status of advanced nuclear reactor development in korea
TRANSCRIPT
1
The 19th Pacific Basin Nuclear Conference(PBNC 2014),
August 24-28, 2014, Vancouver, Canada
Korea Atomic Energy Research Institute
Status of Advanced Nuclear Reactor
Development in Korea
Hark Rho Kim
Senior Vice President
2
Outline
Overview of Nuclear Reactor Development I
Sodium-cooled Fast Reactor Development II
VHTR Development III
SMART (System-integrated Modular Advanced Reactor) IV
Closing Remarks V
4
Nuclear Reactor Technology Development History
Localization of CANDU Fuel
(’87)
Localization of PWR Fuel
(’88)
HANARO (’95)
OPR 1000
(’96)
Advanced Fuels for RR, PWR
and CANDU
DUPIC (’00)
APR+
(’15)
SFR
SMART
(’12)
1990 1995 2000
Localization & Standardization
Improvement
Advancement & Innovation
2010 2020
Pyro Process
S/G
IHTS Piping
Secondary EM Pump
Reactor Core
Primary Pump
Reactor Vessel
IHX
DHX
Reactor Head
Containment Vessel
S/G
IHTS Piping
Secondary EM Pump
Reactor Core
Primary Pump
Reactor Vessel
IHX
DHX
Reactor Head
Containment Vessel
VHTR
New RR
(’16) JRTR
(’15)
Technology Development Steps
1959~1969 Basic Studies
1970~1982 Turn-key Base Import
1983~1996 Localization
1997~2006 Improvement
2007~2016 Innovation
APR1400
(UAE)
5
Development of Advanced Nuclear System
Innovative Nuclear System
Advanced Research
Reactor
VHTR
Hydrogen Plant
SMART
(System-integrated
Modular Advanced
Reactor)
SFR fuel cycle
(Sodium-cooled Fast
Reactor + Pyroprocess)
NHDD
(Nuclear Hydrogen
development and
demonstration)
APR 1000
APR+(1500)
(Advanced Power
Reactor, Gen III+)
APR 1400
(Advanced Power
Reactor)
7
SFR Electrical
Heater
7 MWt
Air cooler
FW pump
SG
PHTS
pump IHTS
pumpIHX
545.0 oC
390.0 oC
30kg/s
320.7 oC
526.0 oC
320.0 oC
503.1 oC
23
0.0oC
230.0 oC
Pump
Drain tank
Plugging
indicator
Cold trap
hot air out
Air stack
hot sodium in
AHX
cold sodium out
cold air in
PDRC
AHX
Expansion tankArgon
LSDT
DHX
IRACS
Air Blower
Active AHX
System Performance
Test
Specific Design
Prototype Plant
Pyro Equipment Development and mock-up Facility
Pyro-
process
Advanced Design
Concept
‘08 ’11 ’16 ’20 ’28 ’26
Korea-USA Joint Fuel Cycle Study
Concept Design (‘12) Specific SAR (‘17) Specific Design Approval (‘20)
PRIDE (‘12)
Construction (‘28)
Pyro Feasibility Evaluation(‘20)
Prototype Facility(‘25)
PRIDE Operation and Improvement
ACPF/DFDF Operation and Improvement
Detailed Design
SFR-Pyroprocess Development Plan
Demonstration of PRIDE & 3S Conceptual Design
Prototype Facility Operation
Detailed Design
• PRIDE : Pyroprocessing Integrated inactive Demonstration Facility
• ACPF : Advanced spent fuel Conditioning Process Facility
• DFDF : Dupic Fuel Development Facility
• 3S : Safety, Security, Safeguards
8
Goal
Design Certification of prototype SFR by
2020 (1st Phase)
Construction of prototype SFR by 2028
Work Scope
Reactor system design
Code and technology validation
Metal fuel development
BOP and component design
Feature of Prototype SFR
Proliferation resistant core without
blankets
Metallic fuel
Enhanced safety with passive systems
TRU fuel irradiation capability
Overview of Prototype Gen-IV SFR Development Plan
Eq. Diameter = 253 cm
Eq. Diameter = 158 cm
Secondary control rod
Primary control rod
Reflector
B4C shield
6
3
78
114
Outer core F.A. 60
Inner core F.A. 52
313
9
Pool-type Reactor
150 Mwe
Fuel : U-Zr (Initial Core)
→ U-TRU-Zr (Reload Core)
Core I/O Temp. : 390/545 ℃
DHR System : PDHRS/ADHRS
2-loop IHTS/SGS (with Single-wall
tube SG)
Superheated Steam Rankine Cycle
(SCO2 cycle option)
Key Design Features of Prototype Gen-IV SFR
S
G
IHTS hot leg
IHTS cold leg
UIS
Pump
Rx.
core
DHX DHX
IHX
EMP
blower cold air in
Argon
Na
hot air out
hot sodium in
AHX
cold sodium out
cold air in
PDHRS
AHX
Expansion
Tank
Argon
Na
hot sodium in
AHX
ADHRS
FHX
hot air out
Rupture
disk
steam
F/W
Flare tip
Gas/Liq.
Separator
EM
PU
MP
Rupture
disk
Sodium
Dump Tank
Argon
Na
Sodium
Storage Tank
Safety Grade
Non-Safety Grade
except rupture disk
10
STELLA Program
STELLA (Sodium Test Loop for Safety Simulation and Assessment)
Phase 1: STELLA-1
• Performance evaluation of key sodium components
• Heat exchanger design codes V&V
Phase 2: STELLA-2
• Verification of dynamic plant response after reactor shutdown
• Construction of test DB to support specific design approval for the prototype SFR
Schedule
11
Irradiation tests of fuel slugs in
HANARO thermal reactor
• Irradiation tests in fast reactor
(planned)
Fuel performance analysis
code development
Fuel performance tests under
simulated transient conditions
Fuel Performance
하단연료봉상단연료봉냉각재
연료심
Hf 튜브
단면 A-A단면 B-B 노심중립면
Bottom view
Advanced FMS(ferritic marten-
sitic steel) cladding development
• Higher strength at high
temperature for higher burnup fuel
• Cladding tube fabrication
• Irradiation tests of cladding
tubes(planned)
Duct and wire fabrication
Fuel Components
100 1000100
650 oC
Str
ess (
MP
a)
Time to Rupture (hr)
HT9
T92
PNC-FMS
KAERI Batch 135% 향상
Fuel slug fabrication
• Advanced injection casting system
• Casting of U-Zr based fuel slugs
• Process optimization
Fuel rod fabrication
• Sodium-bonded fuel rod
Research on hot cell remote
fuel fabrication
Fuel Fabrication
SFR Metal Fuel Development
13
VHTR - Very High Temperature Reactor
Characteristics
TRISO Coated Fuel
Graphite Moderator
Helium Coolant
Benefits
High Temperature
high efficiency
wide range temperature
Inherent Safety
natural decay heat removal
Air Cooling
inland construction
Application
Hydrogen Production
Electricity Generation
Process Heat Application
15
Near Term VHTR R&D in KAERI
Nuclear Hydrogen Key Tech. Development R& D (‘12~‘16)
Computer Code : Core and Safety Analysis Code V & V
Helium Environment Experiment
Material and Graphite Evaluation
TRISO Fuel Fab. & Irradiation Test
Hydrogen Production Technology
(50L/hr demonstration)
VHTR Design Concept Study
(‘12~‘14)
Design concept
Demonstration & Business Plan
16
Nuclear Hydrogen Alliance in Korea
Purpose Cooperate for NHDD project
Information exchange
Industrial requirements of hydrogen and process heat
Participants Nuclear Industries : Vendor, Utility, Engineering Companies, and Institute
Potential End Users : Steel, Oil Refinery, Petro-chemistry, and Motor
Companies
MOU between Nuclear Hydrogen Alliance and NGNP Industrial Alliance
(15 April, 2013)
17
Status Plan
Design and Analysis Computer Codes
Helium Experimental Loop ('11)
TRISO Fuel Fabrication Process
Demonstration of Hydrogen Production under Atmospheric Pressure Condition (3.5L/hr)
Validation and Documentation
Safety Evaluation Test and High Temperature Material Database
Irradiation Test in HANARO
Pressurized Hydrogen Production (50L/hr)
Key Technology Development Status
Helium Experimental Loop TRISO Irradiation Test
Capsule Loaded in HANARO 50L/hr S-I Hydrogen
Production Test Facility
19
SMART
Plant Data
Power : 330 MWt
Water : 40,000 t/day
Heat : 147 Gcal/h
Electricity: 90 MWe
System-integrated Modular Advanced ReacTor
Seawater Potable
water
Electricity
Desalination Plant
Intake
Facilities
Steam
SMART
Steam
Transformer
330MWth
Integral PWR
Electricity Generation, Desalination and/or District Heating
Electricity and Fresh Water Supply for a City of 100,000 Population (Korean)
Suitable for Small Grid Size or Localized Power System
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• All Primary Components in
Reactor Vessel
• Passive Residual Heat Removal
• Modularization for Field
Installation and Maintenance
• Fully Digitized Control System
Proven Technologies
• 17x17 UO2 Proven Fuel
Technology
• Large Dry Containment Building
• Control Rod Drive Mechanism
• Reactivity Control Concepts using
BP and Soluble Boron
Innovative Concept
SMART Technology
Harmonizing Innovative Concept and Proven Technology
for Licensability and Market Acceptability
21
Standard Design
NSSS Design Fuel Design Component
Design BOP/AE Design
Core Design
Fuel Design
Component Design
Main Feedwater and Main Steam
Mechanical Design
General Arrangement
Fuel Assembly Design
System Design
Component Design Analysis
MMIS Design Containment Building
Equipment Vendor Survey Safety Analysis Aux. system Design
180O
A
8
8
8
B
8
20
12
20
8
C
8
20
12
8
12
20
8
D
8
20
12
24
16
24
12
20
8
E
90O
8
12
8
16
8
16
8
12
8
270O
F
8
20
12
24
16
24
12
20
8
G
8
20
12
8
12
20
8
H
8
20
12
20
8
J
8
8
8
0O
1
2
3
4
5
6
7
8
9
N
N
2.60 w/o U-235 21 FA
4.80 w/o U-235 36 FA
N indicates No. of Gd rod
Containment
RV
MS
FW
피동잔열제거계통
PRHRSHX
SCP
정지냉각계통SCHX
SIPM
M
안전주입계통
LHX
RHX
F
PRM
BRM
VCT
CCP
PHIX GS
HUT
HUP
BAST RMWT
RMWP
BAMP
BAC BACIX
M
CHARGINGCONTROL
VLAVE
MM
LETDOWNCONTROL
VALVEBABT
EDUCTOR
M
EDT
RDT
RDP
OUTSIDE(YARD)
화학및체적제어계통
ChemicalAdditionSystem
PIX
IRWST
ECT
2차측기기
복수펌프
복수기
터빈발전기
복수펌프 순환수조
냉 각 탑
우회증기냉각기
기동우회냉각기
C
P
P
C
P
P
증기구역격리밸브 주증기격리밸브
증기구역격리밸브
증
기
발생기
급수구역격리밸브 급수격리밸브
급수격리밸브
급수구역격리밸브
터빈발전기
순환수펌프
2차측냉각수펌프
급수펌프
복수기
주증기격리밸브
급수펌프
비상보충수탱크
비상보충수탱크
기동우회냉각기
우회증기냉각기
DNBR Pressure
SBLOCA
0 6000 12000 180000
2
4
6
8
10
450
490
530
570
610
650
Top of Core
RV Collapsed Water level
Wat
er L
evel,
m
Time, sec
Hot Spot Cad Surface Temperature
Tem
pera
ture
, K
0 20 40 60 80 100 120 140 1601.2
1.4
1.6
1.8
2.0
SLB Feed Flow Increase STEAM Flow Increase FLB CEA Withdrawal CLOF Locker Rotor SGTR
Limit DNBR = 1.41
DNBR
Time, sec0 10 20 30 40 50
8
10
12
14
16
18
20
Pressure Limit = 18.7 MPa
Pres
sure
, MPa
Time, sec
FLB CLOF CEA Withdrawal Locked Rotor SLB SGTR
Over 1500 Simulations
Confirm Safety
23
General Arrangement
Single Unit Construction
Twin Units Construction
300 x 300m for Power System
~20% More Economical than Single Unit
24
SMART vs. Fukushima
Rx Shutdown
Rx Overheat
EDG Start
Batteries
(8 hours) Fukushima
Core Cooling
Station Black out Event Scenario PRHRS
Grace
Time*
1 Yes 20 Days**
2 No 2.6 Days
Grace Time
EDG STOP
Blackout
25
SMART Advantages
SMART is Safe in Fukushima Accident Condition
The core is maintained undamaged for up to 20 days without any corrective actions by
the operator
SMART has Multiple Application
Electricity generation, seawater desalination, district heating and process heat to
industries
SMART is Ready to Construct
The standard design of SMART and Technology Validation was completed
Standard design approval was granted on July 4, 2012
SMART is expected to open up the world’s small reactor market and will take the
leading initiative
27
Closing Remarks
Korea is endeavoring to development advanced nuclear reactors to satisfy the
diverse needs for nuclear energy as well as nuclear electricity generation.
Sodium-cooled Fast Reactor for the technical solution of spent fuel problem
VHTR for diverse applications including hydrogen production
SMART for multiple application like electricity generation, seawater desalination,
district heating and process heat to industries
Korea is open to any countries for the collaboration of the nuclear technology
development for peaceful use.
For a better tomorrow with green nuclear energy