HTR-PM Project Progress
Fu LI
INET, Tsinghua University, [email protected]
VIC, Vienna, AustriaJuly 10-12,2012
IAEA Technical Meeting on Re-evaluation of Maximum Operating Temperatures and Accident Conditions for High
Temperature Reactor Fuel and Structural Materials
1 Background
National requirement Energy supply-amount and security
2500GWe in 2050 total 16% for nuclear?
Greenhouse gas emission Roles of NPP Roles of HTR
Current NPPs Impact from Fukushima accident
3
Roles of NPP
For the national energy supply security
For the structure improvement of energy supply
For the promotion of industry technology progress
4
Roles of HTR
Supplement for the LWR For the process heat application For the technology innovation
5
Nuclear power plants in China
Currently, 15 NPP units are under operation, 26 units are under construction,
Plus 3 units ready for construction More units are under planning
But central government are reevaluating the situation, after Fukushima accident
6
Operating units
No Plant name Type/ num of units Power(MWe)
1 Zhejiang Qinshan I CNP300/1 3102 Guangdong Daya bay M310/2 983.82
3 Zhejiang Qinshan II CNP600/2 6502
4 Guangdong Lin’ao PWR/2 9902
5 Zhejiang Qinshan III CANDU6/2 7282
6 Tianwan VVER/2 106027 Zhejiang Qinshan II ext. CNP600/2 65028 Guangdong Lin’ao II CPR1000/2 10802
Total 8 15 12593.6
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Units under construction
No Plant Name Type/Num of units power(MWe)
1 Zhejiang Fangjiashan CNP1000/2 110022 Hainan Changjiang CNP600/2 65023 Fujian Fuqing M310+/3 110034 Guangdong Taishan EPR/2 175025 Guangxi Fangchenggang CPR1000/2 108026 Guangdong Yangjiang CPR1000/3 108037 Fujian Ningde CPR1000/4 108048 Shangdong Haiyang AP1000/2 125029 Zhejiang Sanmen AP1000/2 1250210 Liaoning Hongyanhe CPR1000/4 10804
Total 10 26 29340
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Government NPP plan Version of 2006
To 2020, installed NPP capacity will reach 40GWe
To 2020, capacity for NPP under construction will maintain 18GWe
Current government consideration after Fukushima accident More cautious than before, affected by
international trend Not determined yet
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Government decision after Fukushima accident
1) Immediate safety evaluation for all nuclearfacilities
2) Enhance the safety regulation foroperating NPPs
3) Thorough assessment of all NPP underconstruction, according to the advancedguidelines
4) Freeze new NPP projects, until newnuclear safety planning is approved by thecentral government
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Progress after Fukushima accident
Safety assessment on NPP wasfinished Some new measures are adopted
New safety planning are open to public Public feedback are completed in this
June Practically eliminate the need for off-site
emergency response New nuclear development plan is
under discussion12
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2 Development team INET
Technical development, NSSS design Experiment
Chinergy Engineering design, EPC contractor
Shidaowan Utility
Supported by manufactures, construction companies, research institutes
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INET roles in HTR-PM project Responsible for design of Nuclear
Steam Supply System (NSSS) Responsible for safety analysis BOP: Chinergy, Turbine plant: SNPC
Responsible for test of key components
Responsible for fuel fabrication technology
Responsible for HTR technology development
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3 HTR-PM project Project was initiated in 2001 Technical design was fixed in 2006 Project was approved by government
in 2008 Including the research, experiment
Government funding available from 2009
Key Component was procured in 2008 CP licensing was finished in 2009
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3 HTR-PM project The design, manufacture, construction and
operation of the demonstration plant V&V of design and components in HTR-PM,
through experiment Including the operation of HTR-10
Development of framework of the regulation and norms for commercial HTR
The development and establishment the fuel element production lines Including fuel qualification test
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Main design parametersReactor module numbers 2Thermal power/module 250MWLifetime 40aCore diameter/height 3.0/11mPrimary system pressure 7.0 MPaHelium inlet/outlet temperature 250/750℃Helium mass flow 96 kg/sFresh steam temperature/pressure
566℃/13.2 MPa
Electric power 210 MW
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4 Experiments The development of the technology
for the key components manufacturing Steam generator Pressure vessel
The full scale test of key components Steam generator Control rod Small absorber ball system Fuel handling system Helium blower
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4 Experiments Safety related experiments
Pebble flow Graphite corrosion Pebble bed equivalent conductivity
coefficients …
Infrastructure 10MW Helium loop Laboratory Power supply
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4 Experiments Operation experience feedback from
HTR-10 Experience for existing components V&V on computer code
Technology for future Hydrogen production Gas turbine …
4 Experiments helical once-through steam generator fuel handling system small absorber ball shutdown system digitalized protection system control rod driven mechanism spherical fuel element fabrication, irradiation test helium purification and helium sealing
Preconditions: Helium test loop Big laboratory
5 Fuel development
Production line for mass production is ready
Irradiation samples are produced Will be irradiated in Petten HFR soon
Design of fuel plant is finished Duplication of same line in INET Construction will follow after the HTR-PM
demonstration plant
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6 HTR-10 Finished:
I&C modernization Optimization of helium purification
system In-service inspection of RPV
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6 HTR-10 Under plan:
Long term operation
Fuel temperature measurement Fission product release Increase the operating parameters Safety experiments
New proposals are welcomed
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