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Development of Modular HTGR
and Other Advanced Reactor
Technologies in China
SUN Yuliang, ZHANG Zuoyi
Institute of Nuclear and New Energy Technology
Tsinghua University, Beijing, China
PBNC-2014, Vancouver, August 2014
Presentation Outline
� Introduction
� Building a modular HTGR test reactor
� Building a modular HTGR demonstration plant
� Development of other advanced reactors
Introduction
� Besides a vigorous commercial NPP construction
program, China also has active development programs
of advanced reactor technologies
� The development programs of advanced reactor
technologies include VHTR, SFR, SCWR, MSR, LFR, technologies include , SFR, SCWR, MSR, LFR,
and light water SMR technologies
� China has been actively participating in international
cooperation frameworks: GIF, IAEA-INPRO, bilateral
Introduction
� VHTR technology
� Helium as coolant
� Graphite as neutron moderator and core structure material
� Coated particle ceramic fuel� Coated particle ceramic fuel
� High temperature capability
� high efficiency power generation
� process heat application
� More robust inherent safety features
� Flexibility in plant output capacity by modular construction
Worldwide HTGR Development
THTR(FRG)
1986 - 1989
FORT ST. VRAIN(U.S.A.)
1976 - 1989
PEACH BOTTOM 1(U.S.A.)
1967 - 1974
AVR(FRG)
1967 - 1988
DRAGON(U.K.)
1963 - 76
EXPERIMENTAL REACTORS DEMONSTRATION OFBASIC HTGR TECHNOLOGY
LARGE HTGR PLANTS up to 1000MWe
Modular HTGR
5
HTR-10 HTTR
EXPERIMENTAL MODULAR REACTORS
Industrial
Demonstration
HTR-PM
NGNP
VHTR
R&D
GIF
Modular HTGR
Self Shut-downSelf Cool-down
� HTR-10: 10 MWt High Temperature Gas-cooled test Reactor
� 1986: became one of the key projects in the “National High Technology Program”
� 1992: government approved to construct HTR-10
� 1995: started to construct HTR-10 in INET, Tsinghua University, Beijing
� 2000: HTR-10 reached first criticality
Building a Modular HTGR Test Reactor
� 2000: HTR-10 reached first criticality
� 2003: HTR-10 operated in full power
HTR-10 in 1995 HTR-10 in 1997 HTR-10 in 2000
The HTR-10 Test Reactor
He BlowerControl Rods
Reactor Power MWth
10
He Pressure MPa 3
℃
Reactor
Heat Exchanger
Connecting Vessel
Reactor Inlet
Temp., ℃250
Reactor Outlet
Temp., ℃700
Number of Fuel Elements
27000
Key Achievement through HTR-10
� Plant technology
� Fuel technology
� Safety demonstration
� Experience and capacity
ATWS, Loss of Cooling
� Experience and capacity building
� Research and Development
� Engineering
� Equipment manufacturing
� Commissioning and operation
� Licensing
ATWS, Control Rod Withdrawal
� It is logic and strategic to build an industrial
demonstration plant as the follow-up innovation step
after the success of the HTR-10 test reactor.
� A 200MWe modular pebble bed HTGR
demonstration project (HTR-PM) has been initiated
HTR-PM
10
demonstration project (HTR-PM) has been initiated
and under implementation since 2004. HTR-PM: the
HTR-Pebble-bed Module.
� Since 2006, the project has become one of the
national key projects within the 2020 National
Science & Technologies Development Program of
China.
Government
HSNPCChinergy Co.
HTR-PM Project Organization
HSNPC
Owner of HTR-PM
Demonstration Plant
Established in 2006
� HUANENG Co.
� CNEC
� TSINGHUA HOLDING
Chinergy Co.
Contractor of Nuclear
Island
Established in 2003
� TSINGHUA HOLDING
� CNEC
� CGNPC
INET
R&D, general design,
engineering of key
systems and components
in Nuclear Island
Plant electrical power, MWe 211
Core thermal power, MW 250
Number of NSSS Modules 2
Core diameter, m 3
Core height, m 11
HTR-PM Plant Design
Core height, m 11
Primary helium pressure, MPa 7
Core outlet temperature, ℃℃℃℃ 750
Core inlet temperature, ℃℃℃℃ 250
Fuel enrichment, % 8.6
Steam pressure, MPa 13.25
Steam temperature, ℃℃℃℃ 567
� 2003: Project proposal, Chinergy established
� 2004: Investment agreement reached
� 2006: Concept design fixed
� 2006: Approved as National Key Project
� 2007: Owner company established
� 2008: Feasibility study approved
� 2008: Basic design finished and reviewed
HTR-PM Project Progress and Status
� 2008: Basic design finished and reviewed
� 2009: CP safety review finished
� 2012: First concrete
� Now underway:
� Detailed design
� Design verification testing
� Equipment manufacturing
� Plant construction
� Fuel qualification
� Schedule target: end of 2017
� Sodium cooled fast reactor
� CEFR (65MW) achieved initial criticality on 2011-07-21� Industrial scale fast reactor plant under development
Other Advanced Reactor Technologies under Development
CEFR: China Experimental Fast Reactor
� Super critical water reactor
� Road-mapping until 2025 to finish a 1000MW NPP standard design
� Design methodologies and code development
Other Advanced Reactor Technologies under Development
� Design methodologies and code development
� Key technology research and development, such as fuel assembly, materials, flow distribution, sealing, ……
� Thermo-hydraulic experiments
� Plant concept studies and design
Other Advanced Reactor Technologies under Development
� Small, modular water cooled reactor technology, power rating 100-150MWe
� Thorium based molten salt reactor
� Lead cooled fast reactor
� Status:
� Design methodology and code development
� Concept studies
� Technology development
� Experimental loops
Conclusion Remarks
� China has a number of advanced reactor
development programs to prepare for the future of
nuclear energy utilization.
� HTGR development is in an more advanced position.
� HTR-10 test reactor project has been successful.� HTR-10 test reactor project has been successful.
� HTR-PM demonstration plant project is under
successful implementation.
� Modular HTGR technology is an advanced (next
generation) nuclear power technology, suitable for
high efficiency power generation with flexible plant
capacities, and process heat applications.