Post on 26-Mar-2022
IS Process Experiment Group
HTGR Research and Development Center
Japan Atomic Energy Agency
Innovation for Cool Earth Forum
8th Annual Meeting, October 6-7, 2021
Myagmarjav Odtsetseg
Technology Section 3“Nuclear Power as a Power Source for Decarbonization”
(10:10 ~ 11:10, Oct. 7, 2021)
Role of high-temperature gas-cooled reactor (HTGR) for carbon neutrality in Japan
Prime Minister Suga presented a plan for global warming countermeasures (Leaders Summit on Climate,
April 22, 2021)
• Mid-term target: 46.0% reduction by FY2030 compared to FY2013
Green Growth Strategy Through Achieving Carbon Neutrality in 2050 was updated on June 18, 2021.
GHG emission in Japan (Final report of FY2018)
Ref. : Website of Ministry of Environment, Japan
Breakdown of GHG emission (2018)
• The emission reduction in FY2018 : 12.0% compared to FY2013
• To achieve the goal,
Reduction by additional 34% by 2030
Reduction by additional 88% by 2050
Role of HTGR
• To produce hydrogen for nuclear steel making
and fuel cell vehicle
• To produce steam for conventional industries
• To absorb renewable power variation2
HTGR development at JAEA and history of HTTR
Conceptual design
System integrity
design
Basic design
H T T R
Detail design
Application and permission
of construction
Construction
First criticality
Reactor outlet coolant
temperature 850ºC (30MWt)
Reactor outlet coolant
temperature 950ºC
850ºC/ 30 days operation
950ºC/ 50 days operation
Safety demonstration test
(Control Rod drawing test)
1973
1969
~
1980
1974~
1984
1981~
1985~
19881989
19901991~
1997
1998
2001
2002
2004
2007
2010
~
Start of Loss of
Forced Cooling test
2014Safety review on the New
Regulatory Requirements toward resumption of operation
Purpose Establishment of HTGR technologies
Establishment of Heat utilization technologies
Reactor Physics
Very High Temperature Reactor
Critical Assembly (VHTRC)
Thermal Hydraulics
Helium Engineering
Demonstration Loop (HENDEL)
Fuels・Materials
In-pile Helium loop (OGL-1)
First in
the world
Restart
2020Approval of restart by NRA (June 3rd)
Specification of HTTR
● Reactor thermal power ・・30MW
● Reactor coolant・・・・・・・・ Helium gas
● Reactor inlet/outlet coolant temperature
・・・・・・・・・・ 395ºC / 850ºC, 950ºC
● Reactor material ・・・・・・ Graphite
● Fuel ・・・・・・・・・・・・・・ UO2 coated particle fuel
● Uranium enrichment ・・・ 3% ~10% (average 6%)
Pressurized Water
Cooler
Intermediate
Heat
Exchanger
(IHX)
Reactor
Building
Concentric Hot
Gas Duct
Reactor Pressure
Vessel
High Temperature Engineering Test Reactor
HTTR
Research and Development
Safety demonstration
tests
JAEA restarted the HTTR in July 30, 2021.
300
350
400
-1 0 1 2 3 4 5 6 7
0102030
0
50
100
Flo
w r
ate
(%
)P
ow
er
(%)
Te
mpera
ture
(ºC
)
Time(h)
Tripping gas circulators
Core cooling flow rate
Results of test
Reactor power
Results of test, Analysis
Average fuel temperature
Analysis
Reactor is naturally shut down as soon as the core
cooling flow rate is reduced to zero.
Reactor is kept stable long after the loss of core cooling.
USA France Germany Korea Czech Hungary
OECD/NEA project
Japan
3
Multi-purpose heat applications using HTGR
4
0 1200oC300oC 600oC 900oCLow
temperatureMedium temperature
High temperature
Heat
application
Iron-making
Hydrogen (IS process)
Hydrogen (steam reforming)
De-sulfurization of heavy oil
Petroleum refineries
Desalination, district heating
Gas turbine power generation
Wood pulp manufacture
LWR: Light water reactor
HWR: Heavy water reactor MSR: Molten salt reactor
HTGR: High temperature gas cooled reactor
HTGR can supply 950ºC of heat, which is significantly higher than other types of reactors.
The heat supplied by HTGR can be used for various applications.
Nuclear
heatLWR, HWR
HTGRMSR
IS process: Iodine-sulfur process
HTGR-H2 system technology development at JAEA
Lab-scale test
( ~ 1998)
Elemental technologies test
(2005 ~ 2009)
Commercial use
Transfer technology to
private sectors
5
Iodine-sulfur (IS)
processIS process decomposes
water with heat of ca. 900oC
using chemical reactions of
iodine (I) and sulfur (S).
I and S are circulated
⇒ No harmful waste
HTGR heat is used
⇒ No CO2 emission.
Filter maintenance
H2 production rate wasintentionally adjusted toreduce risk of cloggingpipe caused by I2
solidification.
Pro
du
cti
on
of
H2
an
dO
2
[m3]
Operations for 3 sections integration was successfully carried out (0.03 m3/h-H2 for 150 h).
H2 (integrated val.)O2 (integrated val.)
Time [h]
Key components in the IS process environment(corrosion resistance, heat resistance)
H2SO4
decomposerCeramic (SiC)(<900oC)
HI decomposerNi-base alloy (<500oC)
Bunsen reactorFluoro-plastic lined steel(<100oC)
• Verification of integrity of total components and stability of hydrogen production
• Development of strength evaluation methodology for ceramic components
H2 test facility (0.1 m3/h)
Ceramic (SiC)
Glass lined steel pipe
Corrosion-resistant lining vessel(fluoro-plastic, glass)
• Plant operation control systemPlant maintenance techniques
• Membrane technologies to improve thermal efficiency
Industrial material component test
(2010 ~)
Present
Bench-scale test
(1999 ~ 2004)
Uncovering an closed-cycle
continuous operation
condition (0.001 m3/h-H2)
Demonstration of
one-week continuous
H2-production by
glass apparatus
(0.03 m3/h-H2)
2045〜
R&D towards commercialization of GT and hydrogen HTGR
6
2020 20502030 2040
Target schedule**
(Priv
ate
se
cto
r)JA
EA
Technology of Steam generator, Steam
system connecting technology
High burnup fuel, High performance core
System with inherent safety
Establishment of safety standard for
steam connecting technology
HTTR-GT/H2 test
HTTR
GT facility
Hydrogen
production
facility
※GT:Gas Turbine, SR:Steam Reforming, IS:IS process, **:JAEA’s draft plan
Research reactor
Demonstration reactor
Inte
rna
tional
co
llab
ora
tion
Design of demonstration
reactor (GT, SR)
Demonstration tests for
component (GT, SR)
Construction of demonstration reactor
(GT, SR) Design of demonstration reactor (GT, IS)
Demonstration tests for component (IS)
Construction of commercial reactor
(GT, SR)
Construction of demonstration reactor
(GT, IS)
HTTR test, HTTR-GT/H2 (SR) test
Confirmation of fuel/material
performance under commercial
reactor condition
Support of establishing design/
material standard
Development of basic
technologies for IS process
HTTR-GT/H2 (IS) test
Confirmation of fuel/material
performance under commercial
reactor condition
Establishment of safety standard
through licensing
Demonstration of H2 plant coupling
technologies
Demonstration of system technologies
Training of operators
International collaboration on HTGR R&D at JAEA
Multilateral collaboration Bilateral collaboration
Civil Nuclear R&D Working Group (CNWG)
Development of simulation algorithm, validation of analytical
model, study of connecting test between HTTR and heat
utilization system
(Department of Energy: DOE, Idaho National Laboratory: INL)
HTTR The only test and
research reactor of
HTGR in the world to
supply heat of 950oC
International joint
researches for needs
of each country
Design collaboration for Kazakhstan HTGR: KHTR (National Nuclear Center: NNC)
ISTC project on irradiation research of oxidation-resistant SiC fuel compact (Institute of
Nuclear Physics: INP)
Safety research (Nuclear Technology Safety Center: NTSC)
Very High Temperature Reactor (VHTR)
Hydrogen Production System Project
Fuel and Fuel Cycle Project
Material Project
Computational Methods Validation and Benchmarking Project
Joint Test by HTTR, LOFC Project (Contracted Research)
Loss of forced cooling test (Completed)
- All three primary helium gas circulators were tripped at the initial reactor power of 30%
Loss of core cooling test (planned)
- All three primary helium gas circulators are tripped at the initial reactor power of 100%
- Vessel cooling system is simultaneous tripped at reactor power of 30%
Technical Working Group on Gas Cooled Reactors (TWG-GCR)
(Number of countries: 17)
Technical Working Group on Small and Medium Sized or Modular
Reactors (TWG-SMR) (Number of countries: 21)
Coordinated Research Project (CRP)
Assessing Technical and Economic Aspects of Nuclear Hydrogen
Production for Near-term Deployment
Development of Approaches, Methodologies and Criteria for
Determining the Technical Basis for EPZ for SMR Deployment
Economic Appraisal of SMR Projects: Methodologies and Applications
Cooperation to U-Battery project (Commercial HTGR system) (URENCO, etc.)
Cooperation on HTGR technology (National Nuclear Laboratory: NNL)
Information exchange on HTGR safety (Office for Nuclear Regulation: ONR)
Czech Hungary USAFrance Germany Korea
VHTR
Information exchange and technology cooperation on HTGR based on memorandum of
cooperation (2017.5-) and implementing arrangement (2019.8-)
(National Centre for Nuclear Research: NCBJ)
Public Information exchange
(Tsinghua University, Institute of Nuclear and New
Energy Technology: INET)
Public Information exchange
(Badan Tenaga Nuklir Nasional: BATAN)GEMINI+ Project (by 2021.2, under consideration of next project)
Design and R&D of HTGR with heat application
USAFrance KoreaCanada Switzer-land
China EU Australia
Poland
United Kingdom
USA
China
Korea Public Information exchange
(Korea Atomic Energy Institute: KAERI)
Kazakhstan
Indonesia
OECD/NEA
IAEA
Generation IV International Forum (GIF)
EU
UK
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