acpr small modular reactor (smr) of cgnpc · acpr small modular reactor (smr) of cgnpc . 1. ... n...

Natural Energy Powering Nature

China General Nuclear Power Corporation (CGNPC)

Oct, 2016

ACPR Small Modular Reactor (SMR) of CGNPC

1. SMR R&D of CGNPC

2. Off-shore Compact SMR ACPR50S

3. Integrated SMR ACPR100

4. Licensing & Regulation Concerned

issues

Contents


3

01 SMR R&D of CGNPC


1.1 Introduction of CGNPC

Specialized nuclear power engineering construction general contracting services

Professional nuclear power operation services

Overhaul Operation preparation

Spare parts Training Engineering design

Engineering procurement

Construction management

Commissioning

Nuclear power business:

x16 17.09GW

x12 14.65GW

As of the end of May 2016

59.8% domestically

Units in operation: remains first domestically, enters top 5 globally

1/5 globally

Units under construction: according to approved standard, 4 new units started construction, makes CGN the largest nuclear power builder


ACPR100

ACPR50S

ACPR50S: Off-shore floating NPP of compact SMR of 60MWe

ACPR100: Onshore NPP of integrated SMR of 140MWe

Two ACPR SMR designs:

1.2 ACPR SMR technical route Ø  ACPR：Advanced Customer-friendly Practicable Reliable


n  High Safety: Passive design and technically no off-site emergency measures needed

n  Modularity n  Multiple application n  Competitive costs because of Integrated energy supply, modularity, Simplified

systems and compact components n  Plant site flexibility: Small site area, low requirement for geology and cooling water n  Convenience of components transportation: Small size and weight n  Clean：Reduced Carbon emission. Environment improvement SMR plant of 2

ACPR100 modules replacing a general fossil firepower plant of 200MW:

1.3 ACPR SMR features: Safe, Flexible, Clean

500K ton

Low enrichment U

Reduce coal Reduce CO2 Reduce SO2 Reduce NO 3ton

Environment improvement

equivalent to forest of 4K ha.

5K ton 3K ton

1.3M ton

Reduce dusts

300 ton

Reduce ash

60K ton


1.4 SMR Multiple Applications

Offshore floating NPP Land

Small and medium-sized power supply

Central heating or cooling for city

Desalination

Supply power and hot water for sea oil production industry

Provide energy of electricity, freshwater, heating and Cooling water for islands.

Distributed compositive energy supply

Supply distributed power, heat and steam for Industrial Park

Two SMR Designs

ACPR100 ACPR50S


Power and hot fresh water supply for sea oil

production

Power and fersh water supply for sea shore or

island

ACPR50S SMR

n Power and heat water supply for

sea oil production

n Provide energy of electricity,

desalinating, heating and

cooling for islands.

1.4 SMR Multiple Applications

ACPR50S SMR deployment drivers : Oil production at offshore oilfields , such as Bohai Sea oilfield near Tianjin, have potential needs of electricity and hot fresh water, which is of the benifit to improving oil production cost and heavy haze in north of China.


1.5 R&D Schedule-ACPR50S


n  Fuel assembly design: Evaluation of fuel and control rod assemblies n  Reactor fuel management design n  Reactor core thermal-hydraulic design n  DBA mitigation and severe accidents mitigation design n  Design of NSSS: Reactor coolant system, safety system and nuclear auxiliary systems n  Design of main RCS components n  Design of IC, IIS, RPN n  Design of DCS n  Design of electric power system n  Design of floating platform and overall layout

Progress: basic design stage 1.5 R&D Schedule-ACPR50S


11

1.5 R&D Schedule-ACPR50S •  Procurement

2016 2017 2018

1 2 3 4 5 6 7 8 9 0 1 2 1 2 3 4 5 6 7 8 9 0 1 2 1 2 3 4 5 6 7 8 9 0 1 2

RPV

RCP

CRDM

The procurement process have been already launched, the contract is expected to be signed before the end of this year in order to carry out detailed design together with manufactures

OTSG

PZR and Short sleeve

RVI


n  6 test facilities for SMR safety test platform

n  4 test facilities for SMR equipment and key technology test platform

n  2 test facilities for SMR wave condition test platform

n  Sufficient hardware and software package for SMR design platform

Design software Thermal-Hydraulic Test Lab. in Shenzhen

1.6 Test and verification facilities


In Vessel Retention (IVR) Test Facility

SMR Test Facilities 1.6 SMR R&D of CGN

integrated Thermal-hydraulic Test Facility

Control Rod Driven Line Test Facility


Large Hydraulics Test Facility

integrated Hydraulics Test Facility

Fuel Assembly Mechanics Test Facility

Mechanics Test Facility

SMR Test Facilities 1.6 SMR R&D of CGN


1.7 Economics of SMR

Analysis shows that the economics of ACPR50S floating NPP for

offshore sea oilfield production is much better than diesel power

generation system and gas turbine power generation system.


1.8 licensing conditions of SMR

ACPR50S floating platform project plans to submit Environmental Impact Report and Site Safety Analysis Report to NNSA and PSAR to NNSA on construction stage for the Construction Permit. Now we are selecting proper shipyard.

Licensing approaches Licensing will be in stages: construction stage, fueling stage, operation stage etc.

Licensing status

PSAR outline and design criteria of overall technology will be also submitted to NNSA for review and discussion.


Off-shore Compact SMR ACPR50s

02


Off-shore SMR NPP

From Land To Sea

Large PWR NPP

SMR Industry-proven sea floating platform

technology

From Large To Small

2.1 Design Philosophy •  Industry proven PWR and sea facility technology •  From large PWR to SMR and from land NPP to off-shore NPP •  The ACPR50S realizes design simplification with less cost and lower investment risks

in order to be competitive with conventional offshore energy sources.


Thermal output (MWt) 200 Secondary pressure (MPa) 4.6 Electrical output (MWe) 60 Inner diameter of RPV (m) 2.3 Primary pressure (MPa) 15.5 RPV height (m) 7.1 Fuel arrangement 17×17 Containment height (m) 16 Assembly number 37 Inner diameter of containment (m) 15 Burnable poison Gd Designed life time (Year) 40 CR material Ag-In-Cd No operation intervention (day) 7 Fuel enrichment <5% Refueling interval (Month) 30 RPV average temperature (℃) 310

2.2 Plant Parameters


2.3 ACPR50s- NSSS Technical Scheme summary （1/3）

Fuel system design

Fuel assembly Shorten FA or STEP-S, Shorten active height，Analyze & determine grid location, Maintain lateral dimension parameters

Core components Control rods、source rods、thimble plug assemblies

Reactor design

Fuel management 37 fuel assemblies，30 months fuel cycle

Thermal-hydraulic design Maintain thermal-hydraulic criteria，DNBR margin>15%

DBC accident mitigation, Capacity design

From the basic safety functions, find the sizing transient of the systems and equipment, also the mitigation methods of DBC accidents.

Severe accident prevention and mitigation

Developed a serious accident prevention measures; Developed SAMG and severe accident mitigation strategies;

Emergency Planning Zone research

EPZ calculation The exclusion area boundary, low population zone and emergency planning zone are calculated with mechanical source terms

20


Compact design

Compact layout of reactor module Welding/Shorter pipes connection; Modular installation

Compact layout in containment Small steel containment, compact layout of safety systems

System design

Simplifying configuration of systems 91 systems as total.

Reactor coolant system 2-loop design

Engineered Safeguard System Passive systems, 2+x configuration

Main nuclear auxiliary system Reactor coolant purification system

Containment system Containment and containment isolation system

Fuel handling and storage system Special designed for SMR

CI systems Simplified configuration and design

2.3 ACPR50s- NSSS Technical Scheme summary（2/3）

21


2.3 ACPR50s- NSSS Technical Scheme summary (3/3）

I&C integration probe Equipment layout 22

premary-loop equipment

RCP Proven technology of Canned Motor RCP /Wet Winding Motor RCP

OTSG Helical-coiled tube OTSG

CRDM Electromagnetic stepping CRDM of PWR

PRZ Proven technology of PWR, simplified design

RPV Proven technology of PWR, simplified design

Shorter pipe Shorter pipes connection main equipment

RVI Proven technology of PWR, simplified design

In-core instrumentation IIS,NIS In-core: IIS；out-core: NIS

I&C MCR 2 NI share one MCR and 1 technology support center.

overall plan Level0~Level3 overall framework finished.

Electric power supply Configuration Finished power supply configuration for DC & AC


•  37 fuel assemblies in core，16 control rod assemblies

•  Shorten active height；

Fuel assembly design 2.4 ACPR50s- Reactor and Fuel

23

Fuel management

Thermal-hydraulic design •  DNBR margin>15%


•  Reliable RCS components: Industry-proven technology PRZ RCP

OTSG

RPV

Coolant flow direction

2.5 Off-shore Compact SMR ACPR50S

pressurizer

CRDM

Steam generator

Reactor pressure vessel

Reactor coolant pump

Compact layout of shorter pipes to reduce the LOCA probability


•  Reactor and RCS components design

17×17 Fuel Assembly

OTSG (Once-through SG with a number of helical coiled tubes inside)

RPV (Reactor pressure vessel)

In-vessel reactor structure

PRZ: Steam pressurizer with electric heaters and spray inside

Reactor core: 37 fuel assemblies, 16 control assemblies

2.5 Off-shore Compact SMR ACPR50S


systems number

NI (29)

Nuclear steam supply system 4

Engineered safeguard system 5

Nuclear auxiliary system 2

Cooling water system 4

Mechanical handling system 2

Radioactive waste system 4

Severe accident mitigation system 2

HVAC system 6

CI (13)

Secondary systems 7

Turbine auxiliary system 4

other 2

other (49)

BOP system 16

Electric system 11

I&C system 22 total 91

Structure and systems list

26

structures number NI 4 CI 2

BOP 4 total 10

2.6 System design


NSSS system: Reactor coolant system (RCS)

27

Design features:

•  2-loop

•  Steam pressurizer

•  Forced coolant circulation & Canned

coolant pump, eliminating seal LOCA

•  Compact design

•  OTSG: primary coolant flow in shell side

2.6 System design

•  Less water inventory contained in OTSG secondary side, decreasing

the consequence of accidents such as MSLB


2.7 Floating platform overall layout ACPR50S general plant arrangement in the float platform


2.8 Onshore base The onshore base of ACPR50S houses the fuelling building, the radioactive waste treatment building, and other balance buildings of plant. •  Refueling and temporary store of spent fuels •  Disposal of nuclear waste •  Maintenance


High level of Safeyty

Design Safety

Inherent Safety

Passive Safety

Multiple Reactivity Barriers

Very Low Reactivity Release

Frequency

No Off-site Emergency

Measure

SG joined to the RPV with short annular pipes which largely reduces the frequency of LOCA.

Residual heat removal depends on natural force. Seawater is used as ultimate heat sink

Negative power reactivity; Low linear power density; Coolant natural circulation in accidents.

6 reactivity barriers, more than conventional PWR

Severe accident mitigation: containment and NSSS flooded by sea water

2.9 High Level of Safety (1/3)


Steel containment

Semi-submersible and deep draught

•  Seawater is used as ultimate heat sink.

•  Radioactive shield by seawater. Severe accident mitigation and prevention •  IVR •  containment cooled by sea water •  NSSS flooded by sea water

Semi-submersible and deep draft

Steel containment



Passive safety system: The following passive safety systems are used to cope with design basis accidents (DBA) and severe accidents with core melts. Passive safety injection system (SIS), automatic depressurization system (ADS), Passive Secondary Residual Heat Removal System (SHR), containment pressure suppression system (CPS), Passive Containment Heat Removal System (CHR).


Coolingwatertankoutsidethecontainment

CMT

RPV

C ORE

F ilter

AC C

ADS-3

LHST

DVI

suppressionpool

MS IV

MF IV

toMS S

fromFWS

suppressionpool

ADS -1

ADS -2

E ngineeredS afetyS ystemofAC PR 50S

AccumulatorTank(AC C )AutomaticDepressurizationS ystem(ADS )C oreMakeupTank(CMT)R eactorC ore(C ore)Pass iveC ontainmentHeatR emovalS ystem(C HR )DirectVesselInjection(DVI)F eed-WaterS ystem(FWS )MainF eed-WaterIsolationValve(MF IV)MainS teamIsolationValve(MS IV)MainS teamS ystem(MS S )Low-headS afety-injectionTank(LHS T)R eactorP ressureVessel(R PV)

Containmentcoolingheatexchanger

S G MakeupTank

Emergencywatersupply


2.11 SMR Experiment

33

No. Experiment Reactor & equipment tests

1 Reactor integrated hydraulic simulation test

2 Fuel assembly structural mechanics test

3 Fuel assembly hydraulics test

4 Fuel assembly CHF test

5 Once-through steam generator (OTSG) principle test

6 OTSG spiral tube heat transfer and resistance test

7 Spiral tube OTSG prototype test

8 Control rod driving system test

9 Reactor Vessel Internal flow-induced vibration test

10 Short cannula sealing & flow-induced vibration test

11 Main pump component test

12 Main pump two-phase characteristics test

13 Main pump prototype test

No. Experiment Safety system tests

14 Core makeup tank (CMT) test

15 Secondary side passive system test

16 Suppression pool test

17 Passive core direct vessel injection (DVI) test

18 Automatic depressurization system (ADS) test

19 In-vessel retention (IVR) engineering test

20 Passive containment engineering validation test

integral performance test 21 Compact SMR integral performance test

Ocean condition tests

22 Effect of ocean conditions on control rod driving system

test

23 Effect of ocean conditions on passive system thermal-

hydraulics performance test

n  Plan：Experiment research and device construction for Fuel, SG, integrated hydraulic, Severe accident, etc.


34

2.11 SMR Experiment No. Experiments compeleted 1 Once-through steam generator (OTSG)

principle test

2 OTSG spiral tube heat transfer and resistance test

3 Passive safety system experiment

4 Natural circulation transient experiment

5 Air cooled RPV vessel principle test

Experimental equipment

Some experimental results


35

2.11 SMR Experiment No. On going experiments

1 Control rod driving system test

The test has been going on LAHYD equipment and now it has completed ontology design.

2 Overall performance of safety system test

The test has been going on SRIPEA equipment and it has completed ontology design.

3 Heat flux density of fuel critical test The test has been going on LATHY equipment.

4 Reactor integrated hydraulic simulation test

.The test includes individual experiment and integral experiment. The former is on ontology design and the latter is on simulated body resistance match-up, quantifier research and trial experiment.

5 Reactor Vessel Internal flow-induced vibration test The test has been going on ISHY equipment.

On going experiments


2.11 SMR Experiment On going experiments.

36

PZR original rational test

截止阀调节阀止回阀安全阀排气阀文丘里管

DC

xy 储

气

罐

MP1

VF-102

VF-103

EV-101

EV-102JV-102

JV-101PRE

JV-105 JV-103

JV-106 JV-104

SV-301

HEX1 HEX2

EV-107EV-105

EV-104

JV-307

JV-308

MP2

VF-201EV-201

CS

SV-201

CSC

QV-501

PRZ

JV-504

SV-501

EV-501JV-503

JV-502JV-501

JV-407

VF-105 VF-106

TAK

PP1

SG

FIT1

FIT2

MIX

VF-104

取样口

离子

交换柱

取样口

再生式

换热器

非再生式

换热器

水再生系统

EV-103

HEX3

EV-106

VF-107

SCT

QV-101

大流量支路

小流量支路

QV-102

JV-306

JV-301

JV-304

JV-302

JV-303

VF-301

JV-401

JV-404

QV-401

JV-406

QV-201

EV-202JV-405

针阀

CV-401

CV-402

VF-202

JV-402

QV-203

SC

JV-305

QV-202

冷却水入口冷却水

入口

冷却水出口

冷却水出口

JV-107

JV-201

孔板

VF-101

ΔP

T P

ΔP

ΔP

ΔP

IU

T

P

T

P

U

I

U

I

T

P

T

P

T

T

ΔP ΔP ΔP

T T T

TP

ΔP

T

T

ΔP

TΔP

T

U

I

T P

T

P

P

T

P

PT

T

T

T

P

ΔP

T

ΔP

T P

T

ΔP T

T

T

P

TP

P

P

P

PP2

ΔP

ΔP

ΔP

T

T温控阀

JV-505

EV-203

EV-401P

P

P

P

Natural cooling cycle of RPV

Air cooled RPV vessel research


Measurement and control system interface

2.11 SMR Experiment OTSG：spiral tube heat transfer and resistance test

37

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.00

100

200

300

400

500

600

700

Nu

Li (m)

A -P -1A -P -2A -P -3A -P -4A -P -5A -G -1A -G -2A -G -3A -G -4A -G -5A -Q -1A -Q -3A -Q -4A -Q -5

15000 20000 25000 30000 35000 40000 45000 50000

80

100

120

140

160

180

200

-25%

试验值 Seban公式

Nu·

Pr-0

.4

R e

+25%

Experimental results


38

Ocean condition & earthquake effect test

facilities is under construction

2.11 SMR Experiment


03 integrated SMR ACPR100


Main Parameters Parameters Value

Thermal output (MWth) 450

Electrical output (MWe) 140

Primary pressure (MPa) 15.5

Refueling interval (Month) 30

Fuel arrangement 17 ×17

Assembly number 69

Burnable poison Gd

CR material Ag-In-Cd

Fuel enrichment <5%

RPV average temperature (℃) 310

Secondary pressure (Mpa) 4.74

Inner diameter of RPV (m) 4.4

RPV height (m) 17

Containment height (m) 22

Inner diameter of containment (m) 9.4

Modual package (ton) ∼350

No operation invention (day) 7

Max heat capacity (GJ/h) 1600

Max steam capacity (t/h) 740

Max fresh water capacity (t/d) 60

SSE 0.3g

Designed life (Year) 60

Construction duration (Month) 24

3.1 ACPR100-Main parameters

40


NSSS main equipment integrated in one

RPV

Inner PZR

Primary pump

Electromagnetism CRDM

Inner OTSG barrel

CORE: shorter 17×17FA、69FA

mixer

41

3.2 integrated SMR ACPR100


•  The 17×17 fuel assembly technology prevails in PWRs.

•  The cylindrical reactor core consists of 69 assemblies.

integrated Reactor: Fuel Assembly and reactor core 3.2 integrated SMR ACPR100



•  16 OTSG are installed inside the reactor vessel.

•  Once-through design with a number of helical coiled tubes.

integrated Reactor: OTSG



•  integrated pressurizer with electric heaters

and spray device located in the top of PRV.

•  Steel barrier between PRZ and top plenum

of OTSG.

integrated Reactor: PRZ



•  8 external canned motor coolant pumps joined to the RPV with short annular pipes.

•  Industry-proven control rod driven mechanism located on the top of RPV.

integrated Reactor: RCP and CRDM



•  Compact stainless steel containment. •  Immersed in a large pool and flooded outside. •  Vacuum between containment vessel and RPV

during normal operation to reduce heat transfer outwards.

Containment


n  4 modular standardized design n  The reactor core and NSSS is constructed underground

3.4 ACPR100 NPP


04 Licensing & Regulation Concerned

issues

All domestic issues are under or to be under discussion with relevant

Regulators, and for cross boarder cases we need to discuss with

group 2.


Thank You !

acpr small modular reactor (smr) of cgnpc · acpr small modular reactor (smr) of cgnpc . 1. ... n...

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