Material Irradiation at HANARO, Korea

Kee-Nam CHOO, Man-Soon CHO, Young-Hwan KANG, Bong-Goo KIM, Young-Ki Kim

Research Reactor Engineering Division

Korea Atomic Energy Research InstituteKorea Atomic Energy Research InstituteKorea Atomic Energy Research InstituteKorea Atomic Energy Research Institute

Contents

� Overview of HANARO

� Fields of Utilization of HANARO

� Irradiation Facilities in HANARO

� Capsule Irradiation Technologies in HANARO

� R&D Programs related to Irradiation Tests in Korea

2

HANAROHANAROFuel fabrication Fuel fabrication facility

In operationIn operationUnder const.Under const.PlanningPlanning

SEOUL Uljin

DaejeonWolsung

GoriYounggwang

4 CANDUs

� Nuclear Power Plants in Korea� 16 PWR, 4 CNADU in operation� 6 PWR under construction� 2 PWR construction plan

� Daejeon Area� KAERI(HANARO)� Fuel Fabrication Facility (KNF)

Status of Nuclear Plants in KoreaStatus of Nuclear Plants in Korea

3

HANARO (High-flux Advanced Neutron Application ReactOr)

Panoramic views of HANAROHANARO Building

Reactor Hall

HANARO means, in Korean, “uniqueness”.

4

IMEF

HANARO

RI PF

CNRF

General Features of HANARO

Type : Open-tank-in-PoolMaximum Thermal Power : 30MWthMax. thermal neutron flux : 4.4x1014 n/cm2·secMax. fast neutron flux : 2.1x1014 n/cm2·secCoolant : Light WaterReflector : Heavy waterFuel Materials : U3Si, 19.75% enrichedAbsorber : HafniumReactor Building : Confinement

HANARO has two kind of fuel assemblies.One is hexagonal type, 36 fuel elements, the other is cylindrical type, 18 fuel elements.

5

Experimental Facilities in HANAROExperimental Facilities in HANARO

Horizontal Beam Ports

Verti

cal T

est H

oles

InstalledST1 : PGNAA, RSI Test Station, PNSST2 : High Resolution Powder Diffractometer

Four Circle DiffractometerST3 : Neutron Reflectometer-VerticalNR : Neutron Radiography FacilityCN : Small Angle Neutron SpectrometerIR : BNCT & Dynamic Radiography

InstalledIR,CT : Capsule Irradiation & RI ProductionOR : Capsule Irradiation & RI ProductionIP, LH : RI ProductionHTS : Hydraulic Transfer System

for RI ProductionPTS : Pneumatic Transfer System

for Neutron activation AnalysisNTD : Neutron Transmutation

Doping of SiliconUnder-developmentIR : Fuel Test Loop by 2008CNS : Cold Neutron Research Facility by 2010

Under-developmentST3 : Neutron Reflectometer-Horizonal

High Intensity Powder DiffractometerST4 : Triple Axis Spectrometer (thermal)

� Multi-purpose research reactor; 32 vertical holes & 7 horizontal beam ports

ORIP PTS

Plan view of HANAROPlan view of HANARO

PTS #3PTS #2

PTS #1

6

Fields of Utilization in HANAROFields of Utilization in HANARO

� Fuel/Material Irradiation Tests� Capsules � Fuel Test Loop

� Neutron Beam Applications� Scattering & Diffraction� Neutron Radiography� Ex-core Neutron Irradiation Facility

(BNCT, Dynamic NR)

� RI Production� Neutron Activation Analysis� Neutron Transmutation Doping of Semiconductor

The HANARO has been operated since its first criticality in February 1995, and is now successfully utilized in many areas.

7

8888

Irradiation Facilities in HANARO

� Reactor Operation� 24-day Op. + 11-day SD

� Irradiation Facilities� Rabbit Irradiation System� Capsule Irradiation System • Temp. Control System• Supporting System (Robot Arm)• In-Chimney Bracket• Capsule Cutting System• Cask for Transfer to IMEF� Fuel Test Loop (FTL) System

9999

Irradiation Facilities in HANARONon-Instrumented CapsuleRabbits (HTS, IP)

Al

(L60 / Dia. 24mm)

Instrumented Capsules

(CT/IR )

(OR/IP )

(L870 / Dia. 60mm)

(L870 / Dia. 56mm)

(L870 / Dia. 60mm)

VHC-M2Fuel Test Loop

Fuel Test Loop (FTL)Fuel Test Loop (FTL)

In-Pile Section►►►► Design Pressure : 17.5 MPa►►►► Design Temperature : 350 ℃℃℃℃

� Installation of OPS : Feb. 2008 � Commissioning test : Nov. 2008.� Applications� Integral Fuel Irradiation Tests(Fuel Qualification, High Burn-up Fuel)� Water Chemistry and Corrosion Tests � Non-fissile Tests of Pressure Tube Material

Out-Pile System10

� 2 holes: NTD1, NTD2� Irradiation of 5" ingot and 6" ingot

� 5" D & 60cm L Ingots (NTD2)� High Uniformity & Accuracy to Target� ~ 10 ton Service in 2006� ~ 13 ton Service in 2007

� 6 & 8" Ingot Irradiation Device (NTD1)� 6" in Service from 2007� 8" Under Testing in 2008

� Flexibility for Future Market� 5, 6, 8 inch Irradiation Capability

Neutron Transmutation DopingNeutron Transmutation Doping

11

IMEF (Irradiated Material Examination Facility)PIEF (Post-Irradiation Examination Facility)

IMEF (Irradiated Material Examination Facility)PIEF (Post-Irradiation Examination Facility)

IMEF : 8 concrete & 1 lead hot cells, 1 pool

Layout of IMEF

PIEF : 4 concrete & 2 lead hot cells, 1 pool - Pool examination on post-irradiated fuel assembly- Non-destructive tests & Destructive Tests- Experiments in relation to reactor safety andfuel design and fabrication improvement

IMEF is to provide PIE services for the irradiated fuels and materials in the HANARO. PIEF is to provide PIE services for the irradiated fuels from commercial reactors.

12

13131313

HANARO Irradiation Capsule

� R & D of Instrumented Capsule (1995~ ) � Irradiation Tests for Users� Research Institute, Industry, University, International Projects� 7,000 specimens : Nuclear, Advanced/Basic Researches� Advances in Irradiation Capsule Technology

Instrumented Capsule for Material

� Design Characteristics�Length : ∼6m ( Main : 60mm D x 870mm H)�5 Stages Independent Temp. Control�Max. Temp. Control : Up to 500℃�Instrumentation : 14 T/C, 5 Heater, 4 F/M, He Gas�Specimen : Tensile, Charpy, CT, SP,

Tube, hardness, PCVN, MBE, TEM, etc.

� Applications�Material Tests- Reactor Pressure Vessel Materials- Reactor Core Materials- Nuclear Fuel Assembly Materials�Safety and Integrity-Related Tests�Study on Extension of Reactor Lifetime�Industry Application Material Tests�Fundamental Researches

Charpy R-CT

Tube 경도/인장

5th stage

Hardness/Tensile

14

Instrumented Capsule for Nuclear Fuel

� Design Characteristics�Length : ∼5m ( Main : 56mm D x 730mm H)�3 Mini-Elements Fuel Rod�Environment Control with Mixed Gas(He/Ne)

� Applications�Fuel Pellet Irradiation Test- Advanced PWR Fuel�Fuel Design Data Production- Surface Temperature of Fuel Pellet- Internal Pressure of Element Fuel Rod- Deformation of Fuel Pellet�Fundamental Researches

15

Creep & Fatigue Test Capsules

� Design Characteristics�Loading by Bellows System of He Gas�Length : ∼6m ( Main : 60mm D x 997mm H)�Irradiation specimen : 1, 2, 4�Instrumentation : 8 TC, 2 heaters, 1 LVDT�Creep test temperature : Max. 600 ℃�Irradiation condition : 1 atm ~ 30 torr (He)

� Applications�Creep and Fatigue behaviors�Extension of Reactor Lifetime�Fundamental Researches

16

IP

CT

17171717

Test Holes in HANARO

LocationHole Inside

Dia.Dia.Dia.Dia.

(cm)

Neutron FluxNeutron FluxNeutron FluxNeutron Flux (n/cm2 . sec)

RemarksRemarksRemarksRemarks

NameNameNameName No.No.No.No.Fast NeutronFast NeutronFast NeutronFast Neutron

(E>0.82 Mev)Thermal NeutronThermal NeutronThermal NeutronThermal Neutron

(<0.625 ev)

CoreCoreCoreCore

CTCTCTCT

IRIRIRIR

OROROROR

124

7.447.446.00

1.95 x 101.95 x 101.95 x 101.95 x 1014141414

1.80 x 101.80 x 101.80 x 101.80 x 1014141414

2.01 x 102.01 x 102.01 x 102.01 x 1013131313

4.30 x 1014

3.83 x 1014

3.30 x 1014

Fuel/material Fuel/material Fuel/material Fuel/material

isotope production

ReflectorReflectorReflectorReflector

LHHTSHTSHTSHTS

IPIPIPIP

1117

15.010.06.0

7.35 x 1011

1.72 x 101.72 x 101.72 x 101.72 x 1011111111

1.43 x 101.43 x 101.43 x 101.43 x 109999 ----

2.17 x 102.17 x 102.17 x 102.17 x 1012121212

9.72 x 1013

8.82 x 1013

2.16 x 1013 -1.81 x 1014

Fuel/materialFuel/materialFuel/materialFuel/material

Isotope, semi-

conductors

18181818

Capsule Design and Analysis

� Basic Design of Irradiation Capsule� Specimen Configuration� Instrumentation Design (H/V Control) � Nuclear Properties (MCNP,VENTURE)� Reactor Reactivity Analysis� Gamma Heatings & Neutron Flux� Thermal / Structural Analysis� GENGTC / ANSYS� Gap / Final Design of Parts� Post Irradiation Analysis� Fluence Monitor Analysis (SAND II)� DPA Analysis (SPECTOR) � Specimen Activation (ORIGEN2)

Thermocouple

Heater1

5

3

4

2

Guide Tube

1

5

3

4

2

Main Body

Fluence Monitor

ProtectionTube

19191919

� Fast /Thermal Neutron Fluence � Fast N. Dosimeter Wires : Fe, Ni, Ti� Thermal N. D. Wires : Ag, Nb, Co� MCNP & SANDII Comparison � ±15% Error Range & SANDII

� Improvement of F/M Analysis� FWT Tube against Water Corrosion� Detailed Spectrum & Reaction� High Purity Wires (Fe,Ni,Ti) and Al � Devices for High Activity Wires

Neutron Fluence Analysis

ThermalThermalThermalThermalFastFastFastFast

FusionFusionFusionFusion

20202020

Precise Temp. Control Capsule

----

100100100100

200200200200

300300300300

400400400400

500500500500

9:00:52 AM9:00:52 AM9:00:52 AM9:00:52 AM

03-08-1503-08-1503-08-1503-08-15

12:20:52 PM12:20:52 PM12:20:52 PM12:20:52 PM

03-08-1503-08-1503-08-1503-08-15

3:40:52 PM3:40:52 PM3:40:52 PM3:40:52 PM

03-08-1503-08-1503-08-1503-08-15

7:00:52 PM7:00:52 PM7:00:52 PM7:00:52 PM

03-08-1503-08-1503-08-1503-08-15

10:20:52 PM10:20:52 PM10:20:52 PM10:20:52 PM

03-08-1503-08-1503-08-1503-08-15

Tim eTim eTim eTim e

Temperature (C)

Temperature (C)

Temperature (C)

Temperature (C)

Control Rod (cm)

Control Rod (cm)

Control Rod (cm)

Control Rod (cm)

----

4444

8888

12121212

16161616

20202020

24242424

28282828

32323232

Reac

tor

Powe

r (MW)

MW)

MW)

MW)

원자로출력 : 24M W, 27-1주기

조사 기간 : '03.08.15~08.21

조 사 공 : CT

300oCSpecimen Temperature

Control Rod24MW

02M-02K

Constant Temp. controlled by Reactor Power/Heater/Gas

Constant Temp.controlled by Heater/Gas

Heat up by Heater/Gas

HANARO

----

100100100100

200200200200

300300300300

400400400400

500500500500

9:00:52 AM9:00:52 AM9:00:52 AM9:00:52 AM

03-08-1503-08-1503-08-1503-08-15

12:20:52 PM12:20:52 PM12:20:52 PM12:20:52 PM

03-08-1503-08-1503-08-1503-08-15

3:40:52 PM3:40:52 PM3:40:52 PM3:40:52 PM

03-08-1503-08-1503-08-1503-08-15

7:00:52 PM7:00:52 PM7:00:52 PM7:00:52 PM

03-08-1503-08-1503-08-1503-08-15

10:20:52 PM10:20:52 PM10:20:52 PM10:20:52 PM

03-08-1503-08-1503-08-1503-08-15

Tim eTim eTim eTim e

Temperature (C)

Temperature (C)

Temperature (C)

Temperature (C)

Control Rod (cm)

Control Rod (cm)

Control Rod (cm)

Control Rod (cm)

----

4444

8888

12121212

16161616

20202020

24242424

28282828

32323232

Reac

tor

Powe

r (MW)

MW)

MW)

MW)

원자로출력 : 24M W, 27-1주기

조사 기간 : '03.08.15~08.21

조 사 공 : CT

300oCSpecimen Temperature

Control Rod24MW

02M-02K

Constant Temp. controlled by Reactor Power/Heater/Gas

Constant Temp.controlled by Heater/GasConstant Temp.

controlled by Heater/GasHeat up by Heater/Gas

HANARO

03M-06U

� Specimen Temp. Control� Temp. Control irresp. of Reactor� Valuable for Researches on � Mechanism of Irradiation Damage

� Out-Pile Test� 03M-06U Capsule� 290oC before Reactor Operation ( by Vacuum/Heater Control )

� In-Pile Test (03M-06U)�CT in HANARO at 30MW �42days irradiation

/ 30MW

21212121

Neutron Fluence Control Capsule

� Needs for Capsule � 24days’ HANARO Operation� Needs for Short Time Irradiation � Needs for Neutron Fluence Control during Rx. Operation

� Out-pile Test� 05M-06K Capsule� Design & Fabrication Technologies� Out-pile Performance Tests� Integrity Analysis in HANARO

22222222

OR / IP Irradiation Capsule

� Needs for Capsule� Need for Different Neutron FluxDifferent Neutron Flux� Different Flux in CT>IR>OR>IP

� Out-Pile Test � 07M-09K Capsule� Nuclear & Thermal Designs � Reactor Safety Analysis(Seismic Safety, Pressure Drop)

� In-Pile Test� 07M-21K in OR5 for 24.6 days (I-NERI Projects (VHTR))

03M-06U

IRIRIRIR

OR 5OR 5OR 5OR 5

IP IP IP IP

CTCTCTCT

23232323

� Irradiation up to 500℃℃℃℃� Standard Capsule Design (Al Thermal Media)

- 522℃℃℃℃ for 4h Out-pile Test with 07M-09K Capsule� Application : VHTR Materials (Cr-Mo-W Alloys)

� Irradiation up to 1000 ℃℃℃℃

� Instrumentations (Inconel Sheathed T/C & Heaters)� Thermal Media for High Temperature

- Candidates : Mo, Nb, Zr, Fe, Ti � Double Layered Structure� Application : VHTR, FBR, Fusion Materials

High Temp. Irradiation

Al105Al105Al105Al105

0000

HT HT HT HT

MatrixMatrixMatrixMatrix

Road Map for HANARO Irradiation Program

Installation of FTL(’08) Irradiation of advanced nuclear fuel for PWR(’13) & PIE

High-performance (Ultra-high burnup) nuclear fuel for PWR(’17) &PIE

Irradiation of Advanced Nuclear Fuel and materials by using FTL & PIE

Irradiation of nuclear fuel & materials by using Capsule & PIE

Irradiation devices development, irradiation test & PIE- VHTR (I-NERI) : TRISO-coated fuel & assembly, High temp. materials- Fusion (ITER & KSTAR) : material (blanket & core), fundamental research- SFR : fuel, cladding materials and structural materials

2015 20202010

Fuel & structural materials of NPPsU-Mo & U-Zr metallic fuels (research reactor & SMART)

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Thank You !