Kim, Han Gon
Korea Hydro & Nuclear Power Co.
GEN III/GEN III+ : Korean Perspective
Ⅰ. Introduction
Ⅱ. Design Char. of APR1400 & OPR1000
Contents
IV. Operation & Cons. of Korean NPPs
V. Design Validation of APR1400
2
III. Safety Evaluation of APR1400
Ⅰ. Introduction
3
Phase IV
(2000s)
Phase II
(1980s)
Construction
of Kori #1 (`71-`78)
Phase III
(1990s)
Establishment of
Localization Plan (`84)
Phase I
(1970s)
Technology
Self-reliance
Introduction
of Nuclear Power
Promotion of
Localization
OPR1000
Development (`95)
Development of
Advanced Reactor
APR1400
Development (`01)
Ⅰ. Introduction
4
YGN 3&4 : Reference Plant of OPR1000− 1000MWe, CE 2-Loop PWR
− Technology transfer agreement between KEPCO & CE
− Main contractor : domestic companies
(Technology transfer by foreign companies as sub-contractor)
1000MWe
COD: 1995/1996
Technology
Transfer
T/G
Perry#2
(GE,1000MW)
PLANT DESIGN
Yonggwang#1&2,
(KOPEC/S&L,1000MW)
NSSS
Palo Verde #2
(CE,1300MW)
YGN #3,4
Phase III - Technology Self-reliance
Core
Ano #2
(CE,1000MW)
Ⅰ. Introduction
5
UCN 3&4 : First OPR1000− 1000MWe, 2-Loop PWR
− Target : 95 % technology self-reliance for duplication of OPR1000
− Design, Manufacturing and construction by domestic companies
ADF
COD: 1998/1999
Design
Improvements
NPPs
Experience
Feed-Back
Latest
Codes & Std
OPR
(Standardization)
Reference
Project
YGN #3,4 UCN #3,4
Phase III - Technology Self-reliance
Ⅰ. Introduction
6
Development of Advanced Power Reactor 1400 (1992~2001)
Licensing agreement with ABB-CE− Perfect technology self-reliance & technology ownership
NSSS Design
Palo Verde #2 (CE,1300MWe)
Core Design
ANO #2 (CE,1000MWe)
In Operation - YGN #3,4 (’95/’96) - UCN #3,4 (’98/’99)
OPR 1000
Improved OPR 1000• In Operation - YGN #5,6 (’02/’02) - UCN #5,6 (’04/’05)
• Under Construction - SKN #1,2 - SWN #1,2
1,400 MWe• Under Construction - SKN # 3,4
• Planning - SUN # 1,2
(CE, 1300MWe)
Sys. 80+
Phase IV – Technology advancedment
Ⅰ. Introduction
7
Design Principles
Adoption of ADF based on proven technology
Enhanced Plant Safety and Cost
Effectiveness
Improved O & M Convenience
• Direct Vessel Injection of Safety Injection System
• Passive Flow Regulator or Fluidic Device in Safety
Injection Tank
• In-containment Refueling Water Storage
Tank & Sparger
• Fully Digitalized I&C and
Operator-Friendly Man-Machine Interface
• Improved Severe Accident Mitigation
System
• Reinforced Seismic Design Basis (0.3 g)
• Extended plant design lifetime (60 years)
• R educed construction time (48 months for Nth unit)
• Extended operator response time
• Reduced occupational exposure
• Easier In-Service Inspection and
maintenance for components
Design Goals
Safety
Economy
Performance
• Core Damage Frequency
< 1.0E-5/RY (2.25×10-6/RY)
• Containment Failure Frequency
< 1.0E-6/RY (2.84×10-7/RY)
• Seismic Design Basis : 0.3 g
• Occupational radiation exposure
< 1 man·Sv/RY
• Thermal Margin (is greate than) > 10 %
• Plant Availability > 90 %
• Unplanned Trip (less than) < 0.8/RY
• Plant Capacity (Gross) : 1,455 Mwe
• Plant Lifetime : 60 years
• Refueling Cycle ≥ 18 months
• Construction Period : 48 months (Nth Unit)
8
Ⅰ. Introduction
Ⅱ. Design Characteristics of
APR1400 & OPR1000
9
Items APR1400 OPR1000
[Economics/Performance]
- Design life time
- Capacity
- Construction period
- Daily load following
- Refueling interval
- I&C
[Safety]
- CDF
- CFF
- Seimic design
- Operator action time
- SBO scoping time
- ECCS
- SG plugging margin
60 yrs
1400 MWe
58 Months(Unit 1,2)
Automatic
18 Months
Full digital
<1.0E-5/RY
<1.0E-6/RY
0.3g
30 mins
8 hours
4 Trains DVI
10% (Inconel 690)
40 yrs
1000MWe
62 Months
Manual
18 Months
Partial digital
<1.0E-4/RY
<1.0E-5/RY
0.2g
10 mins
4 hours
2 Train CLI
8% (Inconel 690)
Ⅱ. Design Characteristics of APR1400 & OPR1000
Top-Tier of APR1400 vs. OPR1000
10
Overall Configuration of OPR1000
Ⅱ. Design Characteristics of APR1400 & OPR1000
11
Basically same configuration
with OPR1000 except safety
system (DVI, IRWST and so on)
Overall Configuration of APR1400
Ⅱ. Design Characteristics of APR1400 & OPR1000
12
Auxiliary Building (AB)
- Quadrant arrangement to enhance safety
- Accommodating MCR, Emergency D/G,
Fuel handling facilities
Reactor Containment Building (RCB)
- Pre-stressed cylindrical wall and hemi-
spherical dome concrete structure
- Wrapped around by auxiliary buildingCompound Building (CB)
- Accessible from both units
- Housing common facilities of Access control,
Radwaste treatment, Hot machine shop, etc
General Arrangement – Building Design
Turbine Building (TB)
- Steel structure with reinforced concrete
turbine pedestal
- Common tunnel for all underground facilities
Ⅱ. Design Characteristics of APR1400 & OPR1000
General Arrangement – Principles of Layout
Protection against internal & external hazards
Flood protection : ANSI/ANS-2.8
Fire protection : SECY-93-087 & NFPA804
Radiation protection : ALARA principle
Safety Systems: Physically separated layout
Ⅱ. Design Characteristics of APR1400 & OPR1000
Quadrant C Quadrant A
Quadrant D Quadrant B
Quadrant Arrangement of Safety Systems
General Arrangement
CCWP 3
CCWP 4 CCWP 2
CCWP1
SCP 1
SCP 2
SIP 3
SIP 2
SIP 1
SIP 4CSP 2
CSP 1
SIP ( Safety Injection Pump) SCP (Shutdown Cooling Pump) CSP (Containment Spray Pump) CCWP (Component Cooling Water Pump)
Ⅱ. Design Characteristics of APR1400 & OPR1000
Quadrant C Quadrant A
Quadrant D Quadrant B
Fire Barrier(3Hr)
Flood Barrier
Fire (3Hr) &
Flood Barrier
Fire & Flood Protection Design
General Arrangement
Ⅱ. Design Characteristics of APR1400 & OPR1000
Quadrant C Quadrant A
Quadrant D Quadrant B
General Arrangement
Clean Area
Hot Area
Radiation Protection Design
Ⅱ. Design Characteristics of APR1400 & OPR1000
4 Inlet nozzles, 2 Outlet
nozzles and 4 DVI nozzles
Flow Path
• Cold leg Downcomer Lower Plenum Core Upper Plenum Hot leg Steam generator Suction leg RCP Cold leg
18
Ⅱ. Design Characteristics of APR1400 & OPR1000
Reactor Coolant System
Reactor Vessel
① Increased thermal margin
② High burn up of 55,000 MWD/MTU
③ Improved neutron economy
④ Increased seismic resistance
⑤ Improved the resistance to fretting wear
⑥ Debris-Filter Bottom Nozzle
Reduced Rod Bow
Top Inconel Grid
High Burnup
Bottom Inconel Grid
Easily Removable
Integrated Top Nozzle
High Seismic Mixing
Vane ZIRLO™ MID Grid
Fretting Wear Resistant
Conformal Spring & Dimple
Debris Filtering
Protective Inconel Grid
Debris Filtering
Bottom Nozzle
19
Fuel Assembly – Plus7
Ⅱ. Design Characteristics of APR1400 & OPR1000
Reactor Coolant System
PSV
SDS ValveSDS Valve
PSV PSV
PSV
Pressurizer
To IRWSTTo IRWST
Pressurizer
4 PSV and 2 SDS Valves
To Hot Leg
To Hot Leg
4 POSRV
To IRWSTTo IRWST
POSRV POSRV
POSRVPOSRV
Over-pressurization protection & Safety depressurization OPR1000 : 3 PSV (OPP) + 2 SDS (SD)
APR1400 : 4 POSRV (OPP+SD)
(POSRV : Pilot Operated Safety and Relief Valve)
Pressurizer
Ⅱ. Design Characteristics of APR1400 & OPR1000
Reactor Coolant System
20
FA
SG IHA
PZR
RCP RV
2 feed lines (downcomer + economizer)
1 aux line (downcomer)
• Increased anti-vibration bars
- Reducing flow-induced tube vibration
Improved Upper Tube Support Bars
& Plate
Design Parameters• Number of tubes : 13,102 / SG (APR1400)
8,340 / SG (OPR1000)
• Plugging margin : 10 % (APR1400),
8 % (OPR1000)
• Tube material : Inconel 690
Ⅱ. Design Characteristics of APR1400 & OPR1000
Reactor Coolant System
21
Secondary Operating Pressure
OPR1000 : 1070 psia (553 ℉ ), APR1400 : 1000 psia (545 ℉ )
Feedwater Control
OPR1000 : Automatic control above 5% power level
APR1400 : Automatic control for all power level
MFP operation
OPR1000 : 2 TDP (65%), 1 MDP (standby)
(1 Pump failure : Power cutback to 65%)
Improved OPR1000, APR1400 : 3 TDP (50%)
(1 Pump failure : No power change (33.3 %*3 50%* 2))
Ⅱ. Design Characteristics of APR1400 & OPR1000
Reactor Coolant System
22
•23
Number : 1
Type : Direct Driven(conductor cooled)
Voltage : 24kV, 3Phase
Frequency : 60Hz
Turbine
Number of Turbines per Reactor : 1 Double Flow High Pressure
and 3 Double Flow Low Pressure
Type of Turbine : 6 Flow, Tandem-Compound
Turbine Speed : 1,800rpm
Generator
Ⅱ. Design Characteristics of APR1400 & OPR1000
23
Comparison of OPR1000 vs. APR1400
• 4 Train vs 2 Train
• No cross-tie between train : easy maintenance
• No Low Pressure SIPs by adoption of fluidic device in SIT
• No recirculation mode change by adoption of IRWST
CONTAINMENT
S/G S/GR
V
SIT
SIT
SIT
SIT
HPSIP
HPSIP
LPSIP
LPSIP
<2 Train CLI Safety Injection System>
Sump
RWST
CONTAINMENT
IRWST
S/G S/GRV
SIT
SIP
SIT
SIP
SIT
SIP
SIT
SIP
<4 Train DVI Safety Injection System>
Ⅱ. Design Characteristics of APR1400 & OPR1000
Safety Injection System
24
Injection location
− OPR1000 : 60 degree at RCP discharged leg
− APR1400 : reactor vessel (83” above CL)
(1) DVI
(2) CLI
Coldleg
45
o45
o
45
o45
o
180o0o
270o
90o
Ⅱ. Design Characteristics of APR1400 & OPR1000
Safety Injection System
25
Passive Fluidic Device in SIT
• Safety Injection Tank (Accumulator)
− Role : Refill reactor vessel lower plenum during LBLOCA
− Initial Condition : Pressurization to ~40bar by Nitrogen gas, 1800ft3 for APR1400
− Problem : Too much water to fill lower plenum
Ⅱ. Design Characteristics of APR1400 & OPR1000
Safety Injection System
26
Passive Fluidic Device in SIT (APR1400 only)
• Principle : Vortex resistance
− Low resistance upper stand pipe
− High resistance lower stand pipe
0 20 40 60 80 100 120 140 160 180 2000
200
400
600
800
1000
1200
Dis
cha
rge
Flo
wra
te, kg
/s
Time, sec
FD-II(b)-C-HH-1
FD-II(b)-C-HH-2
FD-II(b)-C-HH-3
Ⅱ. Design Characteristics of APR1400 & OPR1000
Safety Injection System
27
Functions
Design characteristics
• 4 POSRVs on the top of pressurizer• Discharge to IRWST through sparger to
prevent contamination of containment
• Control RCS pressure during normal
operation and DBA
• Allow feed & bleed operation in Total Loss of Feed Water accident
• Depressurize RCS to prevent high pressure molten core ejection
28
Ⅱ. Design Characteristics of APR1400 & OPR1000
SDVS (APR1400 only)
Water source
• Normal Operation
- Refueling
• Design Basis Accidents
- Safety injection system
- Containment spray system
- No recirculation mode switch
• Severe Accident
- Cavity flooding system
- IVR-ERVC
29
Ⅱ. Design Characteristics of APR1400 & OPR1000
IRWST (APR1400 only)
Containment Spray System
Containment Hydrogen Control System
• Functions
− Maintain hydrogen concentration below design criterion
• Design characteristics
− 30 Passive Autocatalytic Recombiners
(PAR)
− 10 Glow plug type igniters
• Functions
− Remove airborne iodine and particulates
− Reduce containment pressure in LOCA or MSLB
• Design characteristics
− 2 Pumps (OPR1000)
2 pumps (2 backup pumps) (APR1400)
− 329 nozzles/train
− Water source : IRWST(APR1400), RWST(OPR1000)
Containment Safety Systems
Ⅱ. Design Characteristics of APR1400 & OPR1000
30
Design characteristics
• 2 × 100 % motor driven pumps,
• 2 × 100 % turbine driven pumps
• 2 × 100% dedicated auxiliary feedwater tanks
Functions
• Residual heat removal during accidents
Aux. Feedwater System
Ⅱ. Design Characteristics of APR1400 & OPR1000
31
Cavity Flooding System
In-Vessel Retention-ERVCS
• Designed in accordance with SECY-93-087
• Flood reactor cavity to cool molten core
• Water Source : IRWST
• Water driving force : Gravity
• Cavity floor area for molten corespreading > 0.02 m2/MWt
• Submerge reactor vessel lower head before molten core relocation to bottom head
• Water Source : IRWST
• Water driving force : SCP, BAMP
Sevene Accident Mitigation System (APR1400 only)
Ⅱ. Design Characteristics of APR1400 & OPR1000
32
Cavity Flooding System
Ⅱ. Design Characteristics of APR1400 & OPR1000
Sevene Accident Mitigation System (APR1400 only)
33
IVR - ERVCS
• Major Design Parameter of IVR-ERVCS
− Natural circulation Capability
− CHF at vessel wall
Ⅱ. Design Characteristics of APR1400 & OPR1000
Sevene Accident Mitigation System (APR1400 only)
34
T&G
MCR
I&C
System & Components – MMIS
Advanced I&C Design
• Adopted different type and
manufacturer’s product for defense
against common mode failure
• Applied open architecture concept for
easy system modification and upgrade
• Used commercial off-the-shelf
hardware, software, and network
platforms having more than 3,000 years
operating experience
• Applied fault tolerant design by
adopting fail-safe concept
• Used multi-loop controller for non-
safety system to be simplified and
economical
Main Control Room
Safety Console Workstation
LDP
OPR1000 MCR
APR1400 MCR
Ⅱ. Design Characteristics of APR1400 & OPR1000
36
Ⅲ. Safety Evaluation of APR1400
37
Beyond DBA
• Inter-system LOCA
• Multiple SGTR
• Common mode failure
• Total LOFW
• DBA at lower mode operation
Design Bases Accidents
DBA & BDBA Analyses
38
Ⅲ. Safety Evaluation of APR1400
Category Limiting Event
Increase in heat removal MSLB
Decrease in heat removal MFLB
Decrease in RCS flow rate RCP Shaft break
Reactivity anomalies CEA Ejection
Increase in RCS inventory IO SIS
Decrease in RCS inventory Large Break LOCA
Radioactive material release
from a subsystem or component
Fuel handling accident
ATWS ATWS
• Conservative Approaches
− Conservative code system
− Single failure assumption
− Conservative initial/boundary conditions
• For all events, APR1400 meets the acceptance criteria
− Domestic & US NRC (10CFR100, SRP)
− 10CFR50.46 for LBLOCA
• Realistic Approaches
− Realistic assumption
− Best estimate codes
SBO Coping capability
DBA & BDBA Analyses
39
Ⅲ. Safety Evaluation of APR1400
• Off-site AC Power + EDG fail (10CFR 50.63)
− Alternate AC Power
− Aux. Charging Pump for RCP seal cooling
• Off-site AC Power + EDG + AAC fail : DC Battery (8hrs)
− RCS cooling : Turbine driven AFWPs
− RCP seal leakage protection by stand-still seal
• Off-site AC Power + EDG + AAC + Battery fail
− Provision for SG cooling by portable cooling device
CDF Contribution by Full Power Internal Events
PSA
Ⅲ. Safety Evaluation of APR1400
CDF Contribution by Low Power Internal Events
• POS4 : Cold shutdown
• POS6 : Mid-loop Operation
• POS7B : Rx Head Detension
• POS7C : Lift Rx Head and UGS/CEA
CDF Contribution by External Events
• Fire : 13% of Total CDF
• Flood : 2.73% of Total CDF
IV. Operation & Construction of Korean
NPPs
41
0.30.350.60.60.50.60.60.40.50.50.90.41.10.91.1shutdown
91.793.490.392.395.591.494.292.793.290.488.290.287.687.587.3C.F.(%)
40
60
80
100
Capacity
Factor (%)
`95 `96 `97 `98 `99 `00 `01 `02 `03 `04 `05 `06
1
2
3
491.7
Capacity Factor (Korea)
76.0
Capacity Factor (World Average)
0.3
Unplanned shutdown / Unit
IV. Operation & Construction of Korean NPPs
Capacity factor / Reactor Trip
42
`07 `08 `09
• Pre-fabrication and structure module
• Steel linear plate module
• Deck plates method
• Modularization of reactor internals
• Automatic welding of RCS pipe
• Over the top method for NSSS
major components installation
Measures to Reduce Construction time
IV. Operation & Construction of Korean NPPs
43
55MShin-Kori 3&4
Nth Plant
20M 19M 4M4M 8M
17M 17M 4M3.5M6.5M
Ulchin #3
Younggwang #5
Ulchin #6
Shin-Kori 1&2
Shin-Wolsong 1&2
First Concrete PourSetRx. Vessel
Fuel
Load COCHT HFT
1
61M21M 22M 4M 5M 9M
59M22M 20M 5M 5M 7M
55M21M 18M 4M 6M 6M
51M19M 4M4M 7M17M
47M17M 4M 4M 6M16M
Construction Time Schedule
44
IV. Operation & Construction of Korean NPPs
Shin-Kori
Shin-Ulchin
Shin- Kori
#3
#4
Key Milestones of Shin-Kori 3&4
2008 2009 2010 2011 2012 2013 2014
Excavation
Reactor
Vessel Installation
First
EnergizingHot Functional
Test COD
Shin-Ulchin
#1
#2
Construction Plans of Shin-Ulchin #1,2
2010 2011 2012 2013 2014 2015 2016 2017
ExcavationFirst
Concrete
Reactor
Vessel Installation Fuel Loading
Commercial
Operation
APR1400 Construction Schedules
75.8%
100%
92.6%
82.8%80.2%
77.9%
Construction Cost Reduction
46
IV. Operation & Construction of Korean NPPs
Automatic generation of virtual plant through
connecting with Engineering Data Base System
Automatic Modeling
Producing various deliverables
Piping Design Drawing, bill of material, welding data & location, etc
Check physical interference, animation, walk-trough as a virtual character, and data navigation
Design Review
Construction Design Verification by 3D CAD System
47
IV. Operation & Construction of Korean NPPs
V. Design Validation of APR1400
48
• Investigating multi-D phenomena in downcomer during reflood of cold-leg LBLOCA
• Working fluid : Air-Water, Test scale : 1/10, 1/7, 1/5 of APR1400 & 1/7, 1/4 of UPTF
DIVA (Downcomer Injection Visualization and Analysis)
V. Design Validation of APR1400
49
MIDAS (Multi-dimensional Investigation in Downcomer Annulus Simulation)
• Measuring ECC bypass in the reflood phase of cold-leg large break LOCA
• Working fluid : Steam-Water, Test scale : 1/5 of APR1400 & 1/4 of UPTF
50
V. Design Validation of APR1400
Passive Flow Regulator in SIT
VAPER (Valve Performance Evaluation Rig)
• To prevent coolant loss in Large Break LOCA
• Verify SI flow performance of SIT with Fluidic Devices
• Full scale and pressure condition
Fluidic Device in SIT
51
V. Design Validation of APR1400
Measuring air, steam, and water blowdown load on SDVS & IRWST structures
Investigating thermal mixing between discharged fluid and water in IRWST
B&C (Blowdown & Condensation) Loop
52
V. Design Validation of APR1400
ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation)
State-of-the-art integral loop test facility commissioned in 2006
1/2-height & 1/144-area, Full pressure & temperature simulation of APR1400
53
V. Design Validation of APR1400
Full scope & APR1400 specific dynamic mockup tests
Verifying & validating human factors engineering for normal and emergency operation
Performed by licensed operators and human factors specialists 54
V. Design Validation of APR1400
HERMES : Measuring natural circulation flow through region between reactor vessel and insulator
CHF Test : Investigating critical heat flux and thermal margin
55
V. Design Validation of APR1400