Latest Nuclear Power Technology Development in China · Latest Nuclear Power Technology Development...
Transcript of Latest Nuclear Power Technology Development in China · Latest Nuclear Power Technology Development...
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Latest Nuclear Power Technology Development in China
- What are the implications for Europe?
May, 2016Ning Li, Ph.D.
Xiamen University, China
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OutlineChina’s Potentially Exportable NPPs
HTGR
Switzerland?
CAP
Bulgaria?Turkey?
HPR
UK?Hungary (Paks)?
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Global NPP Markets & Supply Chains?
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Nuclear Power Plants in China
HONGYANHE
HAIYANG
SHIDAOWAN(HTR)
TIANWAN
QINSHAN (PHASE –I/II/III)
FANGJIASHAN
SANMEN
NINGDE
FUQING
DAYAWAN
LINGAO
YANGJAING
TAISHAN
CHANGJAING
FANGCHENGGANGNPPs in Operation
NPPs under construction
(PHASE –I/II)
30 units, 28.38GW in operation
24 units , 26.6GW under construction
30 units under Preliminary Work PermissionStatistics by Feb.2016
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Indigenous and Introduced Designs
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QinshanCNP300
Qinshan IICNP600
CNP1000CPR1000
CP1000ACPR1000
ACP1000ACPR1000+
Daya BayM310
Ling’ao IM310
TianwanAES-91
TaishanEPR
Sanmen/HaiyangAP1000
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Progress of HTR-PM
As one class of advanced reactors, HTR attracts extensive attention all over the world. Under the support of national “863 plan”, the prototype of HTR-PM have been verified through a 10MW HTR test reactor by Tsinghua University.
1. Progress of HTR-PM
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Key Characteristics of HTR-PM
Inherent SafetyUtilizes TRISO ceramic coated particle element; no off-site shelter or evacuation technically
High generation efficiencyCore outlet temperature up to 750℃,42% generating efficiency for Ranking cycle, direct cycle will deliver 45-50%
Small module designFlexibility with small module design(250MWt/100MWe) to fit different scale grid
MultipurposeMultiple applications of power generation, hydrogen production, process heat apply, steelmaking, desalination
1. Progress of HTR-PM
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Plant Layout Twin reactor units drive a single turbine, and the generating efficiency reaches
42%, and the expected capacity factor will be no less than 80%.
Twin reactor units driving a single turbine
Turbine Bldg
Spent fuel Bldg
Reactor Bldg
Auxiliary Bldg
Electric Bldg
1. Progress of HTR-PM
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Huaneng Shandong Shidao Bay Site
HTR-PM
CAP1400Demonstration Project
PWR Expansion Project
1. Progress of HTR-PM
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Major Milestones
20122004.3 2006.9 2009.9 2011.3 2012.12
Cooperation agreements signed
Listed in national key S&T Special Projects
Construction started
Approved by the State Council
Assessment of PSAR completed
1. Progress of HTR-PM
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Project Schedule and Progress
For the first unit, estimated construction schedule is 59 months
1. Progress of HTR-PM
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Experimental Verification and Design in Close-Out Phase
CRDM test completed in Feb, 2015
Fuel elements radiation sample
Helium blower test completed in Nov 2014
Fuel handling system completed at the end of 2015
1. Progress of HTR-PM
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Construction Site in 2014
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1. Progress of HTR-PM
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Construction Site in 2015
HTR-PM full view
1. Progress of HTR-PM
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Production Preparation and Fuel Element Fabrication
Maintenance staff practicing at Tianwan NPP
Fuel plant start-up completed
Operation staff training at Catawba NPP
Fuel plant
Procedures
1. Progress of HTR-PM
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Commercial Deployment Planned
600MW HTR-PM layout
Sketch of CHNG Fujian Xiapu site
1. Progress of HTR-PM
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2010.6
Conceptual Design finished
2011.12
Basic Design finished
2014.9
PSAR reviewFinished
2016.04
FCD estimated
2007
Proposal prepared
2014.10
Key tests before FCD completed
2.1 1st CAP1400 -- Key Milestones
2. Progress of CAP1400
Currently, the detailed design could support 12 months continuous construction after the First Concrete.
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2.1 1st CAP1400 -- Licensing Status
Scope and depth are unprecedented• 5 aspects review.• Over 5000 questions replied• The review requirements reflected in the detailed design.After the review, NNSA believed the CAP1400 could meet thelatest China and IAEA nuclear safety standards.
Preliminary work approved
2013.03
The two evaluation reports accepted
2013.06
Feasibility study report accepted
2014.07
Licensing Review
2013.04~2014.09
The Site Safety Evaluation Report and the Environmental Impact Evaluation Report
2. Progress of CAP1400
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….
…Located at Shi Dao Wan, Shandong Province.2×CAP1400 unitsNuclear Island sits on rock basement.Dry site design, large margin against external flooding.
山东荣成石岛湾
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2.1 1st CAP1400 – Construction Preparation
2. Progress of CAP1400
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Chinese Advanced Passive PWR
>1400MWe
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CAP1400National key project Own intellectual propertyTo be a global brand
Led by Chinese government (NEA)Performed by SNPTCSupported by with
participation of domestic and international entities
Based on advanced passive philosophy and AP1000Better safety/economy Better environmental
harmony
2. Progress of CAP1400
2.2 General Picture of CAP1400
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CAP1400 0.17 m2/kW
AP1000 ~0.19 m2/kW
GII+ ~0.21 m2/kW
General Layout2.2 General Picture of CAP1400
2. Progress of CAP1400
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Parameters CAP1400Core thermal power, MWt 4040Electric power, MWe ~1500RCS average temp, ℃ 304RCS pressure, MPa(a) 15.5Fuel assemblies 193
Fuel assembly type RFA or Innovated design
Average linear power, W/cm 181SG type SNP140SG outlet pressure, MPa (a) 6.0Steam flow per loop, kg/s 1122Design flow per pump, m3/h 21642DNBR margin >15%
General Parameters
2.2 General Picture of CAP1400
2. Progress of CAP1400
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Basis 1: Experience Over 40 years R&D, manufacture, construction Experience. Over 20 years safe and safe operation of nuclear power plants.
First operating NPP(Qinshan-I)By self-reliance R&D(85-91)
First export NPP(Chashma-I 93-00)
CPR1000(Hongyanhe)
First PHWR(Qinshan Phase III)
First VVER(Tianwan)
2.3 Basis for CAP1400 R&D
2. Progress of CAP1400
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Basis 2: AP1000 technology introduction AP1000 Technology transfer and feedback from 1st AP1000. Cooperation with US company for AP1000 self-reliance project. Development and implementation of CAP1000 technology.
Sanmen 1# Haiyang 1#
Taohuajiang(Hunan)
Xianning(Hubei)
Pengzhe(Jiangxi)
Sanmen #2(Zhejiang)
Haiyang #2(Shandong)
Lufeng(Guangdong)
On job training /Classroom training Design participation/Subcontract Subcontract /Site technical service
Development of CAP1000 CAP1000 Project implementation, Coastal site Inland site
2.3 Basis for CAP1400 R&D
2. Progress of CAP1400
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Basis 3: National mechanism Mechanism and Functions of National Key Science and Technology,
support by national top expert platform. Basis 4: Cooperation Extensive cooperation and joint efforts from domestic and international nuclear
industry, universities and institutes as well as manufacturers.
National Key S&T Project supervision and evaluation report meeting
Westinghouse(US) provides design consultation
L&M (US) participates in PMS development
OSUs (US) participates in test verification
EMD(US) and KSB (Germany) participate in the development of Reactor Coolant PumpGRS (Germany) participates in engineering verificationLaboratories of OECD provide large amounts of test dataCorporate from USA, Canada and Japan participate in equipment material research and test verification
2.3 Basis for CAP1400 R&D
2. Progress of CAP1400
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193 fuel assemblies (advanced 14 feet fuel assemblies), 18 month refuel cycle, with the capability of 50% MOX fuel loading.
High burnup, and low-leakage core pattern minimizes the fast neutron leakage.
MSHIM control strategy, capability of load-follow without adjustment of boron concentration.
2.4 Design Features -- Core and Fuel Assemblies
2. Progress of CAP1400
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Passive Core Cooling System (PXS) Passive Residual Heat Removal Subsystem: PRHR-HX,
IRWST Passive Safety Injection Subsystem: CMT, ACC, IRWST Automatic Depressurization Subsystem: ADS1-3, ADS4
IRWST
CMTACC
ADS1-3
ADS4
2.4 Design Features – Passive Safety Systems
2. Progress of CAP1400
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Passive Containment Cooling System (PCS) Remove the heat through the steel containment wall by water
spraying and natural air circulation. Water source: PCCWST for 72hr, PCCAWST for next 4days.
Water film Cooling Long-term air Cooling Long-term cooling: Removable pump & alternative water source.
Verification TEST: Phenomena verified on PCS Test Facility (CERT Facility)
2.4 Design Features – Passive Safety Systems
2. Progress of CAP1400
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RCP-CANNED PUMP-SBN/HEC
(1) Finger plate (2) Stator Winding Mockup
(4) Punching(3) Pump Shell
Pumpmanufacture
2.4 Design Features – Equipment Design and Manufacture
2. Progress of CAP1400
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(1) Test loop (2) Prototype
(3) Stator (4) RotatorRCP-RUV PUMP-SEC/KSBPump
Manufacture
2.4 Design Features – Equipment Design and Manufacture
2. Progress of CAP1400
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• Both NuPAC (1E) and NuCON (non 1E) are digital system used for NI and CI monitoring.
• To provide protection and control functions, including turbine control and diagnosis.
• Advanced main control room provided with HFE.
Reactor Protection System--NuPAC30
2.4 Design Features – Instrumentation and Control Hardware
2. Progress of CAP1400
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Advantage of ModularizationParallel construction to reduce the construction period, Achieve manufactory quality,Reduce the probability of crowded on-site construction.
CA20-Struc. ModuleCA01-Struc. Module
Nuclear Island Struc. Module Equip. Module TotalReactor Building 65 12 77Auxiliary Building 19 42 61Total 84 54 138
Q601-Equip. Module 31
2.4 Design Features – Modularization Design & Construction
2. Progress of CAP1400
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Steel plate reinforced concrete structure and high compression strength concrete to resist large commercial aircraft crash.
2.4 Design Features – Aircraft Crash Resistance
2. Progress of CAP1400
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All tests before FCD were finished, supporting the design, safety review, and software V&V.
Totally 887 cases performed.
ACME complex CERT facility Facility for FIV testIVR test facility
Facility for hydro-simulation
Facility for SG steam-water separation test
Tests for passive safety systems
• PXS performance test
• PCS performance test
• IVR test
Tests for key equipment
• SG hot-stage performancetest
• Core hydro-simulation test• Reactor internal flow-
induced vibration test
2.5 Verification and Validation – Design Verification Test
2. Progress of CAP1400
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Some key verification tests witnessed by NEA and NNSA.
CERT tests
ACME tests FIV tests
ISCOE tests
IVR tests
2.5 Verification and Validation – Design Verification Test
2. Progress of CAP1400
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The development of CAP1400 is completed, and site preparation of the first CAP1400 has been finished, the construction permit is estimated to be issued in 1st quarter of 2016.
CAP1400 has better safety, economic and environment advantages, which could make CAP1400 one of the preferred solutions for domestic & overseas utilities.
2. Progress of CAP1400
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3. Progress of HPR
Double-Layer Containment Jetliner Impact Resistant
HPR (HuaLong) Design Features
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1.00E-07
1.00E-06
1.00E-05
Gen II+ EPR AP1000 CAP1400 HL-1
1.11E-05
1.80E-06
3.64E-072.41E-07
1.70E-07
Internal Event Core Damage Frequency
3. Progress of HPR
Improving Reactor Safety
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3. Progress of HPR
CNNC’s Plant Design
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3. Progress of HPR
CGN’s Plant Design
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Supply Chain Example: AP1000
MainEquipment
MainMaterials
MainForging
China YizhongJapan Steel
WorksDoosan Heavy
IndustriesChina Erzhong
Shanghai Heavy
Industries
U-tube
China YizhongJapan Steel
WorksDoosan Heavy
IndustriesChina Erzhong
Shanghai Heavy
Industries
WeldMaterials
ESABJapan Kobe
SteelSandvik
US Special Metals
Main Production
FabricationTechniques
Welding Techniques
Doosan Heavy IndustriesChina Yizhong
Harbin Heavy EquipmentShanghai ElectricDongfang Electric
China Erzhong
Diagnosis Techniques
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SummaryChina’s Potentially Exportable NPPs
HTGR
Switzerland?
CAP
Bulgaria?Turkey?
HPR
UK?Hungary (Paks)?
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Global NPP Markets & Supply Chains?
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College of Energy, Xiamen University
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Xiamen University
THANK YOU!