Overview on the Very High Temperature Reactor...Overview on the Very High Temperature Reactor System...

Overview on theVery High Temperature Reactor

System

INPRO Dialogue Forum Vienna, 13 -14 April 2016

Michael A. Fütterer (EU)presented by Frank Carré (France)

on behalf of theGIF VHTR System Steering Committee

[email protected]

1. Technical Characteristics2. General Characteristics3. Missions4. How does the VHTR fulfil the GIF criteria?5. System overview

• Materials• Fuel and Fuel Cycle• Hydrogen Production• Computational Methods, Validation & Benchmarking• System Integration and Assessment

6. Interaction with other GIF groups7. Future collaborative R&D topics8. Interaction with IAEA and OECD/NEA9. Related international activities10. Wrap-up

Outline

1. Technical Characteristics• He-cooled, graphite moderated SMR, TRISO coated fuel particles • Initially open U fuel cycle, but once required, suitable for Pu and MA

burning, deep burn, symbiotic fuel cycles, and closed Th-U cycle• Strong negative reactivity coefficient, low power density, high thermal

inertia, fully ceramic core � intrinsic safety, benign behavior, no core melt• Two core options, power limited to enable

passive afterheat removal: – Hexagonal block (< 625 MWth) – Pebble bed (< 250 MWth)

• Forging capability can also set limit on RPV diameter and power (e.g. ∅6.7 m � < 350 MWth in South Korea)

• Today, mostly modular design with steel RPV, but formerly also pre-stressed concrete vessel

• Long-term operating experience up to 950°C (AVR, HTTR)• HTGR ≤ 850°C / VHTR > 850°C

Design options are flexible, the customer can choos e.

HTGR – Pebble vs Block-type CoreHigh temperature technology �� Particle fuel technolog y

TRISO particles�� Compacts

�� Graphite blocks

CompactTRISO Fuel Particles

Block

TRISO particles�� Pebbles

Slide 4

2. General Characteristics (1)• Modular design

� "Economy of Replication" instead of "Economy of Size".• High TRL, several existing vendor and technology companies

globally (but little available competence at regulators). • Quicker convergence from FOAK to NOAK cost reduction expected• SMR may not necessarily be cheaper (overnight cost in $/kW or

LCOE in $/kWh), but more affordable. Cost breakeven expected at natural gas price of 7-8 US$/MMBtu.

• Size options adapted to weaker grids and a broad variety of industrial sites.

• Large existing and potential future market (e.g. in chemical industry, synfuel, iron and steel, hydrogen for industry and transport fuel)

• NPP can expand as demand develops.

2. General Characteristics (2)• Reliable and scalable, can be used for grid services (load following,

frequency stabilization, blackstart capability) � not only for baseload but also compatible with variable renewable energy systems ("Hybrid Energy Systems")

• High temperature � high energy and exergy efficiency, lower cooling demand � suitable for arid regions

• Cogeneration for heating and cooling, use of waste heat for seawater desalination or district heating; > 750 reactor-years global experience, but limited so far to lower temperatures and relatively small scale

• one 600 MWth reactor saves about 1 Mt CO2/year if replacing natural gas and almost double if replacing coal firing.

• Intrinsic safety has a price tag: low power density, large components and large volumes of graphite waste which should ideally be decontaminated and recycled.

Operational feedback from:• 40 GCR (with CO2 cooling)• 7 HTGR (with He cooling)

• 5 countries• structures, components, fuel, graphite, gas coolant, design, licensing, operation etc.• temperature range 700 – 950°C

�Today: mostly modular design with coated particle fuel and passive decay heat removal (multiple demonstrations)�In addition: > 750 reactor-years experience with nuclear cogeneration (different reactor types, < 300°C, order of 10 MWth)

Test reactors

Fort Saint-Vrain, US (300 MWe, operated 1976-89)

THTR, Germany (300 MWe,operated 1986-89)

DRAGON, U.K. (20 MW, operated

1963-76)

AVR, Germany(15 MWe, operated 1967-88)

HTTR, Japan (30MWth, operated since 1998)

HTR-10, China (10 MWth, operated since 2000)

Peach Bottom, US (200 MWth,

operated 1967-74)

Industrial prototypes

HTR-PM, China (2 x 106 MWe)

• UK: Dragon, MAGNOX, AGR• Germany: AVR, THTR (know-how at TÜV, HTR GmbH)• US: Ft. Saint Vrain, Peach Bottom, NGNP & DOE (cf. ongoing

interactions with NRC)• Japan: HTTR• China: HTR-10, HTR-PM (under construction)• South Africa: PBMR (halted in 2010)• Outside GIF:

– Indonesian feasibility study– Several private companies (US: X-Energy, Ultrasafe Nuclear,

CDN: Starcore Nuclear, RSA: Thorium 100, UK: HTMR, AREVA+MHI, Westinghouse)

• Updates required to comply with tougher safety standards– Few regulators familiar with non-LWR designs– Coupling to end users: � cogen-specific risks (end-product contamination,

cross-risk exposure reactor/end-end user…)– Clarify responsibilities for licensing of cogen plants

Licensing Experience

Steam Generators

Reactor

Circulator

3. Missions– Short/Medium Term: Cogeneration (process steam):

very large potential market (e.g. 87 GWth < 600 °°°°C in Europe)– Long Term: Very high T applications (H2 production is original

driver, steel and chemical industry, transportation fuel, households)� industrial applications call for small Emergency Planning Zone

Efficiency Gains could be Possible in the Futurewith High Temperature Reactors

District heating seawater desalination

Petroleum refining

Oil shale and oil sand processing

Cogeneration of electricity and steam

Steam reforming of natural gas

HTSE and thermo-chemical hydrogen production

coal gasification

0 100 200 300 400 500 600 700 800 900 1000Process temperature, °°°°C

250-550°°°°C

300-600°°°°C

500-900°°°°C

800-1000°°°°C

350-800°°°°C

HTRsHTRsLWRsLWRs

80-200°°°°C Light Water Reactor

There is a role for existing LWRs, advanced LWRs, and small reactors…

4. How does the VHTR fulfil the GIF criteria?Criteria from GIF evaluation score 2002 (various wa ys of presentation)

1. Sustainability– Resource Utilization– Waste Minimization & Management

2. Proliferation Resistance3. Safety & Reliability

– Reliability & Worker Safety– Safety Features & Uncertainty– Source Term & Robustness

4. Economics– Construction & Operating Costs– Financial Cost & Profitability– Cost for Concept Development

5. System Overview• 7 Signatories: CH, EU, FR, JP, KR, US, CN

+ CDN in H2 Production project+ Australia in Materials project

• Validity of SA: 30 November 2016; extension desired• Last SSC Meeting 6-7 April 2016 in Seoul• Active projects:

1. Materials2. Fuel and Fuel Cycle3. Hydrogen Production4. Computational Methods, Validation & Benchmarking

(provisional)5. System Integration and Assessment

(under discussion)

5.1 Materials• Validity:

- existing PA -2015 (amended to include CN)- new PA -2018 (including CN) after FA is signed

• Signatories: CH, EU, FR, JA, KR, US- CDN, - RSA, + CN+ Australia: high T materials, welding, irradiations, corrosionnew PA was delayed due to legal complexity,problem is solved, next revision (-2018) may already include Australian contribution;

• Structure: 3 WG on Graphite, Metals, Ceramics• Output:

- highly productive, many LLD already available- PMB works on adding HLD

• Crosscutting workshops: (with PMBs from other systems)- on ceramics and composites: organized by KR (Sept. 2015)- on materials: organized by EU at CV Rez (April 2016)- arrangement for informal cross-system information exchange desired- session on next GIF Symposium requested

5.1 MaterialsReport Title Contributing Signatory

Compilation Of Reference Mechanical And Micro-Structural

Data For 800H And WeldmentsJRC European Union

Materials Testing Of Thin Section Alloy 800H Weldments For

Reactor Heat Exchanger ApplicationsJRC European Union

High Dose Experiments at 750°C & 950°C - Full PIE of

INNOGRAPH-IB and INNOGRAPH-2BJRC European Union

Creep Crack Growth Data Of Alloy 617 At 850°C KAERI Korea

Creep Rupture Data of Alloy 617 GTAW Weldment at 850°C KAERI Korea

Oxidation Of CVD Sic And Sicf/Sic Composite In He Atmosphere

With Different Oxygen Partial PressuresKAERI Korea

Creep and Creep-Fatigue of Alloy 617 Weldments DOE United States

The Effect of Weldments on the Creep and Creep-Fatigue

Behavior of Alloy 617DOE United States

Kinetics of Chronic Oxidation of NBG-17 Nuclear Graphite by

Water VaporDOE United States

17

Example of R&D Reported under VHTR Materials PMB Graphite Working Group

Slide 17

18

Example of R&D Reported under VHTR Materials PMB Metals Working Group

Slide 18

19

Example of R&D Reported under VHTR Materials PMB Ceramics Working Group

Slide 19

5.2 Fuel and Fuel Cycle• Validity: - Phase 1 PA: 2006 – 2011, - Phase 2 PA: 2012 – 2017• Signatories: US, KR, EU, JA

- CDN, - CH, FR (observer), + CN (Jan. 2014)• Structure: Phase 2 Workplan 2012-17:

1. Irradiation and PIE2. Fuel Attributes and Material Properties3. Safety testing4. Enhanced and Advanced Fuel Fabrication5. Waste management

• Output:– 97% completion rate in Phase 1 (72/74 deliverables)– already 28% in Phase 2 (15/53 deliverables)

• Productive collaboration:– Workshops on SiC coating properties– Irradiation testing, now with emphasis on PIE and safety testing– Burn-leach round robin (sharing particles to validate key QC measurements)– Workshops on sharing design options for heating furnaces, fuel deconsolidation and IMGA– Code validation of irradiation tests and accident heating tests

Water-cooled cold finger

Exchangeable condenser plate

Ta gas guiding shroud

Ta heater

Fuel pebble or compact

Optics for pyrometry

Heat shields & W/Re thermocouple

Cooling water flanges

Vacuum flange He inlet

He outlet

Power supply

Bottom plate

Lid lifting device

Sliding gate

Cold finger lock, evacuated or He filled

21

IMGA to find particles with low cesium retention

US Methodology for Isolating and Identifying Failed TRISO Fuel Particles Greatly Improves Ability to Characterize and Understand Fuel Performance

300,000 particles

in irradiation

Gamma scan tomography to

identify cesium hot spot and compact

location

Deconsolidation to obtain particles from compact

X-ray tomography and detailed micro-analytic techniques to

study nature of defect

0.15

0.36

0.25

0.00

0.00

0.12

0.00

0.64

1.04

0.51

0.72

0.89

0.49 0.61 0.34 0.19 0.33 0.00 0.24 0.61 0.20 0.31 0.62 0.31

5-2-1 5-2-3

5-2-2

AGR-1 Test TrainVertical Section

Fuel Compacts

Plenum between Capsules

Slide 21

Shared Capability of Fuel Accident Simulation Testing

Water-cooled cold finger

Exchangeable condenser plate

Ta gas guiding shroud

Ta heater

Fuel pebble or compact

Optics for pyrometry

Heat shields & W/Re thermocouple

Cooling water flanges

Vacuum flange He inlet

He outlet

Power supply

Bottom plate

Lid lifting device

Sliding gate

Cold finger lock, evacuated or He filled

Europe

Korea

USA

23

Fuel Performance Benchmark

Slide 23

5.3 Hydrogen Production

• Validity: current PA - 2016• Signatories: CDN, EU, FR, US, KR,

JA + CN• Structure:

1. Iodine-Sulfur Process: KR, JA, CN2. Copper-Chlorine Process: CDN3. High Temperature Steam Electrolysis: US, EU, CN

• Output:– Earlier FR/US decision against IS process now contested by progress in CN,

JA, KR;– Use of HTTR as heat source will enhance credibility of nuclear H2 production;– Good: Contributions mainly from non-nuclear projects– Current project management difficulties are being tackled by SSC:

re-invigoration of PMB dynamics, more collaboration instead of work in parallel (IP issues?)

High Temperature Steam Electrolysis (HTSE)

Achievements:Steam production: 5 kg/hInput Power: 4 kWTemperature: 700°C

SI facility and closed cycle operation

270 5 10 15 20 25 30 35 40 45 50 55 60

0

10

20

30

40

50

60

70

80

产氢速率平均产氢速率累计产氢量

H2

prod

ucin

g ra

te /

(L/h

)

0

500

1000

1500

2000

2500

3000

3500

4000

4500

5000

5500

6000

6500

7000

7500

8000

Total H

2 prroduction / L

0 10 20 30 40 50 600

20

40

60

80

100

O2 production Total production

Time (h)

O2

prod

uctio

n (L

/h)

0

400

800

1200

1600

2000

Total production (L)

Slide 27

Demonstrations of Nuclear H 2 ProductionHTTR I-S H2 continuous production demo (~ 200l/h-scale test in 2015 +)

NGNP project �� R&D program (> 2011)

+ Other possible H 2 demos

�HTR-PM (>2020) ?

� How to prompt expressions of needs for H 2 from nuclear?� Public/Private parnerships

� How to federate national plans into a consistent international technology roadmap?� R&D Gen IV, HTTR, NGNP…

NGNP: Process Heat, Hydrogen, and

Electricity

NGNP: Process Heat, Hydrogen, and

Electricity

5.4 Computational Methods, Validation & Benchmarkin g(provisional)

RSA had the lead in this project until 2010 (PBMR h alted). Then several years of doubtful future until CN pick ed up lead in 2014.• Validity: PA to be signed after FA signed by all signatories (spring 2016)

detailed task contribution sheets under preparation• Signatories: CN, EU, JA, KR, US• Structure: 5 Work Packages

1. Phenomena identification and ranking table (PIRT) methodology (lead EU)2. Computational fluid dynamics (CFD) (lead CN)3. Reactor core physics and nuclear data (lead US)4. Chemistry and transport (lead CN)5. Reactor and plant dynamics (lead CN)

• Output:– HTR-10 in-core temperature measurement ongoing– CN considers input from one or several of 16 HTR-PM engineering test facilities (useful for V&V of

codes and methods)– KR works on experimental validation of hybrid air/water RCCS (safety relevant)– US has constructed test facilities (HTTF, NSTF, MIR…) to validate codes

• Productive upfront collaboration:– Good: several signatories already active and will contribute results as BPI

31

• Refurbished an experiment at Argonne NL to generate data revealing the performance of this passive safety system

• Air-cooled RCCS tests underway

• Conversion to a water-cooled configuration is planned

• http://www.ne.anl.gov/capabilities/rsta/nstf/index.shtml

For Reactor Cavity (vessel) Cooling Studies

Facilities for HTR Code Experimental Validation – Natural circulation Shutdown heat removal Test Facility (NSTF)

October 2015 VHTR SSC, Oak Ridge, TN

5.5 System Integration and Assessment (on hold)

• VHTR SSC discussed SIA, e.g. as an orientation tool for other projects;• SSC drafted TOR for SIA project: due to process heat generation,

VHTR requires wider system boundaries than other reactors:– must include energy customer and interface with reactor;– should ideally encompass integration at energy system level:

e.g. which combination of nuclear, fossil, renewables for which combination of consumers (electricity, heating/cooling, industry, transport);

– desirable to perform market analysis and techno-economic evaluations;

• Most members interested, but new resources would be needed;

• Signatories agreed to share existing resultsin a special folder on GIF website;

Petroleum Refining (50-100)

Potential Number of HTGRs in the USA

Fertilizers/Ammonia (100+)

Petrochemical (150)

Coal-to-Liquids (100s)

Oil Sands/Shale (200+)

1 Million Metric Tons CO 2/year avoidedfor every HTGR (500 MWth) used in lieu of Natural G as

Slide 33

CO

• Uses 70% less coal

• Virtually no CO2 emissions

�� Over 95% of carbon in feed is converted to product

Gasifier

Product Upgrade

Fischer-TropschSynthesis

Gas Cleanup

Nuclear Plant Electrolyzers

CO2

H2S Sulfur Product

Synfuel25,000barrels/day

H2

O2

Nuclear Hybrid Coal to Liquid

Coal 4,400 tons/day

HTEor LTE

Steven E. Aumeier

250 MWe

HTR 2014, Weihai, China, 28 Oct. 2014

Configuration of HES

Max Output of 1061 MWeto the power GRID ►►

CompositeWind Farms

Node

DynamicEnergy

Switching

Nuclear reactor347 MWe (755 MWth)

Reactor Heat ►

1.000.000 t/DM/yr

Variable Electricity ►

+Synfuel Production

1018 MWe

Regional Biomass (80 Km radius or

~2 million hectares)

Drying and TorrefactionProcesses

+ Pyrolysis

104 GWhheat at 200 °°°°C

1169 GWhheat at 500 °°°°C

753m3/day bio-diesel

597m3/day bio-gasoline

Torrified Product

Pyrolyzed oil + char + offgas

42.000 t H2/yr

Hydrogen Electrolysis

Offsetting SMR ▲Electricity

Slide 35

6. Interaction with other GIF groups

• GIF RSWG:Prepared White Paper and Self Assessment; RSWG comments received in 10/2015, amendment finished, document expected final by 05/2016;

• GIF PRPP WG: interaction needs to be reactivated; • GIF EMWG: interaction to be reinforced, in particular to reduce cost uncertainties

and to identify avenues for cost reduction R&D (e.g. on graphite cost)• GIF SIAP: first contact established, focus on industrial aspects of demonstration

and deployment;• GIF Sustainability Task Force:

Focus on "complex" member views, VHTR SSC ready to contribute;VHTR White Paper on Sustainability from 2007; GIF has bias towards fuel resource sustainability;

• GIF Education and Training Task Force:- VHTR SSC participates in LinkedIn group: https://www.linkedin.com/grps/GenerationIV-Educatio n-Training-Task-Force-8416234- SSC and PMBs will prepare a webinar (May 2015, tbc)

Improving R&D CollaborationProject Planning – VHTR (1)

• VHTR Projects: Fuel & Fuel Cycle, Materials, Hydrog en Production, Computational Methods Validation & Benchmarking– VHTR successes

» Sharing irradiation tests for fuel qualification ATR (AGR2), HFR…» Sharing materials characterization work (steels, graphite,

ceramics, Codes & Standards…) + Materials Handbook» Joint ventures in Hydrogen production processes making national

assessments of these processes better documented– VHTR difficulties to implement new projects

» Computational Methods Validation & Benchmarks» Balance of Plant & Components» System integration & Assessment

Improving R&D CollaborationProject Planning – VHTR (2)• VHTR – Beneficial exchanges with RSWG & SIAP

– Safety (RSWG) + IAEA/INPRO» Confinement/containment building» Severe accidents approach » Radiological source term» Stochastic nature of pebble bed reactors» Coupling with industrial processes (H2, synthetic H-C-Fuels…)» Combined safety assessment

– Design convergence / Licensing risks (SIAP)» Unique technology choices / Unique safety and licensing issues» Licensing novel technologies / Licensing in various countries» Fuel cycle including waste management

– Early aspects of commercialization (SIAP)» Qualified advanced materials» Components infrastructures

Improving R&D CollaborationProject Planning – VHTR (3)

• VHTR – Brakes on a more active GIF collaboration– Changing national priorities & funding (RSA, USA, France…)� Withdrawal of members (RSA, Canada…) & Delayed Project Plan updates– No plan for Gen-IV VHTR-Demo or Prototype

(HTR-PM is a near term project)� No real Baseline concept identified: NGNP (USDOE) ?, PBMR (?) ?,

GTHTR300C (JAEA) ?� Too little shared interest and work on Computational methods,

Components, System integration to sustain Projects on these issues

• VHTR – Paths for improving the collaboration– More systematic updates of Project Plans, Work Plans & Monitoring of

deliverables – More active engagement with MWGs (SDC) & SIAP (Position paper on

cogeneration)… – Take greater benefit from HTTR & other large experimental facilities

7. Future collaborative R&D topics

• Targeted towards demonstration and long-term perfor mance.

• Some topics suitable for collaboration within GIF, others more for IAEA or OECD/NEA or bilateral collaboration framewo rks.

• Headlines (details available):

1. Materials, Components and Supply Chain

2. Safety Demonstration

3. Licensing

4. Advanced Materials and Components

5. Fuel, Fuel Cycle, and Waste Minimization

6. Advanced Fuel Cycles

7. Coupling to Cogeneration Applications and Use for Energy System Integration

8. Advanced Energy Use and Storage Methods

8. Interaction with IAEA and OECD/NEA

IAEA:- regular participation in GIF – IAEA interface meetings;- presentation to be given on INPRO Dialogue Forum;- provided input to new CRP on HTGR safety; - development of VHTR Safety Design Criteria in 2016 (tbc);

OECD/NEA:

• Participated in meeting of Group on Safety of Advanced Reactors (Sept. 2015) to enhance regulator understanding of non-water cooled reactors in view of licensing; however, GSAR has limited resources and decided to focus on SFR severe accident issues (irrelevant for VHTR);

• Participating in NI2050 initiative (March/April 2016);

9. Related international activitiesGEMINIJoint effort of NC2I & NGNP IA for demonstration• MoU signed June 2014• Workshops in Paris, Washington, Piketon, Brussels• International Workshop in Washington, March 2016:Participation of Korea and Japan is being explored

• Modular design to meet common needs:– similar components– 300 or 600 MWth (1 or 2 loops)

UK Department of Energy and Climate ChangeSMR Techno-Economical Assessment and £ 250 million SMR call (participation of GEMINI); not sure if non-LWR have a serious chance;

NC2I Task Force in SNETPR&D and other activities towards demonstration: Finalization of Concept Paper, strategy, design activities, project preparation, identification of financing options,

HTR 2016 Conference6-10 November 2016, Las Vegas (200 technical papers plus invited talks)

10. Wrap-up• GIF VHTR projects share expertise and infrastructure and progress well• Isolated project management challenges are being resolved • Excellent collaborative achievements confirm usefulness of GIF • Several countries active in VHTR (several companies, new projects)

– Safety, high efficiency, process heat applications (steam, H2)

– GEMINI (EU+US), BATAN (Indonesia), StarCore Nuclear (Canada), X-Energy (US), HTMR (UK), STL (RSA)

– HTTR (Japan) waiting for regulator OK– HTR-10 (China) is running– HTR-PM (China) start-up at end-2017

• VHTR budgets in several GIF signatorycountries could be in better adequacy with VHTR market potential,safety performance and energy policy impact;

• Items for further collaboration identified

HTR-PM 20 March 2016

Overview on the Very High Temperature Reactor...Overview on the Very High Temperature Reactor System...

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