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1 FR09, Kyoto, 7-11 December 2009
Advanced SFR Concept Design Studies at KAERI
Yeong-il KIM and Dohee HAHN
International Conference on Fast Reactors and Related Fuel Cycles (FR09), Kyoto, Japan
7 December 2009
2 FR09, Kyoto, 7-11 December 2009
Outline
IntroductionIDevelopment of advanced SFR conceptIIR&D ActivitiesIIISummaryIV
4 FR09, Kyoto, 7-11 December 2009
SFRSystem
Performance Test
Standard Design
Detailed Design
Demonstration Plant
Mock-up Facility
(Nat. U, 10t/Yr)Eng.-scaleFacility(10t/Yr)
PrototypeFacility(100t/Yr)
PrototypeFacility
Operation
Pyro-process
Advanced Design Concept
‘07 ’11 ’16 ’20 ’28’26
Licensing Technology Development Metal Fuel Irradiation Test
Long-term Plan for SFR and Pyroprocess
Viability &
Economics
Licensibility Construction
5 FR09, Kyoto, 7-11 December 2009
Technology Goals and R&D Activities
Conceptual Design of Advanced SFR
Technology Goals of Gen IV Reactor SystemSustainability Proliferation
Resistance
Core concept without blankets
- Burner core development- Breakeven core development- Development of MA bearing metal fuel
� No Blanket
R&D
� Burner CR: 0.5-0.8
� Breakeven CR: 1.0
Safety� CDF < 10-6/R·Y� Grace time of more than three days
Validation of analysis codes
⇒Inherent safety
Analysis codes
PDRC concept validation
⇒Passive safety
PDRC Concept
Economics
� FOAK- 4 ¢/kWh- 2,000 $/kWe
- Size optimization - Core and structure optimization
- S-CO2 Brayton cycle system- Integrated components
- High temp LBB
Construction cost ~ $2,300/kWe
7 FR09, Kyoto, 7-11 December 2009
KALIMER-600 System
� 600MWe, Pool-type Reactor� Fuel : U-TRU-Zr� Core I/O Temp : 390/545℃℃℃℃� DHR System : PDRC� 2-loop IHTS/SGS� Net Efficiency : 39.4%
400 cm
63 cm
120 cm
95 cm 210 cm
120 cm150 cm
2-D Seismic
Bearing
Key Design FeaturesKey Design Features
Heat transport system of KALIMER-600
8 FR09, Kyoto, 7-11 December 2009
Design Studies of Advanced Concept
Clad Alloy1st Candidates
Barrier1st Candidates
S/G Tube
TRUBurnerCore
Break-EvenCore
Performance
Safety
High Temp. Mechanical Strength
Core
System
FuelSelection
Decision to Apply
2007 2008 2009
Enrichment Split
Single Enrichment
Power Selection
SingleEnrichment
600MWeEconomy
Burnup Capability
Enrichment Split
Single Enrichment
Power Selection 1,200MWe
Gen IVAdvanced Core
Concept
Single Enrichment600MWe Burner
Enrichment Split1,200MWe Breakeven
Clad AlloyFinal Candidates
Advanced BarrierCandidates
Tensile/Creep Prop.
2nd Candidates
2nd Candidates
Clad Manufacture
Fuel Design
Prevent Eutectic Melting Practicability
Prevent SWR
Viability, Fabricability and Economy
Economy
Efficiency
Single Wall
Double WallStraight
Helical
DoubleWall
System/Component
Design
System 2-Loop
3-Loop2-Loop
Separate
Integral
Canned Motor Pump
Large Scale, ArrangementPump/SG
Reactor Internals and Interfaces
Sensing Accuracy 0.8mm
Integral Rotating Plug/Inspection
Visualization Sensor
Gen IV SFRAdvancedConcept
Economy, Safety
ControllabilityS-CO
2Brayton Cycle
System ConceptComponent
ConfigurationComponentEvaluation
Setting OperatingParameters
S-CO2
Brayton Cycle
Economy
Safety
Economy
Safety
EnrichmentSplit
Barrier Performance Test
High Temp. Creep
Tensile/Impact
Metal Fuel/Barrier
Interaction
9 FR09, Kyoto, 7-11 December 2009
Advanced Concept (1200MWe)
� 1200MWe, Pool-type Reactor� Fuel : U-TRU-Zr metal� Core I/O Temp : 390/545℃℃℃℃� DHR System : PDRC� 2-loop IHTS/SGS� Net Efficiency : 39.4%
Key Design FeaturesKey Design Features
Heat transport system of advanced pool type SFRConceptual NSSS Layout
10 FR09, Kyoto, 7-11 December 2009
Breakeven Core Design
Core Design Parameters KALIMER-600 Advanced SFRPower (MWe) 600 1,200Core height (cm) 94 80No. of fuel regions 3 2Fuel rod outer diameter (mm) 9.0 8.7Clad thickness (IC/MC/OC, mm) 1.02/0.72/0.59 0.6Cycle length (EFPM) 18Charged TRU enrichment (IC/MC/OC, wt%) 14.94 13.16/ - /16.79Average discharge burnup (MWD/kgHM) 80.4 100.1Fissile Pu Loading (ton/GWe) 6.23 5.07Sodium void reactivity ($) 7.51 7.25Axial Moderator Layer (cm) 14.9cm Graphite None
Total
Inner Core 318 Outer Core 306Primary CR 24Secondary CR 12Reflector 96B4C Shield 102IVS 222Radial Shield 120Empty CR 1
1201
11 FR09, Kyoto, 7-11 December 2009
TRU Burner Core DesignInner Core 54Middle Core 72Outer Core 198Primary CR 18Secondary CR 7Reflector 72B4C Shield 78IVS 84Radial Shield 90Total 673
Core Design Parameters TRU BurnerPower (MWe) 600Core height (cm) 89No. of fuel regions 3Fuel rod outer diameter (mm) 7.0Clad thickness (IC/MC/OC, mm) 1.01/0.93/0.73Cycle length (EFPD) 332Charged TRU enrichment (wt%) 30.0 Conversion ratio (fissile/TRU) 0.74/0.57Burnup reactivity swing (pcm) 3,496Average discharge burnup (MWD/kgHM) 127.9Sodium void reactivity (EOEC, $) 7.50
12 FR09, Kyoto, 7-11 December 2009
Heat Transport System Design
Heat transport system of advanced pool type SFR
� Improvement of safety and economics from KALIMER-600�Consideration of Economics
– Reduction of construction costs by increasing IHTS capacity– 600MWe/Loop�Safety Improvement
– Elimination of sodium-water reaction by Double wall tube steam generator– Secure redundancy and diversity by adopting• Passive RHRS(PDRC)• Active RHRS(IRACS)
13 FR09, Kyoto, 7-11 December 2009
PDRC Design Features�System Design Features
– Elimination of active components– Operation by natural circulation– No operator action– Major components• AHX, DHX, expansion vessel and piping
�Design Improvement– Prevention of sodium freezing in PDRC loop• Partial contact of DHX with sodium• Enhancement of local convection by DHX skirt
PDRC design concept
Normal Normal operationoperation
PHTS pump PHTS pump shutdownshutdown
14 FR09, Kyoto, 7-11 December 2009
Mechanical Structure System�Cost competitive NSSS
• Increasing the reactor capacity • Minimizing number of loops• Simplifying systems & components• New ISI, LBB�Structural Design
– Reactor vessel size minimization– 2 loop layouts with large size equipments– Simplified IHTS piping with large piping diameters (135m/loop)– Integrated components (ISI)– LBB on RV & IHTS Piping�Future Work
– Structural design evaluation Conceptual NSSS Design
Reactor VesselReactor VesselReactor VesselReactor Vessel
- SS316
- OD 14.5m
- Length 18.0m
- Thickness 0.05m
16 FR09, Kyoto, 7-11 December 2009
PDRC Experiment�Objectives
– Assessment of initial & long term cooling capability by natural circulation– Verification of design concept– Establishment of database for validating system analysis code
�Test scope– Confirmation of basic design issues• Verification of heat removal capability by transient mode• Prevention of sodium solidification• Countermeasures for a postulated RV fracture
– Dynamic simulation of natural circulation cool-down during key design basis events
Layout of Experimental Facility
17 FR09, Kyoto, 7-11 December 2009
S-CO2 Brayton Cycle System1971.57 [MWt] 16147.52 kg/s
394.27.60
Na 185.31 atm 19.98545.0 189.2
19.98 202.77.53
RHRS
183.7364.4
9.2[MWt]
329.66 [MWt] 19.98389.6
3044.5[MWt]
31.25 84.81 91.177.40 20.00 7.46
390.0
333.90 [MWt]
15445.9 kg/s71.0%29.0%
13.5 MWPump
TURBINEEff.=93.4% HTR
Ef.=91.7%
CORE
REACTORVESSEL
COMP. #1Eff.=89.1%
COMP. #2Eff.=87.5%
COOLERCycle Eff. = 42.8 %Plant Eff.(Gross) =41.2 %Plant Eff.(Net) = 40.3 %
CO2
IHTS pump
Na-CO 2 HX
353.819.94
508.019.74
1528.7 [MWt] X 2
1751.31 [MWt]
4.3 X 2 MW
7400.2 kg/s X 2Na
1256.22 [MWe]
[C][MPa]
LTREf.=94.6%
0.1094526.0
0.1014364.0
0.16230.0
0.10145.0
26140.8 kg/s
1971.57 [MWt] 16147.52 kg/s
394.27.60
Na 185.31 atm 19.98545.0 189.2
19.98 202.77.53
RHRS
183.7364.4
9.2[MWt]
329.66 [MWt] 19.98389.6
3044.5[MWt]
31.25 84.81 91.177.40 20.00 7.46
390.0
333.90 [MWt]
15445.9 kg/s71.0%29.0%
13.5 MWPump
TURBINEEff.=93.4% HTR
Ef.=91.7%
CORE
REACTORVESSEL
COMP. #1Eff.=89.1%
COMP. #2Eff.=87.5%
COOLERCycle Eff. = 42.8 %Plant Eff.(Gross) =41.2 %Plant Eff.(Net) = 40.3 %
CO2CO2
IHTS pump
Na-CO 2 HX
353.819.94
508.019.7419.74
1528.7 [MWt] X 2
1751.31 [MWt]
4.3 X 2 MW
7400.2 kg/s X 2Na
1256.22 [MWe]
[C][MPa][C]
[MPa]
LTREf.=94.6%
0.1094526.00.1094526.0
0.1014364.00.1014364.0
0.16230.00.16230.0
0.10145.00.10145.0
26140.8 kg/s
S-CO2 Brayton cycle for SFR
Air Foil PCHE
Performance of air foil type PCHE
�Objectives– Enhancement of plant economics– Elimination of SWR
�Status– Establishment of system design concept coupled to advanced SFR– Development of MMS-LMR code for evaluation of system control logic– Performance test of air foil type PCHE
�Future Work– Evaluation of system transients
18 FR09, Kyoto, 7-11 December 2009
Na-CO2 Interaction Test�Objective
– Investigation of Na-CO2 interaction and its kinetic features
�Surface reaction tests with well-manipulated conditions– Confirmation of temperature dependency on reaction mechanism– Estimation of kinetic parameters
� Future Work– Validation of reaction models
t = 0sect = 0sec t = 1sect = 1sec
t = 5sect = 5sec t = 10sect = 10sec
t = 0sect = 0sec t = 1sect = 1sec
t = 5sect = 5sec t = 10sect = 10sec
Na-CO2 reaction test apparatusSodium ignition (TNa = 600oC)
19 FR09, Kyoto, 7-11 December 2009
Under-sodium Viewing Technology�Objective
– Development of ultrasonic waveguide sensor for under-sodium viewing
�Experimental facility– Manufacture of 10m long waveguide sensor module and feasibility test in water• 2mm resolution
– Fabrication of double rotating scanner w/ radiation beam steering function– Development of C-scan program (Under-Sodium MultiVIEW)
�Future Work– Setup of mockup facility– Performance test in water and sodium
Ultrasonic Waveguide Sensor module
Under-Sodium MultiVIEW
Double rotating scanner
20 FR09, Kyoto, 7-11 December 2009
Metal Fuel Technology�Metal Fuel
– Selected for the Advanced SFR– To meet requirements of Gen IV�Practicality
– Requires Radiation shielded environment– Fuel fabrication technology– FMS cladding alloys– Advanced fuel casting system
• Induction furnace• Gravity casting
�Future Work– Fuel irradiation test in HANARO
Fuel casting system
Creep Strain Rate of New Cladding Alloys
21 FR09, Kyoto, 7-11 December 2009
Validation of SFR Neutronics Code�Objectives
– Validation of reactor core analysis code (K-CORE) with critical experiments
�Status– Evaluation of BFS critical assemblies by using up-to-date nuclear data files, ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, JENDL-AC2008– Calculation results for the BFS-73-1, BFS-75-1, BFS-55-1
�Future Work– Sensitivity and Uncertainty evaluation code– Development of adjusted multi-group cross section library
C/E k-effective
Sodium void reactivity
ENDF/B-VII.0 JEFF-3.1 JENDL-3.3 ENDF/B-VI.6
-0.8-0.6-0.4-0.20.00.20.40.60.81.01.21.41.61.8
(C/E-
1)*10
0 of k
-effec
tive
Evaluated nuclear data file
BFS-73-1 BFS-75-1 BFS-55-1
Measurement uncertainty of k-effective = 0.15%∆k/k
ENDF/B-VII.0 JEFF-3.1 JENDL-3.3 ENDF/B-VI.6
0.82
0.84
0.86
0.88
0.90
0.92
0.94
0.96
0.98
1.00
1.02
1.04
C/E o
f sod
ium vo
id rea
ctivit
y wort
h
Evaluated nuclear data file
BFS-75-1 BFS-55-1
Measurement uncertainty (1σ) BFS-75-1 : 1.3% BFS-55-1 : 7.1%
22 FR09, Kyoto, 7-11 December 2009
Structural Integrity Evaluation�Objectives
– Development of SIE ASME-NH Computer Program Compliance to ASME-NH Rules for Elevated Temperature Design– Engineering Cost Reduction by Fast and Accurate Structural Integrity Evaluations
�Status– Complete SIE ASME-NH 1.0 Version with Design Material DB
–Easy user interface program �Future Work
– Update Design Material DB– Design Procedures for Inelastic Analysis Method
Procedures for ETD by SIE ASME-NH
Generation of Input Data for Generation of Input Data for Generation of Input Data for Generation of Input Data for
SIE ASMESIE ASMESIE ASMESIE ASME----NH CodeNH CodeNH CodeNH Code
Elastic/Inelastic Structural AnalysisThermal Analysis
Primary Stress LimitsPrimary Stress Limits Inelastic Strain LimitsInelastic Strain Limits Creep-Fatigue LimitsCreep-Fatigue Limits
Results of Structural Integrity Evaluations
RunRunRunRun
SIE ASMESIE ASMESIE ASMESIE ASME----NH CodeNH CodeNH CodeNH Code
Material Data Base
23 FR09, Kyoto, 7-11 December 2009
Safety Analysis Code�Objectives
– To have a flexible modeling capability and enhanced accuracy for the safety evaluation of a SFR
�Status– Simulation of SHRT tests for the validation of MARS-LMR code– Simulation of Natural Circulation Test of Phenix EOL tests for code evaluation– Analysis of accidents for KALIMER�Future Work
– Simulation of KAERI Experiments– Accident analysis of Demonstration Reactor of Korea
Simulation of SHRT tests
Benchmark calculation ofPhenix EOL test
0 200 400 600 800 1000
400
500
600
700
800
900
Temp
eratur
e, o C
Time, s
Instrumented assembly outlet Temp. Exp. : SHRT 17 MARS-LMR : SHRT 17 Exp. : SHRT 45 MARS-LMR : SHRT 45 Exp. : SHRT 39 MARS-LMR : SHRT 39
24 FR09, Kyoto, 7-11 December 2009
Sodium Technology
Double wall tube testLeak detection test
Analysis of SWR PhenomenaWastage characteristics
Sodium velocity measurementLow and local velocity measuring sensors
Acoustic leak detectionPerformance testof SWR detection system
25 FR09, Kyoto, 7-11 December 2009
Summary�Advanced SFR to satisfy the Gen IV technology goals
– sustainability, safety and reliability, economics, proliferation resistance, and physical protection
�Advanced concept design studies from KALIMER-600– Breakeven .vs. Burner– Heat transfer system– Mechanical Design
�Various R&D activities– To support the development of Advanced SFR concepts– PDRC Experiments– SCO2 cycle studies– Under-sodium viewing– Metal Fuel– Development and Validation of Analysis codes
• Neutronics, Structure integrity evaluation, Safety, Performance– Sodium technology