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ANA2017 Conference, Sydney, 6 Oct 2017 9
Presentation 5 – Session 2
Korea Nuclear Power Plants and Technology
Byung Jin LEE, Ph.D
KEPCO Engineering & Construction Company
Biography
Majoring in Nuclear Engineering, Byung Jin Lee
received his Ph.D. degree from KAIST in Korea. He
has an experience of 30 years in nuclear power plant
design, starting his career at Korea Atomic Energy
Research Institute and now working at KEPCO-E&C.
He participated in the development of OPR1000,
APR1400 and APR+ reactors, and is now working on
a future advanced nuclear reactor development project.
Abstract
This presentation will start with a brief history of
Korea’s nuclear technology self-reliance and follow-
up efforts for evolution. Key design features of
APR1400 will be introduced together with major
enhancements to avoid or cope with severe accidents
like that occurred in Fukushima.
The KEPCO Engineering & Construction Inc (KEPCO E&C) was founded in 1975 with the goal of accomplishing self-reliance in power plant engineering technology.
The company focuses on reactor technology and design as well as technology support for the NPPs in operation. KEPCO E&C, with over 4,000 employees in total of which 1,800 are involved in the company’s nuclear business. KEPCO A&E has designed 22 nuclear power plants.
In 2009, KEPCO E&C participated in the bid to win a nuclear power plant project in Barakah, UAE, for the first exportation of Korean-model nuclear power plant, and are performing A/E (Architect Engineering) and NSSS (Nuclear Steam Supply System) Design for the four APR1400 being constructed at Barakah. In addition, from 2016, KEPCO E&C is participating in the engineering of a SMART nuclear power plant, which is a small to mid-sized nuclear power plant, to export to Saudi Arabia.
ANA2017 Conference, Sydney, NSW
06 October 2017
LEE, Byung Jin
This document is the property of
KEPCO E&C and the use of this information is
strictly prohibited without the permission of KEPCO E&C
Contents
1 Korean Nuclear Technology Development
2 Key Design Features of APR1400
3 Countermeasures for Severe Accidents
4 Summary
1
Korean Nuclear Technology Development
2
Our Nuclear Reactors Today & Tomorrow
3
1970s 1980s 1990s 2000s
1st Phase : Gen II2nd Phase : Gen II
3rd Phase : Gen III
5th Phase : Gen IV
Turn-key base
600 MWe
Standardization
(KSNP)
Optimization
(OPR1000)
Evolutionary
PWRs- APR1400
- SMART(100MWe)
Revolutionary- SFR : U recycle and
waste minimization
- VHTR : Hydrogen
production
4th Phase : Gen III+
Evolutionary
PWRs- APR+(1500MWe)
with improved
Economics and Safety
- iPOWER
2020s 2030s2010s
Technology Self-Reliance
Design Standardization
Improvements
Innovations
Strategy for Large NPP Developments
4
Unending Improvements to Stay Competitive
✓ Optimization to improve economics
➢ Based on experience of steady constructions and operation over 40 years
✓ Advanced Design to enhance safety and operational flexibility
➢ Up-to-date Safety Requirements (Korea, USA, IAEA, UAE)
➢ Utility Requirements (domestic & world-wide: KURD, EPRI URD, EUR)
Flexible Response to Market Demands
✓ Diversifying Portfolio
➢ APR1400 / EU-APR / US-APR
➢ APR+
➢ APR1000
➢ iPOWER
✓ Diversifying Applications
➢ Electricity, Desalination
APR1400
APR+
EU-APR
APR1000
iPOWER
Future NPPs
OPR1000
US-APR
Extensive Validation Testing for ADFs
5
Design Verifications for International Market
6
EUR Certification of EU-APR
US NRC Design Certification of US-APR
Key Design Features of APR1400
7
Design Goals
8
Gen-III NPP
PERFORMANCE / ECONOMY
• Thermal Margin > 10 %
• Plant Availability > 90 %
• Unplanned Trip < 0.8/RY
• Plant Capacity (Gross) 1,455 MWe
• Plant Lifetime 60 Years
• Refueling Cycle ≥ 18 Months
• Construction Period 48 Months (Nth unit)
SAFETY
• Core Damage Frequency < 10-5/RY
• Containment Failure Frequency < 10-6/RY
• Seismic Design Basis 0.3 g
• Occupational Radiation Exposure < 1 Man·Sv/RY
Plant Layout
9
Economics
✓ Twin-unit arrangement & Compound building shared by two units
Seismic resistance
✓ Common basemat for containment and auxiliary building
Physical Separation
✓ Four-quadrant arrangement of safety systems
Reactor Coolant System
10
Safety Systems
11
Sump
CONTAINMENT
SIT SIT
SIT SIT
S/G RV S/G
RCP RCP
RCP RCP
RWST
HPSIP
LPSIP
HPSIP
LPSIP
CONTAINMENT
SIT SIT
SIT SIT
S/G RV S/G
SIP
SIP
SIP
SIP
IRWSTRCP
RCP
RCP RCP
Human-Machine Interface System
12
Countermeasures for Severe Accidents
13
Prevention & Mitigation of Severe Accident
14
Protection from External Hazards
15
* EF : Enhanced Fujita scale of Tornado
Post-Fukushima Safety Enhancements
16
Summary
17
Korean Nuclear Technology - Safe and Reliable
18
Proven and improved through accumulated experience of steady constructions and
operation of 40 years
APR1400, Evolutionary ALWR
✓ Advanced design features for safety and operational flexibility
✓ Reinforced design for severe accident mitigation
✓ Complying with global standards of Korea, USA, UAE, EU and IAEA
✓ One and only Gen-III NPP now in operation
✓ Five (5) more units under construction in Korea, and 4 units in the UAE
Our innovation continues.
✓ APR+
✓ iPOWER
Thank You!
19