NPP Personnel Training Center
|
|
- Suzanna Randall
- 6 years ago
- Views:
Transcription
1 NPP Personnel Training Center Juraj Marec, Ivana Maixnerova TM on Developing Systematic Education and Training Approach Using PC Based Simulators for Nuclear Power Programmes, IAEA, Vienna, May 2017
2 Power sources and work locations of VUJE in Slovakia BANSKÁ BYSTRICA KOŠICE EBO EMO TRNAVA BRATISLAVA Vienna Work locations of VUJE: Trnava; Bratislava; Križovany; Mochovce; Košice; Jaslovské Bohunice NPP in operation NPP under construction NPP under decomissioning Power lines 400 kv Main distribution plant Hydroelectric PP Thermal PP 2
3 Overview from PRIS
4 Activities of VUJE in the nuclear power industry
5 Company structure 0100 Department of General Director 0200 Division for Nuclear Safety 0300 Division for Diagnostic of Nuclear Power Components 0400 Division for Preparation of NPP Operation 0500 Division for Support of NPP Operation 0600 Division for NPP Personnel Training Centre 0700 Division for Radiation Safety, NPP Decommissioning and Radwaste Management 0800 Division for Information Technologies 0900 Division for Commerce, Engineering Activities and Services 1000 Division for Economy 1200 Division for Support of Electric Grid Control and Operation 1300 Division for Project Coordination of Research and Development 1700 Division for Preparation and Construction of New Nuclear Power Installations
6 NPP Training center VUJE Training Center performs both theoretical preparation and training of personnel on simulators. The basis of the training is the educational system for the areas of nuclear industry, conventional power plants, electric grid, and for other users. The Training Center develops and designs hardware and software for education and training including simulator development. It carries out examinations for granting licensees for the execution of functions in nuclear power plants and organizes specialized and international courses. Personnel training is carried out in the following areas: Theoretical training Simulator training International courses (EU framework projects) Other training (for NRA, suppliers, internal staff) 6
7 NPP Bohunice V-2, Mochovce 1-2 The Bohunice Nuclear Power Plant (NPP) (Slovak: Atómové elektrárne Bohunice, abbr. EBO) is a complex of nuclear reactors situated in Trnava District in western Slovakia. Bohunice NPP comprises two plants: V1 (shutdown in 2004, now under deccomissioning) and V2. Both plants contain two reactor units. The plant was connected to the national power network in stages in the period between 1978 and The Mochovce Nuclear Power Plant (NPP) (Slovak: Atómové elektrárne Mochovce, abbr. EMO) is a complex of nuclear reactors situated in the Levice District in western Slovakia. Mochovce NPP comprises two units: EMO 1,2 (connected to grid 1999, and second unit 2000). Second plant two units EMO 3,4 are now under construction. All four power reactors are pressurized water reactors (PWR) of the Russian WWER-440, V213 design. 7
8 Section of theoretical training develops programs and elaborates teaching materials and teaching aids for theoretical education, realises teaching of operational and maintenance personnel of the nuclear facilities and training of supplier s organizations for the nuclear facilities. All courses are conducted in accordance with approved training programs for different categories (I.-VI.), professional groups of NPP personnel and different types of training. Nuclear facilities in Slovakia Status Company A-1 Under decommissioning JAVYS V-1 Under decommissioning JAVYS V-2 In operation ENEL RAW Treatment Centre Interim Spent Fuel Storage Facility JAVYS JAVYS EMO-1,2 In operation ENEL EMO-3,4 Under construction ENEL Liquid RAW Treatment Facility JAVYS Basic theoretical training Preparation for the job rotation Periodical training National RAW Repository JAVYS Foreman training Severe accident management training
9 Section of simulator training BANSKÁ BYSTRICA KOŠICE EBO EMO TRNAVA BRATISLAVA FSS Mochovce 1,2 FSS Mochovce 3,4 (operated by S.E.) FSS Bohunice V2 (operated by VUJE) 9
10 Last activities on simulator for NPP Bohunice V-2 WHY FURTHER MODERNIZATION? Two main reasons: Simulator was running on SUN system under Solaris There still were discrepancies between the simulator and reference unit (NPP 3) which needed to be corrected. Slovak NRA (UJD SR) raised a direct demand to S.E. to modernize the simulator software to ensure its long-term and reliable operation and achievement of required accuracy of simulation of EBO V2 Unit. S.E. decided to upgrade simulators in EMO and EBO site in one project due to their similar design and technology used. CORYS TESS used the same scope and tools on these two simulators. 10
11 Project scope and organization :Overall Project Management CORYS - VUJE s competencies for the renovation of Mochovce and Bohunice simulators Mochovce Bohunice Deep knowledge of VVER 440 nuclear plant technology and operation Long experience of CORYS technologies thanks to previous cooperation Extensive know-how on Bohunice simulator CORYS/VUJE/CER 15 years of effective cooperation Data Collection Sim. Executive I&C Containment I/O replacement 3D Core model IS HMI & param. Elec. models Integration & Acceptance Data Collection Sim. Executive I&C 3D Core model IS HMI & param. BNI/BOP model rehosting Integration & Acceptance Containment - development tools (ALICES, T-REX ) and training as necessary were provided to the subcontractor s team - multi-site configuration management tools were implemented to facilitate co-development and support (3 teams in 2 continents) 11
12 Phase 1 - Rehost Rehost stage consisted of five main tasks: 1) All documents were ported from SUN to PC environment and encapsulated in ALICES executive software. All existing snapshots have been converted in ALICES environment. 2) The exchange communication between systems (I&C) was adapted to work in the new PC environment using ALICES software. 3) The code which manages the connection to hard panels was adapted. A graphic visualizer is available. 4) Two new T-Rex instructor stations were provided (119 new graphics P&IDs). 5) New computers were delivered and installed on site. MODELIX ALICES 12
13 Configuration of Bohunice Simulator V2 for full NPP scope Bohunice simulator V-2after upgrade 13
14 Phase 2 Upgrade of hydraulic circuits DRAC THOR HYDRAULIX 14
15 Phase 2 - Upgrade Thermo hydraulic code - THOR two-phase, non-equilibrium, fluid dynamics model for flow networks, model simulates the flow of water, steam, multiple non-condensable gases, and any mixture of those fluids, THOR is used primarily in the areas of the plant that are; high energy subject two phase change important for accurate radio-isotope transport As a result of an extensive installed base for FSS (> 50), THOR is the most thoroughly bench-marked advanced thermal-hydraulic model in the commercial nuclear power industry First NSSS at Watts Bar/USA (1997) First BOP at Surry/USA (2002) First Containment/HVAC at Perry/USA (2006) First ECCS at Farley/USA (2007) First THOR/MELCOR at Monticello (2012) 15
16 Upgrade NEUTRONIC CODE - KIKO KIKO3D - developed in the KFKI Atomic Energy Research Institute - is a three-dimensional reactor dynamics program for coupled neutron kinetics and thermo-hydraulics calculation of VVER type pressurized water reactor cores. - KIKO3D has also its own thermal hydraulic modeling of the reactor core - the thermo-hydraulics is calculated in separate axial hydraulic channels, each of which relates to one fuel assembly - calculation of the middle-fast asymmetric accidents and transients like control rod ejection, start-up of inoperable loop, inadvertent control rod - the equations of the xenon and samarium evolutions are solved and can be accelerated - VVER-440 correlations are used in the thermo-hydraulic module. 16
17 Upgrade T-Rex INSTRUCTOR STATION 17
18 Upgrade T-Rex INSTRUCTOR STATION 18
19 Upgrade EXTERNAL SYSTEMS TPS (Technological information system ) an identical system is used as in the Bohunice NPP SCORPIO (Reactor core surveillance system) - a new SCORPIO system was connected to the TPS Data are sent from simulator to TPS which provides necessary data for SCORPIO modules Center of emergency response - CER - CER computers are now available in Bohunice NPP - it allows to run emergency scenarios on simulator and at the same time in Bohunice NPP 19
20 Upgrade VUJE responsibilities in upgrade cooperation with CORYS TESS in portion of MX modules into ALICES software during integration phase models connection discrepancies cleaning up development of HMI for IS (Mochovce, Bohunice) development of electric model for Mochovce simulator providing of actual plant data and safety analysis support during tuning of THOR and I&C FAT and SAT performance 20
21 Exercise Loss of one MCP Course of event: - MCP nr.6 tripped - reactor power reduced by acting of RLS (reactor limitation system AO3) from 100% reactor power to less then 75% of nominal reactor power - turbine load reduced due to drop of pressure in main steam line (acting of p correctors) - drop of the water level in steam generator and its regulation back to nominal value - unit stabilized by 75% reactor power with 5 MCPs running 21
22 SG 6 narrow level (mm) SG level recovering Level ramping to 0 mm in 10 minutes SG Boiling stop Narrow level -100mm 22
23 reactor neutron power (%) RLS (AO3) Nre < 75% 23
24 Exercise SG pipes leakage Course of event: - leak from primary to secondary water - primary pipes are leaking into steam generator secondary water, increase of level and pressure - SG L tot 2,52m fast acting valve on steam pipe of SG closed - > 5 MPa steam dump valves open to decrease the pressure - new detailed THOR nodalisation ensures the correct response of pressure (i.e. steam trap added to steam lines) 24
25 Leak 25
26 Reactor scram SG4 pressure (MPa), Reactor neutron power (%) Leak started FAV closing > 2.52m in SG 26
27 SG4 total level (m), SG4 pressure (MPa) MSL Full SG4 Full SG4 steam valve closing 27
28 STEAM DUMP STEAM TRAP 28
29 SG4 steam line flow rates (kg/s) STEAM DUMP opening STEAM TRAP flow 29
30 After FSS upgrade after SAT performed in May 2014, Bohunice V-2 simulator is now fully used in training under license given by UJD SR (Slovak nuclear regulatory body) in August 2014 scope of simulation has been extended new scenarios to train (open reactor, SG drainage, over heated steam.) more realistic behavior (tested and compared with NPP data and complied with ANSI norm) better training user friendly environment (PC, Windows OS) more features within instructor station (events, schedules, control from P&IDs) THOR model is ready to be connected to code supporting melting core (i.e. MELCORE) and used in SAM (Severe Accident Management) scenarios 30
31 New initiatives in our division bring more operational staff to the training to cooperate with the shift visualize better implement new tools for better understanding be more realistic create new scenarios for the Severe Accident Management training
32 New initiatives in our division SAM console developed by VUJE installed on Bohunice and Mochovce NPP control room copy of the console also on simulator 2 PCs 4 screens connected via OPC server control of the plant in case of sever accident used during SAM training scenarios for usage of SAM diesel generator in case of blackout
33 CONTAINMENT SPRAY SYSTEM REACTOR HALL SPENT FUEL POOL REACTOR AXIS PASSIVE HYDROGEN RECOMBINERS VENTCENTRUM 33
34 New initiatives in our division new graphic visualisation during refueling Trainees and instructors is able to see in what state they are to better understand the process
35 New initiatives in our division new graphicly visualized and animated technological P&IDs in use for field operator but also for instructors
36 New initiatives in our division electrical scheme based on ThunderElectric better and more realistic behaviour more mesurements and scenarios available
37 Bug tracking system list Filter Excel report 37
38 Bug tracking system bug overview 38
39 elearning sample
40 Conclusion Relation to specific plant FSS E&RS BPS generic BPS specific Simplified animations Plant specific Plant specific Not plant specific Plant specific Licensed Training and usage Based on plant data Personnel with direct impact on NS => MCR staff, field operators, physicists, regulatory body staff Based on design data, later on plant data Engineers, validation of I&C, validation of design, safety analysis Based on code used (thermo hydraulic, neutron) University students, decision makers, regulatory body staff, suppliers, public Based on plant data Personnel with impact on NS => same as generic + MCR staff, field operators, physicists, regulatory body staff Elementary fundamentals for supporting personnel and public 40
41 Questions and answers 41
PSA ANALYSIS FOCUSED ON MOCHOVCE NPP SAFETY MEASURES EVALUATION FROM OPERATIONAL SAFETY POINT OF VIEW
International Conference Nuclear Energy in Central Europe 2001 Hoteli Bernardin, Portorož, Slovenia, September 10-13, 2001 www: http://www.drustvo-js.si/port2001/ e-mail: PORT2001@ijs.si tel.:+ 386 1 588
More informationSupporting Deterministic T-H Analyses for Level 1 PSA
Supporting Deterministic T-H Analyses for Level 1 PSA ABSTRACT SLAVOMÍR BEBJAK VUJE, a.s. Okružná 5 918 64 Trnava, Slovakia slavomir.bebjak@vuje.sk TOMÁŠ KLIMENT VUJE, a.s. Okružná 5 918 64 Trnava, Slovakia
More informationOrganizational and Managerial Aspects of Decommissioning after an Accident
Organizational and Managerial Aspects of Decommissioning after an Accident Miroslav Božik, Peter Gerhart JAVYS, Plc. Slovak Republic JAVYS, Plc. International Experts Meeting on Decommissioning and Remediation
More informationOperatiOn and safety report Of MOchOvce and BOhunice v2 nuclear power plants
2016 OperatiOn and safety report Of MOchOvce and BOhunice v2 nuclear power plants The company is certified according to three management systems: Certificate stn en iso 9001:2008 Quality management system
More informationModule 05 WWER/ VVER (Russian designed Pressurized Water Reactors)
Module 05 WWER/ VVER (Russian designed Pressurized Water Reactors) 1.3.2016 Prof.Dr. Böck Technical University Vienna Atominstitut Stadionallee 2, 1020 Vienna, Austria ph: ++43-1-58801 141368 boeck@ati.ac.at
More informationJADROVÁ A VYRAĎOVACIA SPOLOČNOSŤ
JADROVÁ A VYRAĎOVACIA SPOLOČNOSŤ 01 JAVYS safely with every step JAVYS THE MISSION Safe, reliable, economically effective and efficient operation and decommissioning of nuclear facilities Safe, reliable,
More informationMEASUREMENT AND EVALUATION SYSTEMS FOR NPP COMMISSIONING
MEASUREMENT AND EVALUATION SYSTEMS FOR NPP COMMISSIONING Marek Elko, VUJE, Inc. ABSTRACT Standard core monitoring and information systems are designed with an emphasis on normal operation of nuclear power
More informationManaging severe accidents beyond design conditions (SAM) Vladivoj REZNIK, Engineering Director
Managing severe accidents beyond design conditions (SAM) Vladivoj REZNIK, Engineering Director International Power Summit, Munich February 2014 Slovenské elektrárne, subsidiary of Enel Enel world presence
More informationSpent Fuel Management in Slovakia
Spent Fuel Management in Slovakia Juraj Václav Nuclear Regulatory Authority of the Slovak Republic International Conference on Management of Spent Fuel from Nuclear Power Reactors 31 May 4June2010 Vienna,
More informationVUJE experience in NPP decommissioning and radwaste (RAW) treatment
VUJE experience in NPP decommissioning and radwaste (RAW) treatment JRC - Slovakia Conference Bratislava Peter Líška June 10, 2014 www.vuje.sk A1 NPP Decommissioning A1 NPP - CO 2 cooled, HW moderated,
More informationA Research Reactor Simulator for Operators Training and Teaching. Abstract
Organized and hosted by the Canadian Nuclear Society. Vancouver, BC, Canada. 2006 September 10-14 A Research Reactor Simulator for Operators Training and Teaching Ricardo Pinto de Carvalho and José Rubens
More informationRESULTS OF THE GRADUAL UPGRADING AT BOHUNICE WWER - 440/230 NPP
RESULTS OF THE GRADUAL UPGRADING AT BOHUNICE WWER - 440/230 NPP P. Krupa Ingeneer, e-mail: Krupa_Peter@ebo.seas.sk Bohunice NPPs Introduction The centre of upgrading activities in VVER NPP is clearly in
More informationRole of Slovakia within the IAEA Decommissioning Related Activities 9031
Role of Slovakia within the IAEA Decommissioning Related Activities 9031 Vladimir Michal, Marian Stubna VUJE, Inc. Okruzna 5, 918 64 Trnava, Slovak Republic ABSTRACT Slovakia has a long-term experience
More informationSystems for inspection and repair of WWER type steam generators. Adrian KOVALYK, Pavol JABLONICKY, Peter PILAT
Systems for inspection and repair of WWER type steam generators Adrian KOVALYK, Pavol JABLONICKY, Peter PILAT 2011 What we do... Reconstruction & modernization Nuclear safety Diagnostics & In-service inspection
More informationLEGAL AND REGULATORY FRAMEWORK FOR RADIOACTIVE WASTE MANAGEMENT AND DECOMMISSIONING IN SLOVAK REPUBLIC
LEGAL AND REGULATORY FRAMEWORK FOR RADIOACTIVE WASTE MANAGEMENT AND DECOMMISSIONING IN SLOVAK REPUBLIC ABSTRACT /DGLVODY.RQHþQê-DQD%XUFORYi Nuclear Regulatory Authority of the Slovak Republic Trnava Slovak
More informationSCORPIO-VVER Core Monitoring and Surveillance System with Advanced Capabilities
SCORPIO-VVER Core Monitoring and Surveillance System with Advanced Capabilities Jozef Molnár, Radim Vočka, 19 th AER Symposium 21 25 September 2009 Varna, Bulgaria SCORPIO-VVER The Developers The first
More informationOperation and safety report of Mochovce and Bohunice V2 nuclear power plants
Operation and safety report of Mochovce and Bohunice V2 nuclear power plants ENERGY FOR LIFE The company has certified the three following systems: Certificate STN EN ISO 91:28 quality management system
More informationRELAP5/MOD3.2 INVESTIGATION OF A VVER-440 STEAM GENERATOR HEADER COVER LIFTING
Science and Technology Journal of BgNS, Vol. 8, 1, September 2003, ISSN 1310-8727 RELAP5/MOD3.2 INVESTIGATION OF A VVER-440 STEAM GENERATOR HEADER COVER LIFTING Pavlin P. Groudev, Rositsa V. Gencheva,
More informationDesign, Safety Technology and Operability Features of Advanced VVERs
Technical Cooperation Project INT/4/142 Interregional Workshop on Advanced Nuclear Reactor Technology for Near Term Deployment IAEA Headquarters, Vienna, Austria, 4-8 July 2011 Design, Safety Technology
More informationDevelopment and use of SAMGs in the Krško NPP
REPUBLIC OF SLOVENIA Development and use of SAMGs in the Krško NPP Tomaž Nemec Slovenian Nuclear Safety Administration tomaz.nemec@gov.si IAEA TM on the Verification and Validation of SAMGs, Vienna, 12
More informationSelection, specification, design and use of various nuclear power plant training simulators
XA9846401 IAEA-TECDOC-995 Selection, specification, design and use of various nuclear power plant training simulators Report prepared within The IAEA does not normally maintain stocks of reports in this
More informationVerification and Validation of SAMGs
Verification and Validation of SAMGs SAMG-D Toolkit, Module 3, Chapter 7 Martin Gajdoš Nuclear Engineering, Slovenské elektrárne IAEA Workshop on the Development of Severe Accident Mitigation Guidelines
More informationOperating Nuclear Reactors in Ukraine: Enhancement of Safety and Performance
IAEA-CN-164-6S05 Operating Nuclear Reactors in Ukraine: Enhancement of Safety and Performance S. Bozhkoa, G. Gromovb, S. Sholomitskyb, O.Sevbob, G. Balakanc a State Nuclear Regulatory Authority of Ukraine,
More informationNATIONAL REPORT OF THE SLOVAK REPUBLIC
NATIONAL REPORT OF THE SLOVAK REPUBLIC COMPILED IN TERMS OF THE CONVENTION ON NUCLEAR SAFETY JUNE 2013 Table of contents Table of Contents 1. PREFACE... 9 1.1 PURPOSE OF THE REPORT... 9 1.2 CONCEPT OF
More informationSafety enhancement of nuclear power plants in Russia: response to challenges of the time
Safety enhancement of nuclear power plants in Russia: response to challenges of the time Alexey Kiryukhin IAEA, Vienna, June 2017 Содержание 1. 1 2. SAFETY ENHANCEMENT OF NPPs IN OPERATION.. 3 NEW DESIGN
More information2014 OPERATION AND SAFETY REPORT OF MOCHOVCE AND BOHUNICE V2 NUCLEAR POWER PLANTS
214 OPERATION AND SAFETY REPORT OF MOCHOVCE AND BOHUNICE V2 NUCLEAR POWER PLANTS The company has certified the three following systems: Certificate STN EN ISO 91:28 quality management system Certificate
More informationAccident Management Programme for Indian Pressurized Heavy Water Reactors Chander Mohan Bhatia Nuclear Power Corporation of India Limited
Accident Management Programme for Indian Pressurized Heavy Water Reactors Chander Mohan Bhatia Nuclear Power Corporation of India Limited cmbhatia@npcil.co.in Presentation Contents Indian nuclear power
More informationNPP Simulators Workshop for Education - Passive PWR NPP & Simulator Overview
NPP Simulators Workshop for Education - Passive PWR NPP & Simulator Overview Wilson Lam (wilson@cti-simulation.com) CTI Simulation International Corp. www.cti-simulation.com Sponsored by IAEA Modified
More informationCOMPONENTS DISMANTLING AT NOVOVORONEZH UNITS 1, 2 SHUT DOWN FOR DECOMMISSIONING
COMPONENTS DISMANTLING AT NOVOVORONEZH UNITS 1, 2 SHUT DOWN FOR DECOMMISSIONING Filatov Alexey Engineer, Decommissioning Department Novovoronezh NPP, Russia INTRODUCTION The first phase of Novovoronezh
More informationALLEGRO Project. Branislav Hatala. SES September, 2012 Bratislava.
ALLEGRO Project Branislav Hatala SES 2012 27 September, 2012 Bratislava www.vuje.sk General objectives Gas cooled fast reactors (GFR) represent one of the three European candidate fast reactor types. Allegro
More informationDecommissioning, Radioactive Waste and Spent Nuclear Fuel Management in Slovakia
Decommissioning, Radioactive Waste and Spent Nuclear Fuel Management in Slovakia Presented by Mr. Vladimir Michal Division for Radiation Safety, NPP Decommissioning and RAW Management GSV, Trnava, 11 October
More informationConcepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant
8 Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant KOZO TABUCHI *1 MASAYUKI TAKEDA *2 KAZUO TANAKA *2 JUNICHI IMAIZUMI *2 TAKASHI KANAGAWA *3 ATMEA1 TM is a 3-loop 1100
More informationSAM strategy&modifications and SA simulator at Paks NPP
Technical Meeting on Verification and Validation of SAMGs for Nuclear Power Plants 12-14 December 2016, Vienna, Austria SAM strategy&modifications and SA simulator at Paks NPP Éva Tóth Group Leader Safety
More informationEvolution of Nuclear Energy Systems
ALLEGRO Project 2 Evolution of Nuclear Energy Systems 3 General objectives Gas cooled fast reactors (GFR) represent one of the three European candidate fast reactor types. Allegro Gas Fast Reactor (GFR)
More informationEuropean Decommissioning Academy
European Decommissioning Academy Vladimír Slugeň Slovak University of Technology in Bratislava National Nuclear Fund of SR Slovak Nuclear Society Vladimir.Slugen@stuba.sk 1 9.11.2016 COUNCIL DIRECTIVE
More informationFormat and Content of the Safety Analysis Report for Nuclear Power Plants - Core Set -
Format and Content of the Safety Analysis Report for Nuclear Power Plants - Core Set - 2013 Learning Objectives After going through this presentation the participants are expected to be familiar with:
More informationThe Role of Computer-Based Educational Laboratories in Nuclear Engineering University Programmes
International Conference on Human Resource Development for Nuclear Power Programmes: Building and Sustaining Capacity Vienna, Austria 12 16 May 2014 The Role of Computer-Based Educational Laboratories
More informationCORROSION MONITORING SYSTEM IN THE SLOVAK REPUBLIC NUCLEAR POWER PLANTS
CORROSION MONITORING SYSTEM IN THE SLOVAK REPUBLIC NUCLEAR POWER PLANTS M. Brezina, L. Kupca VUJE Inc. Okruzna 5, 918 64 Trnava, Slovak Republic Email address of main author: brezina@vuje.sk Abstract.
More informationTechnical University of Sofia, Department of Thermal and Nuclear Power Engineering, 8 Kliment Ohridski Blvd., 1000 Sofia, Bulgaria
BgNS TRANSACTIONS volume 20 number 2 (2015) pp. 143 149 Comparative Analysis of Nodalization Effects and Their Influence on the Results of ATHLET Calculations of VVER-1000 Coolant Transient Benchmark Phase
More informationSPECIFIC DEGRADATIONS OF VVER-1000
SPECIFIC DEGRADATIONS OF VVER-1000 (in view of lifetime extension) Dimitar Popov Kozloduy NPP, Bulgaria IAEA Technical Meeting on Degradation of Primary Components of PW cooled NPPs, Vienna, 05-08 Nov,
More informationCurrent reactor technology, part III: Radek Škoda Czech Technical University Prague WNU SI 2010 Christ Church, Oxford
Current reactor technology, part III: VVER RBMK Radek Škoda Czech Technical University Prague Christ Church, Oxford 1 Overview 1. Gen 1-2-3-4 2. Reactor technology: RBMK 3. Reactor technology: VVER 4.
More informationNuclear Energy Revision Sheet
Nuclear Energy Revision Sheet Question I Identify the NPP parts by writing the number of the correct power plant part in the blank. Select your answers from the list provided below. 1 Reactor 2 Steam generator
More informationSTRESS TESTS ACTION PLAN LEONTI CHALOYAN DEPUTY CHIEF ENGINEER ON MODERNIZATION
STRESS TESTS ACTION PLAN LEONTI CHALOYAN DEPUTY CHIEF ENGINEER ON MODERNIZATION VIENNA MARCH 27-29, 2017 1 ANPP * The ANPP is located in the western part of Ararat valley, 30 km west of Yerevan, close
More informationTERMO-HYDRAULICS AND TERMO-MECHANICAL LOADING OF VVER-440 REACTOR PRESSURE VESSEL
TERMO-HYDRAULICS AND TERMO-MECHANICAL LOADING OF VVER-440 REACTOR PRESSURE VESSEL G. Gálik 1, V. Kutiš 2, J. Paulech 3, V. Goga 4 Abstract: This article describes a pressure thermal shock simulation methodology
More informationSevere accidents management in PWRs
Severe accidents management in PWRs J. Rajzrová, J.Jiřičková Abstract According to a new trend in safety upgrades in PWRs, the nuclear power plants have started to adopt strategs to mitigate events beyond
More informationStation Blackout Analysis for a 3-Loop Westinghouse PWR Reactor Using TRACE
The Egyptian Arab Journal of Nuclear Sciences and Applications Society of Nuclear Vol 50, 3, (229-239) 2017 Sciences and Applications ISSN 1110-0451 Web site: esnsa-eg.com (ESNSA) Station Blackout Analysis
More informationNATIONAL REPORT OF THE SLOVAK REPUBLIC
NATIONAL REPORT OF THE SLOVAK REPUBLIC COMPILED IN TERMS OF THE CONVENTION ON NUCLEAR SAFETY MAY 2016 Table of Contents Table of Contents 1. PREFACE... 10 1.1 PURPOSE OF THE REPORT... 10 1.2 CONCEPT OF
More informationSLOVAKIA. FIG. 1. Map of the Slovak Republic TABLE 1. SELECTED PARAMETERS FROM METEOROLOGICAL STATIONS IN BOHUNICE AND MOCHOVCE
SLOVAKIA 708 SLOVAKIA SLOVAKIA 1. GENERAL INFORMATION 1.1. General Overview The size of the Slovak Republic is 49 036 km 2 with 40% of the area situated up to the elevation of 300 m, 45% at the elevation
More informationUSING NEW VERSIONS OF SEVERE ACCIDENT CODES FOR VVER- 440/213 TYPE NUCLEAR POWER PLANTS
USING NEW VERSIONS OF SEVERE ACCIDENT CODES FOR VVER- 440/213 TYPE NUCLEAR POWER PLANTS András Nemes, Pál Kostka nemes@nubiki.hu kostka@nubiki.hu TM on the Status and Evaluation of Severe Accident Simulation
More informationLight Water Reactor in Russia
ROSATOM STATE CORPORATION ON NUCLEAR ENERGY ROSATOM Light Water Reactor in Russia Presented M.A.Bykov OKB GIDROPRESS 17 th TWG-LWR Meeting, Vienna, 18-20 June 2012 NPP Electricity Generation in Russia
More informationSIMULATOR BENEFITS BEYOND TRAINING. ENGINEERING ACTIVITIES SUPPORT
1 Tecnatom 2018 Proprietary information SIMULATOR BENEFITS BEYOND TRAINING. ENGINEERING ACTIVITIES SUPPORT 2018 2 Outline Rationale Examples Conclusions 3 Rationale 4 Modern Simulators features Models
More informationAccident Diagnostic, Analysis and Management (ADAM) System Applications to Severe Accident Management *
Reprint of Paper Presented at the OECD/NEA Severe Accident Management (SAM) Workshop on Operator Training and Instrumentation Capabilities, Lyon, France, 12-14 March 2001 Accident Diagnostic, Analysis
More informationSLOVAKIA 1 1. ENERGY, ECONOMIC AND ELECTRICITY INFORMATION
SLOVAKIA 772 SLOVAKIA SLOVAKIA 1 1. ENERGY, ECONOMIC AND ELECTRICITY INFORMATION 1.1. General Overview The size of the Slovak Republic is 49 036 km 2 with 40% of the area situated up to the elevation of
More informationExperience and Lessons Learned in Developing Training Course for Stakeholders
Experience and Lessons Learned in Developing Training Course for Stakeholders (INDONESIA) Technical Meeting on Cooperation for Human Resource Development among Embarking and Experienced Countries 4 ~ 6
More informationDeveloping a 3 Loop PWR and Severe Accident Simulator for the Japanese Nuclear Regulatory Agency
Developing a 3 Loop PWR and Severe Accident Simulator for the Japanese Nuclear Regulatory Agency 2017 Power Plant Simulation Conference San Diego, Ca January 16-19, 2017 Developing a 3 Loop PWR and Severe
More informationRussian regulatory approach to evaluation of passive systems used for specific BDBA S (SBO, loss of UHS) during safety review of NPP
Federal Environmental, Industrial and Nuclear Supervision Service Scientific and Engineering Centre for Nuclear and Radiation Safety Member of Russian regulatory approach to evaluation of passive systems
More information5,500. years of experience in nuclear power. MOCHOVCE Nuclear Power Plant. New clear power. More than. More than
MOCHOVCE Nuclear Power Plant More than 5,500 More than 50 years of experience in nuclear power people employed in nuclear power in Slovakia New clear power Chronology of Mochovce Unit 1 2 3 4 Start of
More informationDevelopment of a Performance Validation Tool for NSSS Control System
IAEA-CN-164-4S1 Development of a Performance Validation Tool for NSSS Control System Suk-whun Sohn, In-ho Song, See-chae Jeong, Jong-joo Sohn, Eun-ki Kim Korea Power Engineering Company (KOPEC), Daejeon,
More informationTS1-5: Revision of NS-G-2.15 and Its Implementation for Verification and Validation of Severe Accident Management Guidelines
Technical Meeting on Verification and Validation of Severe Accident Management Guidelines for Nuclear Power Plants 12-14 December 2016, Vienna, Austria TS1-5: Revision of NS-G-2.15 and Its Implementation
More informationAnswers to Questions on the National Report
Status of the National Action Plan at the Paks NPP in Hungary on the implementation actions decided upon lessons learned from Fukushima Daiichi accident Answers to Questions on the National Report András
More informationPreliminary Lessons Learned from the Fukushima Daiichi Accident for Advanced Nuclear Power Plant Technology Development
Preliminary Lessons Learned from the Fukushima Daiichi Accident for Advanced Nuclear Power Plant Technology Development A. Introduction The IAEA Report on Reactor and Spent Fuel Safety in the Light of
More informationRELAP5 Analysis of Krško Nuclear Power Plant Abnormal Event from 2011
RELAP5 Analysis of Krško Nuclear Power Plant Abnormal Event from 2011 ABSTRACT Andrej Prošek Jožef Stefan Institute Jamova cesta 39 SI-1000, Ljubljana, Slovenia andrej.prosek@ijs.si Marko Matkovič Jožef
More informationNuScale SMR Technology
NuScale SMR Technology UK IN SMR; SMR IN UK Conference - Manchester, UK Tom Mundy, EVP Program Development September 25, 2014 Acknowledgement & Disclaimer This material is based upon work supported by
More informationIAEA Training in level 1 PSA and PSA applications. Other PSA s. Low power and shutdown PSA
IAEA Training in level 1 PSA and PSA applications Other PSA s Low power and shutdown PSA Content Why shutdown PSA? Definitions Plat damage states and Plant operational states Specific modelling tasks of
More informationREPORT OF THE SLOVAK REPUBLIC
Ref. Ares(2015)3540608-27/08/2015 REPORT OF THE SLOVAK REPUBLIC COMPILED IN TERMS OF ARTICLE 14 par.1 COUNCIL DIRECTIVE 2011/70/EURATOM Contents CONTENTS INTRODUCTION... 5 ART. 4 GENERAL PRINCIPLES...
More informationDESIGN AND SAFETY PRINCIPLES LEONTI CHALOYAN DEPUTY CHIEF ENGINEER ON MODERNIZATION
DESIGN AND SAFETY PRINCIPLES LEONTI CHALOYAN DEPUTY CHIEF ENGINEER ON MODERNIZATION VIENNA OKTOBER 3-6, 2016 1 ANPP * ANPP is located in the western part of Ararat valley 30 km west of Yerevan close to
More informationCountry Presentation. Ukraine
Country Presentation. Ukraine 25th Meeting of the IAEA Technical Working Group on Nuclear Power Plant Instrumеntation and Control (TWG -NPPIC) May 27-29, 2015,, Austria Vladimir Sklyar, RPC Radiy TOP5
More informationAvailable online at ScienceDirect. Procedia Engineering 86 (2014 )
Available online at www.sciencedirect.com ScienceDirect Procedia Engineering 86 (2014 ) 308 314 1st International Conference on Structural Integrity, ICONS-2014 Guidelines for Integrity and Lifetime Assessment
More informationSMR/1848-T21b. Course on Natural Circulation Phenomena and Modelling in Water-Cooled Nuclear Reactors June 2007
SMR/1848-T21b Course on Natural Circulation Phenomena and Modelling in Water-Cooled Nuclear Reactors 25-29 June 2007 T21b - Selected Examples of Natural Circulation for Small Break LOCA and Som Severe
More informationPLUTONIUM UTILIZATION IN REACTOR FUEL
Second Moscow International Nonproliferation Conference PLUTONIUM UTILIZATION IN REACTOR FUEL A. Zrodnikov Director General State Scientific Center of the Russian Federation Institute for Physics and Power
More informationTechnical potentialities of integration of reactor vessel external cooling in operating WWER-440 plant - Assessment results
Technical potentialities of integration of reactor vessel external cooling in operating WWER-440 plant - Assessment results Speaker Pantyushin S.I. ERMSAR-2013 02-04.10.2013 1. Introduction. Current status
More informationApplication of Small Punch Testing Methods for Thermal Ageing Evaluation on Samples from Primary Piping of NPP
Application of Small Punch Testing Methods for Thermal Ageing Evaluation on Samples from Primary Piping of NPP Jana Petzová 1, a *, Martin Březina 1, b, Miloš Baľák 1, c, Ľudovít Kupča 1, e 1 VUJE, a.s.,
More informationNuclear I&C Systems Basics. The role of Instrumentation and Control Systems in Nuclear Power Plants, and their Characteristics
Nuclear I&C Systems Basics The role of Instrumentation and Control Systems in Nuclear Power Plants, and their Characteristics Functions of Nuclear I&C Functions and significance of the Instrumentation
More informationTemelin 1000 MW Units Active Testing Stage - Commissioning Experience
International Conference Nuclear Energy for New Europe 2003 Portorož, Slovenia, September 8-11, 2003 http://www.drustvo-js.si/port2003 1 ABSTRACT Temelin 1000 MW Units Active Testing Stage - Commissioning
More informationResearch Article Evaluation of Heat Removal from RBMK-1500 Core Using Control Rods Cooling Circuit
Science and Technology of Nuclear Installations Volume 8, Article ID 378, 8 pages doi:1155/8/378 Research Article Evaluation of Heat Removal from RBMK-15 Core Using Control Rods Cooling Circuit A Kaliatka,
More informationTHE ROLE OF PASSIVE SYSTEMS IN ENHANCING SAFETY AND PREVENTING ACCIDENTS IN ADVANCED REACTORS
THE ROLE OF PASSIVE SYSTEMS IN ENHANCING SAFETY AND PREVENTING ACCIDENTS IN ADVANCED REACTORS M. Aziz Nuclear and radiological regulatory authority Cairo, Egypt moustafaaaai@yahoo.com Abstract Most of
More informationTechnologies of HTR-PM Plant and its economic potential
IAEA Technical Meeting on the Economic Analysis of HTGRs and SMRs 25-28 August 2015, Vienna, Austria Technologies of HTR-PM Plant and its economic potential Prof. Dr. Yujie Dong INET/Tsinghua University
More informationPerformance indicators of Nuclear Power Plants in Slovakia. Update on MO34 completion
Performance indicators of Nuclear Power Plants in Slovakia Update on MO34 completion Robert Holy head of nuclear communications Atominstitut Wien, 22 November 2013 Slovenské elektrárne, subsidiary of Enel
More informationThe RETRAN-3D code is operational on PCs using the Windows and Linux operating systems.
What Is RETRAN-3D RETRAN-3D is a best-estimate light water reactor and reactor systems transient thermalhydraulic analysis code. Its predecessor, RETRAN-02, was used extensively by the commercial nuclear
More informationAdvanced Sodium Fast Reactor Power Unit Concept
International Conference on Fast Reactors and Related Fuel Cycles: Challenges and Opportunities (FR 09) Advanced Sodium Fast Reactor Power Unit Concept V.M. Poplavsky a, A.M. Tsybulya a, Yu.E. Bagdasarov
More informationScenarios of Heavy Beyond-Design-Basis Accidents in HTGRs N.G. Kodochigov, Yu.P. Sukharev
Scenarios of Heavy Beyond-Design-Basis Accidents in HTGRs N.G. Kodochigov, Yu.P. Sukharev IAEA Technical Meeting on the Safety of High Temperature Gas Cooled Reactors in the Light of the Fukushima Daiichi
More informationSimulation of thermal hydraulics accidental transients: evaluation of MAAP5.02 versus CATHAREv2.5
1/12 Simulation of thermal hydraulics accidental transients: evaluation of MAAP5.02 versus CATHAREv2.5 J. Bittan¹ 1) EDF R&D, Clamart (F) Summary MAAP is a deterministic code developed by EPRI that can
More informationCompany Details. Leeds, UK Sofia, Bulgaria (HQ) Istanbul, Turkey. Hanoi, Vietnam
COMPANY BRIEF Company Details Leeds, UK Sofia, Bulgaria (HQ) Istanbul, Turkey Hanoi, Vietnam Established in 1992 Private ownership Staff: 150 Certificates: ISO 9001:2008 ISO 14001:2004 BS OHSAS 18001:2007
More informationLIFE CYCLE MANAGEMENT OF LOVIISA NPP
LIFE CYCLE MANAGEMENT OF LOVIISA NPP Presentation at International Scientific Forum Intellectual design. Complex Engineering Product Life Cycle Management (PLM), Nizhny Novgorod, Russia, June 15th, 2011.
More informationSteam Generator Ageing Management in Slovakia current practices and related issues
International Atomic Energy Agency Meeting on Update and Upgrade of IAEA-TECDOC on Ageing Management of Steam Generators IAEA, Vienna, 15 18 June 2009 Steam Generator Ageing Management in Slovakia current
More informationIAEA Safety Standards for Research Reactors
Safety Standards for Research Reactors W. Kennedy Research Reactor Safety Section Division of Nuclear Installation Safety Yogyakarta, Indonesia 26/09/2013 International Atomic Energy Agency Contents Safety
More informationINVESTIGATION OF CRITICAL SAFETY FUNCTION INTEGRITY IN CASE OF STEAM LINE BREAK ACCIDENT FOR VVER 1000/V320
International Conference 12th Symposium of AER, Sunny Beach, pp.99-105, 22-28 September, 2002. INVESTIGATION OF CRITICAL SAFETY FUNCTION INTEGRITY IN CASE OF STEAM LINE BREAK ACCIDENT FOR VVER 1000/V320
More informationState Corporation Rosatom Approach to Nuclear Personnel Training
ROSATOM STATE ATOMIC ENERGY CORPORATION ROSATOM State Corporation Rosatom Approach to Nuclear Personnel Training Larissa Strutskaya, PhD HR Director, Rusatom Overseas June 4-6, 2012 Atomexpo, Moscow Rosatom
More informationVerification of the MELCOR Code Against SCDAP/RELAP5 for Severe Accident Analysis
Verification of the Code Against SCDAP/RELAP5 for Severe Accident Analysis Jennifer Johnson COLBERT 1* and Karen VIEROW 2 1 School of Nuclear Engineering, Purdue University, West Lafayette, Indiana 47907-2017,
More informationCAPACITY BUILDING FOR NATIONAL NUCLEAR INFRASTRUCTURE IN EMERGING NUCLEAR COUNTRIES
CENTRAL INSTITUTE FOR CONTINUING EDUCATION & TRAINING INTERNATIONAL TRAINING CENTRE CAPACITY BUILDING FOR NATIONAL NUCLEAR INFRASTRUCTURE IN EMERGING NUCLEAR COUNTRIES R O S AT O M C ATA L O G U E OF TRAINING
More informationNuclear Power Plant Safety Basics. Construction Principles and Safety Features on the Nuclear Power Plant Level
Nuclear Power Plant Safety Basics Construction Principles and Safety Features on the Nuclear Power Plant Level Safety of Nuclear Power Plants Overview of the Nuclear Safety Features on the Power Plant
More informationNuclear Power Plant Safety Basics. Construction Principles and Safety Features on the Nuclear Power Plant Level
Nuclear Power Plant Safety Basics Construction Principles and Safety Features on the Nuclear Power Plant Level Safety of Nuclear Power Plants Overview of the Nuclear Safety Features on the Power Plant
More informationANALYSES OF AN UNMITIGATED STATION BLACKOUT TRANSIENT WITH ASTEC, MAAP AND MELCOR CODE
ANALYSES OF AN UNMITIGATED STATION BLACKOUT TRANSIENT WITH ASTEC, MAAP AND MELCOR CODE Technical Meeting on the Status and Evaluation of Severe Accident Simulation Codes for Water F. Mascari 1, J. C. De
More informationGUIDELINES ON PRESSURIZED THERMAL SHOCK ANALYSIS FOR WWER NUCLEAR POWER PLANTS
IAEA-EBP-WWER-08 (Rev. 1) GUIDELINES ON PRESSURIZED THERMAL SHOCK ANALYSIS FOR WWER NUCLEAR POWER PLANTS Revision 1 A PUBLICATION OF THE EXTRABUDGETARY PROGRAMME ON THE SAFETY OF WWER AND RBMK NUCLEAR
More informationNuclear Power Plant C&I Design Verification by Simulation
GENES4/ANP2003, Sep. 15-19, 2003, Kyoto, JAPAN Paper 1034 Nuclear Power Plant C&I Design Verification by Simulation Joachim STORM 1*, Kim YU 2 and D.Y. LEE 3 1 Simulation Manager, STN ATLAS Elektronik,
More information30 th AND 29 th ANNIVERSARY OF REACTOR ACCIDENTS IN A-1 NPP JASLOVSKE BOHUNICE Summary XXVIII. Dny radiační ochrany, Luhačovice, , Sborn
30 th AND 29 th ANNIVERSARY OF REACTOR ACCIDENTS IN A-1 NPP JASLOVSKE BOHUNICE Summary XXVIII. Dny radiační ochrany, Luhačovice, 20.-24.11.2006, Sborník rozšířených abstraktů (author's formatted copy)
More informationVVER-440/213 - The reactor core
VVER-440/213 - The reactor core The fuel of the reactor is uranium dioxide (UO2), which is compacted to cylindrical pellets of about 9 height and 7.6 mm diameter. In the centreline of the pellets there
More informationNuclear Safety Standards Committee
Nuclear Safety Standards Committee 41 st Meeting, IAEA 21 23 Topical June, Issues 2016 Conference in Nuclear Installation Safety Agenda item Safety Demonstration of Advanced Water Cooled NPPs Title Workshop
More informationIAEA-TECDOC Probabilistic safety assessments of nuclear power plants for low power and shutdown modes
IAEA-TECDOC-1144 Probabilistic safety assessments of nuclear power plants for low power and shutdown modes March 2000 The originating Section of this publication in the IAEA was: Safety Assessment Section
More informationMonitoring of the EU Stress test improvement actions in neighbouring countries
Monitoring of the EU Stress test improvement actions in neighbouring countries Public Workshop: Five Years Fukushima, Thirty Years Chernobyl 26 th February 2016 Approach Review & monitoring of post Fukushima
More information