GenIII/III+ Nuclear Reactors

Similar documents
Olkiluoto Infrastructure

NEW POWER REACTOR DESIGNS

SEVERE ACCIDENT FEATURES OF THE ALTERNATIVE PLANT DESIGNS FOR NEW NUCLEAR POWER PLANTS IN FINLAND

Regulatory Approach to Radiation Protection in new NPPs in Finland

Module 06 Boiling Water Reactors (BWR)

Decommissioning plans for TVO's new reactors

Next and Last Generation of Nuclear Power Plants Paul Howarth

Finnish Approach to Nuclear Waste and Competence Management

Nuclear Fuel Supply. URENCO s Perspective. 15 November Copyright 2017 URENCO Limited

Nuclear Energy in France Current Trends and Impact on the Bilateral Ties with Japan

Module 06 Boiling Water Reactors (BWR) Vienna University of Technology /Austria Atominstitute Stadionallee 2, 1020 Vienna, Austria

Nuclear Power Plant Life

Nuclear Reactor Types

Global Perspectives on SMRs Developing Countries Expectations

Westinghouse Holistic Approach to the Nuclear Fuel Cycle

HTR Reactors for Industry Perspectives of Nuclear Cogeneration

Nuclear Power Reactors. Kaleem Ahmad

National Status on Life Management of NPPs in Finland Meeting of the IAEA TWG-LMNPP February th 2017 Vienna, Jyrki Kohopää

Concept and technology status of HTR for industrial nuclear cogeneration

Module 02 Nuclear Engineering Overview

10. Nuclear Fission Power Generation

Small Modular Reactors

FOURTH GENERATION REACTOR CONCEPTS

Controlled management of a severe accident

A Survey of Power Plant Designs

Finnish report on nuclear safety

Gen-III/III+ Reactors: Solving the Future Energy Supply Shortfall The SWR-1000 Option

Nuclear Power Development in Europe: Rosatom perspective

Nuclear Reactor Types. An Environment & Energy FactFile provided by the IEE. Nuclear Reactor Types

Olli Vilkamo; Kirsi Alm-Lytz Radiation and Nuclear Safety Authority, STUK. Radiation Safety in New Build

ASSESSMENT OF REACTOR VESSEL INTEGRITY (ARVI)

Comparison of In-Vessel and Ex-Vessel Retention

Small Modular Reactors & waste management issues

The Prospects for Nuclear Energy: Fuel Reserves, Waste and Proliferation

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

APPROACH TO PRACTICAL ELIMINATION IN FINLAND

Enhancement of Nuclear Safety

CERTA - TN. F. D Auria

Advanced Reactors Mission, History and Perspectives

High Temperature Gas Cooled Reactors

PRESS CONFERENCE. 3 September Jean-Bernard LÉVY Chairman and CEO. Xavier URSAT Group Senior Executive VP - New Nuclear Projects and Engineering

THE EPR OF FLAMANVILLE

Technological Solutions of SF Storage in the World

Vice President, GDF SUEZ Nuclear Activities May 13, 2010

The European nuclear industry and research approach for innovation in nuclear energy. Dominique Hittner Framatome-ANP EPS, Paris, 3/10/2003

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

AREVA Nuclear Professional School

France s Nuclear Energy : Status and Prospects

Latest Developments in Small Modular Reactors. Dr Adi Paterson Annual Meeting of Four Societies 2015

Challenges for a TSO supporting both the regulator and industry. Eija Karita Puska VTT Technical Research Centre of Finland

A canter around the nuclear jumps..

EPR: Steam Generator Tube Rupture analysis in Finland and in France

Ageing Management and Long Term Operation of Nuclear Power Plants

Up-to-date issues of VVER Technology Development

Small Modular Reactors. Kristiina Söderholm, PhD Head of Nuclear Technology & Innovation Fortum, Finland

Decommissioning of Nuclear Facilities: The Work Ahead and How to Succeed

1.JAEA s Strategy for the International Cooperation (Overview)

AND SITE LICENSING OF THE EPR FOR THE HINKLEY POINT C PROJECT

ANTICIPATED ANALYSIS OF FLAMANVILLE 3 EPR OPERATING LICENSE - STATUS AND INSIGHTS FROM LEVEL 1 PSA REVIEW

From the Safety Approach of a Nuclear Power Plant, to the Manufacturing and Welding of Mechanical Components in line with RCC-M Code

Available online at ScienceDirect. Procedia Engineering 86 (2014 )

Current Status and Future Challenges of Innovative Reactors Development in Japan

5th Meeting of European MELCOR User Group (EMUG): Improved In-Vessel-Retention Model

The risk of reactor pressure vessel material degradation Doel-3/Tihange-2

STUDY ON IN-VESSEL RETENTION (IVR) STRATEGY FOR CPR1000

Nuclear power - basis, challenges and global status

Involvement of EDF in the Halden Reactor Project: a long-term cooperation in R&D

DESIGN, SAFETY FEATURES & PROGRESS OF HTR-PM. Yujie DONG INET, Tsinghua University, China January 24, 2018

EFC WP4 EUROPEAN FEDERATION OF CORROSION EUROPÄISCHE FÖDERATION KORROSION FEDERATION EUROPEENNE DE LA CORROSION

NUCLEAR ENERGY MATERIALS AND REACTORS Vol. I - Pressurized Water Reactors - J. Pongpuak

Status of Advanced Reactor Development and Deployment. Global Nexus Initiative Workshop

NUCLEAR ENERGY MATERIALS AND REACTORS - Vol. II - Advanced Gas Cooled Reactors - Tim McKeen

FRANCE LWR activities

Overview for a feasibility study

The ESBWR an advanced Passive LWR

WM2014 Conference, March 2 6, 2014, Phoenix, Arizona, USA

The Economics of Nuclear Power

Ensuring Spent Fuel Pool Safety

The MIT Research Reactor as a National User Facility for Advanced Materials and Fuel Research

MOX use in PWRs EDF operation experience Jean-Luc Provost Nuclear Operation Division EDF - Generation

Dynamic Analysis of Nuclear Energy System Strategies for Electricity and Hydrogen Production in the USA

Energie. Erzeugung - Netze - Nutzung

Nuclear power: OECD/NEA perspective

The Rise of Power Reactors. Mario van der Borst KIVI/NNS Symposium Delft, 3 November 2017

LIFE CYCLE MANAGEMENT OF LOVIISA NPP

BN-1200 Reactor Power Unit Design Development

AREVA Group development strategy in post- Fukushima environment

High Temperature Gas-Cooled Reactors Now More Than Ever!

Risk-informed classification of systems, structures and components

Risks of Nuclear Ageing

Generation IV reactor systems and fuel cycles (horizon 2030): technological breakthroughs in nuclear fission (int'l RD&DD)

27 June 2013 Warsaw, Poland. Platts 8 th Annual European Nuclear Power 2013 Procurement for New Nuclear Programs

The Current Status and Perspectives for the Use of Small Modular Reactors for Electricity Generation

Experiments of the LACOMECO Project at KIT

WM2013 Conference, February 24 28, 2013, Phoenix, Arizona, USA. Current Status of the Nuclear Waste Management Programme in Finland 13441

International Thorium Energy Conference 2015 (ThEC15) BARC, Mumbai, India, October 12-15, 2015

Rosatom Global Development, International Cooperation Perspective

Simulation of Fatigue relevant thermal Loads of Components in Piping Networks

Small Modular Reactor Materials R&D Program Materials Coordination Webinar

Research on the Mechanism of Debris Bed Stratification. in Vessel Lower Plenum

Transcription:

OL1&2 GenII GenIII OL3 TVO s Olkiluoto Nuclear Power Plant in Finland GenIII/III+ Nuclear Reactors RESEARCH NEEDES AND CHALLENGES FISA 2009, Prague

Contents What are the GenIII features Evolutionary development and improvements Commercial GenIII power plant features OL3 / EPR features Needs and challenges for R&D Areas of research for GenIII nuclear reactors EU FP6 and 7 projects GenIII/III+ New challenges and needs for R&D and resources 2

EARLY PROTOTYPES COMMERCIAL POWER REACTORS NEW GENERATION LWR- PLANTS + HTR GENERATION IV Magnox (1956) Shippingport (1957) Dresden (1959) RBMK (1963) FBR (1963) HTR (1966) LWR: PWR and BWR CANDU, AGR Economically more competitive evolution types High efficiency Long life time Passive safety VVER-1000, ABWR EPR SWR-1000, AP-1000 ESBWR-1500 Very competitive New application, such as process heat Enhanced/inherent safety features Reduced waste generation Improved proliferation resistance 50 MW 500 MW 1 300 MW 1 600 MW (200) -1 600 MW Generation I Generation II Generation III III+ Generation IV 1950 1960 1970 1980 1990 2000 2010 2020 2030 In Finland: Commissioning of present 4 units (Loviisa & Olkiluoto) Olkiluoto3 commissioned Decommissioning of present plants after 50-60 years lifetime 3

GenIII/III+ nuclear reactor features A GenIII reactor incorporates evolutionary improvements in design developed during the lifetime of the GenII reactor designs: improved fuel technology superior thermal efficiency passive safety systems and standardized design for reduced maintenance and capital costs. Development will result in a longer operational life, 50 to 60 years compared to Gen II reactors with 20 to 30 years (today extended +20 yrs to meet the needs before GenIII). The first Gen III reactors were built in Japan, several others have been approved for construction. In Europe in Finland and France plant construction is ongoing (Olkiluoto and Flamanville). 4

GenIII/III+ nuclear reactor features Advanced Pressurized Water Reactors, 600 1 600 MWe: AP 600, AP 1000, APR1400, APWR+, EPR Advanced Boiling Water Reactors, 1 250 1 550 MWe: ABWR II, ESBWR, HC-BWR, SWR-1000 The market prospects: A large industrial offer: USA NRC 28 + China, India, South Korea 85 + Europe 2 + XX = 110 new reactors by 2020. The nuclear power capacity could grow from 400 GWe to 1000-1500 GWe by 2050. Most of the new NPP will be Gen III systems. IAEA energy technology roadmaps, Paris 08 http://www.eia.doe.gov/cneaf/nuclear/page/analysis/nucenviss2.html 5

GenIII/III+ nuclear reactor features EPR at Olkiluoto plant May 2009 6

GenIII/III+ nuclear reactor features Main EPR Safety Features Double containment with ventilation and filtration Melt core cooling area Containment heat dispersion system Water reserves inside the containment Four redundant safety systems 7

OL3 REACTOR MAIN DATA Property value Property value Thermal output 4300 MW Number of fuel assemblies 241 Net electric output Approx. 1 600 MW Amount of uranium in reactor 128 tons Operating pressure 155 bar Number of control rods 89 Main steam temperature 290 C Containment height 63 m Pressure vessel height 13 m Containment diameter 57 m Reactor core height 4,2 m Containment wall thickness 2 m 8

GenIII/III+ features and needs => R&D challenges High safety/passive safety, design for: Reactor core melting Jet aircrash Extreme weather conditions Securing digital instrumentation and control systems with an analogue system (Finnish requirement) 1. Severe accidents 2. Construction safety 3. Probabilistic safety/risk analysis 4. Automation and control room (development and use of digital automation) 5. R&D support for building and manufacturing industry to meet the requirements 9

EU SAFETY and SEVERE ACCIDENTS projects in FP6 and FP7 SARnet NoE - Sustainable integration of European Research on Severe Accident Methodology and Management SARNET 2 - > 2009 NURESIM - European Platform for Nuclear Reactor Simulations: Numerical simulation tools for coupled thermal hydraulics and reactor physics problems FP7, NUclear Reactor Integrated Project = NURISP More accurate physics, multiscale and multiphysics, S&U, integration and fuel performance as a new field. Application to LWR (Gen-II and Gen-III): PWR, VVER, BWR Links with other European Projects : PERFORM, PRACE 10

competitive pre-competitive GenIII/III+ features and needs => R&D challenges New reactor designs: Long life time, design for 60 yrs High efficiency (EPR about 4 % higher than present units) High burn up (fuel & water chemistry issues, core design) New fuel and cladding types High operability requirements Improved predictability for maintenance Power uprating potential 1. Fuel and reactor physics 2. Thermal hydraulics 3. Structural safety of reactor circuit and 4. Aging management 5. Probabilistic safety/risk analysis 6. Asset management 11

EU PERFORM60 Multiscale modelling of irradiation effects and embrittlement for 60 years reactor lifetime (FP7) First stage: PERFECT- Prediction of Irradiation Damage Effects on Reactor Components Core Partners: AREVA NP GmbH, CEA (SRMP), CNRS (Lille, LMPGM), EDF, NRI, SCK-CEN, SERCO, VTT 6 M budget from EU 12

K JC [MPa m] (B 0 =25 mm) Cleavage fracture model development: FEM simulation 350 300 250 REF IRR 95 % 5 % 95 % Effect of irradiation on fracture toughness 200 150 5 % 100 50 0-100 -50 0 50 100 150 200 T [ 0 C] 13

EU NULIFE - Nuclear plant life prediction FP6 NoE (Network of Excellence) OBJECTIVE to create a single organisation structure capable of providing harmonised R&D at European level to all nuclear stakeholders in the area of lifetime evaluation methods for structural components. NULIFE is a key instrument in implementing LTO (long term operation) related topics. Schedule 2006-2011 / 5 years Total budget over 8 M EC funding 5 M Strong link to SNE TP 11 Core contract members and over 30 other members VTT coordinator 14

Beyond 5 years NULIFE Institute with customer-driven programme Major milestones 2007 2008 2009 2010 2011 Preparation of business plan Integration plan Transition plan for permanent entity Creation of Virtual Institute Consolidation of integration plan Structure with permanent entity features Joint use of facilities Investment policy Launching of new RTD projects Development and application of procedures and best practices Business plan, Updated structure Links with national programmes Approaches to training, knowledge and comm. Viable expert groups Coherent structure Communication methods Permanent management structure Long term business plan Acknowledged solution provider Past Networking activities Key integration indicators 15

Challenges for R&D New reactor technologies Knowledge, data and tools for verification of reactor performance and safety Knowledge, data and tools for verification of new components/manufacturing methods/material grades From design to industrial manufacturing and supply. 16

Challenges for R&D Extended operation requirements Tools and data for reactor performance analysis Aging management: Aging mechanisms of systems, structures and components (understanding for LTO) Multiscale modelling tools Methods for aging monitoring. Asset management: Reliable and economic operation and maintenance management for 60 yrs reactor life 17

Challenges for R&D Relevant experimental and modelling tools: Materials testing (active non active) for aging mechanisms and tools for multiscale modelling Simulating tests (component level) for life management Tests and tools for fuel and cladding performances for reactor operability In-reactor tests and tools for reactor performance. 18

Challenges for R&D Resources Training of engineers and scientists Continuous development and verification of codes and models Up to date test reactor facilities and supporting laboratories. 19

Thank You 20