material irradiation at hanaro, korea - iaea na research reactor; 32 vertical holes & 7...
TRANSCRIPT
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)
24
25252525
Thank You !