Nuclear non-electric applications are a proven, safe, and reliable practice- 77 water-cooled reactors with 750 reactor-

years operation experience- District heating- Desalination (10 reactors in Japan) - Industrial process (<200oC)

Generation IV reactors enable high temperature (>200oC) heat applications - Industrial process heat/steam- Transportation fuel (refining, synthesis)- Hydrogen production- Steelmaking- Nuclear-renewable hybrid cogeneration

Currently ~1% of the nuclear energy is directed for non-electric applications !

Opportunities for nuclear non‐electric applications

Opportunities for nuclear non‐electric applications

2

Nuclear reactors and their heat supply temperature range

Industrial process temperature range

Gen

erat

ion

IV

Rea

ctor

s

Generation‐IV Technology Readiness (GIF)

3

実証段階成立性確認段階 性能確認段階

2000 2005 2010 2015 2020 2025 2030

VHTR

SFR

SCWR

MSR

LFR

GFR

Feasibility  Performance  Demonstration plant 

HTGR or VHTR

HTGR Development Worldwide, Today

USA：NGNP PRIME 600 MWt, 750C, heat application, design stage

Indonesia： EPR (Experimental PowerReactor: 10 MWt, 500C‐1,000C, design stage)

ＥＵ：GEMINI+• Design and R&D ofcogeneration HTGR system

United Kingdom：U‐Battery

10 MWt, Power reactor,design stage

Block type HTGR

Japan：HTTR operational (30 MWt, 950C)GTHTR300:(600MWt,electricity, desalination, H2)

Pebble bed type HTGR

Poland：HTGRproject：

Research reactor (10‐30 ＭＷt,design stage)Commercial reactor (‐165 ＭＷt, FS to be started) Heat supply to industries 

instead of coal fired plant

Kazakhstan：KHTR 50 MWt, design stage

Korea：NHDD 600 MWt, design stage Canada：Star Core HTGR

36 MWt, power reactor,design stage

Reactor SG

IHX

Steam turbinePower generation

District heating

Hydrogen productionplant (future plan)

Isolation valve

KHTR

Saudi Arabia：Feasibility study with China of HTR‐PM for desalination and industrial heat application.

China：2x250MWt twin units HTR‐PM under construction

4

North American Markets for HTGR (NGNP IA)

5

North American Markets500 GWt : 810 HTGRs (600MWt/reactor) Co‐generation 75 GWt Oil Sand/oil Shale 18 GWt Hydrogen production 36 GWt Synthetic fuel 249 GWt IPP power 110 GWt

European Markets for HTGR (EUROPAIRS nuclear cogen)

6

100 GWt = 500 HTGRs (200MWt/reactor)

Japan Markets for HTGR (for CO2 reduction)

7

Stealmaking

13%

Civil3%

Automobile17%

Others23%

Power generation26%

CO2 emission11.9 hundred million tone (2010)

Civil13%

Others23%

Power generation26%

30％ decrease30% Decrease with HTGR

Petrochemistry 3%Steal making 4%Automobile 1%

Hi. temp.heat

H2

HTGR (600 MW)

Steal making with H2 reduction Petrochemical plantFuel-cell powered automobile

H2 (Fuel)16％ decrease

HTGR : 30 plants

Hi. temp. heat, H2 (reductant)9% decrease

HTGR : 20 plants

Hi. temp. heat, Steam5% decrease

HTGR : 15 plants

Steam

1 plant : 4x 600 MWt HTGRs

Petrochemistry 8%

Japanese Markets : 180 HTGRs (600MWt/reactor)

HTGR reactor designs : Some selected cases 

8

GT‐MHR (US) HTR‐PM (China) NGNP (GA/US) PBMR (SA) NGNP (AREVA/US)

HTGR and heat applications development in Japan

HTTR

(1) HTTR test reactor 

Developed technologies of fuel, graphite, superalloy and gained experience of operation, and maintenance.

(2) BOP application technology    

(3) HTGR commercial plant design

GTHTR300

Develop GTHTR300 plant design for power generation, cogeneration of hydrogen, steelmaking, desalination, and for hybrid system with renewable energy

Establish safety standards for commercial plants.

R&D of gas turbine technologies such as high‐efficiency helium compressor, shaft seal, and maintenance technology

In 2016, 31 hours of continuous automated hydrogen production with a rate of 20NL/h was successfully achieved.

JAEA built and operated the 30 MWt and 950oC prismatic core HTGR test reactor (Operation from 1998 to present)

He compressor

hydrogen facility 

(4) Connection technology  Couple a cogeneration 

plant to HTTR for demonstration of gas turbine power generation and hydrogen production.

Completed pre‐licensing basic design for the HTTR‐GT/H2 test plant.

9

HTTR‐GT/H2

10

JAEA`s HTGR Test Reactor ‐ HTTR

Main featuresThermal power 30 MWtFuel SiC TRISO UO2 coated

particle fuel, pin in blockDesign type Prismatic coreCoolant HeliumTemperature 950 C (Max.)Pressure 4 MPa

Containment vessel Reactor core

Reactor building Interior

Controlroom

Refuelmachine

Intermediate heat

exchanger

- VHTR test reactor -

Dry cooling tower

Milestone

FYITEM

▼

▼

Commissioning test

Power-up test

Rated power operation and safety demonstration tests

Construction of reactor building & components

Criticality test

Fuel fabrication Fuel loading

1990 1991 1996 1997 1998 1999 2000 2001 2002 2003 2004

First criticality (Nov 10)

Construction decided

▼30 MW, 850C

(Dec 7)

▼

950C(Apr 19)

19871969

▼R&Dsstart

・・・ ・・・・ ・・・

Long-term program for R&D and utilization of nuclear energy

▼Construction start

Construction

Test andOperation

2005 2010・・・

▼

950C50 days

operation

HTTR ‐ History of R&D, Construction, Operations

Safetytest LOFC

▼

11

Station blackout (i.e.Fukushima event) test planned after HTTR restart

2. Auxiliary cooling system

Reactor

Taken off‐line in test  1. Main cooling system

Inherent Safety of HTTR‐ Loss of forced cooling (LOFC) test without scram (2010)

12

Reactor

Heat

Control rods

0

50

100

0

15

30

Flow

(%

)Po

wer

(%

)

Coolant flow rate in core(test data)

Reactor power approaches to zero even without scram(test data) (Analysis)

circulators trip▼

0

50

100

150

200

250

300

-1 0 1 2 3 4 5 6 7 8 9 10 11 12

p(

)

Experiment Analysis

0‐1 0 1 2 3 4 5 6

Time from start of test (hr)

Time from start of test (hr)

Core side reflector temperature

Tem

pera

ture

(oC

)

• Reactor cooling by VCS3. Vessel cooling system (VCS)

HTTR cooling system

Test Analysis

13

HTTR is ready for coupling to non‐electric processes

Coupling of HTGR to various industrial heat applications  may be test demonstratedon HTTR:• Hydrogen production• Heat/steam supply• Desalination• Cogeneration

HTGR hydrogen production pathway

HeatFossil fuels

Hydro-carbon Water Water

Electricity (75%) Heat (25%)

Water Water

Electricity (~50%)Heat (~50%

Steam reforming

Waterelectrolysis

Steam electrolysis

(800oC)

Thermochemical water-splitting

(850oC)

Hybrid cycle water-splitting

(550-850oC)

Energy input

Feed stocks

Hydrogen processes

High temperature gas-cooled reactor (HTGR)750-950oC

ElectricityHeat

Hydrogen, oxygen

Electricity Heat (75%) Electricity (25%)

Energy conversionSupply by

HTGR power/heat cogeneration

H2, CO2

14

Nuclear hydrogen production by steam reforming (saving 35% natural gas/CO2) can be coupled to HTTR for test today !

15

Steam reforming H2 production plan on HTTR (@ 950oC)

Existing

test facility for steam reforming of natural gas (operated in 2004)

Coupling (to be constructed)

Construction of integrated closed‐cycle IS process using industrial materials

Operations : 2016:  20 L/h for 31 hours 2018~2019: 100L/h planned

Thermochemical hydrogen production – IS process (JAEA)

Bunsen

HI decom

p.

H2 SO

4 decomp.

H2 Production Test Facility

0

100

200

300

400

500

600

700

800

0 5 10 15 20 25 30 35

積算製造量

[NL]

試験時間[h]

水素製造量

酸素製造量

Time [h]

Prod

uctio

n of H

2an

d O

2[NL]

Rate of H2(ca. 20 L/h)

H2

O2

16

Heat(HTGR)

400~500oCH2

H2O

I2

I2

H2+ 2HI H2SO4 SO2 + H2O1/2O2+

2HI + H2SO4

I2 + SO2 + 2H2O

Hydrogen iodide (HI) decomposition

Sulfuric acid (H2SO4) decomposition

SO2+

H2O

O2

Bunsen reaction (HI and H2SO4

production)

800~900oC

I S

Oct. 24-26 (2016)

Demonstration plant of nuclear hydrogen production

HTTR-GT/H2 Objectives• To demonstrate nuclear hydrogen and electricity cogeneration

system performance and cost • To license nuclear hydrogen production coupling to HTGR

Reactor

Containment vessel

PPWC

Coupling – high temperature heat transport loop with isolation valves

1. Gas turbine power generator set

3. Heat exchanger for potential heat applications (steam supply, desalination, etc)

Dry cooling tower

HTTR Building（existing facility） 2. Hydrogen production 

(IS process) plant

H2SO4 decomposer

Bunsen reactor

IHX Multiple cogeneration capabilities（New facility for demonstration)

HI decomposer

Pre-licensing design completed in 2017

17

HTTR‐GT/H2 cogeneration parameters and planned tests

IHX

HTTR

H2 production IS process plant

Gas turbinePower generation

Coupling w/ H-Tisolation valves

Heat exchanger for process heat or cooling

850oC

950oC

30 Nm3/h - H2

1 MWe electricity generation

3 MWt process heat supply

10MWt

• Control against loss of H2 load

• Nuclear reactor response to H2 plant accident (chemicals)

• H2 plant startup & shutdown operation in concert with reactor operation

• Cogeneration load following

Planned demonstration tests

• Hydrogen and heat product safety

Operational tests Safety tests

18

Steam generator

Concentric hotgas duct

Steamoutlet

Feed water

To He gascirculator

Process steam supply HTGR commercial design 

19

Prismatic core

Examples of Reactor designs (SMRs):• Xe-100 (Pebble-bed, 200MWt, US X-energy)• HTR50, MHR-100 (Prismatic 50-250 MWt, Japan)• MHTGR (Prismatic 350-450 MWt US/Areva)• MHT (Prismatic 200 MWt, Russian Federation)• Others

HTR50

MHR-100

750oC4.0 MPa

Primary He

Generator

325oC4.04 MPa

538oC12.5 MPa

Condenser

DeaeratorFeed water heaters

Turbine

50MWtReactor SG

50MWt

533oC12.0 MPa

200oC13.4 MPa

8.6 MWeSteam

HX25MWt

533oC12.0 MPa

200oC

Process heat user

Process heat user

20

HTR50S‐ Process steam supply

e.g., desulfurization process in petroleum refinery

Steam

GTHTR300 cogeneration system design variants

21

H2 Cogeneration

Reactor : 600 MWtElectricity: ~203 MWeHydrogen : ~60 t/d

Desalinationcogeneration

Reactor: 600 MWtElectricity: 280 MWe

Potable water: 55,000 m3/d

Reactor thermal: 600 MWtElectricity: up to 300 MWeNet efficiency: up to 50%

Reactor power (max. output) 600 MWtReactor temperature 850‐950oCRefueling interval/period 1.5‐2 yrs/30 daysPlant load factor 90%Reactor coolant pressure 7 MPaMax. production (not all at same time)• Hydrogen (thermochemical method) 120 t/d• Electric power (50% net efficiency) 300 MWe• Desalination (cogenerated w/power) 55,000 m3/d• Steel (CO2 free steelmaking) 0.65 million t/yr

Power GenerationReactor

power plant

Reactor power plant

Cogeneration

22

Desalination using nuclear power plant waste heat

MSF desalination plant (optimized for waste heat recovery)

GTHTR300 reactor power plant

Desalination using waste heat from nuclear reactor No penalty to nuclear plant power generation

23

Waste heat recovery raises thermal efficiency

Reactor power 600 MWtPower generation 280 MWePower generation net efficiency 45.6%Shutdown refueling interval 2 yrsPlant availability factor 90%Reactor inlet/outlet temperature 587/850oCReactor coolant pressure 7 MPaReactor coolant flow rate 441 kg/sRecoverable waste heat (RWH) 220 MWt

(37% of reactor power)RWH temperature range 60 - 140oC

WasteHeat

Gas turbine

Reactor

Heat exchangers

Loss17%

Seawaterdesalination

Powergeneration

Nuclear reactor thermal efficiency

83%

24

Competitive nuclear desalination cost

Plant ‐>CCGT

desalination plant HTGRdesalination plantOil‐fired** Gas‐fired**

Capital (US$/m3) 0.29 0.29 0.39

Energy (US$/m3)HeatElectricity

1.650.13

0.670.13

0.040.09

Operation (US$/m3)ConsumablesO&M

0.020.03

0.020.03

0.020.03

Water cost (US$/m3) 2.13 1.14 0.57

Desalination costs between HTGR and fossil‐fired CCGT  

** Cost of fuel oil is 79.8 US$/bbl, the minimum of the average of Brent, Dubai and WTI benchmarks during 2004.7 to 2014.7 and natural gas 5.6 US$/MMBtu, the minimum of the average of US, Europe and Japan prices in the same period.

HTGR multipurpose cogeneration GTHTR300 is an HTGR system series being developed in Japan for 

cogeneration of power, hydrogen, desalination, steelmaking, etc. Designed by JAEA, Mitsubishi Heavy Industries, Fuji Electric, Kawasaki 

Heavy Industries, Nuclear Fuel Industries, Toshiba, IHI, others. Development status: Pre‐licensing basic design completed.

25

GTHTR300C

GTHTR300Crev.080403

Turbine GeneratorCompressor

Reactormodule

HTXmodule

GTG module

Recuperator

Precooler

Controlvalves

GTHTR300C

Annularblock core IHX

module

helicaltube bundle

process heat

Hydrogen production

Process heat

IHX

Reactor

Gas turbine power generation

900oC

Seawater desalination

District heat

200oC

850~ 950oC

GTHTR300 Nuclear reactor thermal efficiency

75%Hydrogen production

PowergenerationSeawater

desalination

Loss25%

26

Nuclear hydrogen production cost estimation

Evaluation conditions: NOAK plants Estimated by IAEA HEEP

software (CRP*) Used 9 countries`

financing parameters Compared to LWR +

electrolysis HEEP costs of $5.5/kg SMR (360 MWe);$3.5/kg APWR (1.1 GWe)

Japan`s hydrogen target (2030~) :¥30/m3 (~$3/kg)

Hyd

roge

n pr

oduc

tion

cost

(US$

/kg-

H2)

* CRP on “Examining the Techno-Economics of Nuclear Hydrogen Production and Benchmark Analysis of the IAEA HEEP Software”

0

1

2

3

4

5

6

7

X HEEP default financial valuesX HEEP default financing parameters

7

6

5

4

3

2

1

0Case A Case B Case C Case D

Reactor APWR HTGR HTGR VHTRHydrogen technology

Cu‐Cl hybrid

IS thermo‐chemical

Steam reforming

IS thermo‐chemical

Hydrogen (kg/s) 4.25 1.36 3.48 3.08

27

Costs of alternative hydrogen production options Comparison of Hydrogen Production Costs

Target cost of hydrogen production in 2030*5

020406080

100120140160

Hydrog

en produ

ction cost (¥

/Nm

3 )

30

31 ‐ 58

84

76 ‐ 136

20 2024 ‐ 3218 ‐ 46

*2

*2 The cost of equipment of the reformeris not included.

*3 The cost of equipment of the electrolyticdevice and the electric transmission costs,etc. are not included.

*3

*1

HTGR+ IS process cost: JAEA estimation*4

*4

*5 Target cost: METI, Strategic Road Map forHydrogen and Fuel Cells, March 22, 2016.

Hydrogen production cost except HTGR + IS: ANR, Hydrogen and fuel cell strategy conference working group (5th)-handout, April 14, 2014.

*1

Industry application : nuclear steelmaking

Currently, steelmaking emits 140 mton‐CO2/yr or 12% of national GHG total in Japan*1

CO2‐free steelmaking may be performed by hydrogen and electricity produced by HTGR cogeneration system via process below.

*1：Data of 2016. Ref.: Greenhouse gas emission data in Japan (1990‐2016 definite report), Greenhouse Gas Inventory Office of Japan (May 29th, 2018 update).*2：Domestic steel production: c.a. 290,000 t/d (2016).*3：Kasahara and Ogawa, Production of Green Energy and Its Utilization in Ironmaking and Steelmaking Processes, Iron and Steel Institute of Japan, 123‐143, 2012.

Energy and material balance of a plant to produce steel of 10,000 ton/d *2 (Scale of a standard steel plant in Japan) *3

Unit of heat, electricity: TJ/dUnit of materials: t/d

H2: 656

H2O: 5903

Electricity: 22.5 H2O → H2 + 0.5O2

Heat: 172.4

Heat:  85.4

Fe2O3 + 3H2→ 2Fe + 3H2O

Electricity: 17.6(600 MWt×5)

Iron ore: 16043, Scrap: 1081

HTGR

Gas turbine power generation

IS processDirect reduced iron: 10767

Steel: 10098

Shaft furnace

Electric arc furnace

Hydrogen production cost is estimated as about 25 ¥/Nm3.

28

HTGR hydrogen steelmaking process (Korea) 

29HTR2012 conference, Tokyo, Japan.

Time

Short time scale (sec~min) : ±20% of nuclear rated powerUtilize large core thermal inertial (an intrinsic heat storage)

HTGR Nuclear

Solar& Wind

Long time scale (hour~day）Adjust reactor gas pressure to varypower/heat ratio. : ±75% of nuclear rated power

Hybrid constant power

＋Steady constant power to grid

H2(thermal IS, HTE, etc.)

HTGR and renewable hybrid energy systemPo

wer

gen

erat

ion

rate

30

HTGR + renewable hybrid power for grid stability & cogeneration

Power-to-heat ratio control

Power control

BV

IV

Corethermal inertia

Reactor

Core heat capacitance 370 MJ/oC

GTHTR300 Solar/Wind

Summary of economics for HTGR renewable hybrid system

31

HTGR cost sensitivity to load followBaseload

Load follow 

Power generation cost ¥/kWh] (2014) 7.8 7.8

H2 production cost [¥/Nm3]  (2006) 27 32

Costs are largely unaffected as the reactor maintains baseload dispatching two products

Share of variable renewable power

Power adjustment costs*

6% (66 B kWh) 300B ¥/yr (4.5¥/kWh)

12% (124 B kWh) 700B ¥/yr (5.6¥/kWh)

Hybrid with HTGR could avoid these power adjustment costs for renewable power.

Electric grid system of mixed sources

19%

0%

Avoid grid stabilization costs for renewable

* Including 1) thermal and pumped hydro power generation 2) interregional connection of renewable sources; and 3) others (batteries, smart meters, etc.). Source: Power generation cost analysis working group, Report on analysis of generation costs, etc. for subcommittee on long‐term energy supply‐demand outlook, Japan, May 2015. 

HTGR

Renewablepower

Electric grid

LWR

Fossil power

Regional grids

Interconnectionlines

Battery

Hydro power

H2power

H2

FCV, industry

Due to reduced load factor

Demonstrate safe, reliable, and economic supply of high temperature nuclear heato Need for demonstration of licensing, operation, production

Develop compatible heat processes to nuclear reactoro Hydrogen process (HTSE, thermochemical, hybrid process)o Steelmaking process (iron ore reduction furnace)o Desalination process (waste heat recovery)o Others

Safety considerationso Co‐location and coupling of nuclear reactor and industrial process

Remaining issues for nuclear high temperature applications

32

Safety considerations for industrial cogeneration

H2 plant

Tritium

I. Temperature and pressure transients due to H2 plant abnormal events

II. Tritium migration from nuclear facility to product

III. Transportation of chemical substances from H2 plant to nuclear facility

I

II II

III

H2O2Products

HTGR

Combustible gasToxic gas

Corrosive gas

HTGR coupling to H2 plant

33

950oC heat exchanger

900oC heliumisolation valve

Design Consideration for Chemical Substance Leakage

Combustible gas leakage

Reactor building

H2 plant

H2 inventory [ton]

0

100

200

0.01 0.1 1 10

Set appropriate offset distance between reactor building and H2 plant

Safe

dis

tanc

e to

mai

ntai

n al

low

able

ove

rpre

ssur

e fo

r or

dina

ry b

uild

ing[

m]

Combustible gas leakage

34

Measures against tritium migration from nuclear plant

HTGR IHX H2 plant

Permeationthrough tube

Tritiumgeneration Circulation

Tritium is produced ternary fission reaction in the fuel particle and by neutron absorption reaction of 6Li, 10B and 3He in the core.

Tritium permeates through the heat transfer tube of the heat exchanger.

Tritium permeates from the helium loop to atmosphere through the outer wall of the component and piping.

Isotope exchange reactions between tritium and hydrogen‐containing process chemicals, i.e., H2O, H2SO4 and HI.

Tritium generation in core

Primary loop 100%

Secondary loop 69.152%

Product H2

0.946%

Leakage0.106%

PS30.742%

Permeation

Leakage0.105%

PS30.341%

Tertiary loop 8.705%Leakage0.121%

PS35.139%

Product O20.053%

Drain water2.446%

Permeation

Permeation

Tritium mitigation generic scheme

35

Safety design requirements (Proposal) Maintain process values in reactor system within operating limits against temperature and pressure

transients induced by H2 plant abnormal events Mitigate inflow rate of chemical substances to reactor system and control room within allowable limits

against chemical substance transport. Mitigate external load due to combustible gas explosion within allowable limits against chemical

substance transport. Mitigate tritium migration within allowable limits against tritium transport to H2 plant. 36

Safety Functions Reactor safety design considerations

Control, Monitoring, Operation limitCore temperature monitoring, reactor coolant temperature control, secondary system flow rate control, isolation valves, IHX differential pressure control

Prevention of combustible substance inflow Isolation valve

Mitigation of external load Robust confinement, offset distance from industrial plant

Prevention of corrosive substance inflow Isolation valve, offset distance, secondary system pressure control

Prevention of toxic substance inflow CR ventilation system, offset distance from industrial plant

Mitigation tritium migration Reactor coolant purification

HTGR coupling to industrial cogeneration plant (H2 or desalination) as non-nuclear facility

Industrial H2 plant is not assigned to any of the safety design considerations above

Regulatory Demarcation Boundary

Isolation valves are defined as boundary between nuclear facility and non-nuclear facility

IHX

Precooler

Recuperator

Compressor

G

Turbine

H2plant

Reactor

Isolation valve

Nuclear reactor regulation

Industrial legislation

Industrial legislation

Desalination plant

Isolation valve

H. Sato et al., JAEA-Technology 2014-031 (2014). 37

38

Summary

Generation-IV reactors under development worldwide enable a wide ranging of high-temperature heat application. Demonstration of safe, reliable, and economic nuclear high temperature heat supply is needed.

Worldwide markets for high temperature non-electric applications are at least as substantial as nuclear power generation.

Industrial processes compatible to nuclear reactors need to be developed.

Operational / safety / licensing issues related to the coupling of nuclear reactors to high temperature processes remain to be addressed.

38

Thank you! Welcome to JAEA`s Oarai R&D Center

H T T RHTGR test reactor

The Pacific

JoyoSodium Fast reactorJMTR

Material test reactor