THE DESIGN CHARACTERISTICS OF ADVANCED POWER …...ADVANCED POWER REACTOR 1400. KIM, HAN-GON...
Transcript of THE DESIGN CHARACTERISTICS OF ADVANCED POWER …...ADVANCED POWER REACTOR 1400. KIM, HAN-GON...
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International Conference on Opportunities and Challenges for Water Cooled Reactors in the 21th Century
Vienna, IAEA, Oct. 27-30, 2009
THE DESIGN CHARACTERISTICS OF
ADVANCED POWER REACTOR 1400
KIM, HAN-GON
Advanced NPP Development OfficeKorea Hydro & Nuclear Power Co., Ltd.
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CONTENTS
Ⅱ. Description of Nuclear Systems
Ⅰ. Introduction
Ⅲ. Description of Secondary Systems
Ⅳ. Safety System Design Characteristics
Ⅴ. Plant Layout
Ⅵ. Conclusions
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(As of Dec.31, 2007)
Wolsong #1,2,3,4
ShinWolsong #1,2
Under Const.
In Operation
4 (2,779)Units: MW
Units: MW2 (2,000)
Wolsong Total 6 (4,779)
83.04~99.10
Yonggwang# 1,2,3,4,5,6
Under Const.
In Operation
6 (5,900)Units: MW
-
Yonggwang Total 6 (5,900)
86.08~2002.12
Kori #1,2,3,4
Shin Kori #1,2,3,4
Under Const.
In Operation
4 (3,137)
4 (4,800)
Units: MW
Units: MW
Kori Total 8 (7,937)
78.04~86.04
Ulchin # 1,2,3,4,5,6
Shin Ulchin #1,2
6 (5,900)
2 (2,800)
Under Const.
In OperationUnits: MW
Units: MW
Ulchin Total 8 (8,700)
88.09~05.04
Ⅰ. IntroductionNuclear Power Plants in Korea
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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
Ⅰ. IntroductionAPR1400 Construction Schedules
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Ⅰ. IntroductionOverview of APR1400
Development History of APR1400
Evolutionary ALWR in Korea based on current OPR1000 DesignDesign Certification for the Standard Design
General Requirement
Rated Power : 4000 MWthPlant Life time : 60 years for major componentsSeismic Design : SSE 0.3gSafety Goal : CDF < 10-5, CFF < 10-6
Performance & Economic Goals
Plant Availability : 90%
Construction Period : 48 Months for Nth Plant
Economic Goal : 20% advantage over coal
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Rated Power : 4000 MWth
2-Loop PWR :
- One Reactor Vessel
- Two Steam Generators
- Four Reactor Coolant Pumps
- One Pressurizer
Thermal Margin > 10%
Ⅱ. Description of Nuclear Systems
Overall Description
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Ⅱ. Description of Nuclear SystemsRCS Design Characteristics
Hot Leg Temperature Reduction
621℉ 615℉To prevent SG tube corrosion
Integration of- Cooling shroud assembly
- CEDM cooling system
- Missile shielding material
Expected effects of IHA
- Reducing refueling time
- Reducing occupational dose- Reducing comp. storage area- Improving safety for workers
Integrated Head Assembly
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Ⅱ. Description of Nuclear SystemsRCS Design Characteristics
Steam Generator
Increased tube plugging margin : 8 10%Corrosion resistant tube material : I600 I690Increased secondary inventory to prolong SG dryout timeAutomatic level control for all power level
Pressurizer
Larger steam space to accommodate RCS transientsAdoption of POSRV instead of PSV + SDS
- 4 PSVs + 2 SDS 4 POSRVs- Over pressure protection + Safety depressurization function- High reliability
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EMERGENCYOPERATIONSFACILITY CRTs
TECHNICAL SUPPORT CENTER & CONTROL ROOM OFFICES
MCR
REMOTESHUTDOWN PANEL
NON-SAFETY(Design Type 2)SAFETY(Design Type 1)
QUALIFIEDINDICATION ANDALARM SYSTEM
INFORMATIONPROCESSING
SYSTEM
ESF COMPONENTCONTROL SYSTEM
PLANTPROTECTION
SYSTEM
PROCESSCOMPONENT
CONTROL SYSTEM
POWERCONTROLSYSTEM
REMOTEMULTIPLEXORS
PLANT COMPONENT & SENSORS
PRO
TECTIO
N&
CO
NTR
OL
SYSTEM
MO
NITO
RIN
GSY
STEM
QIAS-PQIAS-N
Ⅲ. Description of Secondary Systems
Design Characteristics of I&C Systems
Digital Technology & Data communication networkOpen & Standard ArchitectureDefense on Common mode failureOperability & Maintenance : Auto test, Self-diagnosis
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Ⅲ. Description of Secondary SystemsⅢ. Description of Secondary Systems
Characteristics of MCR Design
Multiple Compact Workstation MCRLarge Display PanelSoft-Controller : Safety & Non-safety controlComputerized Procedure SystemsAdoption of Human Factor Engineering
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Safety Injection System
No cross tie between trains
Design Characteristics
4 independent trains (Each train consists of 1 SIP and 1 SIT)
Effective use of ECC water and Better response to Transient and SBLOCA
No re-circulation mode during LOCA
Unified water source from IRWST
Elimination of LPSIP
Fluidic Device installed in SIT
Ⅳ. Safety System Design Characteristics
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Design Characteristics
Verification of Fluidic Device
Principles : Vortex flow resistance
− Stand pipe : Low resistance
− Control port : high resistance
Purpose : Extending SIT injection period during LOCA
Effect : Removal of LPSIPs
0 100 200 300 400 5000
500
1000
1500
2000
2500
APR1400 CE plant
Flow
rate
(kg/
sec)
Time after LBLOCA (sec)
Ⅳ. Safety System Design Characteristics
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Verification of Fluidic Device
Actual physical dimension- Inside diameter : 2.74 m- Total Height : 12.0 m
Full Pressure : 50 bar
Test Facility Test Results
Test Results
- Total 28 tests has been performed
- Performance is fully verified
- Detailed design spec. is finalized
Ⅳ. Safety System Design Characteristics
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Integral Test Loop
ATLAS Facility
Characteristics
① ½ height and 1/144 scaled down based on flow area
② NSSS and safety systems of APR1400 are modeled
Purpose
① Major system behavior for LBLOCA,
DVI Break, MSLB, MFLB, SGTR, TLOFW and so on
Milestone
① Construction Completion : ’06.5
② LBLOCA Tests : ’06.9 ~
Effects
① Better understanding of APR1400 SIS Performance
② Benchmarking safety analysis codes
Ⅳ. Safety System Design Characteristics
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Ⅳ. Safety System Design Characteristics
FunctionsDesign
characteristicsIRWST
- Supply cooling water during refueling
- Supply the water source to safety injection and containment spray systems during DBA
- Removed recirculation mode because bleeded coolant is collected in IRWST through HVT (Hold-up Volume Tank)
- Supply heat sink during rapid depressurization of RCS and feed and bleed operation
- Supply water source for reactor cavity flooding system
- Collect the coolant from POSRV to IRWST through sparger
- Removing of Pressurizer Relief Tank (PRT)
- Reduce operator's burden with simplified operation mode
- Reduce containment penetrations
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IRWST
Ⅳ. Safety System Design Characteristics
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External Cooling of RPV (ERVC)
ERVC− Strategy to retain corium in vessel by submerging reactor vessel exterior with
water
− Used in Lovisa and AP600 and AP1000
− Theofanous conducted a structured study on its performance
− Chosen as a key accident management strategy for APR1400
Accident Management Strategy of APR1400- If water can be injected to reactor cavity : ERVC
- If not (eg. SBO): corium spread to reactor cavity and cooling from IRWST using
gravity head.
ERVC Concept of APR1400- One train of SCP + BAMP
- Associated system is already
included in APR1400 design.
Ⅳ. Safety System Design Characteristics
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Performance of ERVC in APR1400
RPV Insulation
− Passage way for the water to cool the hot reactor vessel
− Natural circulation path for the two-phase flow and influence CHF
− Streamlined insulation design for APR1400 is in progress
0 10 20 30 40 50 60 70 80 900
200
400
600
800
1000
1200
1400
1600
1800
2000
2200
YANG & CHEUNG
LOFW
MLOCALLOCA
SLOCA
ULPU-2000 Correlation (ULPU-III)
ULPU-V
Heat
Flu
x (k
w/m
2 )
Angle (degrees)
Feasibility Study
− 4 Major scenarios using MAAP
− Margin for APR1400 shows the usefulness of the ERVC strategy
Ⅳ. Safety System Design Characteristics
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Ⅴ. Plant Layout
NI : Reactor Building, Aux. Building, Compound Building
TI : Turbine Building, SwitchGear
Power Block : NI & TI
2 Units reference
Parallel Sliding Type
Aux. Building : Quadrant structure
Basic Design Concept
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Ⅵ. Conclusions
1999 2000 2001 2002 2008 2013
Basic Design of APR1400
has been finished
Design Optimization process to enhance economics
Design Certification
(May 2002)
First commercial NPPs of APR1400[ Shin-Kori 3&4 are in progress ]
Commercial Operation
APR+
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