Advanced SFR Concept Design Studies at KAERI

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Wesley Bridges
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1 Advanced SFR Concept Design Studies at KAERI International Conference on Fast Reactors and Related Fuel Cycles (FR09), Kyoto, Japan 7 December 2009 Yeong-il KIM and Dohee HAHN 1 FR09, Kyoto, 7-11 December 2009

2 Outline I II III IV Introduction Development of advanced SFR concept R&D Activities Summary 2 FR09, Kyoto, 7-11 December 2009

3 I Introduction 3 FR09, Kyoto, 7-11 December 2009

Long-term Plan for SFR and Pyroprocess 07 11 16 20 26 28 Viability &

Performance Test Standard Design Detailed Design Demonstration Plant

4 Long-term Plan for SFR and Pyroprocess Viability & Economics Licensibility Construction SFR Advanced Design Concept System Performance Test Standard Design Detailed Design Demonstration Plant Licensing Technology Development Metal Fuel Irradiation Test Pyroprocess Mock-up Facility (Nat. U, 10t/Yr) Eng.-scale Facility (10t/Yr) Prototype Facility (100t/Yr) Prototype Facility Operation 4 FR09, Kyoto, 7-11 December 2009

5 Technology Goals and R&D Activities Technology Goals of Gen IV Reactor System Sustainability Proliferation Resistance Economics Safety Burner CR: Breakeven CR: 1.0 No Blanket FOAK - 4 /kwh - 2,000 $/kwe CDF < 10-6 /R Y Grace time of more than three days - Size optimization R & D - Burner core development - Breakeven core development - Development of MA bearing metal fuel - Core and structure optimization - S-CO 2 Brayton cycle system - Integrated components PDRC concept validation Passive safety Validation of analysis codes Inherent safety - High temp LBB Core concept without blankets Construction cost ~ $2,300/kWe PDRC Concept Analysis codes Conceptual Design of Advanced SFR 5 FR09, Kyoto, 7-11 December 2009

6 II Development of Advanced SFR Design Concept 6 FR09, Kyoto, 7-11 December 2009

7 KALIMER-600 System Key Design Features 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% 2-D Seismic Bearing 63 cm 400 cm Heat transport system of KALIMER cm 120 cm 150 cm 95 cm 210 cm 7 FR09, Kyoto, 7-11 December 2009

Design Studies of Advanced Concept TRU Burner Core Break- Even Core 2007 2008 2009 Enrichment Split Single Enrichment Power Selection Enrichment Split Single Enrichment Power Selection Performance

8 Design Studies of Advanced Concept TRU Burner Core Break- Even Core Enrichment Split Single Enrichment Power Selection Enrichment Split Single Enrichment Power Selection Performance Single Safety Enrichment Economy 600MWe Burnup Capability Economy Safety Economy Safety Enrichment Split 1,200MWe Single Enrichment 600MWe Burner Enrichment Split 1,200MWe Breakeven Core Fuel System Gen IV Advanced Core Concept Selection Decision to Apply Clad Alloy 1 st Candidates Barrier 1 st Candidates Tensile/Creep Prop. 2 nd Candidates Barrier Performance Test 2 nd Candidates High Temp. Creep Tensile/Impact Metal Fuel/Barrier Interaction Clad Alloy Final Candidates Advanced Barrier Candidates High Temp. Mechanical Strength Clad Manufacture Fuel Design Prevent Eutectic Melting Practicability Gen IV SFR Advanced Concept S/G Tube System 2-Loop 3-Loop Single Wall Double Wall S-CO 2 Brayton Cycle System Concept 2-Loop Prevent SWR Viability, Fabricability and Economy Pump /SG Separate Integral Double Wall Integral Rotating Plug/Inspection Component Configuration Component Evaluation Straight Helical Canned Motor Pump Large Scale, Arrangement Economy Efficiency Reactor Internals and Interfaces Visualization Sensor Setting Operating Parameters System/ Component Design Sensing Accuracy 0.8mm S-CO 2 Brayton Cycle Economy, Safety Controllability 8 FR09, Kyoto, 7-11 December 2009

9 Advanced Concept (1200MWe) Key Design Features 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% Conceptual NSSS Layout Heat transport system of advanced pool type SFR 9 FR09, Kyoto, 7-11 December 2009

10 Breakeven Core Design Core Design Parameters KALIMER-600 Advanced SFR Power (MWe) 600 1,200 Core height (cm) No. of fuel regions 3 2 Fuel rod outer diameter (mm) Clad thickness (IC/MC/OC, mm) 1.02/0.72/ Cycle length (EFPM) 18 Charged TRU enrichment (IC/MC/OC, wt%) / - /16.79 Average discharge burnup (MWD/kgHM) Fissile Pu Loading (ton/gwe) Sodium void reactivity ($) Axial Moderator Layer (cm) 14.9cm Graphite None 10 FR09, Kyoto, 7-11 December 2009 Inner Core 318 Outer Core 306 Primary CR 24 Secondary CR 12 Reflector 96 B 4 C Shield 102 IVS 222 Radial Shield 120 Empty CR 1 Total 1201

11 TRU Burner Core Design 11 FR09, Kyoto, 7-11 December 2009 Core Design Parameters Inner Core 54 Middle Core 72 Outer Core 198 Primary CR 18 Secondary CR 7 Reflector 72 B 4 C Shield 78 IVS 84 Radial Shield 90 Total 673 TRU Burner Power (MWe) 600 Core height (cm) 89 No. of fuel regions 3 Fuel rod outer diameter (mm) 7.0 Clad thickness (IC/MC/OC, mm) 1.01/0.93/0.73 Cycle length (EFPD) 332 Charged TRU enrichment (wt%) 30.0 Conversion ratio (fissile/tru) 0.74/0.57 Burnup reactivity swing (pcm) 3,496 Average discharge burnup (MWD/kgHM) Sodium void reactivity (EOEC, $) 7.50

12 Heat Transport System Design 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) Heat transport system of advanced pool type SFR 12 FR09, Kyoto, 7-11 December 2009

PDRC Design Features System Design Features Elimination of active

components AHX, DHX, expansion vessel and piping Design Improvement

with sodium Enhancement of local convection by DHX skirt Normal

13 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 Normal operation PHTS pump shutdown PDRC design concept 13 FR09, Kyoto, 7-11 December 2009

14 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 - Thickness 0.05m 14 FR09, Kyoto, 7-11 December 2009 Reactor Vessel - SS316 - OD 14.5m - Length 18.0m

15 III R&D Activities 15 FR09, Kyoto, 7-11 December 2009

$Test scope Confirmation of basic design issues Verification of heat removal capability by transient mode Prevention of sodium solidification Countermeasures for a postulated RV fracture Dynamic$

16 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 16 FR09, Kyoto, 7-11 December 2009

S-CO 2 Brayton Cycle System Objectives Enhancement of plant economics Elimination of SWR Status Establishment of system design concept coupled to advanced SFR Development of MMS-LMR code for

52 kg/s Na CO 2 185.3 1 atm 19.98 545.0 353.8 189.2 19.94 COM P. #2 19.98 202.7 Eff.=87.5% 7.53 IHTS pump 183.7 364.4 4.3 X 2 MW 329.66 [MWt] 19.98 3044.5[M W t] CORE 390.0 15445.9 kg/s 389.

17 S-CO 2 Brayton Cycle System 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 RHRS Na 9.2[M Wt] [MWt] [MWe] kg/s Na CO atm COM P. # Eff.=87.5% 7.53 IHTS pump X 2 MW [MWt] [M W t] CORE kg/s Pum p 13.5 MW kg/s X 2 REA CT OR V ESSEL [C] [M Pa] Na-CO 2 HX Cycle Eff. = 42.8 % Plant Eff.(Gross) =41.2 % Plant Eff.(Net) = 40.3 % T URBINE Eff.=93.4% [M Wt] X kg/s HTR Ef.=91.7% LT R Ef.=94.6% [MWt] COM P. # Eff.=89.1% COOLER [MWt] S-CO 2 Brayton cycle for SFR 71.0% 29.0% Air Foil PCHE Performance of air foil type PCHE 17 FR09, Kyoto, 7-11 December 2009

Na-CO 2 Interaction Test Objective Investigation of Na-CO 2 interaction and its kinetic features Surface reaction tests with wellmanipulated conditions Confirmation of temperature dependency on

18 Na-CO 2 Interaction Test Objective Investigation of Na-CO 2 interaction and its kinetic features Surface reaction tests with wellmanipulated conditions Confirmation of temperature dependency on reaction mechanism Estimation of kinetic parameters Na-CO 2 reaction test apparatus Sodium ignition (T Na = 600 o C) Future Work Validation of reaction models t = 0sec t = 1sec 18 FR09, Kyoto, 7-11 December 2009 t = 5sec t = 10sec

Under-sodium Viewing Technology Objective Development of ultrasonic waveguide sensor for

and feasibility test in water 2mm resolution Fabrication of double rotating scanner w/

Ultrasonic Waveguide Sensor module Future Work Setup of mockup facility Performance test

19 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) Ultrasonic Waveguide Sensor module Future Work Setup of mockup facility Performance test in water and sodium Double rotating scanner Under-Sodium MultiVIEW 19 FR09, Kyoto, 7-11 December 2009

alloys Advanced fuel casting system Induction furnace Gravity casting Future Work Fuel irradiation

20 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 20 FR09, Kyoto, 7-11 December 2009

21 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-1)*100 of k-effective C/E of sodium void reactivity worth 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 Evaluated nuclear data file C/E k-effective BFS-75-1 BFS-55-1 Measurement uncertainty (1σ) BFS-75-1 : 1.3% BFS-55-1 : 7.1% ENDF/B-VII.0 JEFF-3.1 JENDL-3.3 ENDF/B-VI.6 Evaluated nuclear data file Sodium void reactivity 21 FR09, Kyoto, 7-11 December 2009

22 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 Primary Stress Limits Thermal Analysis Elastic/Inelastic Structural Analysis Generation of Input Data for SIE ASME-NH Code Run SIE ASME-NH Code Inelastic Strain Limits Results of Structural Integrity Evaluations Material Data Base Creep-Fatigue Limits Procedures for ETD by SIE ASME-NH 22 FR09, Kyoto, 7-11 December 2009

23 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 Temperature, o C Instrumented assembly outlet Temp. Exp. : SHRT 17 MARS-LMR : SHRT 17 Exp. : SHRT 45 MARS-LMR : SHRT 45 Exp. : SHRT 39 MARS-LMR : SHRT Time, s Simulation of SHRT tests Future Work Simulation of KAERI Experiments Accident analysis of Demonstration Reactor of Korea Benchmark calculation of Phenix EOL test 23 FR09, Kyoto, 7-11 December 2009

24 Sodium Technology Double wall tube test Leak detection test Sodium velocity measurement Low and local velocity measuring sensors Analysis of SWR Phenomena Wastage characteristics Acoustic leak detection Performance test of SWR detection system 24 FR09, Kyoto, 7-11 December 2009

25 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 25 FR09, Kyoto, 7-11 December 2009

Experimental Facilities and Plan for a Prototype SFR

Experimental Facilities and Plan for a Prototype SFR IAEA Technical Meeting on Existing and Proposed Experimental Facilities for Fast Neutron Systems 10-12 June 2013 Jinwook Chang Outline I II III STELLA