acpr small modular reactor (smr) of cgnpc · acpr small modular reactor (smr) of cgnpc . 1. ... n...
TRANSCRIPT
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
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01 SMR R&D of CGNPC
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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
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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
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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
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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
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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.
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1.5 R&D Schedule-ACPR50S
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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
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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
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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
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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
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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
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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.
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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.
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Off-shore Compact SMR ACPR50s
02
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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.
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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
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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
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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
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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
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• 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%
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• 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
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• 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
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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
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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
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2.7 Floating platform overall layout ACPR50S general plant arrangement in the float platform
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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
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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)
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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
2.10 High Level of Safety (2/3)
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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).
2.10 High Level of Safety (3/3)
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
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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.
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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
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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
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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
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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
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Ocean condition & earthquake effect test
facilities is under construction
2.11 SMR Experiment
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03 integrated SMR ACPR100
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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
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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
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• 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
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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
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3.2 integrated SMR ACPR100
• 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
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3.2 integrated SMR ACPR100
• 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
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3.2 integrated SMR ACPR100
• 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
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n 4 modular standardized design n The reactor core and NSSS is constructed underground
3.4 ACPR100 NPP
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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.
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Thank You !