ANA2017 Conference, Sydney, 6 Oct 2017 1

Presentation 1 – Session 1

Australia’s Participation in Gen IV International Forum (GIF)

Prof Lyndon Edwards MA, DPhil (Oxon) FIMMM, CEng

Australian Nuclear Science and Technology Organisation

Biography

Lyndon Edwards is currently National Director,

Australian Generation IV International Forum

Research at the Australian Nuclear Science &

Technology Organisation (ANSTO) in which capacity

he led Australia’s recent application for membership

of the Generation IV International Forum (GIF) and its

subsequent relevant research activities. He is a

member of the GIF Policy Group and the GIF Expert

Group.

Prior to his present position he was Head of the

Institute of Materials Engineering at ANSTO for 10

years. Previously a successful UK academic he held a

Personal Chair in Structural Integrity at the Open

University, UK and is currently Adjunct Professor of

Materials Engineering at Monash University in

Australia.

Prof Edwards has a long-standing international reputation in structural integrity particularly of

nuclear, aerospace and defence related materials. He has over 250 publications has worked on

the Structural Integrity of advanced aircraft structures and nuclear power generation plant and

defence platforms. He is also internationally recognized as an expert on Residual Stress and

one of the leading proponents of engineering stress measurement using neutron diffraction.

Prof Edwards studied for both his undergraduate and postgraduate degrees at Oxford

University.

Abstract

On 14 September 2017, Australia deposited its instrument of accession to the Generation IV

International Forum (GIF) Framework Agreement for International Collaboration on Research

and Development of Generation IV Nuclear Energy Systems with the GIF secretariat at the

OECD. The GIF is a co-operative international endeavour, which was established to carry out

the research and development needed to establish the feasibility and performance capabilities

of the next generation of nuclear energy systems. Australia became the 14th member of the

GIF on 22 June 2016 when it signed the GIF Charter. Acceding to the Framework Agreement

enables Australia to become actively engaged in R&D projects related to Generation IV

2 ANA2017 Conference, Sydney, NSW, 6 Oct 2017

systems, particularly in R&D projects on advanced materials. The story of Australia’s

engagement with GIF will be described and the scope and nature of its contributions to future

GIF R&D including which of the six GIF Advanced Reactor systems Australia will support

will be described together with the role of ANSTO as Australia’s implementing agent within

GIF.

Australia’s Participation in the

Generation IV International Forum (GIF)

Prof Lyndon Edwards

National Director, Australian Generation IV International Forum Research

Australian Nuclear Science & Technology Organisation

ANA 2017 Conference, 6 October 2017

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Genesis of Generation IV Concept

From John Kelly: GIF Webinar series at: www.gen-4.org/gif/jcms/c_84314/webinar-series-1-atoms-for-peace-the-next-generation

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Reactor Generations To-date

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Typical Early Reactor Development

From John Kelly: GIF Webinar series at: www.gen-4.org/gif/jcms/c_84314/webinar-series-1-atoms-for-peace-the-next-generation

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n  In 1999, low public and political support for nuclear energy •  Oil and gas prices were low

n USA proposed a bold initiative in 2000 •  The vision was to leapfrog LWR technology and collaborate with international partners

to share R&D on advanced nuclear systems •  9 Countries and EU initially joined USA in developing the initiative •  Oil prices jumped soon thereafter

n Gen IV concept defined via technology goals and legal framework •  Technology Roadmap released in 2002

–  2 year study with more than100 experts worldwide –  Nearly 100 reactor designs evaluated and down selected to 6 most promising concepts

•  First signatures collected on Framework Agreement in 2005; first research projects defined in 2006

Genesis of Generation IV Concept

“This may have been the first time that the world came together to decide on a fission technology to develop together.”

William Magwood IV, First Chairman of the Generation IV International Forum

From John Kelly: GIF Webinar series at: www.gen-4.org/gif/jcms/c_84314/webinar-series-1-atoms-for-peace-the-next-generation

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Current Drivers for Nuclear Power

From John Kelly: GIF Webinar series at: www.gen-4.org/gif/jcms/c_84314/webinar-series-1-atoms-for-peace-the-next-generation

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21 Sep 2017

From John Kelly: GIF Webinar series at: www.gen-4.org/gif/jcms/c_84314/webinar-series-1-atoms-for-peace-the-next-generation

Current Drivers for Nuclear Power

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The Gen IV Opportunity

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Generation IV Goals

n  Safety & Reliability •  Very low likelihood and degree of core damage •  Eliminate need for offsite emergency response

n  Sustainability •  Long term fuel supply • Minimize waste and long term stewardship burden

n  Proliferation Resistance & Physical Protection •  Unattractive materials diversion pathway •  Enhanced physical protection against terrorism

n  Economics •  Life cycle cost advantage over other energy sources •  Financial risk comparable to other energy projects

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AAEC 1952 - 1987

ANSTO 1987 - Today

Australia’s Nuclear R&D Capability

n Australia has had a National Nuclear Laboratory for 65 years

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Australia’s Broader Nuclear Activities

n  Uranium - world's largest reasonably assured resources of uranium

n  Sophisticated engineering capabilities across multiple advanced industries

n  Considerable past experience in front and back end of nuclear fuel cycle

n  Founding member of IAEA Board of Governors

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The GIF Journey

GIF Policy Group Delegation to Australia, 2-4 February 2016

n  Australian Government announced intention to apply in April 2007

n  Application halted after change in Government in late 2007

n  Next Australian Government agreed that Australia should bid to join the GIF in March 2015,

n  Bi-partisan support for bid n  Petition presented to GIF policy

Group in October 2015 n  GIF Policy Group Delegation visit to

Australia in Feb 2016 n  Australia signed the GIF Charter in

June 2016 n  Australia deposited its instrument of

accession to GIF Framework Agreement on 14 Sep 2017

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OPAL Research Reactor Centre for Neutron Scattering

Centre for Accelerator Science Australian Synchrotron

Advisor to Government Gateway to Australian Universities

Nuclear Fuel Cycle Research Nuclear Materials Research

ANSTO is Australia’s Implementing Agent

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14 Current Members of Generation IV

* Argentina, Brazil, and the United Kingdom are non-active, i.e. they have not acceded to the Framework Agreement which establishes system and project organizational levels for further co-operation. ¶ Australia signed the GIF Charter on 22 June 2016 and deposited its instrument of accession to GIF Framework Agreement on 14 Sep 2017 Australia can actively engage in GIF R&D projects after 90 days: i.e. on 13 Dec 2017.

¶

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GIF Organization

•  Proliferation Resistance &

Physical Protection •  Risk & Safety •  Economic Modelling

Methodology Working Groups

System Steering Committees

Project Management Boards

(Multiple R&D projects)

Policy Secretariat •  Policy Director – F. Storrer •  Technical Director – A.

Stanculsecu

•  H. Paulliere

Technical Secretariat

Senior Industry Advisory Panel

Policy Group

•  Chair – F. Gauche (France)

•  Vice Chair – J. Kelly (USA)

•  Vice Chair – H. Kamide (Japan)

•  Country Representatives

Co-Chairs

Experts Group

•  Chair – A. Stanculsecu

•  Country Representatives

Structure as of September 2017

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The Six Gen IV Reactor Systems

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Sodium Fast Reactor

n  Integral part of the closed fuel cycle •  Can either burn actinides or breed fissile material

n  Designs being developed •  ASTRID (France) •  JSFR (Japan) •  PGSFR (Korea) •  BN-1200 (Russia)

n BN-800 (Russia) •  2015 - Start-up •  2016 – Became fully operational

n R&D focus •  Analyses and experiments that demonstrate safety

approaches •  High burn-up minor actinide bearing fuels •  Develop advanced components and energy

conversion systems

500 - 550 ºC

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Lead Fast Reactor

480 – 800 ºC n Lead is not chemically reactive with

air or water and has lower coolant void reactivity

n Three design thrusts: •  European Lead Cooled Fast Reactor

(Large, central station) •  Russian BREST-OD-300 (Medium

size) •  SSTAR (Small Transportable

Reactor) n R&D focus on materials corrosion

and safety

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Gas-cooled Fast Reactor

n High temperature, inert coolant and fast neutrons for a closed fuel cycle •  Fast spectrum enables extension of

uranium resources and waste minimization •  High temperature enables non-electric

applications •  Non-reactive coolant eliminates material

corrosion n Very advanced system

•  Requires advanced materials and fuels n Key technical focus:

•  SiC clad carbide fuel •  High temperature components and

materials

750- 850 ºC

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Supercritical Water-Cooled Reactor

n Merges GEN-III+ reactor technology with advanced supercritical water technology used in coal plants

n Operates above the thermodynamic critical point (374°C, 22.1 MPa) of water

n Fast and thermal spectrum options

n Key technology focus: •  Materials, water chemistry, and

radiolysis •  Thermal hydraulics and safety

to address gaps in SCWR heat transfer and critical flow databases

•  Fuel qualification

510 – 625 ºC

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n High temperature enables non-electric applications n Goal - reach outlet temperature of 1000oC, with near term

focus on 750-950°C n Reference configurations are the

prismatic and the pebble bed •  Designed to be “walk away safe”

n  R&D focus on materials and fuels •  Develop a worldwide materials handbook •  Benchmarking of computer models •  Shared irradiations

–  Confirmed excellent performance of UO2 TRISO

n Japan HTTR in operation n China HTR-10 in operation n China HTR-PM power station

under construction

Very High Temperature Reactor

750 – 1000 ºC

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Molten Salt Reactor

n High temperature system •  High temperature enables

non-electric applications n On-line waste management n Design Options

•  Solid fuel with molten salt coolant

•  Fuel dissolved in molten salt coolant

n Key technical focus •  Neutronics •  Materials and components •  Safety and safety systems •  Liquid salt chemistry and properties •  Salt processing

550 – 800 ºC

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Australia is proposing to work on:

The Very High Temp Reactor (VHTR) The Molten Salt Reactor (MSR)

Intended Australian Membership

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•  The majority of Australia’s initial contribution to GIF research will be in the area of Materials Science and Engineering, Structural Integrity design and assessment and Advanced Manufacturing

•  As the MSR activity is currently a pSSC then our principal

contributions to GIF deliverables in the first years of Australia’s membership would be through participation in the VHTR Material (MAT) Project Arrangement.

•  As involvement in the MSR grows Australia will also support the transition of this System from a MoU to a System Arrangement

•  Our capability and intended research in these areas is capable of supporting all of the other Gen IV reactor systems e.g. SFR, LFR, SCWR and GFR.

Australian GIF R&D

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On signing the Framework Agreement, Australia is proposing to join: • The VHTR SA • The MSR pSSC • The VHTR Material (MAT) PA • The Risk and Safety Working Group.

In addition, we are exploring how we might make contributions to: § The GIF Education and Training Working Group § The Economic Modelling Working Group

Initial Australian GIF R&D

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  Effective since CA EU FR JP CN KR ZA RU CH US

VHTR SA Extended 30 Nov 2016   X X X X X X X

HP PA 19-Mar-08 X X X X S X O XFFC PA 30-Jan-08 X X X X X XMAT PA 30-Apr-10 X X X S X X XCMVB PA Provisional P P P P O P

SFR SA Extended 16 Feb 2016 X X X X X X X

AF PA 21-Mar-07 / expired X X X X X X XGACID PA 27-Sep-07 X X XCDBOP PA 11-Oct-07 / extended O X X O X O XSO PA 11-Jun-09 X X X X X X XSIA PA 22-Oct-14 X X X X X X X

SCWR SA Extended 30 Nov 2016 X X X X X

M&C PA 6-Dec-10 X X O X O TH&S PA 5-Oct-09 X X O X O SIA PA Provisional P P P P P

GFR SA Extended 30 Nov 2016 X X X

CD&S PA 17-Dec-09 X X FCM PA Provisional P P P

LFR MOU   X X O X X OMSR MOU   X X O O O X X XX = SIGNATORY P = PROVISIONAL PARTICIPANT O = OBSERVER S = SIGNATURE PROCESS ONGOING

GIF System Membership at Oct 2017

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  Effective since AU CA EU FR JP CN KR RU CH US

VHTR SA Extended 30 Nov 2016  X   X X X X X X X

HP PA 19-Mar-08 X X X X S X O XFFC PA 30-Jan-08 X X X X X XMAT PA 30-Apr-10 X X X X S X X XCMVB PA Provisional P P P P O P

SFR SA Extended 16 Feb 2016 X X X X X X X

AF PA 21-Mar-07 / expired X X X X X X XGACID PA 27-Sep-07 X X XCDBOP PA 11-Oct-07 / extended O X X O X O XSO PA 11-Jun-09 X X X X X X XSIA PA 22-Oct-14 X X X X X X X

SCWR SA Extended 30 Nov 2016 X X X X X

M&C PA 6-Dec-10 X X O X O TH&S PA 5-Oct-09 X X O X O SIA PA Provisional P P P P P

GFR SA Extended 30 Nov 2016 X X X

CD&S PA 17-Dec-09 X X FCM PA Provisional P P P

LFR MOU   X X O X X OMSR MOU   X  X X O O O X X XX = SIGNATORY P = PROVISIONAL PARTICIPANT O = OBSERVER S = SIGNATURE PROCESS ONGOING

Intended Australian Contributions

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MSR Materials Environment

=> Operating temperatures of 630-700 oC => Corrosive molten fluoride salt (FLiNaK; FLiBe) => 200 dpa neutron radiation => 0.6 MPa pressure => 30+ years reactor design life

High Temperature

Corrosion Irradiation

Irradiation + High

Temperature

Irradiation + Corrosion

Corrosion + High

Temperature

MSR Operating

Environment

Requirements of MSR structural materials:

=> High Temperature Creep => Radiation Damage => Corrosion

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n Shanghai Institute of Applied Physics (SINAP), Chinese Academy of Science (CAS)

•  Centre for Thorium Molten Salt Reactor (TMSR) systems

•  Initial $400M R&D investment •  Prototype reactor (2MW) •  Non-active Demonstrator

n ANSTO-SINAP Joint Research Centre

•  Materials technology for Molten Salt Reactors

– Molten salt corrosion –  Radiation damage –  High temperature properties

ANSTO-SINAP Joint Research Centre

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=> (a) and (b) are the fracture surface of 150 and 500 kPa infiltrated grade IG-110 graphite respectively; (c) and (d) are fracture surface of 150 and 500 kPa infiltrated grade G1 graphite respectively.

Z. He et al., JNM 84, pp. 511-518.

Salt Infiltration in Graphite

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VHTR Materials Environment

=> Operating temperatures of 750-1000oC => Inert gas environment => 7 MPa pressure => 100 dpa neutron radiation ⇒ 30+ years reactor design

life

High Temperature Creep

High Temperature Fatigue

Irradiation

Irradiation + Creep

Irradiation + Fatigue

Creep/Fatigue

VHTR Operating

Environment

Requirements of VHTR structural materials:

=> High Temperature Creep => High Temperature => Radiation Damage

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Micromechanical Tensile Testing

Radiation direction

In situ micro tensile testing of He+2 ion irradiated and implanted single crystal nickel film. Acta Materialia, 2015, 100, pp. 147-154.

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Trends in Radiation Strengthening with Dose

§ Ion irradiation provides useful qualitative information

§ Current research linking micro to macro properties

In situ micro tensile testing of He+2 ion irradiated and implanted single crystal nickel film. Acta Materialia, 2015, 100, pp. 147-154.

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RemLife

n Creep-fatigue cycling n RBI Assessment n Crack Growth n Material Properties included in database

RemLife Creep Fatigue Crack Growth

Life

Inspection Results

ScarLife

TubeLife

Maintenance Scheduling

RBI

Creep Fatigue Crack Initiation

Life

RemLife is a simulator that calculates the effects of unit cycling on the accumulation of creep and creep-fatigue damage on components

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Creep/Fatigue Materials Database

1Cr0.5Mo (P12) 1.25Cr0.5Mo (P11) 2.25Cr1Mo (P22) 0.5Cr0.5Mo0.25V (CMV) 1Cr1Mo0.25V (CMV) 1.25Cr1Mo0.25V (CMV) P9 X10CrMoVNb (P91) 9Cr0.5Mo1.8WVNbB

(P92) AISI 304 AISI 316 25Cr35NiNbMa (HK40) X20CrMoV12-1 7-9Cr2WV P23 Hastelloy XR Fe0.75Ni0.5MoCrV Fe2.25Cr1Mo0.25V

Full C-F Model

Under Development

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Is the Landscape Changing?

From: www.thirdway.org/report/the-advanced-nuclear-industry

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MSR GIF-like startups and supporters

ONE

TerraPower Fast Breeder Liquid Fuel Salt Cooled Uranium (Could use Th)

TWO

Thorcon Thermal Burner Liquid Fuel Salt Cooled Thorium

THREE

Terrestrial Energy Thermal Burner Liquid Fuel Salt Cooled Uranium (Could use Th)

FOUR

Flibe Energy Thermal Breeder Liquid Fuel Salt Cooled Thorium

FIVE

Transatomic Power Hybrid Burner Liquid Fuel Salt Cooled Uranium

SIX

Elysium Industries Liquid Fuel Salt Cooled

SEVEN

Alpha Tech Research Corp Liquid Fuel Thorium Fluoride Salt

n  MSR’s are seen by many as a disruptive technology

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n Over the last decade Gen IV has had major accomplishments •  Legal framework established for collaboration •  Collaborative projects started with significant R&D investment worldwide •  Prototype demonstrations are being designed and/or built

–  SFR (France and Russia) –  VHTR (China

n  Much still needs to be done before Gen IV systems are a reality •  Continue R&D on Gen IV systems •  Develop advance research facilities •  Engage industry on the design of Gen IV systems •  Develop the workforce for the future

n  Australia will be part of this future

Conclusions

Thank you for your attention.