Status of SFR Development in Korea

FR13, Paris, France

2013. 3. 5

Yeong-il Kim

2 FR13, Paris, France, 4-7 March 2013

National Plan for SFR Development

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 s

tack

hot sodium in

AHX

cold sodium out

cold air in

PDRC

AHX

Expansion tankArgon

LSDT

DHX

IRACS

Air Blower

Active AHX

System Performance

Test

Design Approval

Detailed Design

Prototype Reactor

Conceptual Design

‘07 ’11 ’16 ’20 ’28 ’26

2017: Safety Analysis Report for Prototype SFR

2020: Design Approval

2028: Completion of Construction

3 FR13, Paris, France, 4-7 March 2013

SFRA

Organized on 16th of May, 2012

Affiliated organization of KAERI

Goal of SFRA : acquisition of design approval for prototype SFR

Background of Organizing SFRA

Phase change in SFR development program

From key technology development in the past

To overall system engineering including SFR system design and

optimization, design v&v tests, major component development etc.

In order to perform prototype SFR development efficiently and

consistently

Project Period : 2012 ~ 2020 (9 years)

SFR development Agency (SFRA)

4 FR13, Paris, France, 4-7 March 2013

Organization of SFRA

Ministry of Education, Science and

Technology (MEST)

Committee for Promotion of

SFR Development

National Research

Foundation of Korea (NRF)

Director Steering Committee

Advisory Board Executive Office

NSSS Design

(KAERI)

Technology

Verification

(KAERI)

Fuel

Development

(KAERI)

BOP Design,

Component Design,

… (industry)

SFRA

5 FR13, Paris, France, 4-7 March 2013

NRF

MEST/ KAERI

Planning and Evaluation,

Funding Allocation

Policy and Public

Relations

Project Management

Role of SFRA

Design and R&D Team SFRA

6 FR13, Paris, France, 4-7 March 2013

Overview of Prototype SFR

Objectives

– Irradiation test of TRU fuels

–Acquisition of design, construction, and operation technologies

Safety analysis is being performed for conceptual design.

Major design features will be finalized in 2013.

MTRU Core

• LTRU and Recycled

TRU Fuels

• Closed Fuel Cycle

• TRU Burning Test

LTRU Core

• LTRU Fuel

• Open Fuel Cycle

• Recycled TRU Fuel

Test

Commercial SFR Burner

• LEU Fuel

• Open Fuel Cycle

• LTRU Fuel Test

LTRU : TRU from LWR spent fuels

MTRU : LTRU and recycled TRU

U Core

7 FR13, Paris, France, 4-7 March 2013

Pool-type Reactor

150 MWe

Fuel : U-Zr -> U-TRU-Zr

Core I/O Temp. : 390/545 ℃

DHR System : PDHRS/ADHRS

2-loop IHTS/SGS

Double-wall tube SG

Superheated Steam Rankine Cycle

Key Design Features (Draft)

AHX #1

AHX #2FHX #1

FHX #2

Steam

Generator#1

Steam Generator

#2

DRAC Piping

IHTS Piping

Guard Vessel

IHTS Pump#1

IHTS Pump#2

Reactor Vessel

Core

Reactor Support

8 FR13, Paris, France, 4-7 March 2013

Parameter Value

Core electric power (MWe) 150

Core thermal power (MWt) 392.6

Core mixed mean inlet/outlet temp. (℃) 390/545

Total flow rate (kg/s) 1,991.8

Effective full power days (EFPD) 290

Number of batches (inner core/outer core) 5/5

Active core height (m) 1.0

Enrichment (IC/OC) (wt.%) 14.0/19.5

Burnup reactivity swing (pcm) 1,184

Discharge burnup (MWD/kg) Avg. 50.2

Peak 78.7

Fast neutron flux (x1015 n/cm2·sec) Avg. 0.98

Peak 1.54

Peak fast neutron fluence (x1023 n/cm2) 1.95

Linear power density (W/cm) Avg. 104.7

Peak 180.0

Avg. power density (W/cm3) 143.6

Bundle pressure drop (MPa) 0.255

Uranium Core Configuration of a 150 MWe Prototype SFR

Fuel : U-Zr metal fuel of < 20 wt.% U-235

Cladding : D9 to secure the mechanical integrity

under the core exit temperature of 545C

D9 cladding dpa : < 100 dpa

Bundle pressure drop : < 0.26 MPa without

uncertainty

Cladding mid-wall temperature : < 650 C to ensure

the cladding CDF < 0.001

9 FR13, Paris, France, 4-7 March 2013

Fluid System Design

Primary Heat Transport System (PHTS)

- Pool type

- 4 IHXs

- 2 mechanical PHTS pumps

Intermediate Heat Transport System (IHTS)

- 2 loops

- 2 double-wall SG

- 2 IHTS pumps

Power Conversion System (PCS)

- Superheated steam Rankine cycle

Residual Heat Removal System (RHRS)

- 2 passive circuits (PDHRS)

- 2 active circuits (ADHRS)

SWR Pressure Relief System (SWRPRS)

10 FR13, Paris, France, 4-7 March 2013

System Heat Balance at 100% Plant Power

11 FR13, Paris, France, 4-7 March 2013

Simple reactor enclosure system

− Reactor vessel has a uniform thickness of 5cm

− There are no penetrations and no attachment on

the reactor vessel

Advanced design technologies

− Mechanical structure design of SSC will be carried

out to be compliance with the elevated temperature

design rules of ASME BPV III, division 5

− Horizontal seismic isolation design will be adapted

for a reactor island including a reactor building, an

auxiliary building, and a wastage/maintenance

building

Advanced design materials

− 9Cr-1Mo-V steel is used for the IHX, DHX, IHTS

piping, and steam generator

− The others such as reactor vessel, reactor internal

structures, and reactor head are composed of 316

stainless steel.

CRDM

Reactor Head

Reactor Support

Reactor Vessel

Guard Vessel

Vessel Liner

Baffle Plate

IHX

IVTM

Core Restraint

Pre-Heater

Receptacle

Center Pivot Core Support Structure

Core

Internal Piping

Separation Plate

TC Instrumentation

Flow Guide Structure

CR Shroud Tube

Upper Internal Structure

Primary Pump

Shielding Plates

Rotating Plug

Mechanical Structure Design

PHTS Arrangement of the Prototype SFR

12 FR13, Paris, France, 4-7 March 2013

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

STELLA

13 FR13, Paris, France, 4-7 March 2013

Main test loop

– Test components

• Sodium-to-sodium heat exchanger

(DHX)

• Sodium-to-air heat exchanger (AHX)

• Mechanical sodium pump (PHTS

pump)

– Electrical loop heaters, EM pumps, Flow

meters, Expansion tanks,

Sodium storage tank

Working fluid Liquid sodium Total electric power 2.5 MW

Total sodium inventory ~ 18 ton Heat capacity of HXs 1.0MW

Design temperature 600oC Design pressure 10 bar

Max. flowrate for HX test 10 kg/s Max. flowrate for Pump test 125 kg/s

Overall Size (W×L×H): 15m×8m×22m

Overall Characteristics of STELLA-1

Sodium Expansion Tank

Mechanical Sodium Pump

Mechanical Sodium Pump Test

PerformanceCoastdownflow

Heater(1000kW)

Sodium-AirHeat Exchanger (AHX)

EM Pump

Blower

EM Flowmeter

Air Out

AHX and DHX Performance Test

Heat transfer characteristicsPressure drop characteristics

Air In

Sodium Storage

Tank

EM Pump

Cold Trap Plugging-meter

Sodium Purification

Heater

Flowmeter

Heater

Flow-meter

Sodium-SodiumHeat Exchanger (DHX)

Flowmeter

EM Pump

Flowmeter

Major Characteristics

14 FR13, Paris, France, 4-7 March 2013

Setup of sodium test facility for the

performance demonstration of under-

sodium visualization technology using

ultrasonic waveguide sensor

– Glove box system, sodium test tank

and storage tank

Design and manufacture of 10 m long

under-sodium ultrasonic waveguide

sensor module

– SS304 waveguide plate (15 mm

thickness)

– Ultrasonic transducer (1 MHz)

installed on the top of the waveguide

sensor module

C-scan performance test of under-

sodium waveguide sensor modules

under 200C liquid sodium

– Spatial resolution : 2 mm slit in

sodium

Development of Under-Sodium Viewing Technology

Sodium test experimental facility and prototype

under-sodium waveguide sensor modules

C-Scan performance test in sodium

2mm 1mm 0.8mm 0.5mm

Test Target Specimen C-Scan Images

Loose parts

(Step Block, Washer, Pin)

Glove

Box

Sodium

Test

Tank

Sodium

Storage

Tank

Bellows

Flange

Ultrasonic

Transducer

Radiation

End Section

Ar Gas

WG sensor (Sodium)

Be coating

(0.25 mm) Ni Plating

(0.1mm)

Rx Internals

ISI Concept

15 FR13, Paris, France, 4-7 March 2013

Fuel slug gravity casting system - Control of volatile elements during casting

Fuel slug fabrication - U-Zr-Ce-Mn slugs(Φ5.0 x 300mmL) with

varying compositions

• U-(5,10,15)Zr, U-10Zr-(2,4,6)RE, U-

10Zr-5Mn, U-10Zr-RE-Mn

• Mn retention(higher than 94%)

- Casting conditions(temperature, pressure,

heating rate, time) optimization

Fuel rod fabrication - Sodium bonding

- End plug welding

- Fuel rod wiring

(U,Si)Zr2

Zr ppt

U-10Zr

Chamber

Mold

Coil

Control Panel

Vacuum Pump

Pressurizer

Chamber

Mold

Coil

Control Panel

Vacuum Pump

Pressurizer

Ce ppt

10Zr

Microstrucure of U-10Zr and U-10Zr-Ce

Fuel Slug and Gamma Radiography

Fuel Rods for HANARO Irradiation Test Fuel Rod Wiring

Na Bonding

Sodium level

Fuel Slug Cladding

He

Fuel Fabrication

16 FR13, Paris, France, 4-7 March 2013

Advanced FMS cladding alloy

development

- Alloy design and manufacturing

• 38 alloys in 3 batches

- Performance tests

• Microstructure examination

• Mechanical / sodium compatibility tests

Creep rupture strength (650oC)

improved by more than 35 % from HT9

Cladding tube fabrication - Process investigation

• Large ingot(1 ton) melting, hot extrusion,

pilgering and drawing

• Effect of cold work and heat treatment

- Cladding tubes of HT9 and Gr.92

(OD7.0mm x WT0.56mm x L3,000mm)

- Performance tests

100 1000100

650 oC

Str

es

s (

MP

a)

Time to Rupture (hr)

HT9

T92

PNC-FMS

KAERI Batch 1

+ Mo + W

+ W

Solid Solution

Strengthening

Solid Solution

Strengthening

+ V + Nb

+ V + NbC, N, B Ta

Precipitation

Strengthening

Precipitation

Strengthening

Strengthening mechanisms of FMSStrengthening mechanisms of FMS

Orange: M23C6

Green: Laves phase

Purple: Z phase

Gray: MX

M23C6

Nb2C

(VNbTa)CN

M23C6

M23C6

M23C6

M23C6

M23C6

(VNbTa)CN

ZA//[110]

1-11-111

Cladding Development

17 FR13, Paris, France, 4-7 March 2013

Fuel design

- Fuel design for SFR core design

• Fuel composition and dimension

Barrier technology

- Barrier to prevent interaction between

fuel and cladding

• Eutectic melting at high temperature

• Degradation of cladding by rare earth

fission products

- Practical barrier fabrication technology

Fuel irradiation test in HANARO - Fuel irradiation capsule design

• Simulation of fission density and

temperature of SFR fuel

- 12 fuel rodlets

• U-(Ce)-10Zr fuel slug

• Electroplated Cr barrier(20 μm)

- Irradiation complete(2.73 % burnup)

and PIE underway

Fe

Ce

LaCr

Fe

Cr

Ce

La

Fe

Ce

LaCr

(a) Zr (c) ZrN (Gradient)(b) ZrN (Uniform)

Fe

Cr

Ce

La

VFe

Cr

Ce

La

VFe

Ce

LaCr

V

(d) V (e) VN (Uniform) (f) VN (Gradient)

740 C,

25 hr

Lower fuel rodlet

Upper fuel rodlet

Coolant

Fuel slug

Hf tube

A-AB-B Neutral plane of core

Bottom view

Fuel

Cr barrier

Clad

Fuel Performance Evaluation

18 FR13, Paris, France, 4-7 March 2013

Summary

National SFR development program

Design approval of a prototype SFR by 2020

Construction of a prototype SFR by 2028

SFRA was established in May 2012 for efficient and consistent

development of a prototype SFR

Project Budget Funding and Management of SFR Development Project including NSSS,

BOP, Component Design, and Development of Related Technologies

Current R&D activities for a prototype SFR

Conceptual design is being developed from 2012

NSSS design and related v&v tests, metal fuel development by KAERI

BOP and component designs by industries