latest nuclear power technology development in china · latest nuclear power technology development...

Latest Nuclear Power Technology Development in China

- What are the implications for Europe?

May, 2016Ning Li, Ph.D.

Xiamen University, China

OutlineChina’s Potentially Exportable NPPs

HTGR

Switzerland?

CAP

Bulgaria?Turkey?

HPR

UK?Hungary (Paks)?

2

Global NPP Markets & Supply Chains?

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

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


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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


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Huaneng Shandong Shidao Bay Site

HTR-PM

CAP1400Demonstration Project

PWR Expansion Project


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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


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Project Schedule and Progress

For the first unit, estimated construction schedule is 59 months


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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


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Construction Site in 2014

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Construction Site in 2015

HTR-PM full view


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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


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Commercial Deployment Planned

600MW HTR-PM layout

Sketch of CHNG Fujian Xiapu site


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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.

1 2 3 4 5 6

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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


….

…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


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


2.2 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


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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


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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


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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



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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



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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


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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


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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


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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


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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


• 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


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


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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


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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


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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


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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.


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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

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)?

41

Global NPP Markets & Supply Chains?

College of Energy, Xiamen University

42

Xiamen University

THANK YOU!

latest nuclear power technology development in china · latest nuclear power technology development...

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