kim, han gon korea hydro & nuclear power co. han gon korea hydro & nuclear power co. gen...

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


11

Basically same configuration

with OPR1000 except safety

system (DVI, IRWST and so on)

Overall Configuration of APR1400


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


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


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)




Fire Barrier(3Hr)

Flood Barrier

Fire (3Hr) &

Flood Barrier

Fire & Flood Protection Design

General Arrangement




General Arrangement

Clean Area

Hot Area

Radiation Protection Design


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


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



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



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



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))



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


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>


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



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



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



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


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


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


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


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)


32

Cavity Flooding System



33

IVR - ERVCS

• Major Design Parameter of IVR-ERVCS

− Natural circulation Capability

− CHF at vessel wall



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


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


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


• 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


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


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


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


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



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)


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


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


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


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


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


HERMES : Measuring natural circulation flow through region between reactor vessel and insulator

CHF Test : Investigating critical heat flux and thermal margin

55


kim, han gon korea hydro & nuclear power co. han gon korea hydro & nuclear power co. gen...

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