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KO Programme on Liquid Metal Breeder Blankets
Dong Won LEEFusion Engineering Division, Korea Atomic Energy Research Institute (KAERI)
21th Jan., 2009SNU, Korea
Dong Won LEE
Fusion Engineering Development DivisionKorea Atomic Energy Research Institute (KAERI)
23rd Sep. 2010Madrid, Spain
International Workshop on Liquid Metal Breeder Blankets
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 1/26
Outline
1. Overview on fusion technology development in KO- Roadmap of nuclear fusion technology development- KO position on ITER TBM program
2. KO Activities for developing the liquid metal breeder blanket - Codes development and validation - Fabrication technology- Cooling technology- Liquid breeder technology - Tritium extraction technology
3. Gen-IV reactor development in KO- Overview of the GEN-IV reactor development in KO- SFR development plan and R&Ds- VHTR development plan and R&Ds
4. Conclusions
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 2/26
Development path to fusion plant in KO
1. Overview on fusion tech. development in KO
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 3/26
Fusion energy development roadmap
1. Overview on fusion tech. development in KO
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 4/26
KO position on ITER TBM program
Leadership (Partnership) [from TBM-PC-03]- KO is interested in the exploring partnerships with TBM concept leaders rather than being a
TBM concept leader. - KO will participate in both ceramic breeder and PbLi based blanket concepts.- Even though we will not take any leadership of KO TBM concept for Day-One, we would like to
have possibility of testing our TBM concept in the later phase
KO status for developing the TBMs- NFRI (National Fusion Research Institute)
has developed ceramic breeder blanket and operated KSTAR.- KAERI (Korea Atomic Energy Research Institute)
has developed PbLi(or Li) based breeder blanket and Gen.-IV reactors.
1. Overview on fusion tech. development in KO
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 5/26
1. Codes development and validation(1) Design and safety analysis- Based on the nuclear technologies (e.g. GEN-IV) of Very High Temperature Reactor System (VHTR) and
Sodium-Cooled Fast Reactor System (SFR), KO is developing an integrated design tool for fusion reactor.
2. KO Activities for liquid metal breeder blanket
Participating IAEA FENDEL 3.0
development
MARS-GCR
GAMMA
MARS-LMR
MARS-FR
TRITGO
MARS-T
MARS-FR
GAMMA-FR
For Coolant (He)
For Breeder (Li, PbLi)
For Tritium
Integration
System Codes Development
DevelopedV&V with Experiments (‘09~’10)
Developing in GCR
Developed in ORNL, Modified in GCR
DevelopingV&V with Experiments
Developing in SFR
Used for License integrating all developed MARS codes
For System Design & Safety Analysis based on MARS-FR
CFX EM moduleFor MHD
Separate Code Verification
On verifying with exp. Data
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 6/26
1. Codes development and validation(2) MHD analysis- CFX EM module has been being verified with the previous works
2. KO Activities for liquid metal breeder blanket
Selected benchmarking problemsComparison results for CFX EM
module with the experimental data
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 7/26
2. Fabrication technology (1) For joining FMS to FMS- HIP(hot isostatic pressing) and PHHT(post HIP heat treatment) conditions were developed and verified through the thermal fatigue test (1.0 MW/m2 for 1000 cycles, no failure)
Developed HIP & PHHT conditions Fabricated mockup & KoHLT-2 Tested mockup & measured temperature during the last 30 cycles
2. KO Activities for liquid metal breeder blanket
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 8/26
2. Fabrication technology (2) For joining Be to FMS- HIP(hot isostatic pressing) conditions were developed and one of them was verified through the thermal fatigue test - Interlayers (Ti/Cr/Cu and Cr/Cu) and Cu layers in FMS(or SS) were tried for Be joining- Mockup with Cr/Cu interlayer and explosive welded Cu layer survived up to 1000 cycles under 0.5 MW/m2 heat flux
Fabricated mockups & conditions KoHLT-1 Measured temperature during the last 50 cycles
UT & DT results after HHF test
SOFT-26 presentation [P3-114] by Y.I. Jung
SOFT-26 presentation [P2-120] by D.W. Lee
2. KO Activities for liquid metal breeder blanket
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 9/26
2. Fabrication technology (3) For joining W to FMS- HIP(hot isostatic pressing) conditions has been developed - The interlayers of Ti films were used to reduce the difference in thermal expansion of W and FMS- The interlayers of Cu films were used to form diffusion bonding between W and Cu
W
FMS
TEST MATRIX
Interlayer: Ti / Cu coating + filmHIP: 900°C, 100MPa, 1.5h
W (4.5 um/m.K)Ti Interlayer
(8.4 um/m.K)FMS (12.3 um/m.K)
FMS Ti W
Fe
TiW
FMS
Cu
W
Ti
Before Test
After Test
Thermal Expansion (Ti film) Diffusion Bonding (Cu film)
2. KO Activities for liquid metal breeder blanket
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 10/26
2. Fabrication technology (3) Heat load test facilities for fabrication technology development- For thermal fatigue test, KoHLT-1 & 2 (Korea Heat Load Test facilities) were developed- E-beam facility will be prepared by the end of 2013 (300kW/EH800V)
Photos of KoHLT-1 and graphite heater Photos of KoHLT-2 and graphite heater
2. KO Activities for liquid metal breeder blanket
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 11/26
3. Cooling technology(1) He supplying system for KoHLT-2 (by Jan. 2011)- to test TBM FW (10 Channels) up to 0.73 kg/s
He supplying systemDesign T: 300 - 500 CDesign P: 8 MPaDesign flow: 0.73 kg/s
2. KO Activities for liquid metal breeder blanket
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 12/26
3. Cooling technology(2) TH test for codes validation using High pressure (6 MPa, 900 oC) gas loop (N2, He) at KAERI Loops developed for HTGR project- CFD code (CFX-11), MARS-GCR, GAMMA code was simulated with the same test condition
2. KO Activities for liquid metal breeder blanket
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 13/26
PCHE concept He/He heat exchange He/Water heat exchange
2. KO Activities for liquid metal breeder blanket 3. Cooling technology(3) Heat Exchanger Development- PCHE (Printed Circuit Heat Exchanger) for He/He and He/Water- PHE (Printed Heat Exchanger) for He/H2SO4
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 14/26
4. Liquid breeder technology(1) Li & PbLi Reaction test- Li melting and reaction with water/air were performed- reaction control with nano-particle was confirmed- PbLi melting test was performed before inserting in the ELLI
TEM image for Ni nano-particles
Reaction test facility and Li melting/reaction test results (movie & measured temperature) PbLi melting test
2. KO Activities for liquid metal breeder blanket
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 15/26
4. Liquid breeder technology(2) PbLi loop (ELLI, Experimental Loop for Liquid breeder)- early 2010, ELLI was constructed and operation was started- objectives: EM pump design verification, MHD test, flow-corrosion test
SOFT-26 presentation [P3-112] by J.S. Yoon
2. KO Activities for liquid metal breeder blanket
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 16/26
4. Liquid breeder technology(3) Compatibility test
2. KO Activities for liquid metal breeder blanket
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 17/26
5. Tritium extraction technology(1) Study for gas-liquid contactor and design of the batch type facility- Installation in 2010 (Batch Type), 2011 (Loop)- Extraction method of liquid-gas contactor was considered
(Batch Type)
PbLi Inlet
PbLi Outlet
Gas Sparger
Structured Filler Unit
Gas Inlet
Band Heaters
Pipe Heater (Incoloy)
Gas Outlet
Design of T-Extractor
2. KO Activities for liquid metal breeder blanket
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 18/26
3. Gen-IV reactor development in KO1. Overview"National Long-term Development Plan for Future Nuclear Energy Systems (2008.12.)"
(1) Objectives- Expansion of Nuclear Energy : Energy security while addressing climate change issues- Improved Transparency : Peaceful use of nuclear energy - Establishment of National Roadmap : Long-term milestones
(1) Major R&D topicsSFR and Pyroprocess
for proliferation resistant spent fuel managementVHTR
for efficient hydrogen production
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 19/26
1. Overview
DEMO'26-'28
3. Gen-IV reactor development in KO
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 20/26
2. SFR development
’92’11
Basic Research
’97 ’02’20
’07
KALIMER-150Conceptual
Design
KALIMER-600Conceptual
Design
Sodium T/H Experiment
Facility
Standard Design
Approval
Demonstration SFR
AdvancedSFR
Concept’28’15
Goal Construction of demo. SFR by 2028
Work Scope Advanced design concept development Design validation Metal fuel development
Proliferation resistant core without blankets MA bearing metal fuel Enhanced safety with passive systems
3. Gen-IV reactor development in KO
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 21/26
2. SFR development
•PDRC experiment
Advanced Concept Design Studies
Development of Basic Technologies
Development of Advanced Technologies
•Sustainable and proliferation resistant core
•Na-CO2 interaction test
1971.57 [MWt]
16147.52 kg/s
394.27.60
Na 185.31 atm 19.98
545.0 189.219.98 202.7
7.53
RHRS
183.7364.4
9.2[MWt]
329.66 [MWt] 19.98
389.63044.5[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-CO2 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 19.98
545.0 189.219.98 202.7
7.53
RHRS
183.7364.4
9.2[MWt]
329.66 [MWt] 19.98
389.63044.5[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-CO2 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%
0.1094526.0
0.1094526.0
0.1014364.0
0.1014364.0
0.16230.0
0.16230.0
0.10145.0
0.10145.0
26140.8 kg/s
•S-CO2 Brayton cycle system
•Design improvement of fluid and structural system
•System analysis code development
•Sodium technology development
•Metal fuel technologies
AfterBefore
•Under-sodium viewing technique
Liquid Wedge
UltrasonicTransducer
AcousticShieldingTube
10 m
WaveguidePlate
Cross-cutting area with NTFR
3. Gen-IV reactor development in KO
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 22/26
2. SFR development
AHX
Reactor Vessel
Sodium Storage Tank
IHX Gas Cooling System
Sodium Purification
System
Gas Supply System
Overall Layout
Key design parameters of the facility
Major characteristics
PDRC (Passive Decay-heat Removal Circuit) development
3. Gen-IV reactor development in KO
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 23/26
3. VHTR development
VHTR technology and hydrogen production technology
3. Gen-IV reactor development in KO
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 24/26
3. VHTR development
•Materials & component development
Advanced Concept Design Studies
Development of Basic Technologies
Development of Advanced Technologies
•Block and pebble type of 950 oC
•High temperature experiment
•Development of cooled vessel design concept
•Nuclear Design System code development
•Safety analysis code development
•TRISO fuel technologies
•GUI development
3. Gen-IV reactor development in KOCross-cutting area
with NTFR
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 25/26
4. Cross-cutting area and collaboration
There are many technology challenges that advanced fission reactors (Gen-IV) and fusion have in common
Examples of the overlap are- Design tools- Power conversion technologies; Brayton cycle- High temperature materials design rules- Materials corrosion: high temperature materials and coolant compatibility - Materials response under neutron irradiation- Welding and joining technologies- First-principles materials modeling - Tritium/hydrogen behavior in materials
3. Gen-IV reactor development in KO
LMBB workshop, Spain, 23rd Sep. 2010 Dong Won LEE (KAERI, KO) 26/26
4. Conclusions- KO has been developed liquid metal breeder blanket for fusion reactor- We have participated ITER TBM program and related R&Ds have been performed;
Codes development and validation,Fabrication technology, Cooling technology, Liquid breeder technology, and Tritium extraction technology.
- Gen-IV technologies have been developed, which can be the cross-cutting area with fusion field.- We hope to have chances to collaborate with you.
Thanks for your attention.