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.

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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.

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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