smr in china -tong - nucleus

Second Meeting of the Technical Working Group forSmall and Medium‐sized of Modular Reactor (TWG‐SMR)

08‐11 July 201908‐11 July, 2019IAEA Headquarters, Vienna International Centre

SMR Design, Technology Development S es g , ec o ogy e e op e tand Construction Status in China

Prof. Jiejuan TONGInstitute of Nuclear and New Energy Technology (INET)

Tsinghua University, Beijing, China

OutlineOutline

SMR programs in China

Non-PWR fleet Non-PWR fleet

PWR fleet

2

SMR PROGRAMS IN CHINASMR PROGRAMS IN CHINA

Non-PWR fleet INET INET

HTR-PM, HTR-PM600

CNNC CNNCFast Reactor Demonstration Project

CAS CASThorium-based Molten Salt Reactor

3

SMR PROGRAMS IN CHINASMR PROGRAMS IN CHINA

PWR fleet CNNC CNNC

ACP25S, ACP-100, ACP-100S, DHR400…

CGN CGNACPR50S, ACPR100

INETNHR200-II

SPICHAPPY200, LandStar, OcearStar

4

S~~Offshore floatingHR~~ heating

HTR-PM, HTR-PM600

SMR PROGRAMS (1)

5

HTGR Roadmap in ChinaHTGR Roadmap in China

Test reactor Demonstration plantCommercial plant

B i h

1970s 1986, HTR-10 2001, HTR-PM 2014~, HTR-PM600Basic research

6

HTGR Roadmap in ChinaHTGR Roadmap in China

Key feature of HTGR: extend the application of nuclear energy to process heat, a similar market volume to nuclear power

HTGR Roles in China

Hydrogen production as next step

Supplement to LWR for power

as next step

generation Co-generation to supply steam

7

Water desalination District heating Oil recovery Petroleum refinery Coal liquefaction

HTR-PM• 2004 Investment Agreement Signed

1 Module = 1 reactor + 1 SG

• 2004 Investment Agreement Signed• 2006 Accepted by the National Science & Technology Important

Project Program 2008 D j G l D i A d• 2008 Demo-project General Design Approved

• 2012.12 First Concrete Deployment• 2019 All major components installed, commissioning j p , g• 2020 Will connect to the grid

ValueValue

Power, MWth 2x250Power, MWe 211Primary Pressure, MPa 7Helium Temperature, oC 750

8

Main Steam Temperature, oC 566

Number of Fuel balls 420,000

HTR-PM

Civil Work of Nuclear Island Production line of Fuel Element, 360,000 Elements have been produced

(as of 2017)

Reactor Vessels Installed

( )

Metallic Internal Water cooled Wall DCS Full scope simulator

9

Metallic Internal，Water-cooled Wall，DCS，Full scope simulator，。。。

HTR-PM Engineering Verification Tests

First of the kind

Engineering Verification Tests

Fuel Element Steam Generator Main Helium Blower Fuel Loading /Unloading System

• Control Rods Driven Mechanism• Spent fuel Storage System• Absorption Balls Shutdown System

10

• Helium Purification System• …

HTR-PMIrradiation Test of Fuel element Irradiation Test of Fuel element PETTEN HFR 2012 9 8 2014 12 30 2012.9.8-2014.12.30

Best records in the world up to now 5 elements, ~60,000 coated particles, 0 failure observed

11

General Design of HTR PM600General Design of HTR-PM600

Following HTR-PM: commercialization based on HTR-PM experiences

HTR-PM HTR-PM600Engineering verification tests

Design

Manufacture

Construction

Commissioning

Licensing

Project managementProject management

12

General Design of HTR PM600

Objectives of HTR PM600

General Design of HTR-PM600

Objectives of HTR-PM600

Inherent safety

Proven technologygy

Standardized plant

C tiCogeneration

Economic competitiveness

13

General Design of HTR PM600General Design of HTR-PM600

Potential markets

Small to medium size Cogeneration Overseas marketsSmall to medium size power generation

Cogeneration Overseas markets

• Displacement of coal-fired plant

• Electricity• District heating

Maturity• Designp

• Supplement to LWRConstrained sitingLack of water

ResidentialCommercial

• Process steam

• Supply chain• Project management• Licensing

Limited grid capacity Industrial

14

General Design of HTR PM600General Design of HTR-PM600The same site footprint and the same The same site footprint and the same reactor plant volume comparing with PWRs of the same sizePWRs of the same size.

HTR PM600 Feasibility StudyHTR-PM600 Feasibility Study

Sanmen,Zhejiang

Ruijin, Jiangxi

Xiapu, FujianW ’ F jiWan’an Fujian

Bai’an, Guangdong

Way to reduce the costWay to reduce the cost

200MWe200MWeHTR-PMDemo Plant

1×200MWe to 2×600MWe Plant

Eliminate 1st

of its kind costs CommercializedCommercialized

plants

S f HTGR d l t i ChiSummary of HTGR development in China

HTR PM pebble bed modular HTGR inherent HTR-PM, pebble-bed modular HTGR, inherent safety, steam turbine, electricity generationK t t t d Key components tested

Most components installed, commissioning underway

Fuel factory, production capacity achievedy, p p y Next, 6-module unit (HTR-PM600), replacing

coal-fired plant co-generationcoal fired plant, co generation

18

Fast Reactor Demonstration ProjectFast Reactor Demonstration Project

SMR PROGRAMS IN CHINA(2)

19

Xi F t R t D t ti P j tXiapu Fast Reactor Demonstration Project

CFR 600 600MW CFR-600 600MW 2017-12-29 FCD Be completed in 2025

20

ACP100


21

ACP100 ProgressACP100 Progress

2016.12，Submit the application of the Hainan site;

2017 7 Submit Feasibility Study Report and Environmental 2017.7，Submit Feasibility Study Report and Environmental

Impact Report;

2017.10，Review of the Feasibility Study Report;

2018.1， Complete Preliminary Design

i i i f h l 2019.5, Optimization of the layout

22

ACP100 featuresACP100 featuresReactor type PWR

Thermal power 385MWtElectrical power 125MWeDesign life 60 yearsDesign life 60 yearsFuel cycle 24 monthsCoolant average temperature

303℃p

Operation pressure 15.0MPa（a）Fuel assembly type CF3S shortened

assemblyFuel assembly number 57Fuel enrichment ≤4.95%Steam generator type OTSGg ypSteam pressure 4.5MPa（a）Steam temperature ＞290℃CDF ﹤﹤11××1010--66

23

CDF ﹤﹤11××1010

ACP100 featuresACP100 features Compact layout of Primary systems small Compact layout of Primary systems, small

size primary pipe (5~8cm) 4 main pumps (canned) , 16 OTSG, 1 PZRa pu ps (ca ed) , 6 O SG,

Passive residual heat removal system Passive core cooling systemPassive core cooling system Passive cavity cooling system Passive containment heat removal system Passive containment heat removal system Reactor and spent fuel pool are laid lower

than the ground level for better protection g pagainst external events and release containing.

24

E P d i lifi tiEmergency Preparedness simplification

EAB 300m ＜500m EAB 300m ＜500m LPZ 800m ＜ 5Km EPZ EPZ Evacuation 500m ＜5Km Sheltering 900m ＜10Km Sheltering 900m ＜10Km

EPZEPZLPZLPZ EPZEPZ

ACP100ACP100ACP100ACP100

25

ACP100ACP100ACP100ACP100

NHR200 II250m厂区

（非居住区）

NHR200-II


26

NHR Roadmap in ChinaNHR Roadmap in ChinaNHR200-II

Pool type NHR t t

NHR200-INHR200-II

Verification tests

NHR test reactor

1st reactor

Vessel type NHR test reactor

Regulatory reviewed, Construction

NHR200-II

Design completed

completedDemonstration project being

t1st reactor designed by Chinese

(NHR-5) permit approved

completed setup

2016

Chinese

1964 19891996 2006

27

1964

NHR200 IINHR200-II

201℃ sat rated steam 201℃ saturated steam Purposep

Heating, industrial steam supply, steam/water cogeneration, heat-steam/water cogeneration, heatelectricity cogeneration, sea water desalinationdesalination

28

NHR200 featuresNHR200 featuresCompletely integrated, without primary pipeCo p ete y teg ated, t out p a y p peFull scope natural circulation，without main pumpSelf stabilization of pressure by Nitrogen and Steam

In-vessel hydraulic type control rod driven mechanism (INET property)

Main heat exchanger

Double layer Pressure Vessel

Reactor core Large LOCAControl Rod ejectionMain pump failureVessel rupture……

29Core remains covering under all the DBA and important BDBAs

NHR200 featuresNHR200 features

Passi e safet Passive safety Passive residual heat removal Passive boron injection

30

NHR200 featuresNHR200 features

M ltiple la ers of isolation Multiple layers of isolation 3 loops, Pintermediate >Pprimary

31

NHR TestsNHR Tests

NHR 5 ATWS test NHR-5 ATWS test

32

NHR TestsNHR Tests

More than 50 tests More than 50 tests

33

Industrialization ActivityIndustrialization Activity 2014 11 CGN initialized Hebei Heat Electricity 2014.11 CGN initialized Hebei Heat-Electricity

Cogeneration Program with NHR200-II as

the reactor design

2015 4 CGN INET and CHINERGY signed the 2015.4 CGN, INET and CHINERGY signed the

agreement

2016.5 Project Proposal submitted

2016.12 PSAR rev1 2016.12 PSAR rev1

2017.5 Project Feasibility Analysis Report

completed34

Recent progress of NHR II projectsRecent progress of NHR-II projects

D t ti j t i Demonstration project in Hebei Province Investor: CGN Investor: CGN Alleviating the escalating air

pollution in north China District heating: ~130℃ hot

water Industrial steam: board Industrial steam: board

processing

Recent progress of NHR II projectsRecent progress of NHR-II projects Demonstration project Demonstration project

May, 2016, Project Proposal submittedJan 2018 Feasibility study permitted by National Jan, 2018, Feasibility study permitted by National Energy Administration

Recent progress of NHR II projectsRecent progress of NHR-II projects Demonstration projectp j

Nov, 2018, Most investigation and research work for feasibility study completed

Now, In the reviewing process, by NNSA Environmental impact report(plant siting phase) Plant site safety analysis report

Recent progress of NHR II projectsRecent progress of NHR-II projects Clean energy project in Guizhou Southwest China Clean energy project in Guizhou, Southwest China

Investor: CGN Manganese ore processinga ga ese o e p ocess g ~¥175/ton, economically acceptable 2018.9 Prefeasibility study completed 2018.11 Project Proposal submitted

DHR400SMR PROGRAMS IN CHINA (5)

39

Origin of DHR400

Developed by CNNC D l L t t H ti R t (DHR Y Deep-pool Low-temperature Heating Reactor (DHR, Yan

Long，燕龙) on the basis of a pool type research reactor.

The prototype of DHR(Yan Long) is the swimming poolreactor (SPR IAE) located at CIAE of CNNC.reactor (SPR IAE) located at CIAE of CNNC.

40

Developing Ideas

SPR IAE DHR

Scaling-up & optimizing

• Cooling tower Heat supplyHeat discharge mode

• Several MW

• One month

Hundreds of MW

Over one year

Power

Refueling cycleOne month

• 40℃

Over one year

~100℃

Refueling cycle

Core outlet TEMP

• Relay on manual operation

Highly automatedControl

41

Plant layoutPlant layout

Auxiliary buildingCooling towerDiesel generatorReactor building

Desalted water workshop

42

DHR Schematic

The reactor core isplaced in the bottomof an atmospheric-pressure pool

A proper core outletTEMP is achieved byincreasing the staticpressure of the waterlayer

Schematic view of DHRSchematic view of DHR

General ParametersItem Parameter Item Parameter

thermal power /MW 400 enrichment of equilibrium refueling 3.1%

cooling type forced refueling period /EFPD 450

diameter of pool /m 10.0 average discharge burnup /GWD/tU ~30

depth of pool /m 26 refueling number per year /assembly 24

height of active zone /m 2.15 temperature of pool water /℃ 68

equivalent diameter of core /m 2.02 inlet/outlet of core /℃ 68/98equivalent diameter of core /m 2.02 inlet/outlet of core /℃ 68/98

type of assemblytruncated PWR

assembly(CF3-S)inlet/outlet of secondary circuit /℃ 63.5/93.5

b f bli 69 i l / l f h i l /℃ 60/90number of assemblies 69 inlet/outlet of heating loop /℃ 60/90

form of assembly 17×17-25 pressure of primary /MPa 0.6

diameter of fuel rod /mm 9.5 pressure of secondary /MPa 1.2p y

fuel loading of core /t 23.45 pressure of heating loop /MPa 1.8

average linear power density / /

8.87 type of heat exchanger for primary i i i i

Plate-type/kW/m circuit and secondary circuit

yp

Core arrangement and Fuel assembly51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 燃料棒

51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 61 导管

51 51 71 51 51 61 51 51 61 51 51 61 51 51 71 51 51 71 载钆燃料棒

51 51 51 61 51 51 51 51 51 51 51 51 51 61 51 51 51 82 中心导管

51 51 51 51 51 51 71 51 51 51 71 51 51 51 51 51 51

51 51 61 51 51 61 51 51 61 51 51 61 51 51 61 51 51

Fuel enrichment

首炉堆芯 51 51 51 51 71 51 51 51 51 51 51 51 71 51 51 51 51

51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51

51 51 61 51 51 61 51 51 82 51 51 61 51 51 61 51 51

51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51

51 51 51 51 71 51 51 51 51 51 51 51 71 51 51 51 51

51 51 61 51 51 61 51 51 61 51 51 61 51 51 61 51 51

51 51 51 51 51 51 71 51 51 51 71 51 51 51 51 51 51

51 51 51 61 51 51 51 51 51 51 51 51 51 61 51 51 51

51 51 71 51 51 61 51 51 61 51 51 61 51 51 71 51 51

51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51

51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51 51

A Shutdown rod 8C Regulating/shim rod 32

1st core arrangement Gd-loaded UO2 fuel Assembly

Share of refueling:1/3

Average discharge

CF3-S truncated assembly

burnup~30GWD/tU

Refueling cycle>450dC 3 S t u cated asse b y g y

Internals in Pool

Inertia tank：replace of pump flywheelCore inlet

Core outlet D t k

Core barrel

Decay tank

Upper，middle，lower core basket

Core barrel

Support frameSupport frame

Perspective view of DHR Overlook of DHR

46

Configuration of circuit system

Setting up the 2nd

Reactor core 2nd circuit 3rd circuit

Sett g up t eisolation circuit

P3>P2>P1 ， to ensuredi ti it ill tradioactivity will not

enter heating pipe

1st circ it1st circuit

3(1st,2nd and 3rd )circuits layout, 2 times heat exchange

Plant –wide integrated DCS

One key start-stopL d t

Control room

Less person on duty Automatic tracking load

Inherent safety

1800 tons of water1

Underground reactor2

No overpressure, LLOCA, ejection of control rod, failure of safety valve, etc.3Inherent Safety

Huge steam specific volume under low pressure, self-

Large negative reactivity coefficient4

5 protection of phase change5

49

The most serious credible accidentThe most serious credible accidentNearly “zero” meltdown

Time（s） Accident sequences

0 SBO ATWS FP0 SBO ATWS,FP

0~6000 ρ, P, Tc,Tf，oscillating notoscillating ，not beyond the limit

6000 Smooth change, t bili i t 10%stabilizing at 10%

P3.1E7(10d) Core uncover

• Automatic shutdown only relying on the negative reactivityf db k ith t i t ti

50

feedback, without any intervention.

Almost none release

Multiple means to reduce radioactive release

4 Confinement

3 Underground

DHR is equipped with four barriers,effectively isolating radioactivity

A i t di t i l ti i it ith2 Reactor pool

1 Fuel cladding

An intermediate isolation circuit withhigher pressure ensure that the coolantdoes not enter the heating loop.

Equipped with a gaseous and liquid effluence collection and treatment system

Environmental Benefits

No carbon emission, noemission of NO SO dustemission of NOX, SO2, dust,ash, etc. DHR400 canreplace 320 000 tons of coalreplace 320,000 tons of coalper year，equivalent to 1300hectares afforestationhectares afforestation.

CO SO NO Dust Ash RadioactivityHeat source CO2(tons/y)

SO2(tons/y)

NOX(tons/y)

Dust(tons/y)

Ash(tons/y)

Radioactivity(mSv/person)

Coal 520000 6000 2000 3200 100000 0.013Gas 260000 1000Gas 260000 1000

Nuclear 0 0 0 0 0 0.005

Site Selection

Less requirements for site locationfor site location

No off-site emergency and small site area

No special RQMT for water source

No special RQMT for geological conditions

Soft Foundation

siteClose to

cities CostalBed rock site InlandRiverside

DHR can access to the existing urban heat network directly

53

M ltiMulti-purpose

Energy application District heating supply Non-heating seasong pp y

Refrigeration(lithium-bromide absorption-type refrigerating machine)

Desalination of Sea Water(low temp multiple effect distillation(MED)

g

Desalination of Sea Water(low temp. multiple effect distillation(MED)

Supply hot water for green-house, farming, cultivation, etc.

Multi-purpose Neutron application

Irradiation testing for fuel assemblies and material Irradiation testing for fuel assemblies and material Production of RIs, NTD silicon, gem, topaz, pearl,

nuclear membrane, etc.uc ea e b a e, etc Neutron analysis, NAA, NRG, Neutron scattering, etc. Medicine, BNCT,FNT, etc.

Roadmap of DHR

3rd step

DD

Commercial promotionCommercial promotion

After 2022After 20222nd stepDemo Project Demo Project

~2022~2022

After 2022After 2022

1st step

Principle verification

20172017--1212

HAPPY200HAPPY200


57

HAPPY200 is a two-loop low pressure water reactor with low th l t d ithermal parameters and passive safety systems.

For the safety of heat consumerFor the safety of heat consumer, there are four loops from reactor to the consumer.

Based on large volume pool completely passive technologies, HAPPY200 can provide anHAPPY200 can provide an inherent technical guarantee for the safety of the reactor.

58

Main ParametersMain ParametersMain parameters HAPPY200 Main parameters HAPPY200

Thermal Power（MWt） 200

Heat capacity per unit（GJ/ ）

3,000,000

Core inlet/outlet temperature (℃）

80/120

Primary/secondary water（GJ/y）3,000,000

Heating area per unit（million m2）

5~7

37/t t d

Primary/secondary water load（t） 20/100

Shield and Cooling Pool volume(m3)

1000

Fuel No./Type 37/truncatedstandard FA

Active length （m） 1.92/2.15

( )Containment free

volume(m3)3000

Operation/design 0 8/1 6g

Core equivalent diameter（m）

1.51secondary pressure （MPa）

0.8/1.6

Secondary inlet/outlet temperature（℃）

67/115

Fuel mass（t） 10

Operation/design primary pressure (MPa)

0.6/1.6

Heat network pressure（MPa）

0.6

Heat network inlet/outlet t t （℃）

50/110

59

pressure (MPa) temperature（℃）/

Concept DesignConcept Design

For the Secondary loop

Pressure is higher than Pressure is higher than primary pressure, isolates the potential radioactive leakage.

60

Engineered Safety FeaturesEngineered Safety Features Engineered safety feature Engineered safety feature

− 1 Passive Residual Heat Removal System2 Passive Safety Injection System− 2 Passive Safety Injection System

− 3 Passive Air Cooling System

The fuel assemblies are seated inside The fuel assemblies are seated inside the reactor vessel, and the vessel is deployed in shielding and cooling pool.

Based on the conceptual design of HAPPY200, it could have a lot of technical advantages, such as safety, g , y,economic, maturity and so on.

61

Main featuresMain featuresMarket AdaptabilitySafety(inherent safe)

Ready for near-term deployment

Phase I: pure district heating

Market Adaptabilityy( )

Large safety margin

Low parameter operation

S f hil h b d l f Phase II: cogeneration application

Safety philosophy based on natural force

Economy Environment-friendly simplified system configuration

short R&D and construction cycle

d i f &

“zero“ pollution emission

Small radioactive waste gen.

62

adoption of mature& proven

technology

Robust FP barriers and risk minimization

R&D ProgressR&D Progress

2×200MW commercial

demonstration reactor is

planed for construction

Screening of site is completed

Pre-feasibility study is

completed

Key technology research is

ongoing

Preliminary design and PSAR

will be implemented jointly

63

LandStarOceanStar

SMR PROGRAMS IN CHINA (7)

64

©SPIC 2018. All Rights Reserved.

SMR： Model serialization, technology platform

NPP：Design、Equipment supply chain、R&D system

Technical Route and Development Basis of SMR by SPIC

•Small

•Light

•Intelligent

•High reliability

•Maintenance - free

• Mature direct connection

• Less welds

• High natural circulation ability

• More efficient OTSG

• All main equipment internally

installed——save more space

• Full natural circulation ability

SNERDI compact design SNERDI integrated design

SPIC SMR Development

©SPIC 2018. All Rights Reserved. 3

Application Field Type number Power Technical route

LandStar （LS-1/3/5）

LandStar-1 200MWt Integrated design

LandStar-3 200MWt Compact design

LandStar-5 600MWt Compact design

OceanStar （OS-1/3/5）

OceanStar-1 50MWt Integrated design

OceanStar-3 200MWt Compact design

OceanStar-5 600MWt Compact design


SMR series Developing by SPIC


Typical SMR reactor types and responding progress

Field Small grid power

supply

Industrial power supply

Civil heating

Industrial steam

Type LandStar-5 (LS-5) LandStar-1 (LS-1)

Technical route Compact design Integrated design

Design progress Conceptual design

completed

Preliminary design

ongoing

Project progress Marketing Feasibility study ongoing



General Introductions of LS-5

Underground

Electric Power

Heat Supply

Desalination

Flexible

Undersea by submerged

block


LBLOCA eliminated

Less building volume

Less in-service inspection


Multi Functions of LS-5



General Features

Reactor

building

Annex

building

Reactor building

Deep underground

Steel Containment

Vessel

Heating station

Heat exchanger and

load regulation for

multi-function

Three circuits

Higher pressure for

intermediate circuit

Isolate the potential

radioactive matter

from primary circuit to

heating circuit

LS-1 The overall configuration：3 main buildings, 3 Circuits

Heating

station



LS-1 Multi-function: civil and industrial heating

Compatible & Extensible & Standardized

Heating 3,640,000m2 or Steam 260t/h

1 unit

General Parameter

Thermal Power 200MWt

RCS Pressure 9.0MPa

RCS Tin 200℃

RCS Tout 270℃

Design life 60years

Availability 95%

CDF ＜1×10-7

LRF ＜1×10-8

Refueling Cycle 24Mons

Residents

Industry

Water

tank

Main loop

Isolation loop

Heating loop

Steaming loop

Water plant



LS-1 uses simplified passive design to improve inherent safety and harmonize

Nearly zero risk

Almost eliminate the risk of radioactive release and reduce the size of emergency

planning zones

Waste liquid is disposed and reused

in the plant during operation， and

stored after accident

Nearly zero rad-effluent

S-PRHR

Emergency core cooling

Air cooling of containment


Thanks for your attention!

Thanks so much for the information support from INET, CNPE, CIAE, SPICRI d SNERDISPICRI and SNERDI

smr in china -tong - nucleus

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