2245-9 joint ictp-iaea advanced school on the role...

2245-9

Joint ICTP-IAEA Advanced School on the Role of Nuclear Technology in Hydrogen-Based Energy Systems

Karl Verfondern

13 - 18 June 2011

Research Center Juelich Institute for Energy and Climate Research

Julich Germany

[email protected]

The Production of Hydrogen with Nuclear Energy Part 2: Hydrogen Production Systems

[email protected]

Mitg

lied

der H

elm

holtz

-Gem

eins

chaf

t

The Production of Hydrogen with Nuclear EnergyPart 2: Hydrogen Production Systems

Karl Verfondern Research Center Jülich, Institute for Energy and Climate Research (IEK-6)

Joint IAEA – ICTP Advanced School on “Development and characterization of materialsfor hydrogen-based energy systems: Role of nuclear technology”

June 13-18, 2011, Trieste, Italy

Production of Hydrogen with Nuclear EnergyTrieste, Italy, June 13-19, 2011

Folie 2IEK-6 Reactor SafetyKarl Verfondern

ContentsPart I- Hydrogen Economy and the Role of Nuclear PowerPart II- Hydrogen Production Methods Using Nuclear Heat/Power - Steam Reforming- Coal Gasification- High Temperature Electrolysis- Thermochemical CyclesPart III- Nuclear Process Heat Reactors



Routes of Hydrogen Production



Current Hydrogen Production Methods

48% natural gas steam reforming30% oil partial oxidation

18% coal gasification

4% electrolysis



Hydrogen Plant

• Steam-methane reformer of Uhde design

• Capacity: 13.8 t/h or 153,000 Nm3/h corresponding to 550 – 630 MW (HHV)

• purity > 99.9%

• Feedstock: natural gas, refinery off-gas,liquid propane (mixed feed, alternativefeed, spare feed)

• Load range: 100% - 40%

• Heat flux: 70 kW/m2

Uhde



Nuclear Steam ReformingEVA-I reformer tube at FZJ

• most widely appliedconventional productionmethod

• savings of ~ 35% of NG,if process heat is fromnuclear

• tested under nuclearconditions in pilot plantsin both Germany andJapan

Pr gy Folie 7IEK-6 Reactor SafetyKarl Verfondern

EVA-II Reformer Tube Bundle at FZJ



EVA-ADAM (Long-Distance Energy Transport)

EVA

ADAM



Technical Data of EVA-II/ADAM-II Facility

Power Input 10 MWeCooling gas flow rate 4 kg/s of heliumPressure 4 MPaTemperature max/min 950/350 °CSG temperature/pressure 700 °C / 5.5 MPaMethane input 0.6 kg/sSteam reforming temp. max 820 °CMethanation temp. max 650 °CADAM-II heat release rate 5.3 MWt

From 1981 - 1986: 13,000 hours of operation, of which 7750 h at 900 °C and 10,150 h as complete process



Combined HTTR/SR Complex

HTTR

SteamGenerator

SteamReformer

Naturalgas

Water(H2O)

Hydrogen

IHX10MW

IsolationValve

950C

30MWFeed gas preheater

395°C

Pressurized water cooler

20MW

150°C Radiator

Heliumcooler

905°C

Steamsuper heater



He circulator

Electricheater

Steamreformer

Steamgenerator

H2; 120m3/h, COF low Diagram and Main Test Items oO ut-of-Pile Demonstration Test Facili1/ 30 scale model of HTTR hydrogen productio

R eplacement of nuclear heat with electricityH2:110Nm3/h,COM LN2 tankLNG tankPumpPumpEvaporato rEvaporato rSurgetankFlarestacSurgetankProductgasInert gas feed li neProductgascombustion

880℃

Condenser

Steam generator

Steamreformer

Electric heaterCirculator Hot gas duct

Helium gas circulation system

Product gas

Nitrogen feed lineProduct gas combustion system

Natural gas feed system

Steam feed system

600℃

650℃

450℃

Shematic Diagram of Simulation Test

Oarai, Japan

JAEA Steam Reforming Out-of-Pile Pilot PlantSchematic of Simulation Test



Coal Refinement

790 kWh electricity

360 kg coal dust

250 kg charcoal

280 l methanol

160 kWh gasoline

550 m3 synthesis gas

150 m3 SNG

Conversion of 1000 kg of lignite



Coal Gasification with Nuclear Energy

with steam: C + H2O H2 + CO - HCO + H2O H2 + CO2

------------------CO + 3 H2 CH4 + H2O

with hydrogen: C + 2 H2 CH4 + H

------------------CH4 + H2O CO + 3 H2 - H

CO + H2O H2 + CO2



Gas Composition after Steam Coal Gasification

High pressure increases methane content good for SNG productionHigh temperature increases hydrogen content good for syngas production

Pr tion of Hydrogen with Nuclear EnergyTrieste, Italy, June 13-19, 2011


Nuclear Simulated Steam Coal Gasification

Lab scale testing:1973-1980 with 5.0 kg/h

Semi-technical scale testing: 1976-1984 with 0.5 t/h

Gasification: at 750-850°C and 2-4 MPa

Total coal gasified: 2413 tOperation time: ~26,600 h with

~13,600 h under gasification cond.



Pilot Plant for Hydro Coal Gasification

Semi-technical scale testing: 1975-1982 with 0.2 t/h

Pilot plant scale testing:1983-1986 with 10.0 kg/h

Gasification: at 850-950°C and 6-12 MPa

Coal throughput: ~40,000 twith up to 6400 Nm3/h of SNG

Operation time: ~8000 h



Steam Coal Gasifier Design for Prototype Plant

Thermal Power: 340 MWCoal throughput: 50 t/hEffective volume: 318 m3

Heat exchanging area: 4000 m2



General Achievements of PNP Project

Confirmation of technical feasibility of allothermal, continuous coal gasification

Manufacture and successful operation of high temperature heat-exchanging components

Demonstration of licensing capability of a nuclear process heat HTGR by resp. safety research

But under the given conditions at that time, the nuclear process was not competitive

with the conventional process!



200 m3/h

Electrolysis

Electrolysis ideal for remote and decentralized H2 production

Off-peak electricity from existing NPP (if share of nuclear among power plants is large)

As fossil fuels become more expensive, the use of nuclear outside base load becomes more attractive.

Norsk Hydro



High Temperature Electrolysis

Increased efficiency; Reduced electricity needs; Capitalize from SOFC efforts.

Erdle 1995



High Temperature Electrolysis Ceramatec SOEC

stack test2 x 60 cells, ½ ILS module operated for 2000 h

Herring



Thermochemical Cycles

Decomposition of water by a series of thermally driven chemical reactions

Criteria arereaction kinetics, thermodynamics, max. temperature, heat transfer, separation of substances, side reactions, material stability, toxicity, corrosion, processing scheme, thermal efficiency, cost

Top candidates- sulfur family (S-I, HyS, Mark13) with H2SO4 splitting- Ca-Br (UT-3) cycle- Cu-Cl hybrid cycle



Sulfur-Iodine Cycle

Nuclear HeatNuclear HeatHydrogenHydrogen OxygenOxygen

H2O22

1

900 C400 C

Rejected Heat 100 C

Rejected Heat 100 C

S (Sulfur)Circulation

SO2+H2O+O22

1H2SO4

SO2+

H2OH2O

H2

I2+ 2HI

H2SO4

SO2+H2OH2O

+

+ +

I (Iodine)Circulation

2H I

I2

I2

WaterWater

Nuclear HeatNuclear HeatHydrogenHydrogen OxygenOxygen

H2O22

1 O22121

900 C400 C

Rejected Heat 100 C

Rejected Heat 100 C

S (Sulfur)Circulation

SO2+H2O+O22

1H2SO4

SO2+

H2OH2O

H2

I2+ 2HI

H2SO4

SO2+H2OH2O

+

+ +

I (Iodine)Circulation

2H I

I2

I2

WaterWater

(9 I2)l + (SO2)g + (16 H2O)l



S-I Process DemonstrationILS Loop by GA, Sandia, CEA

４０

３０

２０

１０

０１０２０３０４０５０

２０

１０

－２０

－１０

０

０

Operation time (h)Flu

ctu

atio

n o

f I 2 c

onc. in

sulfuric a

cid

(%)

Ｈ２Ｏ２

５０

２：１

Pro

duction o

f H

2 an

d O

2 ( )

0

1

2

3

4

5

6

0 50 100 150 200

H2, O

2 Pro

duct

ion

[Nm

3 ]

Operation Time [h]

H2

O2

JAEA 2004

Achieved 65 l/hAchieved 30 Nl/h over 1 week



Nuclear H2 R&D Projects in Japan

HTTR + S-I to become the world‘s first nuclear H2 production plant



Nuclear H2 R&D Projects in Japan

GTHTR300H

direct cycle,block-type core950°C at coolant exit

168 MW(th) for the sulfur-iodine processfor 24,000 Nm3/h of H2

plus 202 MW(e)



Thank youfor your kind attention !

email: [email protected]

2245-9 joint ictp-iaea advanced school on the role...

Documents