International Atomic Energy Agency Overview Nuclear Power ...grouper.ieee.org/groups/npec/N13-02_NPEC presentations/NPEC_Jul… · International Atomic Energy Agency . 2012- Status

International Atomic Energy Agency

Overview Nuclear Power Technology Development Section

Thomas Koshy, Head [email protected]

Division of Nuclear Power Presented to

NUCLEAR POWER ENGINEERING COMMITTEE

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International Atomic Energy Agency 2

Programme Areas

Nuclear Power Technology

Development

Water Cooled Reactors

Gas Cooled Reactors

Fast Reactors

Small and Medium Size Reactors

Non-Electric Applications


Common Programme Activities

• Monitor worldwide activities on technology development

• Coordinate Research & Development with member states and international organizations for effectiveness and efficiency

• Facilitate exchange of information among IAEA Member States on technology development

• Support near term development and deployment for both emerging and existing countries in technology

• Provide technology training

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Water Cooled Reactors Group

Database • ARIS (Advanced Reactor Information System)

Training • Science and Technology of Super Critical

Water Reactors • Natural Circulation Phenomena and Passive

Safety Systems in Advanced Water Cooled Reactors

• Reactor Technology Assessment for Newcomers

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Cooperative Research Projects (CRPs)

• Heat Transfer Behaviour and Thermo-hydraulics Code Testing for Super-Critical Water-Cooled Reactors (SCWRs)

• Benchmarking Severe Accident Computer Codes for Heavy water Reactor Applications

• Application of Computational Fluid Dynamics (CFD) Codes for NPP Design

• Prediction of Axial and Radial Creep in Pressure Tubes • Investigation of Degradation Mechanisms of Candidate

Materials in an SCWR Environment (In Preparation)

International Collaborative Standard Projects (ICSPs)

• Integral PWR Design Natural Circulation Flow Stability and Thermo-hydraulic Coupling of Containment and Primary System during Accidents

• Comparison of HWR Thermal-hydraulic Code Predictions with SBLOCA Experimental Data

• HWR Moderator Sub-cooling Requirements to Demonstrate Backup Heat Sink Capabilities of Moderator during Accidents

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International Atomic Energy Agency 6

• Held at the IAEA HQs, Vienna, Austria, 23 - 26 April 2012

• Attended by 8 external experts and 11 IAEA staff members

• The first step for Action12 “Effectively utilize R&D” in the IAEA Action Plan on Nuclear Safety

• To share information and discuss Lessons Learned • Suggestions for IAEA activities

“Applying Lessons Learned from the Fukushima Accident to WCR Technology Development”


Potential for Improving Thermal Efficiency of Nuclear Stations

Improves overall efficiency Recover some Waste Heat Off Peak Power Utilization

Net Electricity

Net Electricity

Potential heat

recovery

Losses

Losses

34% 72%

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Non – Electric Applications: Benefits • Higher efficiency by utilizing waste heat • Improvement of economics

(cogeneration + sharing of infrastructures)

• Benefits of coupling (eg. provide necessary industrial quality water to the NPP, make use of the off-peak power)

• Reduced temperature on water discharge • Process heat for paper mills, petroleum,

chemical and plastic industries

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IAEA-Tools available for NEA analysis

• Desalination Economic Evaluation Program (DEEP 5.0) Performance and cost evaluation of various power and water co-generation configurations

• Desalination Thermodynamic Optimization Program (DE-TOP 2.0b) Thermodynamic analysis and optimization of nuclear cogeneration systems

• Hydrogen Economic Evaluation Program (HEEP) Performance and cost evaluation of various power and hydrogen co-generation configurations

OBJECTIVE: Support for feasibility analysis, research and education

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Activities

• Completed CRP on New technologies for Sea water Desalination using NPPs

• New CRP planned for low temperature desalination

• Completed Efficient Water Management in Water Cooled Reactors (No. NP-T-2.6),

• CM and regional workshops on cogeneration and desalination continues

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Electricity

Hydrogen

District Heating

High Temperature Reactors

Greater suitability for non-electric

applications

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HTGR / LWR COMPARISON Item HTGR LWR Moderator Graphite Water Coolant Helium Water Avg coolant exit temp. 750° - 1000 °C 310°C Structural material Graphite Steel Fuel clad Graphite & silicon Zircaloy Fuel UCO/ UO2 UO2

Fuel damage temperature >2000°C 1260°C Power density, w/cc 6.5 58 - 105 Linear heat rate, kW/ft 1.6 19 Avg neutron energy, eV 0.22 0.17 Migration length, cms 57 6

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Inherent Safety Approach l Ceramic fuel retains radioactive materials

up to ~2000˚C

l Coated particles stable to beyond maximum accident temperatures

l Heat removed passively without primary coolant

l Fuel temperatures remain below design limits during loss-of-cooling events

Centre Reflector Pebble Bed Side Reflector Core Barrel RPV RCCS Citadel

RadiationConduction

Conduction

Conduction

Convection

Radiation

Convection

Conduction

Radiation

Convection

Conduction

Convection

Radiation

Convection

Conduction

Radiation

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CRP on the Creep Phenomenon

in Irradiated Graphite • 7 Member States are participating in the CRP

• Expected Output: A validated model for the irradiation creep of nuclear graphite based upon a mechanistic understanding of the controlling processes – important for the life extension of British AGRs and new HTGR graphite qualification

• The objective is to determine the uncertainty at all stages of coupled reactor physics/thermal hydraulics and depletion

calculations – • Eventually important for the licensing of design codes for

HTGRs • 8 Member States are participating in the CRP

On-going CRP on Uncertainty Analysis in HTGR Modelling

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Activities Planned for 2013

• Re-evaluation of maximum operating temperatures and accident conditions for HTR fuel and structural materials – TM 10 -12 June 2013, Vienna

• Development of ‘Deep-burn” concepts using coated HTGR coated particle fuel for incineration of nuclear waste, surplus fissile materials and plutonium without recourse to multiple reprocessing (August 14 – 16 2013)

• Continue with yearly courses for preserving knowledge

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Fast Reactors….

LWR Open Fuel Cycle

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Plutonium Recycling

Spent Fuel Direct

Disposal

Natural Uranium

Time (years)

Rel

ativ

e ra

diot

oxic

ity

Spent Fuel Transmutation

Duration Reduction

1.000x

Volume Reduction

100x

Why Fast Reactors : Waste Management

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Pu + MA + FP

MA +

FP FP

Radiotoxicity of ultimate waste


Why Fast Reactors: Great flexibility excess of neutrons and transmutation performances

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As first discovered by Enrico Fermi in 1944, the nuclear characteristics of transuranics (TRU) cross sections in a fast neutron spectrum allow a great FR flexibility:

Breed (i.e. Conversion Ratio CR> 1) Sustainability

Burn (TRU or MA), i.e. CR <1 Transmutation to facilitate waste management

Breed (e.g. Pu) and burn (MA)

CR~1: Self-sustaining cycles (isogenerator systems)

Extremely important for the sustainability is also the concept of Doubling Time (CDT) – associated with breeding - i.e. the time required for a breeder reactor to produce enough material to fuel a second reactor


What is PRIS?

• A complete databank on nuclear power reactors • Reference data source used worldwide • 40 years of nuclear plant experience • Open system for development • Publications and analyses • Comprehensive reporting system • Modern on-line communication • Team of collaborators

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Most Popular Data Elements

• Reactor status overview • Reactor status changes • Historical development of nuclear power • NPP performance analyses using well defined

and internationally accepted indicators • Industrial standards – average, median, quartiles • Trend analyses • Process of reactor decommissioning

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Power Reactor Plant Types

BWR Boiling light water cooled and moderated reactor FBR Fast breeder reactor GCR Gas cooled graphite moderated reactor LWGR Light water cooled graphite moderated reactor PHWR Pressurized heavy water moderated and cooled reactor PWR Pressurized light water moderated and cooled reactor

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Nuclear Share of Electricity Production

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Total Power Reactor Plants by Nation

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Current Power Reactor Plant Status

435 reactors in operation (370 GWe) 5 reactors in long-term shutdown (3 GWe) 62 reactors under construction (59 GWe)

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Age of operating reactors

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Outages by type Grid disconnection break-down

World

63%12%

8%

15%2%

Planned w ithrefuelling

Planned w ithoutrefuelling

Unplanned outageextension

Unplanned duringoperation

Externally caused

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History of Power Reactor Construction

North America

2003 2004 2005 2006 2007 2008 2009 2010 2011 2012America - Latin 1 1 1 1 1 1 1 2 2 2America - Northern 0 0 0 0 1 1 1 1 1 1Asia - Far East 10 9 7 9 13 21 30 38 35 33Asia - Middle East and South 9 10 10 9 8 8 7 8 9 9Europe - Central and Eastern 10 7 7 8 10 12 16 17 16 16Europe - Western 0 0 1 1 2 2 2 2 2 2

0

10

20

30

40

50

60

70

Number of reactors under construction by region

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Refuelling outages for PWR and BWR

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Unavailability

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Net Nuclear Power Capacity by Region

North America

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2011- Status Changes in Power Reactors 7 new connections to the grid (5 in 2010):

• KAIGA 4 (202 MWe, PHWR, India), 19 January • CHASNUPP 2 (300 MWe, PWR, Pakistan), 14 March • LINGAO 4 (1000 MWe, PWR, China), 3 May • CEFR - China Experimental Fast Reactor (20 MWe, FBR, China), 21 July • BUSHEHR 1 (915 MWe, PWR-VVER, Iran), 3 September • KALININ-4 (950 MWe, PWR, RUSSIA) on 24 November • QINSHAN 2-4 (610 MWe, PWR, CHINA) on 25 November

13 final shutdowns (1 in 2010): • FUKUSHIMA-DAIICHI 1,2,3,4 (439/760/760/760 MWe, BWR, Japan), 20 May • OLDBURY A2 (217 MWe, GCR-Magnox, UK), 30 June • BIBLIS A and B (1167/1240 MWe, PWR, Germany), 6 August • BRUNSBUETTEL (771 MWe, BWR, Germany), 6 August • ISAR 1 (878 MWe, BWR, Germany), 6 August • KRUEMMEL (1346 MWe, BWR, Germany), 6 August • NECKARWESTHEIM 1 (785 MWe, PWR, Germany), 6 August • PHILIPPSBURG 1 (890 MWe, BWR, Germany), 6 August • UNTERWESER (1345 MWe, PWR, Germany), 6 August

4 construction initiations (16 in 2010): • CHASNUPP 3 (315 MWe, PWR, Pakistan), 28 May • RAJASTHAN 7 (630 MWe, PHWR, India), 18 July • RAJASTHAN-8 (630 MWe, PHWR, India) on 30 September • CHASNUPP 4 (315 MWe, PWR, PAKISTAN) on 18 December

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2012- Status Changes in Power Reactors 2 new connections to the grid:

• SHIN-WOLSONG-1 (960 MWe, PWR, KOREA) on 27 January • SHIN-KORI-2 (960 MWe, PWR, KOREA) on 28 January

1 final shutdowns: • OLDBURY-A1 (217 MWe, GCR, UK) on 29 February

2 construction starts :

• BALTIISK-1 (1082 MWe, PWR-VVER, Russia), 22 February • Barakah-1 (1340 MWe), PWR, UAE) on 18 July

2 cancelled constructions:

• BELENE 1 & 2 (953 MWe, PWR-VVER V-466, BULGARIA) on 28 March

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How to get information?

• Annual publications: • Nuclear Power Reactors in the World (since 1981) • Operating Experience with NPP (since 1970)

• Public website www.iaea.org/pris

• Web-based on-line system “PRIS-Statistics” for registered users

prisweb.iaea.org/statistics

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http://www-pub.iaea.org/MTCD/publications/PubDetails.asp?pubId=8531

http://www-pub.iaea.org/MTCD/publications/PubDetails.asp?pubId=8540

http://www.iaea.org/pris

http://prisweb.iaea.org/statistics

Documents

International Atomic Energy Agency Overview Nuclear Power ...grouper.ieee.org/groups/npec/N13-02_NPEC presentations/NPEC_Jul… · International Atomic Energy Agency . 2012- Status