the Mochovce nuclear power plant

  15. News of the world

    International Nuclear Information System (INIS)

    Anon.

    2008-01-01

    Areva will supply 9 steam generators that will replace equipment on EDF's 900 Mw power plants, they will be delivered in 2012, 2014 and 2015. IAEA inspectors have visited the Kozloduy plant in Bulgaria to check that the unit compels well with European standards after upgrading works that were performed from 2002 to 2007. The main electricity producer of Slovakia has announced the beginning of the construction of the units 3 and 4 of the Mochovce plant. The construction of the 2 units whose cost is 2.7*10 9 euros will end in 2013. The Algerian authorities have announced that a nuclear plant will be built within 10 years and that uranium mining will be developed. Algeria's uranium resource has been assessed to reach 30.000 tonnes. South-african's authorities have cancelled its ambitious program for the construction of nuclear power plants (this program was estimated to 12*10 9 dollars). India and Russia have signed a deal for the construction of 4 reactors in the south of India, 4 more reactors are planned to be built on the Kudankulam site that is already equipped with Russian technology. Venezuela and Russia have signed a broad cooperation agreement concerning nuclear activities that includes the construction of research and power reactors, the production of radionuclides and their applications, and the working of uranium and thorium mines. The European Union favours the creation of a nuclear fuel bank whose role would be to supply every asking country with fuels designed only for civil uses. In France a few tens of towns (among about 3300 selected on geological grounds) are candidate to house a low-level radioactive wastes storage center. (A.C.)

  16. Application of discontinuity factors in C-PORCA 7 code

    International Nuclear Information System (INIS)

    Pos, I.; Parko, T.; Szabo, S. P.

    2010-01-01

    During last years there were up-rated the reactor power up to 1485 MW and new fuel types have been utilised at the Paks NPP. To fulfil the demand of the accuracy and correctness of on-line core monitoring and off-line core analysis the HELIOS/C-PORCA models have been modernised as well. The main step of this developing process was to change the mathematics of the 3D two group diffusion model on the basis of hybrid finite element method. The upgraded mathematics gave very good results comparing the C-PORCA calculations against mathematical benchmarks and measurements of different units and cycles of NPP Paks and Mochovce. As a final step of the modernisation process the application of flux discontinuity factors has been made. In the frame of VVER community the usage of this parameter in core analyses codes is very unusual in contrast with codes for the same purpose in western countries. In this paper both the reason of the introduction of discontinuity factors into HELIOS/C-PORCA models and its effect on the accuracy of calculation are also presented. We tried to emphasise which kind of codes and which kind of reactor-physical parameters can be influenced mainly by discontinuity factors. The method of the calculation of flux discontinuity factors in fuel and non-fuel regions of the core is also described. As the most important effect of the utilisation of this parameter was that almost all fittings in C-PORCA code based on in-core measurements have became needless. (Authors)

  17. Nuclear power: Europe report

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    Last year, 1999, nuclear power plants were available for energy supply, respectively, in 18 countries all over Europe. In eight of the fifteen member countries of the European Union nuclear power plants have been in operation. A total of 218 plants with an aggregate net capacity of 181,120 MWe and an aggregate gross capacity of 171,802 MWe were in operation. Two units, i.e. Civaux 2 in France and Mochovce-2 in Slovakia went critical for the first time and started commercial operation after having been connected to the grid. Three further units in France, Chooz 1 and 2 and Civaux 1, started commercial operation in 1999 after the completion of technical measures in the primary circuit. Last year, 13 plants were under construction in Romania, Russia, Slovakia and the Czech Republic, that is only in East European countries. In eight countries of the European Union 146 nuclear power plants have been operated with an aggregate gross capacity of 129.772 MWe and an aggregate net capacity of 123.668 MWe. Net electricity production in 1999 in the EU amounts to approx. 840.2 TWh, which means a share of 35 per cent of the total production. Shares of nuclear power differ widely among the operator countries. They reach 75 per cent in France, 73 per cent in Lithuania, 58 per cent in Belgium and 47 per cent in Bulgaria, Sweden and Slovakia. Nuclear power also provides a noticeable share in the electricity supply of countries, which operate no own nuclear power plants, e.g. Italy, Portugal and Austria. (orig.) [de

  18. Chapter No.3. Assessment and inspection of nuclear installations

    International Nuclear Information System (INIS)

    2002-01-01

    The assessment activity of UJD in relation to nuclear installation lies in assessment of safety documentation for constructions realised as nuclear installations, or construction through which changes on nuclear installations are realised. The assessment activity of UJD in 2001 was focused on National Repository of Radwaste in Mochovce, on Radwaste conditioning and treatment technology in Jaslovske Bohunice and on the assessment of documentation for the project of modernisation of Bohunice V-2 NPPs which is under preparation. The assessment of the technical condition of equipment, important in terms of nuclear safety, primarily based on results of in-service inspections and surveillance testing of safety related components and systems, is also a part of the safety assessment of nuclear installation operation. The inspectors take part in training courses and participate in other technical meetings and workshops organised by the IAEA and also take part in special training courses organised by the Nuclear Authorities of European countries, USA and Japan. Bohunice V-1 NPP is equipped with two reactors of WWER 440 type V-230 and was put into operation in 1978-1980 as one of the last nuclear power plants with this type of reactor. Both units of NPP V-1 Bohunice operated in 2001 according to the requirements of energy dispatching at nominal power, or in a regime of tertiary regulation. November 2000, a mission of experts invited by UJD and delegated by IAEA took place at the Bohunice NPPs. The mission members together with experts of the plant operator assessed the safety of the units of WWER-440/V-230 of Bohunice V-1 NPP after the reconstruction. The members of the mission prepared the report on the current status of safety of these units for the IAEA. In 2001, UJD by its decision, issued the approval for further operation of both reactor units of Bohunice V-1 NPP. In sense of the relevant decree on operational events, 20 events have been recorded, at Bohunice V-1 NPP in

  19. Chapter No.9. Emergency planning

    International Nuclear Information System (INIS)

    2002-01-01

    Emergency preparedness is a set of measures the aim of which is to mitigate possible impacts of events during the operation of nuclear facilities, transport of nuclear materials and radioactive waste as well as to reduce consequences to environment and population. An emergency planning of UJD is understood as an establishment of technical and organisational means determined for prognosis of development of events having radiation consequences together with capability to suggest the countermeasures needed to minimise the impact to population. Emergency Response Centre (ERC) of UJD is a technical support tool of UJD and at the same time it fulfils the role of advisory body for the National Emergency Commission for Radiation Accidents (NECRA) In 2001 UJD continued in further increase of equipment quality in the ERC by completion of facilities necessary to transmit necessary data from nuclear facilities, for communication and other HW and SW means. That it is why the application of geographic information systems (GIS), higher quality of data transmission from nuclear facilities and installation of new database platform could be enabled. Also the documentation of ERC has been completed by the emergency procedures of NPP Mochovce and guides of the RODOS system were finished. In the area of emergency preparedness UJD activities in 2001 were focused on preparation and realisation of emergency exercises and execution of inspections. In accordance with the inspection plan inspectors executed several inspections which were targeted to control the course of exercises at nuclear facilities, documentation and the way of training of members of the UJD headquarters. The function of systems of notification and warning, communication, monitoring and technical support means of both NPP Bohunice and NPP Mochovce has been verified and checked as well. The ultimate attention, however, was paid to the preparation of UJD emergency headquarters. The preparation was realised in a form of

  20. Chapter 4. Assessment and inspection of nuclear installations

    International Nuclear Information System (INIS)

    2001-01-01

    Supervisory activity of Nuclear Regulatory Authority of the Slovak Republic (UJD) upon the safety of nuclear installations in compliance with the 'Atomic Act' and other legal regulations includes also inspection and assessment activities of UJD. Assessment activity of UJD in relation to nuclear installations lies in assessment of safety documentation for constructions realised as nuclear installations, or constructions through which changes are realised on nuclear installations. The scope of safety documentation required for the assessment is stipulated in the Atomic Act. In 2000 the assessment activity focused first of all on Unit 1 of NPP Bohunice after completing its Gradual Reconstruction Programme, on National Repository of Radioactive waste in Mochovce and on radioactive waste conditioning and treatment technology in Jaslovske Bohunice. Activities of UJD in assessment focused mainly on control of compliance with requirements for nuclear safety, assessment of commissioning programmes, operating procedures, limits and conditions, etc. The assessment of changes, which influence nuclear safety of nuclear installations in operation, realisation of which is conditioned by the approval from UJD, is a significant part of the assessment activity of UJD. Mainly it is the assessment of design changes, changes in limits and conditions, operating procedures, changes in programmes of periodical testing of equipment important in terms of nuclear safety, changes in physical protection of nuclear equipment, etc. The assessment of nuclear installations operational safety, based on assessment of operational events, on maintaining limits and conditions of safe operation, on operational safety performance indicators and on inspection results is a separate category in the assessment activity of UJD. Inspection activity specified in the 'Atomic Act' is governed by an internal guideline, an important part of which is an annual inspection plan that considers the following types of

  1. Proposed approach to derivation of acceptance criteria for disposal of disused sealed sources mixed with other accepted wastes in near-surface repository

    International Nuclear Information System (INIS)

    Salzer, P.; Stefula, V.; Homola, J.

    2003-01-01

    The Mochovce repository is described in the report. It is vault type near surface repository with 80 concrete vaults (2x2x20), 90 FRC containers (3.1 m 3 ) in one vault (3x10x3), compacted clay bath-tub around double row. 300 years of institutional control are envisioned.The following scenarios are examined: Normal evolution scenario; Alternative evolution scenarios (perforated clay barrier; well in close proximity); Intruder scenarios (construction of simple dwelling; construction of multi-storey building; construction of road; residence scenario). It is being proposed that the DSSs are disposed of in the containers together with normal operational waste. Long-lived alpha emitters - excluded a priori (e.g. 226 Ra); Short-lived (T 1/2 = 10 2 days) radionuclides - interim stored until decayed down to clearance level 60 Co - no activity limit, with due consideration of operational safety. The DSSs disposal issue is thus reduced to the disposal of 137 Cs. No limit has been imposed on total activity. Existing limits for operational waste: 3.13.10 13 Bq / container in the upper layer; 3.41.10 13 Bq / container in the bottom or intermediate layer. The acceptance criteria are assessed according to the risk. Two are models set up in MicroShield ver. 5.0. Homogenous source of 137 Cs in cubic concrete container and point source (hot spot) of the same activity. The result is - dose from the point source is 16.6 times higher than the one from the cube. As a result the following new restrictions arise for disposal of the 137 Cs spent industrial sources: disposal of DSSs is forbidden in the upper layer of the containers; maximum activity of the 137 Cs disused industrial source emplaced into the FRC container is 3.41x10 13 / 16.6 = 2.05x10 12 Bq in case of FRC filling by non-radioactive cement mortar; if the cemented radioactive waste is to be used for filling of FRC, decrease of the limit for the disused sealed source is equivalent to the radioactivity of the cement mixture

  2. Severe accident management development program for VVER-1000 and VVER-440/213 based on the westinghouse owners group approach

    International Nuclear Information System (INIS)

    Felix, E.; Dessars, N.

    2003-01-01

    The development of the Westinghouse Owners Group Severe Accident Management Guidelines (WOG SAMG) between 1991 and 1994 was initiated in response to the U.S. Nuclear Regulatory Commission (NRC) requirement for addressing the regulatory severe accident concerns. Hence, the WOG SAMG is designed to interface with other existing procedures at the plant and is used in accident sequences that have progressed to the point where these other procedures are not applicable any longer, i.e. following core damage. The primary purpose of the WOG SAMG is to reach a controlled stable state, which can be declared when fission product releases are controlled, challenges to the confinement fission product boundary have been mitigated, and adequate heat removal is provided to the core and the containment. Although the WOG SAMG is a generic severe accident management guidance developed for use by the entirety of the operating Westinghouse PWR plants, provisions have been made in their development to address specific features of individual plants such as confinement type and the feasibility of reactor cavity flooding. Similarly, the generic SAMG does not address unique plant features and equipment, but rather allows for consideration of plant specific features and strategies. This adaptable approach has led to several SAMG development programs for VVER-1000 and VVER-440 type of power plants, under Westinghouse' s lead. The first of these programs carried out to completion was for Temelin NPP - VVER-1000 - in the first quarter of 2003. Other ongoing programs aim at providing a similar work for VVER-440 design, namely Dukovany, Mochovce and Bohunice NPPs. The challenge of adapting the existing generic WOG material to plants other than PWRs mainly arises for VVER-440 because of important differences in confinement design, making it more vulnerable to ex-vessel phenomena such as hydrogen burn. Also, for both eastern designs, cavity flooding strategy requires special consideration and

  3. Radiological characterisation of V1 NPP technological systems and buildings - Activation

    International Nuclear Information System (INIS)

    Kristofova, Kristina; Rapant, Tibor; Svitek, Jaroslav

    2012-01-01

    from all activated components. Subsequently gamma spectrometry and hard-to-detect analyses have been applied. As a result, detailed radionuclide vectors for all activated components in accordance with requirements for near surface repository at Mochovce site have been determined. Based on radionuclide vectors, the radiological inventory including all radiological parameters for all activated components has been determined. Finally, obtained unique data on activated components, representing in total 1118 DDB items, have been imported into database developed within B6.4 project. (authors)

  4. Emergency preparedness

    International Nuclear Information System (INIS)

    1998-01-01

    According the conception of the Emergency Response Centre (ERC) of the Nuclear Regulatory Authority of the Slovak Republic (NRA), and the obtained experience from exercises, and as well as on the basis of recommendations of international missions, the NRA SR started, in 1997 the ERC extension. The new room enable the work for radiation protection group, reactor safety and logistic group separately. At the same time special room was build for work of the NECRA Technical Support Group of the Emergency Commission for Radiation Accidents of the SR.This group co-operates closely with ERC while evaluation the situation, and by using the information system of the NRA and database of ERC to generate the conditions of nuclear facilities in once of emergency. Extension of the mentioned rooms was carried out. The financing by the European Union helped to build the project RAMG. In this way the NRA gained a working site which, with its equipment and parameters belongs to the top working sites of regulatory bodies of developed European countries. The NRA preparation of exercise and special staff education was carried out in 1997, for employees of the NRA and members of Emergency Headquarters (EH) for work in ERC in case of nuclear installation accident. The task of education of member of EH was their preparation for carrying out three exercises. These exercises are described. In the area of emergency preparedness, in accordance with inspection plan of the Office, 7 team inspections were carried out in individual localities; in NPP Bohunice, two in NPP Mochovce and one in Bohunice Conditioning Centre for radioactive wastes. Solution of the task of development of science and technology in the area of 'Development of technical and programme means for analyses of accidents and solutions of crisis situations'continued in 1997. Another regulations were elaborated for activity of members of EH of the NRA. The following was was carried out: selection of data for transfer and the

  5. New system of the in core monitoring - PTK SVRK

    International Nuclear Information System (INIS)

    Urban, P.

    2000-01-01

    In this paper author describes new system (PTK SVRK) for in-core monitoring system of the Mochovce nuclear power plant installed instead of the HINDUKUSH in-core monitoring system, which are determined to monitor the core parameters. This system (HINDUKUSH), supplied by the Russian party in scope of the original design, became old during the idle time, and the components, which is it built from, are not produced any more. Thus, its utilisation had to undergo a technical end economic analysis. It resulted in classification to the work complex of the technical specification of safety measures. Its implementation conditioned the commissioning of the power plant nuclear unit. The program and technical system of the in-core monitoring (PTK SVRK) consists of two levels - a 'closed' basic, which fulfils the task of the primal system operation for the Unit operators, and an 'open' top level, which serves as a tool for the additional tasks of a prognosis, monitoring, and analysis of the processes taking place in the nuclear core by the monitoring physicists. The basic level of PTK SVRK has 100% redundancy because of its composition and configuration. It is namely formed by two identical, equivalent, and independent sets. Any of them may be operational or redundant. Every set consists of an apparatus processing the signals coming from the technology or the calculation complex, which converts these signals to physical parameters and controls the physically mathematical model of the monitored equipment. The results are presented to the operational staff as outputs on the workstations in the control room in a form of cartograms, graphs, histograms, tables, etc. The bases of the system calculation model are time-proven programs BIPR7 and PERMAK, which are used also in this power plant. The top level of PTK SVRK has a structure supporting the system openness for its further utilisation. Today it is formed by a server and two workstations. Besides the above-mentioned tasks, the

  6. VUJE

    International Nuclear Information System (INIS)

    Anon

    2006-01-01

    The year 2006 presents a continuing successful development of the company aimed at complex services for the energy. At the end of 2006 our company will have celebrated the thirtieth anniversary of a self-existent Nuclear Power Plant Research Institute (VUJE), which was established on January 1, 1974 by the Czechoslovak Federal Ministry of Fuel and Power. On this occasion we can assert that a way of preservation of the institute and later its existence as the incorporation with the activities to manage all the activities of nuclear power plant was a good choice. Our company has shown during its 30-year existence that it is able to preserve the commenced trend to be a significant engineering company in the field of energy and it has confirmed continuously its image of modern, flexible and viable company. Our prosperity has been based on the prosperity of our clients and on our ability to offer and realise top technical solutions that will provide economic, reliable and safe operation of the devices in energy. In the past including 2006 our company has been realising the most important projects in Slovak energy as Modernization of Bohunice V-2, Technology of medium and low-level radioactive treatment for Mochovce nuclear power plant, the Reconstruction oj Krizovany substation. Our success has been achieved thanks to our employees, their knowledge, qualitative products and modern technologies. Regarding the approaching the thirtieth anniversary of our institute we have to take into consideration that the success of our company depends on the collective work of all employees and their activities. Therefore it is obvious that in the 2006 we have been continuing in the improvement of social security scheme of our employees and in the process of increasing of their qualifications. A story of our company is the story of a successful firm, which managed to hold its own trend under difficult economic conditions of the last time. I believe in a well done joint realisation of

  7. The Inspector General's report on Nuclear Safety and Radiation Protection 2008

    International Nuclear Information System (INIS)

    2009-01-01

    abroad; 20.1 - Japan: Kashiwasaki-Kariwa and Hamaoka power plants, the JSW casting and forging facilities at Muroran; 20.2 - Slovakia: Slovenske Elektrarne, Bohunice and Mochovce nuclear power plants; 20.3 - The USA: Constellation Energy, Calvert Cliffs nuclear power plant and Unistar Nuclear Energy; 21 - Appendices

  8. Analysis of the similarity factors of the villages in the areas of the nuclear power plants from the premature death-rate performed by fuzzy logic method

    International Nuclear Information System (INIS)

    Letkovicova, M.; Rehak, R.; Korec, J.; Mihaly, B.; Prikazsky, V.

    1998-01-01

    Our paper examines the surrounding areas of NPP from the proportion of premature death-rate which is one of the complex indicators of the health situation of the population. Specially, attention is focused on NPP in Bohunice (SE-EBO) which has been in operation for the last 30 years and NPP Mochovce (SE-EMO) which was still under construction when data was collected. WHO considers every death of the individual before 65 years of age a premature death case, except death cases of children younger that 1 year. Because of the diversity of the population, this factor is a standard for the population of Slovak Republic (SR) as well as for the european population. The objective of the work is to prove, that even a long term production of energy in NPP does not evoke health problems for the population living in the surrounding areas, which could be recorded through analysis of premature death cases. Using the fuzzy logic method when searching for similar objects and evaluating the influence of the NPP on its surrounding area seems more natural than classical accumulation method, which separates objects into groups. When using the classical accumulation method, the objects in particular accumulation group are more similar than 2 objects in different accumulation groups. When using the fuzzy logic method the similarity is defined more naturally. Within the observed regions of the NPP, the percentage of directly standardized premature death cases is almost identical with the average for the SR. The most closely observed region of SE-EMO up to 5 kilometers zone even shows the lowest percentage. Also we did not record any areas that would have unfavourable values from the wind streams perspective neither than from the local water streams recipients of SE-EBO Manivier and Dudvah. The region of SE-EMO is also within the SR average, unfavourable coherent areas of premature death case are non existent. Galanta city region comes out of the comparison with the relatively worse

  9. Political pressure on nuclear - responsibility or business?

    International Nuclear Information System (INIS)

    Petrech, Rastislav; Holy, Robert

    2001-01-01

    After more than 10 years since the fall of the 'iron curtain' some Central and East European countries were invited to talks on possible joining the European Union. The nuclear power industry and future development programmes in the countries were one of the crucial topics discussed. Nuclear field is probably the most sensitive one in terms of perception and acceptance by the public as well as politicians. To be able to really solve the issue of the nuclear industry future, it is necessary to know and understand the problems, which we'll have to cope with in a situation when the nuclear industry gets face-to-face in a competition with other electricity producers. Safety became the dominant issue roughly since the mid 80's, especially after the Chernobyl accident. Safety had always been important, however it was the top priority is this period. Public relations were seriously dealt with in parallel. Market liberalisation, decentralisation and privatisation has been the determining factor of further development of the nuclear industry since mid 90's. Probably the most important problem are the Public Relations. Positive public attitude and acceptance of nuclear power as an ,'ordinary' industry is the basic precondition for the further development. It is almost common practice that posts of NPP directors are occupied by public relations experts and experienced orators, whose power of arguments can convince people. Results of public opinion polls in many countries demonstrate that political views on the future of nuclear are in contradiction with public opinions. In Slovakia, for example, the nuclear has the support of 60-70 % in long-term. However, what is missing is a political force which might help completing Mochovce NPP units 3 and 4, even though in terms of near-future liberalisation this option proves to be the most advantageous one for replacement of older two units of Bohunice NPP (since the Government promised the units will be shut down in 2006 and 2008

  10. 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

  11. The view at nuclear renaissance via actual European and Slovak approach to nuclear education

    International Nuclear Information System (INIS)

    Slugen, Vladimir

    2010-01-01

    level nuclear education is very important also due to permanent increasing of nuclear experts age. To replace some of them are not easy. Beside this, the nuclear community needs some internal dynamic, which is connected to the young people activities. The problem is that the amount of students taking these lectures is low. Proper education at the university is a source of knowledge and attitudes for the whole life. Theoretical and practical experiences, professional approach and consistency are very important also from the safety culture point of view. University lectures and seminars are basically opened for public and this academic field can be made better use of in public relations. It is an investment mainly to young generation. During discussions with students, teachers can form their professional orientation according to their abilities and needs. Good teacher encourages also the growth of student and shapes his personality. Graduated students have to learn to take responsibility for their decisions and their academic level of education. Unfortunately, there was not real interest for educated nuclear engineers from industry till know. Although oral declaration how these graduates are necessary for NPP operators, in reality the nuclear industry does not attract young specialist. About 50 percent of graduates of specialized nuclear power engineering study at STU Bratislava went completely out from this area. Hopefully next years connected to the commissioning of Mochovce 3, 4 will change this approach. The actual status of education and training in nuclear power engineering is the real cause for concern. This education has to be based on the serious long term basis organised and guaranteed by high quality academic institution. It is a duty of educated and responsible people to highlight the necessity for a renaissance in nuclear education and training and recommend the following points: We must act now; Strategic Role of Governments; The Challenges of revitalising

  12. The view at nuclear renaissance via actual European and Slovak approach to nuclear education

    Energy Technology Data Exchange (ETDEWEB)

    Slugen, Vladimir [Slovak University of Technology, FEI STU, Ilkovicova 3, 812 19 Bratislava (Slovakia)

    2010-07-01

    tools. The high level nuclear education is very important also due to permanent increasing of nuclear experts age. To replace some of them are not easy. Beside this, the nuclear community needs some internal dynamic, which is connected to the young people activities. The problem is that the amount of students taking these lectures is low. Proper education at the university is a source of knowledge and attitudes for the whole life. Theoretical and practical experiences, professional approach and consistency are very important also from the safety culture point of view. University lectures and seminars are basically opened for public and this academic field can be made better use of in public relations. It is an investment mainly to young generation. During discussions with students, teachers can form their professional orientation according to their abilities and needs. Good teacher encourages also the growth of student and shapes his personality. Graduated students have to learn to take responsibility for their decisions and their academic level of education. Unfortunately, there was not real interest for educated nuclear engineers from industry till know. Although oral declaration how these graduates are necessary for NPP operators, in reality the nuclear industry does not attract young specialist. About 50 percent of graduates of specialized nuclear power engineering study at STU Bratislava went completely out from this area. Hopefully next years connected to the commissioning of Mochovce 3, 4 will change this approach. The actual status of education and training in nuclear power engineering is the real cause for concern. This education has to be based on the serious long term basis organised and guaranteed by high quality academic institution. It is a duty of educated and responsible people to highlight the necessity for a renaissance in nuclear education and training and recommend the following points: We must act now; Strategic Role of Governments; The Challenges

  13. Environmental report 2005

    International Nuclear Information System (INIS)

    Ruzzini, P.

    2006-01-01

    This is the tenth Environmental Report we have been regularly issuing annually since 1996 in order to give you information about our efforts and activities taken in the environmental protection area and, at the same time, to keep the mutual dialogue on a standard high level. The year 2005 was not easy for Slovenske elektrarne, a.s. Our company was subject to complicated internal changes to implement as effective company management model as possible. We strove, above all, to enhance the process management system that had already been developed previously. It is true that we also had to resolve personnel matters when looking for an effective power engineering company management model and we had to part from many of our colleagues during that stage. The second priority task we faced was to make preparations for the takeover of our company by the Italian company ENEL, S.p.A., and to complete the privatization process covering 66 % of Slovenske elektrarne, a.s., stock. It was especially the second half of 2005 that brought very intensive mutual discussions and working negotiations held on all management levels. The third, but not less significant, task consisted in detaching the assets which would not be covered by the privatization, namely to detach the Set of Gabcikovo Hydro Power Plants, to detach the VYZ - Decommissioning of Nuclear Installations, Radioactive Treatment and Spent Fuel Management Plant and the EBO V-1 Plant. Despite relatively complicated conditions and the opened and liberalized market in the Slovak Republic, our company produced 26,470,901 MWh of electricity whereby the target was met to 115.00 %. Our company kept the stability of the electric power supply system of the Slovak Republic, despite a complicated situation in the area of electric power supplies in Europe. We can really state that we produced in a safe, reliable, ecological and economical manner. The reliable operations of nuclear power plants in Jaslovske Bohunice and Mochovce where 17

  14. IAEA Operational Safety Team Review Bohunice Nuclear Power Plant, Slovak Republic

    International Nuclear Information System (INIS)

    2010-01-01

    that enables both Bohunice and Mochovce sites to learn of workers doses in real time; and a strong independent nuclear safety oversight organization has been set up at the utility level to support the plants in term of safety analysis and assessment. The team has made recommendations and suggestions related to areas where operational safety of Bohunice NPP could be improved. Examples include: Work clearances orders and communication procedures are not always implemented in a safe manner; identification and reporting of field deficiencies are not at the optimal level; and contamination control practices could be further improved. BNPP management expressed a determination to address all the areas identified for improvement and requested the IAEA to schedule a follow-up mission in approximately 18 months. The team handed over a draft of their recommendations, suggestions and good practices to the plant management in the form of ''Technical Notes'' for factual comments. The technical notes will be reviewed at IAEA headquarters including any comments from BNPP and the Slovak Regulatory Authority. The final report will be submitted to the Government of Slovak Republic within three months. This was the 159th mission of the OSART programme, which began in 1982. General information about OSART missions can be found on the IAEA website: OSART Missions. (IAEA)

  15. Results of trial operation of new generation assemblies with improved vibration stability for WWER-440 reactors of V-230 and V-213 plants

    International Nuclear Information System (INIS)

    Vasilchenko, I.; Lushin, V.; Shumeev, A.

    2006-01-01

    FAs, in the region of FA-and-absorber rod butt joint due to arrangement of hafnium plates in the upper part of FA casing was also solved. The correctness of solutions, laid down in the design of the new generation fuel assemblies, is successfully confirmed by the results of trial operation. It is planned to apply the new generation fuel for WWER-440 reactors of V-213 type at power units of Dukovany NPP in 2005, and in 2006 at Mochovce NPP and at Bohunice NPP V-2 units 3 and 4. In 2007 it is planned to extend an application of vibration-proof working assemblies of new generation for power units of V-230 type at Kola NPP Unit 1

  16. The true costs of nuclear power

    International Nuclear Information System (INIS)

    Wallner, A.; Mraz, G.

    2013-01-01

    Worldwide, many nuclear power plants will be reaching the end of their lifetimes over the next few years. States must therefore decide now on the direction they intend to steer their energy policies. Possible options are the construction of new nuclear power plants, extending the lifetime of existing ones, or changing direction towards a sustainable energy future. Arguments put forward by the nuclear power lobby in favour of new builds are, on the one hand, the claim that nuclear power is low in CO2 emissions,1and on the other, that it is low cost. This paper examines the second claim and identifies the “true costs of nuclear power”. This paper provides an overview for the general reader and presents the most important aspects of “costs of nuclear power”, as well as sound information to contribute to discussions of this complex issue. The first part of this paper focuses on the costs of nuclear new-build: Approximately two thirds of electricity generation costs consist of fixed costs, the largest part of which covers the construction of the nuclear power plant (NPP) itself, including the interest rates (capital costs). Consequently, construction costs are a crucial factor in the overall cost of nuclear power. The issue of nuclear new build is currently under discussion in many states in Europe which are considering replacing their aged nuclear power plant fleet, e.g. UK (Hinkley Point and further plans for new builds), Finland (Olkiluoto 3), France (Flamanville 3), the Czech Republic (Temelin 3/4), Slovakia (Mochovce 3/4) and Romania (Cernavoda 3/4). Those projects have one crucial point in common: problems with costs or financing. The Massachusetts Institute of Technology (MIT) has calculated that construction costs rose 15% per annum from 2003 to 2009; construction costs rose from 2,000 to 4,000 USD, amounting to total construction costs of US$ 4 billion for a 1,000 MW NPP. A current example of cost and construction time overrun is the Finnish reactor

  17. International Expert Team Concludes IAEA Peer Review of Slovakia's Regulatory Framework for Nuclear Safety

    International Nuclear Information System (INIS)

    2012-01-01

    that consideration of these would enhance the overall performance of the regulatory system: Coordination and allocation of responsibilities among State Authorities in the area of safety and improvement of planning and coordination of their activities; The development of a national policy and strategy document for nuclear safety; and A unified national radiation monitoring system to ensure its results could be used by competent authorities in normal situations as well as during emergencies. In a preliminary report, the IAEA has conveyed the team's main conclusions to UJD SR. A final report will be submitted to the Government of Slovakia in about three months. UJD SR has informed the team that the final report will be publicly available. The IAEA encourages nations to invite a follow-up IRRS mission about two years after the mission has been completed. Background. The IRRS mission to Slovakia was conducted from 28 May to 7 June 2012, mainly in Bratislava. The IRRS team carried out a review of nuclear legal and regulatory framework for nuclear safety. Special attention was given to the review of the regulatory implications for Slovakia of the TEPCO Fukushima Daiichi accident. The review addressed all facilities regulated by UJD SR including nine nuclear power units, as well as spent fuel and waste management facilities. The IRRS mission did not include a comprehensive review of the national regulatory infrastructure for radiation safety of Slovakia, which is planned to be covered in the IRRS follow-up mission. Team experts came from twelve different countries: Belgium, Brazil, Czech Republic, Finland, France, Hungary, Romania, Slovenia, South Korea, Sweden, Ukraine and United Kingdom. The IRRS team consisted also of 6 IAEA staff members. Quick Facts. Slovakia has nine nuclear power reactors at two sites (Bohunice, Mochovce): 3 units are in decommissioning, four units are in operation and two units under construction. Slovakia has no other fuel cycle facilities or research

  18. 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

  19. Electricity producer SE decided to solve crisis through offensive

    International Nuclear Information System (INIS)

    Janoska, J.

    2003-01-01

    Instalment payments in this and the coming two years amount to 32 billion Sk (762.8 mn Euro) - that is about 60 percent of the overall credit burden of the electricity producer Slovenske elektrarne (SE). And so the situation from three years ago is repeating itself - a new financial department of the company is expected to lead the company out of the substantial cash-flow crisis caused by credit burden. This difficulties have been caused by decisions taken by state like building of power plant in Mochovce. Minister Nemcsics will not be in the position to complete his ambition to direct the activities of SE, his successor will need time to find his way and so the solution stays in hands of the company management. Where will they look for the necessary recourses? The operation generates virtually no cash-flow increase - reminds General Manager for Economy and Finances, Milos Sujansky. What the manager considers a possible solution is loan restructuring. 'We have to review the whole loan portfolio in order to eliminate the pressure caused by the necessity to repay the debts in 2004 and the beginning of 2005 and that would allow as to survive in a relatively normal state,' unveils the company plans M. Sujansky. That would mean postponing the instalment payments until 2007. Before this strategy was prepared the existing debts had to be analysed. The results of this analysis showed 'an inconsistent debt portfolio with many non-standard elements anchored in relevant contracts'. In the opinion of Director for External Financing this fact makes the loan management and decision making in regards to assets/liabilities structure difficult. 'When you have 35 different loans and every contract is different - communication and monitoring costs much effort,' he adds. According to an Auditors Report for 2002 prepared according to ISA standards even the share of third-party capital is high and inhomogeneous. The previous financial management managed to minimize the deficit. The fact