WSRC-STI-2006-00344 APP Max Gorensek, PhD, PE Senior Fellow Engineer Computational and Statistical Science 16 th HAPL Workshop Princeton, NJ December 12-13, 2006 Feasibility of Hydrogen Production Using Laser IFE as the Primary Energy Source
WSRC-STI-2006-00344APP
Max Gorensek, PhD, PESenior Fellow Engineer
Computational and Statistical Science
16th HAPL Workshop Princeton, NJ
December 12-13, 2006
Feasibility of Hydrogen Production Using Laser IFE as the Primary Energy Source
WSRC-STI-2006-00344APP
National Security Demands Energy Security
• The U.S. imports more than 50% of its crude oil and is expected to import more than 60% by 2010.
• U.S. consumers pay foreign countries over three billion dollars a week to satisfy the demand for imported oil.
• Much of our oil is imported from politically unstable areas of the world.
Photo: oil fire in Kuwait following Desert Storm
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Oil Production Will Peak Before Mid-Century
Source: US (DOE) Energy Information Administration
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Fossil Fuels Have an Inherent Problem
Source: The White House Initiative on Global Climate Change, Barnola et al.
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Atmospheric CO2 Concentration Is Growing…
Source: Climate Change 2001:The Scientific Basis, Contribution of Working Group I to the Third Assessment Report of the Intergovernmental Panel on Climate Change.
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… and Could Double Pre-Industrial Level By 2100
Source: United Nations Environment Programme / GRID-Arendal
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A “Hydrogen Economy” Is Part of the Solution
Broad-based use of hydrogen as a fuel– Energy carrier analogous to electricity– Produced from variety of primary energy sources– Can serve all sectors of the economy: transportation, power,
industry and buildings– Replaces oil and natural gas as an end-use fuel– Makes renewable and nuclear energy “portable”
Advantages:– Inexhaustible– Clean– Universally available to all countries
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Hydrogen Can Be Made from a Variety of Domestic Energy Resources
HydroWindSolar
Geothermal
.
Distributed Generation
Transportation
Biomass
Water
Coal
Nuclear
NaturalGas
Oil
Wit
h C
O2
Seq
ues
trat
ion
HIGH EFFICIENCY& RELIABILITY
ZERO/NEAR ZEROEMISSIONS
Source: US DOE
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A Hydrogen Economy Will Need a Lot of Hydrogen
H2 demand for all U.S. light-duty vehicles 110 MMt/yr by 2050*
– 12-fold increase over current (industrial) use
– Power content = 450 GWth (current average US electricity demand = 450 GWe)
Other applications could double H2 demand
Energy for H2 production would be similar to energy for electric power generation, will require multiple primary sources
– Fossil fuels with CO2 sequestration
– Renewable energy with electrolysis– Nuclear water-splitting* “The Hydrogen Economy; Opportunities, Costs, Barriers, and
R&D Needs”, National Academy of Engineering (2004).
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Current Industrial Hydrogen Market Is AlreadySignificant
World hydrogen consumption is 42 MMtons/yr– Major users are refineries and fertilizer (ammonia) plants
– Represents 200 GWth of power (5.7 Quad)
U.S. production is 9 MMtons/yr– 1.1% of primary energy (5% of U.S. natural gas usage)– Sufficient to power 60 million fuel cell vehicles– Equals energy output of 40 nuclear power plants
Rapidly growing hydrogen demand in refineries to process heavier, higher sulfur crude oils
Development of tar sands and oil shale will require additional hydrogen
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Time of Day/MonthH2 Storage
High Capacity Pipeline
Industrial H2 Users
Hydrogen Fueled Future
Distributed Power
Transport Fuel
Centralized Nuclear Hydrogen Production Plant
Nuclear Hydrogen Future
Thermochemical Process H2O → H2 + ½ O2
DOE-NE’s Nuclear Hydrogen Initiative actively supporting development of H2 production technology
Could easily substitute Laser-IFE (or other fusion energy device) for VHTR
Heat
Modular Helium Reactor (850 to
1,000°C)
O2
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“Big Dumb” Laser IFE Chamber Concept
Tungsten-armored ferritic steel first wall
Molten lithium self-cooled blanket
Maximum radius 6.5 m Twelve side blanket modules Separate upper and lower
blankets Coolant connections at
bottom Vacuum vessel supports
blanket modules
Sviatoslavsky, I.N et al., Fusion Science & Techn., 47(3), 535 (2005).
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Lithium Self-Cooled Blanket Concept Parameters
Fusion Power (MW) 1,800
Total Thermal Power (MW) 2,103
First Wall Material F82H FS ODS FS
FW Maximum Average Temperature (°C) 550 700
FS/Li Interface Maximum Temperature (°C) 600 600
Li Inlet Temperature (°C) 383 533
Li Outlet Temperature (°C) 650 800
Li Pressure Drop, MPa < 0.5 < 0.5
Power Conversion Cycle Efficiency 0.40 0.45
Sviatoslavsky, I.N et al., Fusion Science & Techn., 47(3), 535 (2005).
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Laser IFE with Magnetic Diversion Concept
SiC first wall (Tmax = 1,000°C)
Liquid Pb-17Li self-cooled blanket (Pb-Li/SiC interface Tmax = 1,000°C)
Magnetic diversion mitigates first wall ionic bombardment– Cusp-shaped magnetic field
diverts ions to collectors– >90% of ion energy resistively
dissipated in SiC structure (can’t use metal structure)
– <10% of ion energy deposited in collectors
Graphic Courtesy A.R. Raffray, University of California, San Diego
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Magnetic Diversion Chamber Concept
Courtesy G. Sviatoslavsky, University of Wisconsin
Magnets
Upper Pole Blanket
Upper-mid Blanket
Lower-mid Blanket
Lower Pole Blanket
Ring Cusp Armored Dump
Point Cusps Armored Dump
6m
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Magnetic Diversion Concept Blanket Parameters
First Wall Material SiCf/SiC
Total Thermal Power (MW) Pb-17Li
FW Maximum Average Temperature (°C) 1,000 1,100
SiC/Pb-Li Interface Maximum Temperature (°C) 900 950
Li Inlet Temperature (°C) 483 580
Li Outlet Temperature (°C) 799 930
Li Pressure Drop, MPa 0.3 0.3
Power Conversion Cycle Efficiency 0.50 0.55
A.R. Raffray et al., 15th HAPL Program Workshop, La Jolla, CA, August 9, 2006
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HAPL Blanket Development Summary
Detailed conceptual design of W-armored, FS chamber with liquid Li self-cooled blanket completed
Conceptual design of SiCf/SiC chamber with magnetic diversion underway– Pb-17Li and Flibe self-cooled blankets considered– Outlet temperatures up to 930°C calculated for Pb-17Li– Current work at UCSD suggests outlet temperatures as high as 1,100°C
may be possible with Pb-17Li
Helium-cooled, dual-cooled blanket concepts will be considered Blanket development has been focused on power production High temperature, low pressure blankets hold promise for water-
splitting applications to make hydrogen
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Water Splitting Options Using Laser IFE Heat
Conventional Electrolysis– Thermal Energy → Electricity → Hydrogen– ηHHV = 24% (LWR), 36% (HTGR), 40+% (Laser-IFE?)
High Temperature Steam Electrolysis– Uses both heat and electricity– ηHHV = 45-55%
Thermochemical Water-splitting– Direct heat to chemical energy conversion– ηHHV = 45-60%
η = ΔH(H2)/QIFE
H2O(l) → H2(g) + ½O2(g) ΔHrxn = 285.7 MJ/kmol
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Conventional Electrolysis
H2O (l) → ½O2 (g) + 2H+ + 2e-2H+ + 2e- → H2 (g)
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Conventional Electrolysis
Electricity Generation Electrolysis
of Water
Energy(IFE Heat)
Energy Losses
Hydrogen
Oxygen
Overall Electrolysis Process
Water
CCGT generating efficiency for Laser IFE up to 57% (MWe/MWth) Typical electrolysis efficiency is
75% (HHV H2/MWe)Combined efficiency no more
than 42% (HHV H2/MWth)
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Raising temperature of electrolysis reaction decreases cell potential (work requirement).
Basis for High Temperature Electrolysis
High Temperature Electrolysis
Temperature, °C Cell potential, V*
25 1.23
500 1.06
1000 0.94
1500 0.81
2000 0.64
* P = 1 atm.
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High Temperature Steam Electrolysis
Source: US DOE-NE, Nuclear Hydrogen R&D Plan, March 2004
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Steam Electrolysis
Electrolysis reactions:H2O(g) + 2 e– → H2(g) + O= cathode reaction
O= → ½ O2(g) + 2 e– anode reaction
H2O(g) → H2(g) + ½ O2(g) net reaction
O= is the charge carrier in the ceramic electrolyte (solid oxide, typically yttria-stabilized zirconia)
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Simplified Flowsheet of Laser IFE-driven High Temperature Steam Electrolysis Process
Adapted from US DOE-NE, Nuclear Hydrogen R&D Plan, March 2004
Laser IFE Heat Source
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Thermochemical Water-splitting
What is a thermochemical cycle?– Chemical process– Series of chemical reactions that combine to split water– All intermediate reactants regenerated– True thermochemical cycles use only heat to drive process– Hybrid cycles use both heat and electricity– Extensively studied from mid 1970s to early 1980s– Hundreds have been proposed– At least 115 reported in the literature
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The Sulfur Family of Thermochemical Cycles
Source: US DOE-NE, Nuclear Hydrogen R&D Plan, March 2004
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Hybrid Sulfur (HyS) Hybrid Cycle for Production of H2
H2SO4 ½O2 + SO2 + H2O> 800°C
Heat
H2 + H2SO4 SO2 + 2H2O100°C
Electric Energy SO2 + H2OH2SO4 (H2O)
H2OH2O
H2H2
½O2½O2
Inputs:
• Water
• Heat (>800°C)
• Electricity
Outputs:
• Hydrogen
• Oxygen
• Waste heat
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HyS Cycle Simplified Flowsheet
Power Generation
Laser IFE Heat Source
Sulfuric Acid Decomposition
Electrolyzers and Auxiliaries
Sulfur Dioxide / Oxygen Separation
Thermal Energy
H2O, SO2, O2
H2SO4
H2O FeedO2 By-product
H2O, SO2
Electric Power
H2 Product
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SRNL Electrolyzer Configuration
• Nafion® or other proton exchange membrane
• Gas diffusion carbon electrodes
• Membrane electrode assembly (MEA) construction
• Porous carbon flow fields• Recirculating acid anolyte• No catholyte needed
Anode
(+) (−)
Cathode
PEMSeparator
2 H+
2 e−
2 H+ + 2 e− → H2(g)
H2(g)
SO2(aq) + H2O(l) → SO3(aq) + 2 H+ + 2 e−
SO2(aq), H2O(l)
SO3(aq) + H2O(l) → H2SO4(aq)
H2SO4(aq)
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E-1
5
3
ANODE
CATHODE
1
THR-01
6
4
2
HX-01
7
8
9
THR-02
10
HX-02
11
12
13
THR-03
14
HX-03
15
16
17
PUMP-01
18
HX-04
19
20
21
PUMP-02
22
HX-05
23
25
24
PUMP-03
26
TO-01
KO-05
KO-04
KO-03
KO-02
KO-01
56 HX-17
57 KO-06
58
53
Hot He In
Hot He Out
RX-01
52
54
59
HX-16
HX-18
60
KO-12
61
62
HX-19
63
HX-20
64
KO-13
6566
HX-06
27
PUMP-04HX-07
28
PUMP-05
HX-08
KO-06
29
35
36
PUMP-06
37
CO-01
39
HX-11
HX-09
KO-07
30
41
PUMP-07
CO-02
44
HX-12
KO-08
47
PUMP-08
45
HX-10
31
CO-03
46
HX-13PUMP-09
50
51
48
38
33
32
34
Hx-14
75
KO-10
76
77
78
DR-02
82
MCOMP-01
79
KO-11
81
THR-04
80
43
40
42
85
83 SEP-01
84
MCOMP-02
86
PUMP-11
87
PUMP-10
69
HX-21
68
MIX-01
TO-02
67
74
71
73
72Oxygen Product
70 Water Feed
Hydrogen Product
HX-15
DR-01
55
49
SRNL HyS Process Flowsheet
electrolyzer
3-stage vacuum flash 2-stage pressurized flash
acid decomposition loop
single stage absorber
H2/water separation
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Hydrogen Production Using Laser IFE
SRNL white paper study for HAPL program– Feasibility of concept– Advantages over other H2 production methods (especially nuclear)– Suitability of FTF for H2 production demonstration
Self-cooled blanket temperatures overlap GenIV coolant temperatures – most technology can be “borrowed” from NHI– Same thermochemical and high temperature electrolytic methods as NHI– Low coolant pressure, higher temperature range may provide advantage– If Laser IFE being developed for power production, Laser IFE H2
production should also be considered Differences that will need further study
– Need for secondary coolant– Heat source/ H2 plant separation– Heat transfer at higher temperatures with molten salts
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Net Thermal Efficiency Estimates for HAPL Blanket Concepts
Case No. T 1, °C T 2, °C η p, id * η p, max *
1. Li / FS 383 650 0.746 0.4812. Li / ODS FS 533 800 0.820 0.5293. Pb-17Li / SiCf/SiC (1,000°C) 483 799 0.808 0.5224. Pb-17Li / SiCf/SiC (1,100°C) 580 930 0.852 0.5505. He / SiCf/SiC A-HCPB 350 700 0.747 0.4826. Pb-17Li / SiCf/SiC ARIES-AT 800 1,100 0.910 0.587
* assumes T 0 = 25°C
Tp Q
H
)½(22222 OHOHOHOH hhhnH
Enthalpy change between end product and starting materials
Total heat requirement from primary energy source
Enthalpy change for water-splitting
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Acknowledgements
This work sponsored by U.S. Department of Energy under Contract No. DE-AC09-96SR18500
Funding provided by the Naval Research Laboratory under the High Average Power Laser Program– Dr. John D. Sethian
Consultation– Prof. A. René Raffray (University of California, San
Diego)