development and world-wide cooperation within the gif...development and world-wide cooperation...

Development and World-Wide

Cooperation within the GIF

Hark Rho Kim

INPRO Dialogue Forum on Generation IV Nuclear Energy Systems

IAEA Headquarters, Vienna

13-15 April 2016

2INPRO DF, 13-15 April 2016

I. Overview of GIF

II. Current R&D Status of Six Reactor Systems

III. Methodology Working Groups and TFs

IV. Plan for International Cooperation

V. Conclusion

Contents


I. Overview of GIF




V. Conclusion


� The GIF was founded in July 2001 as a co-operative international

endeavor to carry out the R&D needed to establish the

feasibility and performance capabilities of the next generation

nuclear energy systems

� Gen IV concepts defined via technology goals and legal

framework

� Thirteen Members signed its founding document,

the GIF Charter, which was first signed in July 2001 and

extended in July 2011

� The technology goals (sustainability, safety, economics,

PRPP) provided the basis for identifying and selecting six

nuclear energy systems for further development

� Technology Roadmap 2002 was updated to additional 10

years in Jan. 2014

� Framework Agreement (FA) was extended to additional 10

years in Feb. 2015

About GIF


� Sustainability

�Secure long term fuel supply

�Minimize waste and long term stewardship burden

� Safety & Reliability

�Excel in safety and reliability

�Keep very low likelihood and degree of core damage

�Eliminate need for offsite emergency response

� Economics

�Maintain life cycle cost advantage over other energy

sources

�Reduce financial risk comparable to other energy projects

� Proliferation Resistance & Physical Protection

�Prevent unattractive materials diversion pathway

�Enhance physical protection against terrorism

GIF Technology Goals


Canada China France Japan Korea Russia

South

Africa Swiss USA EU

SFR ● ● ● ● ● ● ●

VHTR ● ● ● ● ● ● ●

LFR* ● ● ● ●

SCWR ● ● ● ● ●

GFR ● ● ●

MSR* ● ● ● ●

*All activities, except LFR and MSR, are carried out based on the system arrangement.

The activities of LFR and MSR are carried out based on Memoranda of Understanding.

Argentina Brazil UK

are also members as non-active member.

Membership and System Development


Safety and Operation (SO)

System Steering

Committee (SSC)

Methodology Working

Groups (MWG)

SFR

SCWR

Economic Modeling Working

Groups (EMWG)

Proliferation Resistance and Physical Protection Working Groups (PRPPWG)

Risk and Safety Working

Groups (RSWG)

Advanced Fuel (AF)

Project Management Board (PMB)

Computational Methods Validation and Benchmarking (CMVB)

Thermal-Hydraulics & Safety (TH&S)

Global Actinide Cycle Int. Demonstration (GACID)

Component Design and Balance-O-Plant (CDBOP)

System Integration and Assessment (SI&A)

Hydrogen Production (HP)

Fuel and Fuel Cycle (FFC)

Materials (MAT)

Materials and Chemistry (M&C)

GFR

LFR

MSR

Conceptual Design and Safety (CD&S)

Fuel and Core Materials (FCM)

already set up

under preparation or discussion

VHTR

System Integration and Assessment (SI&A)

Task Force (TF)

Safety design criteria (SDC)

Education and Training (E&T)

Sustainability

R&D Projects, Methodology WG and Task Force


� Depending on their respective degrees of technical maturity, the

Generation IV systems are expected to become available for

commercial introduction in the period around 2030 or beyond.

� The path from current nuclear systems to Generation IV systems is

described in the technology roadmap update:

www.gen-4.org/gif/upload/docs/application/pdf/2014-03/gif-tru2014.pdf

Updating Technology Roadmap


I. Overview of GIF




V. Conclusion


550°°°° C

� Started in Feb. 2006

– China, EU, France, Japan,

Korea, Russia, USA

� Integral part of the closed fuel

cycle

– Can either burn actinides or

breed fissile material

� System options

– Loop, pool, small modular

� R&D focus

– Analyses and experiments that

demonstrate safety approaches

– Development of High burn-up

minor actinide bearing fuels

– Development of advanced

components and energy

conversion systems

500 ∼∼∼∼ 550℃℃℃℃

Sodium-cooled Fast Reactor (SFR)


� Large past experience + Several Demonstrator projects either in

Operation/Construction* or at Design stage**:

Performance Phase: Will be in demonstration phase around 2022

in *China, *Japan**, *Russia**,

France**, Korea** +

India(outside GIF)

SFR : Current Phase

� Designs being developed

– CFR600 (China)

– ASTRID (France)

– JSFR (Japan)

– PGSFR (Korea)

– BN-1200 (Russia)

� Operation/Construction

– CEFR (China)

– JOYO, MONJU (Japan)

– BOR-60, BN-600, BN-800

(Russia)

– FBTR, PFBR (India)

Loop Pool Small Modular

KALIMERJSFR AFR-100

IHX

DHX

PHTS pump

Reactor core

Steam Generator

AHX Chimney

PDRC piping

In-vessel core catcher

IHTS piping

IHTS pump

IHX

DHX

PHTS pump

Reactor core

Steam Generator

AHX Chimney

PDRC piping

In-vessel core catcher

IHTS piping

IHTS pump

12.03 m3,186 gal .

P LAN VIEW OF THE CORE

PRIMARYCONTROL RODS

1m TRAVEL DISTANCEOF THE CONTROL RODS

( 10 '- 8")

THERMALSHIEL D

(29 .5")0 .75m

3.25m

Na-CO

HEAT EXCHANGER

7m

IHXX-SECT ION (F LATTENED FOR CLARITY )

(23 ')

(Ø 7 .5 ' x 12 .6' LONG)

IHX

2

SECT ION A - A

No rm al s o di um le v e l

No r ma l s o di um l ev e l

So d ium fa ul te d l ev e l

P ump o f fSo d ium L e v el

SODIUM DUM P TANKØ 2.5 m x 3 .8 m LONG

CORE BARREL Ø266 / 268 cm(104.7" / 105 .5")

SECONDARYCONTROL RODS

CONTROL

RODS (7 )

PUMPS (2 )

ON Ø 142 .5" B.C.

P LAN VIEW OFIHX AND PUM PS IHX (2)

1 .7m EACH2

DRACS (2 )0.4m EACH2

Prima ry Ve sse l I.D.

Gua rd Ve sse l I.D.

Ho t P oo l

Co ld P o o l

PRIMARY VESSEL(2" THICK)

3 .5m( 11 '- 8")

GUARD VESSEL(1" THICK)

1m(39 .4")

3

TURBINE/ GENERATORBUIL DING

ELEVATOR

(Ø 25 .5 ')Ø 7.7m

Na -AirHEAT EXCHANGER (2 )

CONTROLBUIL DING

0 1 2 3 10METERS4 5

5 .08m

[16.7FT ]

4 .57m [15FT ]

7m [23F T]

1 .89m [6 .2F T]

12.72m [41.7FT ]

14 .76m [48.4FT ]

1 .93m

[6 .3F T]

.61m [2F T]

2 .29m [7.5FT ]

EXHAUST TO VENT STACK

ESFR


�Advanced Fuel: – Selection of high burn-up MA bearing fuel(s), cladding and wrapper

withstanding high neutron doses and temperatures, e.g., ODS steel

�Global Actinide Cycle Int. Demonstration: GACID– Demonstration of MA transmutation using reactors, Joyo and Monju

�Component Design and Balance-Of-Plant:– Development of advanced cycles for energy conversion

– Development of straight tube type SG and evaluation of SWR

– Development of ISI using ultrasonic technologies

� Safety and Operation:

– Improving core inherent safety, development of passive shutdown system

– Prevention and mitigation of severe accident with large energy releases

– Validation of decay heat removal (DHR) & ultimate heat sink, ISI&R

– Prevention & mitigation of sodium fires

� Safety Design Criteria (SDC) consolidation

Key R&D challenges for demonstration phase:

SFR R&D Plans


� Started in Nov. 2006

– China, EU, France, Japan, Korea, Swiss, USA

(Canada, South Africa withdrawn)

� High temperature enables non-electric applications

900 ∼∼∼∼ 1,000℃℃℃℃

� Reference configurations are the

prismatic and the pebble bed

– Designed to be “walk away safe”

� R&D focus on materials and fuels

– Development of a worldwide

materials handbook

– Benchmarking of computer models

– Shared irradiations

• Confirmed excellent performance

of UO2 TRISO

Very-High-Temperature Reactor (VHTR)



� Leading projects: HTR-PM, Construction in China

NGNP, R&D & Design study in USA

HTTR study in Japan

� Two stages of development

– 700-950℃℃℃℃ outlet

• Technical maturity: 950℃℃℃℃ is demonstrated in AVR & HTTR

• Large market: electricity, process heat

• Main tasks: demonstration, optimization, deployment

– 1000℃℃℃℃ outlet

• Need more R&D

• Improve fuel performance

• Develop material for this high temperature

VHTR : Current Phase


【【【【Long term R&D：：：：1000℃℃℃℃】】】】

� Require developments of advanced materials (SiC/SiC composites,

graphite, …) and fuels at high burnup up to 200 GWd/tHM)

� Key component development for heat users and H2 production:

Intermediate Heat Exchanger, etc.

【【【【Near term R&D：：：：700-950℃℃℃℃】】】】

� Hydrogen Production: Outlet temperatures between 700 and 950℃

� Materials: Qualification of Ni alloys & of new grades of graphite

� Fuel and Fuel Cycle: Qualification of UCO TRISO fuel (1,250℃;

burnup≤ 150 GWd/tHM)

� Computational Methods Validation and Benchmarking:

Thermal-hydraulic safety demonstration (LOCA, Passive DHR, etc.)


VHTR R&D Plans



– Canada, China, EU, Japan, Russia

� Merges GEN-III+ reactor technology with

advanced supercritical water technology used in coal plants

� Operates above the thermodynamic critical point

(374℃℃℃℃, 22.1 MPa) of water

� Fast and thermal spectrum

options

� R&D 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℃℃℃℃

Supercritical-Water-cooled Reactor (SCWR)


� 2017, possible decision about a SCWR by demonstrator

Just entering Performance phase:

Demonstration phase foreseen in 2025

SCWR : Current Phase

� Canadian SCWR design concept with

pressure tubes

– Design completed and assessed

in Oct. 2015

� China SCWR design concept with

pressure vessel-CSR1000

– Design to be completed and

assessed in 2018


【【【【Near term R&D: - 2017】】】】

� Materials and Chemistry ：：：：

– Out-of pile, small scale fuel assembly test; cladding

material selection

� Thermal-Hydraulics & Safety:

– Qualification of computational tools

� System Integration and Assessment:

– Pre-conceptual design phase completion

【【【【Long term R&D: 2017 – 】】】】

� In-pile, small scale fuel & assembly tests


SCWR R&D Plans



– EU, France, Japan (Swiss withdrawn)

� 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

� Very advanced system

– Requires advanced materials and

fuels

� R&D focus

– SiC clad carbide fuel

– High temperature components and

materials∼∼∼∼ 850℃℃℃℃

Gas-cooled Fast Reactor (GFR)


Viability Phase: Will be in performance phase around 2022

� Viable concepts for fuel and cladding have been developed

� Work remains to be done on refining the safety architecture such that the

safety goals can be met in a cost effective manner

� Design studies for an experimental reactor under

consideration: ALLEGRO

GFR : Current Phase

� Work continues in the V4G4*

consortium on developing ALLEGRO to

be a GFR demonstrator – funded at a

fairly low level by the European

Commission and the Governments of

the V4 member states

� ALLEGRO concept has been re-worked

to start with a much smaller core of

10MWth, instead of 75MWth, starting

with UO2 fuel as opposed to MOX

*Czech Republic, Hungary, Slovakia and Poland


� Conceptual Design and Safety:

– Design for safe LOCA

management system & robust

DHR system without external

power supply

� Fuel and Core Materials:

– Developing suitable Fuel

technologies (out-of-pile test +

irradiation experiments)

Key R&D challenges for performance phase:

GFR R&D Plans


480 ∼∼∼∼ 800℃℃℃℃


– EU, Japan, Korea, Russia

� Lead is not chemically reactive

with air or water and has lower

coolant void reactivity

� Three design thrusts:

– European Lead Cooled Fast

Reactor (Large, central station)

– Russian BREST-OD-300

(Medium size)

– SSTAR (Small Transportable

Reactor)

� R&D focus on materials corrosion

and safety

Lead-cooled Fast Reactor (LFR)


� Demonstrators: in Russia PSVBR-100 (Pb-Bi) and BREST-300, ALFRED project (120 MW) in Europe

� Selection of Materials resistant to erosion-corrosion for fuel cladding and reactor structures & components

� Material / Lead chemistry management for T > 480-500℃

� Fuel developments: MOX; Nitride fuel; MAs bearing fuels;

� Fuel handling technology and operation: Core instrumentation. Advanced modeling and simulation, etc.



LFR : Current Phase and R&D Plans


� Started in Oct. 2010

– EU, France, Russia, Swiss

� High temperature system

– High temperature enables

non-electric applications

� On-line waste management

� Design Options

– Solid fuel with molten salt

coolant

– Fuel dissolved in molten

salt coolant

� R&D focus

– Neutronics

– Materials and components

– Safety and safety systems

– Liquid salt chemistry and properties

– Salt processing 700 ∼∼∼∼ 800℃℃℃℃

Molten Salt Reactor (MSR)


Viability Phase: Will be in performance phase around 2025

� Management and salt control (2012-2014)

– Liquid salt chemistry: multi –component solubility limits

versus T℃ & salt composition

� Confirmation of bubbling efficiency (2014-2015)

� Heat exchanger viability (2015-2017)

� Validation of reprocessing flow sheets at laboratory scale

� Definition of safety analysis methodology and

specification of accident scenarios

Key R&D challenges for performance phase:

MSR : Current Phase and R&D Plans

In baseline, the Molten Salt Fast Reactor, MSFR (a liquid fuel concept);

In addition: Fluoride salt-cooled High-temperature Reactor, FHR (solid fuel)

� 2 conceptual designs : MOSART (Molten Salt Actinide Recycler &

Transmuter); MSFR


I. Overview of GIF




V. Conclusion


� Established in 2003 to create economic models & guidelines for

assessment of Gen IV systems

– Canada, EU, France, Japan, Korea, USA

� GIF economic goals

– To have a life cycle cost advantage over other energy sources (i.e. to have

lower levelized unit cost of energy on average over the lifetime)

– To have a level of financial risk comparable to other energy projects (i.e.,

to involve similar total capital investment and capital at risk)

� EMWG Products

– Cost Estimating Guidelines for Generation IV Nuclear Energy Systems

Revision 4.2

– Spreadsheet (EXCEL-based) model, i.e., G4-ECONS (Generation 4-EXCEL

Calculation Of Nuclear Systems) Ver 2.0

– User’s Manual for G4-ECONS Ver. 2.0

� Available on a CD-ROM from the GIF Secretariat, Nuclear Energy Agency, OECD

(or at https://www.gen-4.org/gif/jcms/t1_13959/outcomes for members)

Economic Modeling Working Group (EMWG)


� G4-ECONS calculates Total Capital Investment Cost (TCIC) and

Levelized Unit Energy Cost (LUEC)– The Cost Estimating Guidelines define what is to be included in calculation

of TCIC and LUEC

– Bottom-Up Approach: detailed cost estimating technique for mature

designs

– Top-Down Approach: cost estimating technique for systems with less

advanced design detail

� G4-ECONS and cost estimation methodologies demonstrated for– Gen III and Gen III+ systems – HWR, LWR

– Gen IV systems – SCWR, Japanese SFR, GT-MHR

– Hydrogen and process heat – GT-MHR, PH-MHR

– Fuel Cycle Facility costing

� Next Version of G4-ECONS to be released soon for beta-testing

� Continue collaboration with IAEA – Benchmarking of G4-ECONS with INPRO’s NEST for fast reactors in closed

fuel cycle

Economic Modeling Working Group (cont’d)


� Created in Dec. 2002 to establish a framework for assessing

Generation IV nuclear systems against the proliferation

resistance and physical protection goals of GIF– China, Canada, EU, France, Japan, Korea, Russia, USA

� Objectives– Facilitate introduction of PR&PP features into the design process at the

earliest possible stage of concept development ⇒ PR&PP by design

– Assure that PR&PP results are an aid to informing decisions by policy

makers in areas involving safety, economics, sustainability, and related

institutional and legal issues

Proliferation Resistance and Physical Protection Working Group (PRPPWG)

� PR&PP Methodology– A systematic approach to evaluating

vulnerabilities in designs with respect

to the PR&PP goals.

• It provides the assessment

approach that ensures that

assessors “did not do things wrong.”


� Major Accomplishments– The Methodology developed through a succession of revisions – currently

in Revision 6 report

– An example (sodium-cooled) reactor system was chosen to develop and

demonstrate the methodology – resulted in a major report

– Joint Efforts with six GIF design areas - resulted in a major report

� Can be obtained at: https://www.gen-4.org/gif/jcms/c_9365/prpp

� Implementation Activities within National Programs of USA,

Japan, Canada, Europe

� Workshops on PR&PP– To familiarize non-experts on methodology and its applications

– Industry, government, academics, and GIF member community attended

– 2004 (USA), 2006 (Italy), 2007 (Japan), 2008 (South Korea), 2011 (Japan),

2012 (Russia), 2013 (IAEA), 2014 (France), 2015 (USA)

– Joint Workshop with GIF-RSWG: 2003, 2012

� Activities related with IAEA– Interaction between GIF and the IAEA’s INPRO program

– Safeguards by Design ongoing at IAEA and in various countries

Proliferation Resistance and Physical Protection Working Group (cont’d)


� Started in 2005

– Canada, China, EU, France, Japan, Korea, Russia, UK, USA

– In close collaboration with IAEA

� Objectives

– Provide an effective and harmonized approach to the safety

assessment of Generation IV systems in collaboration with and in

support of all six System Steering Committees

� Work Scopes

– Propose safety principles, objectives, and attributes based on Gen IV

safety goals to guide R&D plans

– Provide consultative support to SSCs and other Gen IV entities and

undertake appropriate interactions with regulators, IAEA, and other

stakeholders

– Develop a Safety Assessment Methodology

Risk and Safety Working Group (RSWG)


� Products

– “Basis for the Safety Approach for Design & Assessment of Generation

IV Nuclear Systems” (2009)

– “Integrated Safety Assessment Methodology (ISAM)” (2011)

� Current Activities

– Supports SFR SDC-TF Activities

– Reviews Safety Assessment Document for GIF Systems prepared by

SSCs

– Prepares ISAM Application Guidance Document

– Joint meeting between RSWG and PRPPWG (2015, 22th RSWG meeting)

� Continued collaboration with IAEA

– IAEA supports and reviews to establish safety principles in RSWG

(Basis for the Safety Approach, Integrated Safety Assessment

Methodology, SFR Safety Design Criteria/Guidance)

Risk and Safety Working Group (cont’d)


� SFR Safety Design Criteria (SDC) Task Force was established

by the GIF Policy Group (PG) in Oct. 2010 for the

development of the SDC for the Gen IV SFR system

– Establish reference criteria for safety design of structures,

systems and components

– Achieve harmonization of safety approaches among GIF

member states

» Realization of

enhanced safety

designs common to

Gen IV SFRs

» Preparation for

upcoming licensing

efforts

SDC Task Force


� The SDC Phase-I Report has been approved by GIF in May 2013

– Review is in progress among regulatory bodies/technical

support organizations of FR development countries and by

international organizations (IAEA, OECD/NEA/CNRA, etc.)

– Russia, China, India etc. intend to reflect in the safety design

� The draft report

“Safety Approach

SDG” has been

submitted to

PG/EG/SFR-SSC/RSWG

on 8 October 2015 for

review

SDC Task Force (cont’d)


� Education & Training Task Force (ETTF)

− Established by the GIF PG in Oct. 2015

− To serve as a platform to enhance open education and training as well as

communication and networking of people and organizations in support of

GIF

− will work during the period of 2016-2018

� The ETTF members are basically nominated by PG members

− ask again the PG members for a nomination from China and Canada

Education & Training Task Force (ETTF)


� A social medium platform (Linkedin group of Generation-IV ETTF: https://www.linkedin.com/grp/home?gid=8416234)

− Was created on October 06, 2015

− To communicate with the target groups and start collecting the materials

− The number of members increased to 113 as of 17 Mar. 2016

� Development of first webinar series on GEN IV − Creation of a list of topics

− Finding lecturers who would be willing to present the webinars

� Next steps− Continue GIF-ETTF teleconference monthly to discuss missions and progress

− Launch the first webinar series on GEN IV

− Continue development and maintenance of the social medium platform

− Develop the concept of a summer school for 2017

− Collaborate with relevant conferences, schools and courses

ETTF Activities


� Created in Nov. 2014 by PG authorization (May 2014) with

the purpose of finding out

– if there is any need to develop a GIF-specific narrow

definition of sustainability evaluation methodology

� The 1st and last Interim Sustainability Meeting

– Held in the OECD headquarter, Sep. 16-17, 2015

– Reviewed the relevant sustainability activities in IAEA, NEA

and elsewhere (methodologies and evaluations)

– Collected national views on sustainability

� Conclusion

– More precise evaluation methodology seemed elusive due

to the imprecision of definitions, goals, assumptions,

economics data, technological uncertainties, etc.

– Terminate the Interim Sustainability TF (Phase I)

Interim Sustainability TF


I. Overview of GIF




V. Conclusion


� External GIF collaborations include interactions with IAEA , OECD/NEA, and

their various initiatives or international projects, to include, but not be

limited to:

– INPRO and other IAEA endeavors (such as GIF-INPRO Interface Meetings,

Joint IAEA-GIF Technical Meetings on Safety of SFR, etc.);

– The International Framework for Nuclear Energy Cooperation (IFNEC);

– The Nuclear Innovation 2050 (NI2050);

– Engagement of national nuclear safety regulators through the

Multilateral Design Evaluation Program (MDEP), the Committee on

Nuclear Regulatory Activities (CNRA), the Committee on the Safety of

Nuclear Installation (CSNI), and the Ad-Hoc Group on the Safety of

Advanced Reactors (GSAR)

� The objective will be to coordinate, where possible, the GIF’s efforts with

these international endeavors to avoid the duplication of efforts

Plan for International Cooperation


I. Overview of GIF




V. Conclusion


� Members have collaborated successfully via international

synergistic collaboration framework, GIF

– SFR, VHTR, SCWR, GFR based on system arrangements

– LFR, MSR based on Memoranda of Understanding

� Most of the GIF goals are very challenging and, after the

Fukushima accident, a stronger & more effective International

cooperation is required to be able to reach all of them,

particularly those regarding safety & economic

competitiveness

� GIF maintains a long-standing collaborative relationship with

the IAEA with previous emphasis on IAEA’s International

Project on INPRO

– Cooperation on evaluation methodologies for economics, safety, physical

protection, and proliferation resistance has been ongoing for several

years

Conclusion

Thank you for your attention!

Reference

44

Generation Taxonomy of Nuclear Reactor Systems

45

Sodium-cooled Fast Reactor (SFR)

Lead-cooled Fast Reactor

(LFR) Very-High-Temperature

Reactor (VHTR)

Supercritical-Water-

cooled Reactor (SCWR) Gas-cooled Fast Reactor

(GFR)

Pool

type

Loop

type

Molten

fuel salt

type

Molten Salt Reactor (MSR)

Six Generation IV Reactor systems

A fluoride salt coolant high-

temperature reactor (FHR)

Molten salt serves as the coolant

of solid fuel core

46

Comparison of Gen IV systems

SystemNeutron

Spectrum CoolantOutlet temp.

(℃℃℃℃)Fuel cycle

Power

(MWe)

Sodium-cooled Fast

Reactor (SFR) Fast Sodium 500-550 Closed 50-1500

Very-High-

Temperature Reactor

(VHTR)Thermal Helium 900-1000 Open 250-300

Lead-cooled Fast

Reactor (LFR)

FastLead 480-570 Closed 20-1200

Supercritical-Water-

cooled Reactor

(SCWR)

Thermal/

Fast Water 510-625

Open/

Closed 300-1500

Gas-cooled Fast

Reactor (GFR) Fast Helium 850 Closed 1200

Molten Salt Reactor

(MSR)

Thermal/

FastFluoride

salts700-800 Closed 1000

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