nuclear non-electric applications are a
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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
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
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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.
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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.
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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
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