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

3

Overview of Nuclear Reactor

Development in Korea I

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)

6

Sodium-cooled Fast Reactor Development II

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

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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

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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

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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

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VHTR Development III

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

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VHTR/ Nuclear H2 Development Roadmap

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

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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)

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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

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SMART (System-integrated Modular

Advanced ReacTor) IV

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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

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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

22

Technology Validation

23

General Arrangement

Single Unit Construction

Twin Units Construction

300 x 300m for Power System

~20% More Economical than Single Unit

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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

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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

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Closing Remarks V

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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

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Korea Atomic Energy

Research Institute