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HTR Development progress in China
Prof. Dr. Yujie Dong
Deputy Director, INET/Tsinghua University Beijing, China
25 February 2015
IAEA Meeting of the Technical Working Group on Gas Cooled Reactors (TWG-GCR)
25-27 February 2015, VIC, Vienna, Austria
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Contents
HTR-PM: High Temperature gas-cooled Reactor Pebble-bed Module
Design and Licensing
Test of components and systems
Construction of demonstration plant
Fuel
Future of HTR Development
Design - technical goals
HTR-PM project objectives
Completing 200 MWe HTR-PM demonstration plant, and providing sound foundation for the further development of Generation IV nuclear system.
HTR-PM technical objectives
Demonstration of inherent safety features
Demonstration of cost competitiveness
Standardization and modularization
Confirmation of proven technologies3
Design - philosophy
Mature technology
Steam cycle, based on HTR-10
Pebble bed, single zone
Full scale test of key components/systems
Safety features
Inherent safety, modular design
Passive cavity cooling system
Commercial scale
2 NSSS modules with 1 steam turbine
Worldwide procurement
Mostly domestic manufacturing, because of first of a kind
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Reactor building
HTR-PM plant buildingCross section 3D-view
Control building
Auxiliary building
Spent fuel storage building
Steam turbine building
Reactor & SG 2 X 250 MW Fuel enrich. 8.5%
Primary helium 250/750ºC, 7 MPa
Avg. burn- up
90 MWd/tU
Plant life-time 40 a Main steam 567 ºC/13.25 MPa
Final technical solution in 2006
Overview of HTR-PM Design
Reactivity control
Licensing - safety criteria
Quantitative Safety Goal
Possibility with accident consequence at site boundary exceeding 50mSv less than 10-6 per reactor year
Achievable
Practically exclude the need for off-site emergency plan
Meet the newest safety requirement
Safety re-assessment after Fukushima accident
All requirements were met for HTR-PM, safety advantages of HTR-PM are obvious
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Licensing - process
Early involvement
Design criteria, review guideline
Review of PSAR
1.5 years, more than 100 reviewers,
Dialogue, question sheet, answer sheet
3 dialogue meetings, 8 topics reports and review meetings, more than 2000 worksheets
Supporting reports
Safety expert committee, for PSER
Test - facilities
Engineering Laboratory
Started construction in 2009 and finished in 2010
The laboratory overview The facility is ready for test
Large-scale helium loop power:10 MW tempt.:750 ℃ pressure:7 MPa coolant:helium
Full scale, under HTR-PM helium conditionssteam generator, one of the 19 unitshelium circulator fuel handling systemcontrol rods driving systemsmall absorber balls reserve shutdown systemhelium purification systemreactor protection system and control room
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Circulator design
Vertical layout
Driven by high speed, frequency control electrical motor
Single stage, centrifugal impeller
Active magnetic bearing (AMB),
no shaft penetration of vessel, no lubrication
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Parameter Unit ValuePressure rise kPa 200Temp. of helium ℃ 250Rotation speed rpm 4,000Electrical power kW 4,500
Circulator
Proto 1: full scale motor with oil lubrication bearing,
Proto 2: motor with domestic magnetic bearing,
Proto 3: full scale helium circulator with domestic bearing, hot state 500 hours in nitrogen, and is being tested in hot helium condition
Proto 4: full scale motor with the magnetic bearing of the final product, to test the catch-down capability.
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Steam Generator
Vertical, counter flow, once- through type, helical tubes for efficient and compact heat transfer
Middle size, multi-layer helical tube assemblies
In-service inspection (ISI) feasible
Flow distribution, testable
Mass production
Manufactured in China
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Parameter Unit ValuePower MW 253
No. of Units 19No. of tubes per unit 35Total No. of Tubes 665
Design
Helical tubeassemblies
Outlet tubes
Inlet tubes
Prototype
Test of SG
The Helium Technology facility provides heat source for testing a full-scale unit constructed
Electrical heating
10MWth,
7.0MPa, 750℃, helium
The dedicated secondary loop and tertiary loop constructed
Reactivity control systems
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Barrel
Rods
SAS
Graphite
Carbon
Two independent systems: rods plus small absorber spheres (SAS), located in side reflector
Primary: rods, 24, motor driven
Play a dominant role as the actuators of reactor control and protection system
startup, power operation, power regulation, normal shutdown and scram can be accomplished
Secondary: SAS, 6 , falling by gravity, pneumatic conveyance
backup shutdown system
A full scale engineering CRDM prototype has been tested in a step-by-step method
In 2012, cold tests
In 2014, hot tests
Recently, seismic tests
All tests have been witnessed by NNSA
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CRDM
DM
Rod
Channel
Chain
Rod
SAS
Individual tests:
Conceptual prototype of drive mechanism verified, including solid lubrication, bearings, level indicator.
Samples of small absorber sphere produced
Feeder of sphere and pneumatic conveyance system verified
A full scale engineering prototype is being tested in hot conditions.
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MM
Feeder
DM
Tank
Channel
SAS
Fuel Handling System
Functions:
Charge and discharge fuel elements on line
Separating out the broken fuel elements
Measure burn-up of fuel element and screening out spent fuel
Transfer spent fuel elements to storage tank
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Test facilities
TF-FHS
Tests of individual components, parts: finished
TF-FHS: verification of the fuel movement, finished
ETF-FHS: Full scale verification of fuel handling system, in progress
HTR-PM project locationShidao Bay, Rongcheng City, Shandong
Province, China.
Progress of HTR-PM project
HTR 2014
EngineeringCompleting the primary design and PSAR evaluation. Working drawings is nearly finished. FSAR will be submitted this year.
Progress of HTR-PM project
Procurement
Pressure vessel, metal internals, carbon and graphite internals, control rod drive mechanism, second small absorber ball system, fuel handling system, etc.
Nuclear fuel, primary helium circulator and steam generator are the main challenges.
Progress of HTR-PM project
Reactor Pressure Vessels, will be delivered this year.
The key difficulty which was overcome is the 460 tons forge。
(Top head)(Bottom vessel I)
(Bottom head & bottom vessel II)
Pressure vessel
Progress of HTR-PM project
(Steam Generator Tube)
(Hot Gas Duct Nozzle Flange)
(SG Vessel Magnetic Particle Testing)
Steam generator vessel
Progress of HTR-PM project
-15~-11m wall Aug. , 2013,-11m floor Nov. , 2013,-5m floor
Mar. , 2014,0m floor Aug. , 2014,+7.5 wall
ConstructionCivil Engineering: December 9, 2012 first concrete poured
Progress of HTR-PM project
Loop Loop embededembeded partpart Waste Waste
storage tankstorage tanknegative negative pressure pressure
ventilation ventilation shieldshield
Steam generator Steam generator accident dischargeaccident discharge
tanktank
manholemanhole((--8m 8m belowbelow))
Main Main feedwaterfeedwater
Penetration Penetration assemblyassembly
Construction-Installation
Progress of HTR-PM project
Fuel fabrication
In 2010, INET demo production facility, 100k/a, finished the first production
In the end of 2014, irradiation test of fuels, Petten, Netherlands, finished, results are good
Commercial fuel plant, 300k/a, finished equipments installation, to start production in 2015
Multi-module plant: HTR-PM600 as commercial plants for next deployment
6 reactor modules (250MWt, 250/750℃, 7.0MPa each) connecting to 1 steam turbine (13.25Mpa, 566 ℃), provide a 650 MWe nuclear plant.
Co-generation of electricity and steam.
Nearly the same site footprint of PWR plants.
Rough estimation of capital costs shows that such plant has promising economic competition for sites with special requirements.
Hydrogen production
Iodine-Sulfur cycle
Full technological process, closed, continuous test, finished: 86h(60h for hydrogen production), 60L/h
High temperature electrolysis
More than 100h (60h for continuous steady hydrogen production, 105L/h
Concluding Remarks
Key components and technologies have been/are being tested and verified. The remain full scale demonstration tests will be finished in this year.
The key components will be shipped to the site in succession from this year.
Fuel irradiation test and the equipment installation of the fuel fabrication plant has been finished.
The target to connect grid is 2017.
The conceptual design of the commercial 600 MWe unit has been finished.
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