Date post: | 10-Nov-2015 |
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China mainly develop the following types of SMR
CNP
CANDU Reactor
High Temperature Reactor (HTR)
Low Temperature Heating Reactor (LTHR)
Fast Neutron Reactor (FNR)
CNP CNP in Qinshan Nuclear Power Plant
Project Capacity
Phase 310MW
Phase 2650MW
AfterQinshanPhase, China stopped building more CNP for many years.
Reason:NotEconomical
CNP CNP in Changjiang Nuclear Power Plant (Under Construction)
Project Capacity
Phase I 2650MWPhase
(under planning) 2650MW
Reason for Choosing CNP:
The Limit of Local Grid
Conclusion:
SMRs,suchasCNPstillhavemarketprospectinsomeareas.
Back
CANDU Reactor CNP in Qinshan Nuclear Power Plant
Project Capacity
Phase 2700MW
AfterQinshanPhase, no more CANDU reactor has been build in China ever since.
Reason:
ChinahasdecidedtomainlybuildPWRsfornewnuclearplants.
Back
HTR
TsinghuaUniversitystartedresearchingonHighTemperatureGasCoolingReactorin1980s.
TheexperimentalHTGRwentcriticalin2000andcombinedtothegridin2003.
HTR,featuringinherentsafety,hasbeenregardedastheleadingreactortypeofthefourthgenerationnuclearreactor.
ChinaHuanengGrouphasstartedthedemonstrationprojectofHTGR(200MW)inShidaoBay,ShandongProvince.
Timelimitis50moths:18monthsforconstruction18monthsforinstallation14monthsforprecommission
ThehightemperaturesteamproducedbyHTGRcanbeusedinnumerousindustrialareassuchas:
Theheliumgasoutofthereactorcanreach750 high.Basedonthat,Producehydrogeninlargescalebynuclearenergycanbemakepossible.
OilRefining ChemicalIndustry HeavyOilRecovery
Parameter Unit ValueCapacity of the Power Plant MWe 211
The Number of Reactors // 2
The Thermal Output of Each Reactor MW 250
The operating pressure of Helium Gas in Primary Loop MPa 7.0
The Average Temperature of Helium Gas in Reactor Core/Outlet 750/250
The Diameter/Height of Active Zone m 3/11
The Enrichment of New Fuel Pellets % 8.9
The Mess of Heavy Metals in Each Fuel Pellet g 7.0
The Average Power Density of Reactor Core MW/m3 3.22
The Maximum Power Density of Reactor Core MW/m3 6.57
The Total Number of Fuel Cartridges in Reactor Core 10000/Each Reactor 42
The Cycle Index of Fuel // 15
The Average Number of Fuel Cartridges put in Reactor Each Day // 400
TheMainTechnicalParametersofHTGR
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LTHR Tsinghua University built a 5MW experimental nuclear heating reactor In November 1989.
1 Radioactive Shield2 Containment Vessel3 Pressure Vessel4 Main Heat Exchanger5 Control Rod6 Reactor Core
Features:
DoubleHullStructure IntergradedDesigned AutomaticVoltageSystem
Parameter Unit Value
mal Output of Each Reactor MWt 200
rating Pressure of Coolant MPa 2.5
ture of Reactor Core Inlet/Outlet 210/140
and Height of Active Zone mm 1900/1940
chment of the Fuel Newly Put in the Reactor % 3.0
Linear Rating of Fuel Rod W/cm 80
l Number of Fuel Assemblies Box 96
mber of Control Rod // 32
Main Technical Parameters of 200MW Demonstration HTGR
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FNR
e China Experiment FNR began construction in May 2000 and mbined to the grid in July 2011.
he reactor is three-loop (natrium- natrium-water) designed with liquid atrium as coolant.
The advantage of safety, modularization, and high compatibility with girds
Promising market in China
Problems waiting to be solved
The necessity of further development technology of SMR and improving nuclear power safety through international cooperation