Country Report Switzerland 2011

Size: px
Start display at page:

Download "Country Report Switzerland 2011"

Transcription

1 Country Report Switzerland 2011 Manfred Märzendorfer NPP Leibstadt Switzerland (KKL) 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 1

2 NPP s in Switzerland & quota on electricity production 2010 KKL KKG 985 MW 1979 KKL 1165 MW 1984 KKG KKB1+2 PSI KKB MW KKM KKM 373 MW GWh 38 % Nuclear 57 % Hydro 5 % Other 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 2

3 Swiss NPP Net Production rd Meeting IAEA TWG-NPPCI Vienna Slide 3

4 Swiss NPP Performance figures Time availability (average) Energy utilization (average) Unplanned Scrams (total) Since 20 years no Scram in KKG!! 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 4

5 NPP Beznau Hydro Power Station will be replaced (reason for AUTANOVE) AWARE LCD Display elements will be replaced by LCD-monitors with similar look and feel (NEXIS) Kernenergie 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 5

6 NPP Beznau I&C-Projects since 2009 (in progress) Plant Process Computer (NEXIS) - Replacement of the 8.4 WDPF- based Process Information System incl. AWARE & COMPRO with an Emerson Ovation 3.5 System from Westinghouse. Upgrade of Teleperm XS - Upgrade of the reactor protection- & control-system from Siemens AREVA from Release 2.38c to Release 3.6 including deterministic physical barrier regarding IT-Security Independent Emergency Power Supply (AUTANOVE) - As part of a large plant modernization, the I&C for the independent emergency power supply will take advantage of COMMON-Q (AC-160) safety system supplied by Westinghouse 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 6

7 NPP Gösgen 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 7

8 NPP Gösgen I&C-Projects since 2009 (completed) Plant Process Computer (PRODIS) - Modernization of Data Aquisition System KKG development - Modernization of NW-structure - Redesign Display Pictures Turbine Control - Turbine control & protection Teleperm XS 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 8

9 NPP Gösgen I&C-Projects since 2009 (in progress, planned) Turbine Control - Bypass control (2011) Teleperm XS Process Control System Modernization (LETA) - Reactor control Teleperm XS - Reactor power limitation Teleperm XS - Feedwater control / Emergency feed control Teleperm XS - Neutron Flux Measurement (Incore) - Rod control & Rod position display Plant Process Computer (PRODIS) - Interface to digital I&C via MODBUS-Gateway 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 9

10 NPP Mühleberg Energie Kernkraft Mühleberg 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 10

11 NPP Mühleberg I&C-Projects since 2009 (completed) Plant Process computer NIS (Siempelkamp) Plant Process Visualisation System in the whole plant environment KKM development Core Monitoring upgrade GE-H and GNF Stability Monitor upgrade GSE Sweden Radwaste Simatic S7 Fire alarm management Siemens 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 11

12 NPP Mühleberg I&C-Projects since 2009 (completed) Reactor protection System - Replacement of rotating MG-sets by static UPS-systems Gutor Reactor Recirculation Pumps, Feedwater Pump C - Replacement of rotating MG-sets by static UPS-systems ABB ACS - Replacement of controls Procontrol P13 Enhancement of protection an control - for 6 kv bus E and start up transformer Siemens / Pfiffner Replacement of recorders by paperless recorders Yokogawa Renewal of pressure transmitters for turbine A & B Rosemount Replacement of fire protection system of SUSAN Siemens 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 12

13 NPP Leibstadt 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 13

14 NPP Leibstadt I&C-Projects since 2009 (completed) PCS - Modernization step 1 (ANIS+ PROMOD) 800xA/ - Additions & Expansions - control & monitoring new Block Transformer auxiliaries - Integration of several new or modified systems (Profibus) - Radwaste analog signals & alarms - Air Compressors etc. Radwaste - Measurement and analog control (Teleperm C) Simatic S7 Transient Analysis & Recording - Replacement of GETARS/GETPAR Computers ANIS+ / OSI PI - Replacement of Formatters C3-TREK Server IFTS - Replacement of relay control & conventional HSI Simatic S7 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 14

15 NPP Leibstadt I&C-Projects since 2009 (in progress) PCS - Modernization step 2 (ANIS+ NAMOD) 800xA/ HVAC-Systems (non safety related): Containment systems, Annulus systems Reactor auxiliary building, Radwaste Spent fuel building Turbine building (14 Cabinets) Condensate polishing plant (7 Cabinets) Demineralization plant Cooling tower makeup water plant (26 Cabinets) 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 15

16 Local Control Room Demineralization / Cooling tower make up water Auxiliary Control Room Demineralization, Cooling tower make up water Simatic S1 / Teleperm C panels 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 16

17 Local Control Room HVAC (will be taken out of service) Control Panel pneumatic analog control Operating Panel Automation & binary control Automation & binary control cabinet 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 17

18 Local Control Room Condensate polishing plant 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 18

19 Scope of modernization step MS2 (ANIS+ NAMOD) Process-Level - Sensors (analog & binary) approx Drives (open loop control) approx. 700 (incl. Solenoid valves) - Drives (closed loop control) approx Pneumatic control of HVAC approx. 70 pneumatic control loops approx. 50 pneumatic sensors HSI-Level - 2 Operating-Stations (PPA) in Auxiliary Control Room ( Water-House ) - 1 Large Screen Display in Auxiliary Control Room ( Water-House ) - 1 to 5 Touchpanel in Condensate Polishing Plant local control position 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 19

20 ANIS+ - actual concept of platform (as plant information system) Data to and from enterprise -NW C/S-NW Connection to MS2 C-NW1 + several expansions and new plant parts Serial time stamped events from existing I&C Hardwired analog and binary signals from existing I&C 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 20

21 2 PBS in ZM3 Control Room ANIS+ - Network & Controller expansion for MS 2 Connection to MS1 Client/Server-NW Control-NW2 CS21/22 2x2 Connectivity-Server ZE14R212 CS31/32 ZE14R213 Control-NW3 ZM10R355 Cooling 10 (Combit) Heating 10 (Combit) UW S800 S800 S800 S800 S800 TL1 TL2 UV1 UF, VF S800 UF10 S800 UF11 S800 UB1 S800 UB2 ZE12R105 ZB22R116 Ventilation 10 (Combit) ZB26R101-6 ZF10R035 CPP (Memostep) Div. 10 S800 S800 S800 S800 TL1 TL2 UV2 UF, VF ZB22R117 Ventilation 20 (Combit) Div. 20 UA1 S800 S800 VB1 VB2 S800 UW S800 Heating 20 (Combit) ZE12R105 Cooling 20 (Combit) S800 UF12 ZB26R101-6 S800 UF13 Demineralization (Simatic) S800 S800 S800 UA1 VB1 VB2 ZM10R355 CT-Make Up Water (Simatic) 18 redundant Controllers 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 21

22 ANIS+ - Modernization of process level (only one Division shown) MCR ZM3-CR Control-NW1 Control-NW3 ED1000 Combit (im ZE) Simatic (im ZM3) /S800 in ZE /S800 in ZM3 for UA und VB MCC MCC Prozess M M P M P M P P Prozess M M P M P M P P Example UA und VB 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 22

23 NPP Leibstadt I&C-Projects since 2009 (in progress) Rod Control & Information System - Replacement of transponders and display Flux Monitoring - Replacement of SRM- and IRM-Monitoring by a WRM-Solution NUMAC New WRNM displays on reactor desk New WRNM cabinets in RSD 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 23

24 NPP Leibstadt I&C-Projects since 2009 (in progress) Security Systems (ERSIS) - Display and alarm management system Simatic S7/Rubin 3C - Intrusion supervision - CCTV, perimeter supervision, access control, etc. - Alarm intercoms, etc. Fire protection and alarm management (TEBRA) - Fire alarm management Simatic S7/WIN CC - Fire protection Sinteso FC20xx (fire detectors, fire panels, extinguishing panels etc.) 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 24

25 Swiss Utilities New Nuclear Power Plant Projects 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 25

26 Swiss Utilities New Nuclear Power Plant Projects General Licence Applications for 3 new NPP s submitted to the SFOE - RESUN AG (Axpo / BKW) in December 2008: - at NPP Beznau and NPP Mühleberg site - KKN AG (Alpiq) in June 2008: - at NPP Gösgen site Conditional approval for all 3 sites published by SFOE in Nov Fukushima 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 26

27 Consequences of Fukushima Daiichi accident (1) Procedures for pending General Licence Applications suspended by Federal Council in March ENSI issued 3 directives to NPPs to proof their design for years earthquake years flooding - Combination of earthquake and flooding ENSI required a central storage for SAMG equipment which has to be - earthquake and flood proof - accessible by helicopter stationed in Switzerland - equipment has to be transportable by helicopter (if accessibility of plants in emergency is not given) Additionally ENSI issued a further directive to investigate spent fuel pool cooling (individual for each site) 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 27

28 Consequences of Fukushima Daiichi accident (2) Before Fukushima rather pro-nuclear public opinion skips to antinuclear (amplified by the media) May 22 nd people current against atom organized by anti nuclear organizations in the NPP Beznau vicinity - About participants - Peaceful event May 25 th the federal council (Bundesrat) decides on nuclear future - Different scenarios will be considered (fast, slow or no phase out) June 8 th the parliament (Nationalrat) discusses on nuclear future Outcome open, if pro nuclear Referendum against new nuclear plants almost sure!! 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 28

29 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 29

30 Swiss Recommendations (1) Design, Qualification, and Application of Digital I&C Systems - Investigating the best practices for the diversity and defence-in-depth analyses performed for digital I&C systems and determining what constitutes an adequate diversity and defence-in-depth - Selection and justification for level of diversity - Qualification of digital equipment and its programming. Type test of platforms. Requirements for safety application. Does object oriented programming provide the required reliability? - Hardware & Software Qualification Method for ASIC/CPLD/FPGA - TECDOC to establish engineering rules for plant computer system connecting to outsiders with respect to security - Qualification of I&C components. Harmonisation of qualification and type test of LOCA as well as non-loca, seismic and non-seismic, etc. qualified equipment 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 30

31 Swiss Recommendations (2) Modernisation of I&C Systems and Components - I&C Modernization Strategies for Plant-Wide Simplification and Cost Reduction I&C HW and SW Life-Cycle Related Issues - Configuration management guidelines for digital I&C systems - Dealing with short lifecycle of digital components Human Factors and Reliability, Main Control Room (MCR) Design, Human System Interface (HSI) - Upgrading existing control rooms: opportunities and limitations 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 31

32 I thank you for your kind attention! 23 rd Meeting IAEA TWG-NPPCI Vienna Slide 32

Modernisation of existing NPPs in Switzerland

Modernisation of existing NPPs in Switzerland Modernisation of existing NPPs in Switzerland Wolfgang Denk, Alpiq Suisse SA OECD/NEA Workshop in Innovations in Water-cooled Reactor Technologies Paris, 11 February 2015 Daily generation profiles 2013

More information

Design Safety Improvements at Swiss BWRs after Fukushima

Design Safety Improvements at Swiss BWRs after Fukushima Design Safety Improvements at Swiss BWRs after Fukushima IAEA Technical Meeting on Evaluation of NPP Safety Design in the Aftermath of the Fukushima - Daiichi Accident IAEA Technical Meeting, Vienna 26-29

More information

LONG-TERM OPERATION OF EXISTING REACTORS IN SWITZERLAND NEA WORKSHOP ON STAKEHOLDER INVOLVEMENT IN NUCLEAR DECISION MAKING RALF STRAUB

LONG-TERM OPERATION OF EXISTING REACTORS IN SWITZERLAND NEA WORKSHOP ON STAKEHOLDER INVOLVEMENT IN NUCLEAR DECISION MAKING RALF STRAUB LONG-TERM OPERATION OF EXISTING REACTORS IN SWITZERLAND NEA WORKSHOP ON STAKEHOLDER INVOLVEMENT IN NUCLEAR DECISION MAKING RALF STRAUB LONG-TERM OPERATION OF EXISTING REACTORS IN SWITZERLAND In 2011, after

More information

NPP I&C status In Brazil and Recommendations to IAEA. 26th Meeting of the IAEA TWG-NPPIC May 2017 Vienna

NPP I&C status In Brazil and Recommendations to IAEA. 26th Meeting of the IAEA TWG-NPPIC May 2017 Vienna NPP I&C status In Brazil and Recommendations to IAEA 26th Meeting of the IAEA TWG-NPPIC 24-26 May 2017 Vienna Salomão Gonçalves O. Jr Fuad Kassab Junior Eletrobras Eletronuclear University of São Paulo

More information

Integrated Plant Assessment to enable LTO in Gösgen

Integrated Plant Assessment to enable LTO in Gösgen Integrated Plant Assessment to enable LTO in Gösgen Dr. Jens-Uwe Klügel, NPP Goesgen-Daeniken (CH) Folie 1 Overview Summary Overview on actual Swiss Regulations related to LTO Post-Fukushima Safety Assessment

More information

Why I love working in the energy sector. Joanna Weng (BKW) Probabilistic safety Nuclear Power Plant

Why I love working in the energy sector. Joanna Weng (BKW) Probabilistic safety Nuclear Power Plant Why I love working in the energy sector Joanna Weng (BKW) Probabilistic safety analyst @ Nuclear Power Plant My HEP career at CMS 2002: Diploma thesis @ : simulation study Higgs to 4 muons 2003-2006: PhD

More information

Filtered Containment Venting Systems

Filtered Containment Venting Systems Swiss Federal Nuclear Safety Inspectorate ENSI Filtered Containment Venting Systems at Swiss NPPs and KKL in particular January 15, 2014, Ft. Lauderdale J. Hammer, ENSI, and A. Ritter, KKL Agenda Swiss

More information

Nuclear 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 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 information

Experience of operating nuclear district heating in Switzerland

Experience of operating nuclear district heating in Switzerland Experience of operating nuclear district i heating in Switzerland Technical & Economic Assessment of Non-Electric Applications Of Nuclear Power, 4 5 April 2013 Roland Schmidiger, Head of Asset Management

More information

ADVANCED I&C SYSTEMS FOR NUCLEAR POWER PLANTS FEEDBACK OF EXPERIENCE

ADVANCED I&C SYSTEMS FOR NUCLEAR POWER PLANTS FEEDBACK OF EXPERIENCE 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 information

Monitoring of the EU Stress test improvement actions in neighbouring countries

Monitoring 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

RESULTS OF THE GRADUAL UPGRADING AT BOHUNICE WWER - 440/230 NPP

RESULTS 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 information

Convention on Nuclear Safety

Convention on Nuclear Safety Implementation of the obligations of the Convention on Nuclear Safety CNS National Report of Switzerland for the Second Extraordinary Meeting in Accordance with Article 5 of the Convention May 2012 Implementation

More information

Steps towards a large-scale I&C modernization at the Paks NPP to support the planned plant service time extension

Steps towards a large-scale I&C modernization at the Paks NPP to support the planned plant service time extension Paks NPP Steps towards a large-scale I&C modernization at the Paks NPP to support the planned plant service time extension T. Túri, B. B Katics, J. Végh, E. Holló,, I. Varga e-mail: vej@sunserv.kfki.hu

More information

Protection of Nuclear Installations Against External Hazards

Protection of Nuclear Installations Against External Hazards TM on Evaluation of Nuclear Power Plant design safety in the Aftermath of the Fukushima Daiichi Accident Vienna, 26-29 August 2013 Protection of Nuclear Installations Against External Hazards Ovidiu Coman

More information

ASSESSMENTS OF SWEDISH NUCLEAR POWER PLANT IN THE AFTERMATH OF THE FUKUSHIMA DAIICHI ACCIDENT

ASSESSMENTS OF SWEDISH NUCLEAR POWER PLANT IN THE AFTERMATH OF THE FUKUSHIMA DAIICHI ACCIDENT ASSESSMENTS OF SWEDISH NUCLEAR POWER PLANT IN THE AFTERMATH OF THE FUKUSHIMA DAIICHI ACCIDENT Lovisa Wallin-Caldwell Outline Introduction Swedish nuclear power plants Swedish nuclear power regulation Back-fitting

More information

OE Supply-Chain in Nuclear Dr. Boris Gehring March 2017

OE Supply-Chain in Nuclear Dr. Boris Gehring March 2017 OE Supply-Chain in Nuclear Dr. Boris Gehring March 2017 2015-02-12 It should not finally look like this! Owners Engineers and Supply-Chain services In NPP New build, OE and SCS will help to keep: -Time-line

More information

Technical Meeting (TM) on Spent Fuel Storage Options IAEA Vienna, July

Technical Meeting (TM) on Spent Fuel Storage Options IAEA Vienna, July Technical Meeting (TM) on Spent Fuel Storage Options IAEA Vienna, July 2-4 2013 External Spent Fuel Storage Facility at the Nuclear Power Plant in Gösgen Urs Appenzeller, Nuclear Fuel Division, KKG Technical

More information

Raymond Cron, President STENFO Berne, Switzerland

Raymond Cron, President STENFO Berne, Switzerland Decommissioning Fund for Nuclear Facilities Waste Disposal Fund for Nuclear Power Plants International Conference on Financing of Decommissioning, 20-21 September 2016, Stockholm Financing Arrangements

More information

DESIGN AND SAFETY PRINCIPLES LEONTI CHALOYAN DEPUTY CHIEF ENGINEER ON MODERNIZATION

DESIGN 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 information

Improvement and Harmonisation in Nuclear Safety through Peer Reviews Key Note 2 Dr. Anton von Gunten, Mühleberg NPP BKW FMB Energie AG

Improvement and Harmonisation in Nuclear Safety through Peer Reviews Key Note 2 Dr. Anton von Gunten, Mühleberg NPP BKW FMB Energie AG Improvement and Harmonisation in Nuclear Safety through Peer Reviews Key Note 2 Dr. Anton von Gunten, Mühleberg NPP BKW FMB Energie AG Brussels, 25 April 2013 Plant Information Chronology of the Mühleberg

More information

PHWR Group of Countries Implementation of Lessons Learned from Fukushima Accident in CANDU Technology

PHWR Group of Countries Implementation of Lessons Learned from Fukushima Accident in CANDU Technology Implementation of Lessons Learned from Fukushima Accident in CANDU Technology Greg Rzentkowski Director General Directorate of Power Reactor Regulation Canadian Nuclear Safety Commission on behalf of CANDU

More information

SAM strategy&modifications and SA simulator at Paks NPP

SAM 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 information

Is Nuclear still an Option?

Is Nuclear still an Option? Is Nuclear still an Option? SCCER School Shaping the Energy Transition Engelberg, 19 October 2017 Dr. Philippe Renault, swissnuclear Who is swissnuclear? 1979 swissnuclear 1969 / 1971 is an association

More information

Wir schaffen Wissen heute für morgen

Wir schaffen Wissen heute für morgen Paul Scherrer Institut Wir schaffen Wissen heute für morgen Hakim Ferroukhi Laboratory for Reactor Physics and Systems Behaviour Switzerland LWR Activities 2012/2013 TWG-LWR 18 th Meeting, IAEA, Vienna,

More information

Format 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 - 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 information

Upgrading to modern computerized I&C. From old analog and computerized equipment to modern technology Karin Ferm Christoffer Calås

Upgrading to modern computerized I&C. From old analog and computerized equipment to modern technology Karin Ferm Christoffer Calås Upgrading to modern computerized I&C From old analog and computerized equipment to modern technology Karin Ferm Christoffer Calås Agenda 1. Purpose and research questions 2. Limitations 3. Analog versus

More information

Joint ICTP-IAEA Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety. Trieste,12-23 October 2015

Joint ICTP-IAEA Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety. Trieste,12-23 October 2015 Joint ICTP- Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety Trieste,12-23 October 2015 Safety classification of structures, systems and components

More information

Dr.-Ing. Rainer Kaulbarsch, Gösgen Power Plant (CH) August, 26th, 2013, Vienna

Dr.-Ing. Rainer Kaulbarsch, Gösgen Power Plant (CH) August, 26th, 2013, Vienna Safety Examinations and Improvements after Fukushima, Status Dr.-Ing. Rainer Kaulbarsch, Gösgen Power Plant (CH) August, 26th, 2013, Vienna Folie 1 Overview Introduction Examinations easures Outlook and

More information

THE 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 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 information

Accident 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 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 information

URESANDACTIONSCROSS-BORDERNETHER

URESANDACTIONSCROSS-BORDERNETHER ARTHQUAKESICEGERMANYMINIMUMTECH ICALSAFE TYREQUIREMENTSCZECHREPUB ICMUEHLEBERGSLOVAKRE PUBLICCOMPA ATIVECRITERIAFLOODINGNUCLEARACCID NTINFUKUSHIMABELGIUMNATURALDISAS ERSEXTREMECOLDEXTREMEHEATDAMA INGEFFECTSGOESGENSNOWEUWIDETEST

More information

Managing I&C Obsolescence for Plant Life Extension

Managing I&C Obsolescence for Plant Life Extension Managing I&C Obsolescence for Plant Life Extension IAEA-CN-155/075 Larry Chi Consulting Engineer Bin Zhang Senior Engineer GE-Hitachi Nuclear Energy October 2007 1 Managing I&C Obsolescence for Plant Life

More information

Pakistan s HWR Activities

Pakistan s HWR Activities 14 th Meeting of the Technical Working Group on Advanced Technologies of Heavy Water Reactors (TWG-HWR) Vienna, Austria 18-20 June 2013 Pakistan s HWR Activities by Shahid Saghir, Senior Manager (Technical)

More information

Relko Experience with Reliability Analyses of Safety Digital I&C

Relko Experience with Reliability Analyses of Safety Digital I&C Relko Experience with Reliability Analyses of Safety Digital I&C Jana Macsadiova a*, Vladimir Sopira a, Pavol Hlavac a a RELKO Ltd., Bratislava, Slovak Republic Abstract: The using of digital technologies

More information

Westinghouse Small Modular Reactor Development Overview

Westinghouse Small Modular Reactor Development Overview Westinghouse Small Modular Reactor Development Overview Small Modular Reactor Development Team Westinghouse Electric Company Dr. Nick Shulyak Presentation to IAEA July 4, 2011 1 SMR Product Specifications

More information

Implementation of the obligations of the

Implementation of the obligations of the Implementation of the obligations of the The fourth Swiss report in accordance with Article 5 July 2007 2 Convention on Nuclear Safety fourth Swiss report Contents Contents Foreword...3 Summary and conclusions...4

More information

Compilation of recommendations and suggestions

Compilation of recommendations and suggestions Post- Fukushima accident Compilation of recommendations and suggestions Peer review of stress tests performed on European nuclear power plants 26/07/2012 Compilation of Recommendations and Suggestions

More information

Removing a Blind Spot in Our Safety Culture

Removing a Blind Spot in Our Safety Culture Removing a Blind Spot in Our Safety Culture By: Karl N. Fleming, President KNF Consulting Services LLC KarlFleming@comcast.net Presented to: American Nuclear Society PSA 2017 Pittsburgh, PA September,

More information

AP1000 European 16. Technical Specifications Design Control Document

AP1000 European 16. Technical Specifications Design Control Document 16.3 Investment Protection 16.3.1 Investment Protection Short-term Availability Controls The importance of nonsafety-related systems, structures and components in the AP1000 has been evaluated. The evaluation

More information

Implementation of post-fukushima international recommendations. Switzerland

Implementation of post-fukushima international recommendations. Switzerland Implementation of post-fukushima international recommendations Switzerland Table of contents 1 Introduction 2 2 Implementation status in Switzerland of International Recommendations 5 2.1 Table 1: ENSREG

More information

AP1000 European 21. Construction Verification Process Design Control Document

AP1000 European 21. Construction Verification Process Design Control Document 2.5 Instrumentation and Control Systems 2.5.1 Diverse Actuation System Design Description The diverse actuation system (DAS) initiates reactor trip, actuates selected functions, and provides plant information

More information

The Risk of Nuclear Power

The Risk of Nuclear Power 13 th International Conference on Probabilistic Safety Assessment and Management [PSAM13] The Risk of Nuclear Power Soon Heung Chang Handong Global University Oct 4, 2016 Contents 1 2 3 4 Introduction:

More information

Module 05 WWER/ VVER (Russian designed Pressurized Water Reactors)

Module 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 information

Cost Study 2011 (CS11) Overview Report

Cost Study 2011 (CS11) Overview Report Cost Study 2011 (CS11) Overview Report swissnuclear Nuclear Energy Section of Swisselectric Aarauerstrasse 55 P.O BOX 1663 CH-4601 Olten T +41 62 205 20 10 F +41 62 205 20 11 info@swissnuclear.ch www.swissnuclear.ch

More information

Accident Diagnostic, Analysis and Management (ADAM) System Applications to Severe Accident Management *

Accident 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 information

SAFETY IMPROVMENTS AT KANUPP. Ahsan Ullah Khan Principal Engineer Karachi Nuclear Power Plant

SAFETY IMPROVMENTS AT KANUPP. Ahsan Ullah Khan Principal Engineer Karachi Nuclear Power Plant SAFETY IMPROVMENTS AT KANUPP Ahsan Ullah Khan Principal Engineer Karachi Nuclear Power Plant General 137 Mwe CANDU Plant Started commercial operation in 1972 Design life of 30 years completed in 2002 An

More information

ACTIONS TO PROTECT NPPS AGAINST EXTERNAL AND INTERNAL EVENTS AND R&D ACTIVITIES IN FINLAND

ACTIONS TO PROTECT NPPS AGAINST EXTERNAL AND INTERNAL EVENTS AND R&D ACTIVITIES IN FINLAND ACTIONS TO PROTECT NPPS AGAINST EXTERNAL AND INTERNAL EVENTS AND R&D ACTIVITIES IN FINLAND International Experts Meeting on Strengthening Research and Development Effectiveness in the Light of the Accident

More information

THE FUKUSHIMA ACCIDENT: IMPLICATIONS FOR NUCLEAR SAFETY. Edwin Lyman Union of Concerned Scientists May 26, 2011

THE FUKUSHIMA ACCIDENT: IMPLICATIONS FOR NUCLEAR SAFETY. Edwin Lyman Union of Concerned Scientists May 26, 2011 THE FUKUSHIMA ACCIDENT: IMPLICATIONS FOR NUCLEAR SAFETY Edwin Lyman Union of Concerned Scientists May 26, 2011 The accident: many unknowns Many of the details of the Fukushima Daiichi accident are still

More information

Selection, specification, design and use of various nuclear power plant training simulators

Selection, 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 information

Development and use of SAMGs in the Krško NPP

Development 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 information

Preliminary 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 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 information

New Safety Requirements Addressing Feedback From the Fukushima Daiichi Accident

New Safety Requirements Addressing Feedback From the Fukushima Daiichi Accident FEDERAL ENVIRONMENTAL, INDUSTRIAL AND NUCLEAR SUPERVISION SERVICE (ROSTECHNADZOR) New Safety Requirements Addressing Feedback From the Fukushima Daiichi Accident Alexander Sapozhnikov Department for Safety

More information

Answers to Questions on the National Report

Answers 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 information

Extension to 60 years lifetime

Extension to 60 years lifetime SFEN Conference Atoms for the future October 22 nd -25 th 2012 Extension to 60 years lifetime J.M.Moroni EDF Nuclear Engineering Division PLIM 2012-14-18 May 2012 - Salt Lake City, USA. Summary Elements

More information

CNS. Convention on Nuclear Safety. July 2016 Switzerland s Seventh National Report to the Convention on Nuclear Safety

CNS. Convention on Nuclear Safety. July 2016 Switzerland s Seventh National Report to the Convention on Nuclear Safety CNS Implementation of the obligations of the Convention on Nuclear Safety July 2016 Switzerland s Seventh National Report to the Convention on Nuclear Safety Implementation of the Obligations of the Convention

More information

4.2 DEVELOPMENT OF FUEL TEST LOOP IN HANARO

4.2 DEVELOPMENT OF FUEL TEST LOOP IN HANARO 4.2 DEVELOPMENT OF FUEL TEST LOOP IN HANARO Sungho Ahn a, Jongmin Lee a, Suki Park a, Daeyoung Chi a, Bongsik Sim a, Chungyoung Lee a, Youngki Kim a and Kyehong Lee b a Research Reactor Engineering Division,

More information

Post-Fukushima Assessment of the AP1000 Plant

Post-Fukushima Assessment of the AP1000 Plant ABSTRACT Post-Fukushima Assessment of the AP1000 Plant Ernesto Boronat de Ferrater Westinghouse Electric Company, LLC Padilla 17-3 Planta 28006, Madrid, Spain boronae@westinghouse.com Bryan N. Friedman,

More information

OSART Good Practices OPERATIONAL EXPERIENCE FEEDBACK Utilization and dissemination of operating experience

OSART Good Practices OPERATIONAL EXPERIENCE FEEDBACK Utilization and dissemination of operating experience OSART Good Practices OPERATIONAL EXPERIENCE FEEDBACK Utilization and dissemination of operating experience St. Laurent, France Mission Date; 27 Nov.-14 Dec., 2006 Operational experience during outages

More information

INA - OFIG/ETAN - Gas treatment plant DCS - Automation System

INA - OFIG/ETAN - Gas treatment plant DCS - Automation System INA - OFIG/ETAN - Gas treatment plant DCS - Automation System About the Plant Gas treatment plant OFIG/ETAN is operated by national oil & gas company "INA industrija nafte d.d.". The plant started with

More information

Results and Insights from Interim Seismic Margin Assessment of the Advanced CANDU Reactor (ACR ) 1000 Reactor

Results and Insights from Interim Seismic Margin Assessment of the Advanced CANDU Reactor (ACR ) 1000 Reactor 20th International Conference on Structural Mechanics in Reactor Technology (SMiRT 20) Espoo, Finland, August 9-14, 2009 SMiRT 20-Division 7, Paper 1849 Results and Insights from Interim Seismic Margin

More information

ABSTRACT DESING AND IMPLEMENTATION OF FORCED COOLING TOWERS FOR LOVIISA NPP SAFETY- AND RESIDUAL HEAT REMOVAL (RHR) COOLING CIRCUITS

ABSTRACT DESING AND IMPLEMENTATION OF FORCED COOLING TOWERS FOR LOVIISA NPP SAFETY- AND RESIDUAL HEAT REMOVAL (RHR) COOLING CIRCUITS ABSTRACT DESING AND IMPLEMENTATION OF FORCED COOLING TOWERS FOR LOVIISA NPP SAFETY- AND RESIDUAL HEAT REMOVAL (RHR) COOLING CIRCUITS S.Tarkiainen, T.Hyrsky, I.Paavola, A.Teräsvirta Fortum Nuclear and Thermal

More information

Nuclear Power Plant C&I Design Verification by Simulation

Nuclear 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 information

India s HWR Activities S.G.Ghadge Executive Director (Reactor Safety & Analysis) Nuclear Power Corporation of India Limited

India s HWR Activities S.G.Ghadge Executive Director (Reactor Safety & Analysis) Nuclear Power Corporation of India Limited India s HWR Activities S.G.Ghadge Executive Director (Reactor Safety & Analysis) Nuclear Power Corporation of India Limited 13 th Meeting of the Technical Working Group on Advanced Technologies for HWRs

More information

Expanding Capabilities of PSA To Address Multi-Unit Sites

Expanding Capabilities of PSA To Address Multi-Unit Sites Expanding Capabilities of PSA To Address Multi-Unit Sites By: Karl N. Fleming, President KNF Consulting Services LLC KarlFleming@comcast.net Presented to: CRA s 6 th Risk Forum Warwick UK September 16

More information

ESSENCE AND CHARACTERISTICS OF THE ATMEA TECHNOLOGY: THE ATMEA1 REACTOR

ESSENCE AND CHARACTERISTICS OF THE ATMEA TECHNOLOGY: THE ATMEA1 REACTOR ESSENCE AND CHARACTERISTICS OF THE ATMEA TECHNOLOGY: THE ATMEA1 REACTOR Antoine VERDIER Business Development Manager BULATOM Varna / June 4 th, 2014 An AREVA and MHI Company Introduction ATMEA Company

More information

Training Center Germany. Course Catalog. Training DTITY5-G

Training Center Germany. Course Catalog. Training DTITY5-G Training Center Germany Course Catalog Training DTITY5-G Editorial Welcome to your center for nuclear training courses A company s success and ability to compete critically depends on the competency of

More information

Country Presentation. Ukraine

Country 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 information

Fukushima Daiichi NPP Accident

Fukushima Daiichi NPP Accident Fukushima Daiichi NPP Accident Plant Design and Preliminary Observations K. Moriya and K. Sato Hitachi GE Nuclear Energy, Ltd. May 3, 2011 [Note] 1. The view expressed herein are not the official view

More information

Olkiluoto 3 EPR PSA Main results and conclusions fulfillment of the regulatory requirements for operating license

Olkiluoto 3 EPR PSA Main results and conclusions fulfillment of the regulatory requirements for operating license Olkiluoto 3 EPR PSA Main results and conclusions fulfillment of the regulatory requirements for operating license Presented by: Heiko Kollasko Framatome Co-Authors: Roman Grygoruk AREVA Gerben Dirksen

More information

Challenges going from analog to digital controls in NPP NUCLEAR POWER EUROPE 2012

Challenges going from analog to digital controls in NPP NUCLEAR POWER EUROPE 2012 ABB, Atos, 2012 Challenges going from analog to digital controls in NPP NUCLEAR POWER EUROPE 2012 101216_BaldorIntegration_SteeCo_1_0 June 14, 2012 Slide 1 Summary ABB-Atos fully integrated nuclear solution

More information

Accident Management Guidance for Spent Fuel Pools and Shutdown Conditions

Accident Management Guidance for Spent Fuel Pools and Shutdown Conditions Accident Management Guidance for Spent Fuel Pools and Shutdown Conditions Roy Harter RLH Global Services rlharter@aol.com SAMG-D course, IAEA, Vienna, Austria 19-23 October 2015 IAEA Safety Guide NS-G-2.15

More information

Document Preparation Profile (DPP)

Document Preparation Profile (DPP) Document Preparation Profile (DPP) 1. IDENTIFICATION Document Category: Safety Guide Working ID: DS 431 Proposed Title: Proposed Action: Design of I&C Systems for NPPs Combine and update NS-G-1.1 and NS-G-1.3

More information

WENRA and its expectations on the safety of new NPP

WENRA and its expectations on the safety of new NPP WENRA and its expectations on the safety of new NPP INPRO Dialogue Forum on Global Nuclear Energy Sustainability Licensing and Safety Issues for Small- and Medium-sized Reactors (SMRs) Vienna, 29 July

More information

KEEPING PACE WITH THE DEVELOPMENT OF NUCLEAR ENERGY IN SWITZERLAND - ACTIVITIES OF THE SWISS NUCLEAR SOCIETY YOUNG GENERATION

KEEPING PACE WITH THE DEVELOPMENT OF NUCLEAR ENERGY IN SWITZERLAND - ACTIVITIES OF THE SWISS NUCLEAR SOCIETY YOUNG GENERATION KEEPING PACE WITH THE DEVELOPMENT OF NUCLEAR ENERGY IN SWITZERLAND - ACTIVITIES OF THE SWISS NUCLEAR SOCIETY YOUNG GENERATION Maria Andersson 1, Matthias Horvath 2, Paolo Mini 3, Dragoslav Tanić 4, Thomas

More information

MONITORING OF WATER LEVEL INSIDE REACTOR PRESSURE VESSEL

MONITORING OF WATER LEVEL INSIDE REACTOR PRESSURE VESSEL U'!:'/,,SAFETY RELATED MEASUREMENTS IN PWRs" MONITORING OF WATER LEVEL INSIDE REACTOR PRESSURE VESSEL Dr. rer. Nat. Wilfried Harfst Framatome ANP GmbH mm 11 SK02ST010 1 Introduction Up to the TMI accident

More information

Control Systems. Engineering and Technical Services. From conception to completion, we are ready to make your control system project a success.

Control Systems. Engineering and Technical Services. From conception to completion, we are ready to make your control system project a success. From conception to completion, we are ready to make your control system project a success. 2017 Control Systems Engineering and Technical Services CONTACT: Kevin Cole +1 201.986.4279 office +1 201.334.6064

More information

Online Interfaces and Optional Features

Online Interfaces and Optional Features Product Data Sheet Online Interfaces and Optional Features n Fully implement predictive diagnostics to improve plant availability and reduce maintenance costs n Gain enhanced information and diagnostic

More information

NPP Simulators Workshop for Education - Passive PWR NPP & Simulator Overview

NPP 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 information

Post Fukushima actions in India. Mukesh Singhal, Chief Engineer, Reactor Safety & Analysis Directorate NPCIL

Post Fukushima actions in India. Mukesh Singhal, Chief Engineer, Reactor Safety & Analysis Directorate NPCIL Post Fukushima actions in India Mukesh Singhal, Chief Engineer, Reactor Safety & Analysis Directorate NPCIL 14 th Meeting of IAEA-TWG on advance technologies, IAEA, Vienna, June 18-20, 2013 Presentation

More information

UKEPR Issue 04

UKEPR Issue 04 Title: PCSR Sub-Chapter 7.2 General architecture of the Instrumentation and Control systems Total number of pages: 76 Page No.: I / IV Chapter Pilot: B. WORINGER Name/Initials Date 05-11-2012 Approved

More information

Han MK, Business Development (Power Generation), 23rd March 2010 ABB Power and Automation Days ABB in Power Generation

Han MK, Business Development (Power Generation), 23rd March 2010 ABB Power and Automation Days ABB in Power Generation Han MK, Business Development (Power Generation), 23rd March 2010 ABB Power and Automation Days ABB in Power Generation Content ABB Power Generation ABB Solutions for Power Generation ABB Solutions for

More information

Nuclear Safety Standards Committee

Nuclear 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 information

TS1-5: Revision of NS-G-2.15 and Its Implementation for Verification and Validation of Severe Accident Management Guidelines

TS1-5: 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 information

Eletronuclear ( Brazil) Fukushima Response Plan

Eletronuclear ( Brazil) Fukushima Response Plan Eletronuclear ( Brazil) Fukushima Response Plan Edmundo Selvatici Site Manager Mario de Mello Ferreira Junior Manager, Materials Engineering Technical Meeting on Operational Experience with Implementation

More information

CNSC Fukushima Task Force Nuclear Power Plant Safety Review Criteria

CNSC Fukushima Task Force Nuclear Power Plant Safety Review Criteria CNSC Fukushima Task Force E-doc 3743877 July 2011 Executive Summary In response to the March 11, 2011 accident at the Fukushima Daiichi Nuclear Power Plant (NPP), the CNSC convened a Task Force to evaluate

More information

Considerations on the performance and reliability of passive safety systems for nuclear reactors

Considerations on the performance and reliability of passive safety systems for nuclear reactors January 2016 Considerations on the performance and reliability of passive safety systems for nuclear reactors I. Background Pressurized water reactors currently operating in France are equipped with safety

More information

Country Presentation. Ukraine

Country Presentation. Ukraine Country Presentation. Ukraine 24th Meeting of the IAEA Technical Working Group on Nuclear Power Plant Instrumеntation and Control (TWG -NPPIC) May 22-24, 2013,, Austria Vladimir Sklyar, RPC Radiy TOP5

More information

A Research Reactor Simulator for Operators Training and Teaching. Abstract

A 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 information

AP1000 European 7. Instrumentation and Controls Design Control Document

AP1000 European 7. Instrumentation and Controls Design Control Document 7.5 Safety-Related Display Information 7.5.1 Introduction An analysis is conducted to identify the appropriate variables and to establish the appropriate design bases and qualification criteria for instrumentation

More information

Sixth Implementation Report: Report in accordance with PARCOM Recommendation 91/4 on radioactive discharges

Sixth Implementation Report: Report in accordance with PARCOM Recommendation 91/4 on radioactive discharges Sixth Implementation Report: Report in accordance with PARCOM Recommendation 91/4 on radioactive discharges Switzerland Radioactive Substances Series 2014 Sixth Implementation Report: Report in Accordance

More information

DEVELOPMENT OF INTEGRATED SITE RISK USING THE MULTI-UNIT DYNAMIC PROBABILISTIC RISK ASSESSMENT (MU-DPRA) METHODOLOGY

DEVELOPMENT OF INTEGRATED SITE RISK USING THE MULTI-UNIT DYNAMIC PROBABILISTIC RISK ASSESSMENT (MU-DPRA) METHODOLOGY DEVELOPMENT OF INTEGRATED SITE RISK USING THE MULTI-UNIT DYNAMIC PROBABILISTIC RISK ASSESSMENT (MU-DPRA) METHODOLOGY Matt Dennis Mohammad Modarres Ali Mosleh September 24-28, 2017 PSA 2017 Pittsburgh,

More information

HPR1000: ADVANCED PWR WITH ACTIVE AND PASSIVE SAFETY FEATURES

HPR1000: ADVANCED PWR WITH ACTIVE AND PASSIVE SAFETY FEATURES HPR1000: ADVANCED PWR WITH ACTIVE AND PASSIVE SAFETY FEATURES D. SONG China Nuclear Power Engineering Co., Ltd. Beijing, China Email: songdy@cnpe.cc J. XING China Nuclear Power Engineering Co., Ltd. Beijing,

More information

Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant

Concepts 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 information

Nuclear 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 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 information

Nuclear 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 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 information

Westinghouse AP1000 Nuclear Power Plant

Westinghouse AP1000 Nuclear Power Plant Westinghouse AP1000 Nuclear Power Plant Westinghouse AP1000 Nuclear Power Plant AP1000 is a registered trademark in the United States of Westinghouse Electric Company LLC, its subsidiaries and/or its affiliates.

More information

Implementation of Lessons Learned from Fukushima Accident in CANDU Technology

Implementation of Lessons Learned from Fukushima Accident in CANDU Technology e-doc 4395709 Implementation of Lessons Learned from Fukushima Accident in CANDU Technology Greg Rzentkowski Director General, Power Reactor Regulation Canadian Nuclear Safety Commission on behalf of CANDU

More information

Raising automation level at a Swiss HPP Rene Neubert, Sales Director Valmet, Automation business line Austria

Raising automation level at a Swiss HPP Rene Neubert, Sales Director Valmet, Automation business line Austria 1 Raising automation level at a Swiss HPP Rene Neubert, Sales Director Valmet, Automation business line Austria Abstract Energie Wasser Bern Felsenau hydroelectric power plant is situated on the Aare River

More information

STATUS, ACHIEVEMENTS & FUTURE CHALLENGES

STATUS, ACHIEVEMENTS & FUTURE CHALLENGES STATUS, ACHIEVEMENTS & FUTURE CHALLENGES FOR KANUPP By Muhammad Rashidullah, Senior Manager Technical Division, KANUPP, Pakistan 13 th Meeting of TWG-HWR on Advance Technologies, June 18-20, 2012, Vienna,

More information