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1 Current Status of Research and Development on System Integration Technology for Connection between HTGR and Hydrogen Production System at JAEA Hirofumi Ohashi, Yoshitomo Inaba, Tetsuo Nishihara, Tetsuaki Takeda, Koji Hayashi and Yoshiyuki Inagaki Japan Atomic Energy Agency, Japan

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1

Current Status of Research and Development on System Integration Technology for Connection between HTGR and Hydrogen Production System

at JAEA

Hirofumi Ohashi, Yoshitomo Inaba, Tetsuo Nishihara,

Tetsuaki Takeda, Koji Hayashi and Yoshiyuki Inagaki

Japan Atomic Energy Agency, Japan

2

Contents

Concept of the HTGR hydrogen production system

R&D items on the system integration technology

Control technology to keep reactor operation against thermal disturbance caused by the hydrogen production system

Estimation of tritium permeation from reactor to hydrogen

Development of a high-temperature isolation valveto separate reactor and the hydrogen production system in accidents

Conclusion

Countermeasure against explosion of combustible gas

3

HTGR Hydrogen Production System

Isolation valve

Concept of the HTGR Hydrogen Production System

Chemical reactorSecondary heliumhot gas duct

Intermediate heat exchanger (IHX)

Reactor

4

IHX Chemicalreactor

Primary He gas Secondary He gas Process gas

Raw material

Hydrogen

Reactor

R&D Items on System Integration Technology

IHX ChemicalreactorReactor

Control technology to keep reactor operation against thermal disturbance caused by the hydrogen production system

IHX ChemicalreactorReactor IHX ChemicalreactorReactor

Reactor scram

Estimation of tritium permeation from reactor to hydrogen

IHX Chemicalreactor

Raw material

Hydrogen

Reactor

Control technology to keep reactor operation against thermal disturbance caused by the hydrogen production system

TritiumTritium

Hydrogen

Countermeasure against explosion of combustible gas

Estimation of tritium permeation from reactor to hydrogen

IHX Chemicalreactor

Raw material

Hydrogen

Reactor

ExplosionBlast

IHX Chemicalreactor

Raw material

Hydrogen

Reactor

Isolation valve

Countermeasure against explosion of combustible gas

Development of a high-temperature isolation valve to separate reactor and the hydrogen production system in accidents

5

Control Technology (1/3)

ObjectiveDevelopment of the control technology to keep reactor operation against thermal disturbance caused by the hydrogen production system.

ApproachJAEA proposed to use a steam generator (SG) as the thermal absorber which

is installed downstream the chemical reactor in the secondary helium gas loop.In the HTTR hydrogen production system, target value of the mitigation for the

helium gas temperature fluctuation is within 10 oC at SG outlet.

Simulation test on the loss of chemical reaction was carried out using a mock-up test facility

Primary He gas Secondary He gas Process gas

Raw material

Hydrogen

IHX SGReactorChemicalreactor

6

Control Technology (2/3)Simulation test on loss of chemical reactionMock-up test facility

880oC

LN2 tank

LNG tank

Water tank

Radiator

Steam generator

Chemical Reactor(Steam reformer)

Electric heaterCirculator

Flare stack

Hot gas ductHelium gas circulation loop

Nitrogen feed line

Natural gas feed line

Steam feed line

600oC

CH4+H2O3H2+CO

450oC

650oC

Steam generator

Electric heater

Helium gas circulator

Chemical reactor

Flare stack

Steam generator (SG)

With electrical heater instead of IHX of HTTR

Helium gas temperature and pressure at the chemical reactor inlet (880oC, 4MPa) are same as those of the HTTR hydrogen production system.

4MPaSteam reforming of methane is used instead of the IS process.

7

Control Technology (3/3)Simulation test on loss of chemical reactionProcedure

The supply of the raw gas for the hydrogen production, methane, was suspended during the normal operation.

Radiator

SG

NitrogenNaturalCirculation

Helium gas(840oC, 4MPa)

Loss of chemical reaction

Chemical reactor

Feed water

Chemical reactor

Helium gas(840oC, 4MPa)

SG

Raw gasHydrogen

Radiator

200

400

600

800

1000

-1 0 1 2 3 4 5 6

Experimental result

The fluctuation of the helium gas temperature could be mitigated at SG outlet within the target range of 10 oC.

Elapsed time [h]

SG outlet

SG inlet

Chemical reactor inlet

Chemical reactor outlet

Hel

ium

gas

tem

pera

ture

[oC

]

8

Estimation of Tritium Permeation (1/2)

ObjectiveTo investigate the permeability on the material of the IHX tubes, Hastelloy XR.

Apparatus

Measurement Pipe(Hastelloy X)

Measurment System-Hydrogen

Cooling System

AutomaticControl System

MeasurmentSystem-Temperature-Pressure-Flow Rate

Heating System

Main Heater(6kW)

Gas Supply SystemH2/He,D2/Ar,etc.

Gas Purge SystemAr, He,etc.

Vacuum System

Flow Control

Pre-Heater(1kW)

Molecular Sieve

Flow Control

Molecular Sieve

Exhaust System

Hastelloy XR(Test Pipe)

Hydrogen and deuterium are used instead of tritium

9

Estimation of Tritium Permeation (2/2)

The basic data on the permeability of hydrogen and deuterium has been obtained for the Hastelloy XR tube.

Experimental result

Temperature [oC] Partial pressure of H2 [Pa] E0 [kJ/mol] F0 [cm3(NTP)/(cm⋅s⋅Pa0.5)]

Hydrogen570 ∼ 820

1.06×102 ∼ 3.95×103 67.2 ± 1.2 (1.0 ± 0.2)×10-4

deuterium 670 ∼ 820 9.89×102 ∼ 4.04×103 76.6 ± 0.5 (2.5 ± 0.3)×10-4

Permeability : Kp = F0 exp(-E0 / RT)

Next research itemsTo investigate the permeability on the heat transfer tube material of the chemical reactor in IS process, SiC.To estimate the tritium concentration in the IS process and the produced hydrogen.

10

Countermeasure against Explosion (1/2)

Principal countermeasures against explosion of combustible gas

Take a distance between the reactor and the hydrogen production system enough to mitigate the overpressure within an allowable range.

Protect blast with barriers such as wall, bank and so on.

Limit the leak amount of combustible gas.

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Countermeasure against Explosion (2/2)

Inner pipe

Outer pipe

Combustible gasFilled with nitrogen gas

Support

Manhole

Limit the leak amount of combustible gasDesign of coaxial pipe of combustible gas

Next research itemA conceptual design using a wall and/or a bank is under way from the viewpoint of mitigation of blast

12

Development of High-Temperature Isolation Valve (1/4)Objective High-temperature

Isolation Valve (HTIV)Development of an isolation valve for the high-temperature condition around 900oC.

Technical issuesPrevention of the valve seat from thermal deformation

An angle valve with an inner thermal insulator was selected.

Development a new coating metal for the valve seat surface

A new coating metal was developed based on the Stellite alloy that is used for valves at around 500 oC.

Selection of a valve seat structure having a high sealing performance

A flat type valve seat was selected.

Confirmation of the seal performance and structural integrity

A component test was carried out using 1/2 scale model of HTIV.

13

Development of High-Temperature Isolation Valve (2/4)

HTIV 1/2 scale modelNominal Size 22 B 16 BBore 200 mm 100 mmDesign Temp. (Casing) 350 oCDesign pressure 5.0 MPa 4.5 MPa

1/2 scale model of HTIV Actuator

Thermal insulator(Glass wool)Electric heater

Seat (HastelloyX)Coating metal (Stellite No.6 + 30wt%-Cr3C2)

RodBody (HastelloyX)

Casing (Carbon steel)

14

He gas supply system

Ar gas supply system

Actuator

1/2 scale model of HTIV

Cooling water

To He gas detector

Exhaust

Electric heater

Electric heater

Thermal insulator

Development of High-Temperature Isolation Valve (3/4)

Apparatus

Experimental condition and procedure

(1) Helium gas was supplied to the 1/2 scale model of HTIV and increased up to 4.0MPa and heated up to 900oC.

(2) Valve seat was closed and helium gas at the upstream of the closed valve seat was exhausted. The pressure difference across the valve seat was set to 4.1MPa.

(3) The electric heater was shut off and the helium gas leak rate through the closed valve seat was measured from 900oC to 200oC by the helium gas detector.

Component test

15

0 200 400 600 800 1000

10

1

10-1

10-2

10-3

10-4

Temperature of valve seat (oC)

4.4 cm3/s : Target valueLe

ak ra

te o

f hel

ium

gas

(cm

3 /s)

Development of High-Temperature Isolation Valve (4/4)

Experimental resultComponent test

Next research itemThe improvement of the durability of the valve seat

The current technology can be applied to the HTTR hydrogen production system, however, the lapping of the valve seat is necessary after closing at a high temperature.

16

Conclusion (1/2)The system integration technology has been developed for connection

of the hydrogen production system to HTGR. The following conclusions were obtained.

The control technology to keep reactor operation against thermaldisturbance caused by the hydrogen production system

JAEA proposed to use SG as the thermal absorber, which is installed downstream the chemical reactor in the secondary helium gas loop, to mitigate temperature fluctuation of secondary helium gas. By thesimulation test with the mock-up test facility, it was confirmed that SG could be used as the thermal absorber.

The permeability on Hastelloy XR which is the heat transfer tube material of IHX was obtained.

Tritium permeation from reactor to hydrogen

Next research item is to investigate the permeability on the heat transfer tube material of the chemical reactor in IS process, SiC, and to estimate the tritium concentration in the IS process and the produced hydrogen.

17

Conclusion (2/2)

The new material for the coating of the valve seat surface was developed and the seal performance of the valve was confirmed to satisfy the design target with the 1/2 scale model of the high-temperature isolation valve. The improvement of the durability of the valve seat is the next target for the development.

The coaxial pipe of combustible gas was designed from the viewpoint of protection of the leakage aiming at arrangement of the hydrogen production system closed by the reactor. A conceptual design using a wall and/or a bank is under way from the viewpoint of the mitigation of the blast.

Countermeasure against explosion of combustible gas

Development of the high-temperature isolation valve to isolate reactor and hydrogen production systems in accidents

18

The present study is the results of “Development of Nuclear Heat Utilization Technology“ in fiscal year from 1997 to 2001, 2003 and 2004 entrusted by Ministry of Education, Culture, Sports, Science and Technology (MEXT) to Japan Atomic Energy Research Institute (JAERI) succeeded by into Japan Atomic Energy Agency (JAEA).

The authors are indebted to Dr. S. Shiozawa and Dr. M. Ogawa fortheir useful advice and discussion in this research.

Acknowledgement

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20

Control TechnologySimulation test on loss of chemical reaction

0

20

40

60

80

020406080

100120140

-1 -0.5 0 0.5 1

Experimental result

200

400

600

800

1000

0123456

-1 0 1 2 3 4 5 6Elapsed time [h]

SG outlet

SG inlet

Chemical reactor inlet

Chemical reactor outlet

Pre

ssur

ein

SG

[MP

a]H

e te

mpe

ratu

re [o

C]

Elapsed time [h]

Flow

rate

[g/s

]H

ydro

gen

prod

uctio

nra

te [m

3 /h]

Steam

Methane

Nitrogen