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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

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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

From test reactor to

industrial demonstration

The HTR-PM Project

� 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

HTR-PM Plant 3D Model

13

� 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

Beijing

HTR-PM Project Progress and Status

� 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.