coordinating meeting on r&d for tritium and safety issues in lead-lithium breeders (pbli-t...
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Coordinating Meeting on R&D for Tritium and Safety Issues in Lead-Lithium Breeders (PbLi-T 2007). PbLi research activities at Kyoto University. June 11,2007 Satoshi Konishi, Institute of Advanced Energy, Kyoto University. Institute of Advanced Energy, Kyoto University. - PowerPoint PPT PresentationTRANSCRIPT
Coordinating Meeting on R&D forTritium and Safety Issues in Lead-Lithium Breeders
(PbLi-T 2007)
PbLi research activities at Kyoto University
June 11,2007Satoshi Konishi,
Institute of Advanced Energy, Kyoto University
Objective Kyoto University pursues advanced blanket concept based on
LiPb – SiC – He combination to be opearated at 900 degree or above. Research objective includes, -to Establish a possible advanced blanket concept with supporting technology -to Demonstrate the attractiveness of fusion energy with safety and effectiveness i.e. high temperature efficient generation and hydrogen production, minimal waste generation and tritium release, technical feasibility, adoptability to attractive reactor designs.
Activity in Kyoto University
Research Items Current researtch efforts are on the following tasks Conceptual design with neutronics and thermo-hydraulics, MHD LiPb-SiC-hydrogen system study: compatibility, solubility, permeability LiPb technology : Loop experiment, purity control, high temperature handling SiC component development : cooling panel, tubings, fittings and IHX Mockup development : heat transfer, tritium recovery and control
Institute of Advanced Energy, Kyoto University
SiC-LiPb Blanket ConceptSiC-LiPb Blanket ConceptOuter blanket
calculation model•Module box temperature made of the RAFS must keep under 500 ºC.
•Li-Pb outlet temperature target 900 ºC.
•We propose the new model of active cooling in Li-Pb blanket.
•This concept is equipped He coolant channels in SiC/SiC composite and provides more efficient isolation between the RAFS and high temperature Li-Pb.
•We evaluate the feasibility of high temperature blanket in this model.
Li-Pb Flow
3.High temp. outlet (~900ºC)
1.RAFS module box (~500ºC)
2.SiC/SiC active cooling panel
Research Update and Hilights1.Concept verification
- neutronics and heat balance
Typical configurationTypical configuration
Li17-Pb83
FW ( F82H):1.5 [cm]w/cooling channel
SiC/SiC : 1.5 [cm] w/cooling channel
Neutron
Flux
Plasma
Li-Pb [cm]
( Net thickness [cm] )
40.5~55 ( 45~59.5 )
6Li [%] 7.4 ~ 90
1MW/m2
One Dimensional Neutron Transport Code (ANISN)
•TBR
•Neutron Shield
•Nuclear Heating
Vacuum vessel
multiplier
0 10 20 30 400.0
0.1
0.2
0.3
0.4
TB
R
Li- Pb thickness [cm]
Total
6Li
7Li
40 42 44 46 48 50 52 540.0
0.2
0.4
0.6
0.8
1.0
1.2
1.4
TB
RLi- Pb [cm]層 厚
7.4% 30% 50% 70% 90%
Tritium BreedingTritium Breeding
Relation with Thickness (Li-Pb) and TBR
TBR >= 1.26Li 70% 55cm
6Li 90% 50cm
6Li = 7.4 ~ 90%
•Contribution to 7Li for TBR is less than 5% of all.
•6Li concentration is needed.
•With VV, ca.0.1 increases.
Tritium Breeding Rate
6Li = 7.4%,
Li-Pb thickness [cm]
TB
R
Thickness (Li-Pb) [cm]T
BR
Evaluation of Nuclear HeatingEvaluation of Nuclear Heating
100 102 104 106 108 1100
10
20
30
40
[W
/cm
発熱
量2 ]
[cm]中 心 からの距 離
Photon Neutron Total
F82H SiC/SiCHe Li-Pb
Distribution of nuclear heating
6Li = 90%, TBR = 1.2, Li-Pb = 50cm
Wall thickness [cm]He
at
ge
ne
rati
on
pe
r u
nit
vo
lum
e [
W/c
m3 ]
• Distribution of nuclear heating was calculated.
• Intense nuclear heating by neutron was observed at the front of Li-Pb
• Heat removal must be within a reasonable He flow range.
Heat Transfer AnalysisHeat Transfer Analysis
d1
v
L
Temperature of RAFS side must keep under 500ºC. Temperature of Li-Pb is determined by active cooling of SiC/SiC composite panel with He channels.
Max 500 [ºC]
600 [ºC]
RAFSside~500 [ºC]
Li-Pb
side
SiC/SiC Layer
He
Channel
1. High Temperature Li-Pb
2. Large Nuclear Heating
For example : THe=350 [ºC], VHe = 8 [m/s]
Results of Heat Transfer AnalysisResults of Heat Transfer Analysis
•Max Li-Pb temperature is obtained as a function of He coolant flow speed.He Coolant Temp. = 350 ºC
Relation with Li-Pb side temperature and He velocity ( PHe = 8 [MPa] )
SiC/SiC 1.5 cm, He channel 0.5x0.5cm
600 650 700 750 800 850 9000
20
40
60
80
100
120
140He temp.
He
Flo
w S
peed
[m
/s]
Li- Pb side temperature [deg.C]
300 350 400 450
•900 ºC Li-Pb is possible with moderate He velocity.
Max LiPb temp.
He flow speed
600ºC 11.6 m/s
700ºC 16.5 m/s
800ºC 21.0 m/s
900ºC 25.5 m/s
0 1 2 3 4 5 6 7 8 9 100
500
1000
1500
2000
2500
3000
[W/ cm体 積 発 熱 量 3]
[W
/cm
体積
発熱
量3 ]
[cm/ s]流 速
0
200
400
600
800
1000
1200
1400
1600
1800
2000
[℃]出 口 温 度
[℃
]出
口温
度
Outlet Temp. and Velocity of Li-PbOutlet Temp. and Velocity of Li-Pb
Relation with outlet temperature and Li-Pb flow velocity
Net thickness 54.5 cm, Li-Pb thickness 50 cm
6Li = 90%, TBR = 1.2
Li-Pb inlet : 300ºC
Mean Flow Path 100 cm, Flow path height 10cm
Outlet [deg.]Heat value [J/cm3]
Li-Pb velocity [cm/s]
Out
let
[deg
.]
T
ota
l acc
epte
d he
at
valu
e on
out
let
[J/c
m3]
The MHD pressure drop is considered to be negligible in this condition ( ~1 cm/s).
Outlet temp.
LiPb flow speed
600ºC 1.01 cm/s
700ºC 0.78 cm/s
800ºC 0.68 cm/s
900ºC 0.51 cm/s
•Required Li-Pb velocity is calculated.
Research Update and Hilights2. Tritium Permeation through
Structural materials
The device consists of two lines with high and low pressure divided with disk sample
Permeation of deuterium was measured by using quadrupole mass spectrometer.
Permeation experiments
QMS
IG
RP
TMP
Fig. 1 A schematic diagram of the experimental setup.
manometermanometer
heater
sample
high pressure
line
low pressure
line
D2
Institute of Advanced Energy, Kyoto University
Sample
• Disc samples 20 mm in diameter and 2.79 mm thick were used.
• The sample is fixed between two VCR Couplings with metal gaskets.
• Outside of this test section was vacuum.
After experimentBefore experiment
High pressure lineHigh pressure line Low pressure lineLow pressure line
The method for fixing sample
Hydrogen permeability through SiC
Sample: CVD SiCThickness: 2.79 [mm]Temp: 800 [ºC] Gas: 100% D 2 1.0x105 [Pa]
0 5 10 1510-9
10-8
10-7
10-6
10-5
time [h]
Pl [
Pa]
CVD 800℃Hexoloy 800℃
Permeation flow rate of CVD was larger than that of Hexoloy by 2 orders
x200
Institute of Advanced Energy, Kyoto University
Temperature dependence of Permeability
Comparative arrhenius plot of the obtained permeability.
hPA
dnK
K: permeabilityn: permeation flow rated: thickness of the samplePh: the pressure of high pressure
line A: geometrical area of the sample
[mol ・ Pa-1/2 ・ s-1 ・ m-1]
0.8 1 1.2 1.410-13
10-12
10-11
10-10
10-9 ℃400500600700800900
1000/T [1000/K]deut
eriu
m p
erm
eabi
lity
, K [
mol
・s-1
・m
-1・
Pa-1
/2]
SUS316CVDHexoloy
Institute of Advanced Energy, Kyoto University
Diffusivity
SUS316:a few secondsCVD: a few minutesHexoloy: a few hours
It is considered that the time taken to start the permeation is related to diffusivity.
The time required to start the detection of permeation gas is…
0.8 1 1.2 1.410-12
10-11
10-10
10-9
10-8
10-7
1000/T [1000/K]
Dif
fusi
vity
[m
2 s-1
]
SUS316CVDHexoloy
Activation energy of the diffusion of Hexoloy is 110 kJ/mol.
Institute of Advanced Energy, Kyoto University
Solubility
Solubility was calculated by permeability and diffusivity.
The solubility in SiC material is ranging 10-4 to 10-3 [mol m-3 Pa-1/2 ] at the temperature above 700 degree C
0.8 1 1.2 1.410-6
10-5
10-4
10-3
10-2
10-1
100
1000/T [1000/K]
solu
bili
ty [
mol
m-3
Pa-1
/2]
SUS316HexoloyCVD
Institute of Advanced Energy, Kyoto University
bccfcc
Institute of Advanced Energy, Kyoto UniversityPermeation in FAFM
0.8 1 1.2 1.4 1.6 1.810 -12
10 -11
10 -10
10 -9
10 -8
1000/T [K -1]
perm
eab
ility
[m
ol P
a-1/2
sec
-1 m
-1]
℃300400500600700800900
0.93mm F82H1.93mm F82HNi
Diffusion in RAFM
Difference understood as the change in crystal structure
Institute of Advanced Energy, Kyoto University
bccfcc
0.8 1 1.2 1.4 1.6 1.810 -9
10 -8
10 -7
10 -6
1000/T [K -1 ]
Diff
usi
on
coeffi
cient
[m
2 sec
-1]
0.93mm F82H1.93mmNi
400500600700800900 ℃
F82H
Research Update and Hilights 3. Compatibility
Compatibility testsKyoto University Institute of Advanced Energy
SiC/SiC composite tube was installed in the LiPb loop Tube section was heated above 600 degree C with LiPb flow Possible corrosion is observed with mucroscopes.
SiC/SiC tube
Test section : heated and cooled
Inner surface of SiC afterexposure
Reaction between LiPb and SiC
Kyoto UniversityKyoto University
Pb mapping
Si の mapping
SiC/SiC composites
LiPb
SiC/SiC did not react with LiPb below 750 degree C.
Corrosion of stainless steelInstitute of Advanced Energy, Kyoto University
Tube surface 、 x100
Inside of tube Welding x100
welding 、 x100
Corroded steelInstitute of Advanced Energy, Kyoto University
(x10000) elements analyses : Cr,Ni missing
X500 SEM elements
Microstructure of SiCInstitute of Advanced Energy, Kyoto University
SEM observation of SiC : deposit of Cr and Fe found
Research Update and Hilights 4. Chemistry control
- With ion conductor cells
• YSZ (Yttria-stabilized zirconia)–Inside electrode was
made of Pt mesh and Pt paste exposed to air as a standard gas
–Liquid LiPb was used as outside electrode
Solid electrolyte cells for LiPb chemistry control
Ceramics tubes of YSZ for oxygen
Solid electrolyte
Pt paste and mesh
Mulite tube
Thermo-couple Pt wires
EMF
Fig. The cell structure
Pb-17Li
SrCeYbO3 for proton conductivity
Institute of Advanced Energy, Kyoto University
Mass flow controller Gas chromatograph
Potentiostat
Cold trap
Helium gasHelium gas with 10% O2
Pressure gage
Electric heater
electrodes
electrode
YSZ ceramic
Pt paste
Crucible
heat insulation
Solid electrolyte cell
Institute of Advanced Energy, Kyoto UniversityExperiments
- 250
- 200
- 150
- 100
- 50
0200 300 400 500 600 700
measurement oxygen activity in LiPbPeater Hubberstey's report (calculation)
• The cell generates EMF• EMF is converted into
aO2 with Nernst equation
• The theoretical aO2 is calculated from Gibbs free energy equation
• Observed aO2 for LiPb by the EMF agreed well with theoretical value.
)17(/67322882.0ln
ln4}/][{ln 20
2
LiPbatTa
aRTOLiGa
Li
LiO
lna O
2
Oxygen Potential in LiPb
Li⇔Li2O
Pb⇔PbOTemperature[℃]
Measurement Oxygen activity in LiPb
Pb-17Li⇔Pb-17Li-O*
metalinO
airinO
a
P
F
RTE
2
2ln4
*Peter Hubberstey; Pb-17Li and lithium: A thermodynamic rationalisation of their radically different chemistry
*
*
Institute of Advanced Energy, Kyoto University
1.90
1.95
2.00
2.05
2.10
0 2000 4000 6000 8000 10000 120000
2
4
6
8
10
12
EMFOxygen concentration measured at micro GCcaluculated oxygen concentration
Interaction with O2 in cover gas
• Absorption of O2 in LiPb was observed • Absorbed oxygen corresponds to O/Li=0.17.• Increase of oxygen potential in LiPb was detected at the EMF plot
Relationship between EMF and oxygen concentration of cover gas
time [sec]
Oxy
gen
conc
entr
atio
n
[%]
EM
F [V
]
at 450℃
• Cover gas on LiPb is replaced with He-10%O2
Fig. State before and after measurement
0
10
20200 300 400 500 600 700
lna O
2ac
rivity
Metal temperature[℃]
hydrogen activity in LiPb measured withProton conductor cell.
Hydrogen Potential in LiPbInstitute of Advanced Energy, Kyoto University
Research Update and Hilights 5. Loop, Engineering
Development and MHD
Fabrication test of cooling panelKyoto University Institute of Advanced Energy
Fabrication technique for cooling panel and other blanket parts such as FCI and HX are being tested.
Fabrication process15.12 mm
17.89 mm6 mm
15.12 mm
17.89 mm6 mm
SiC cooling panel unit
0.5mm
cutting junction
Institute of Advanced Energy, Kyoto UniversityCooling channel structure
LiPb loop and SiC insertKyoto University Institute of Advanced Energy
SiC/SiC Tube 149mm
SUS316 Tube
流速: 0.7 ~ 1.0 [cm/s]
・ operated at 900 maximum℃
・ Heat transfer and removal requires improvement
Institute of Advanced Energy, Kyoto University
TE43 イメージ炉制御用TE42 予熱器出口TE-B 液温TE32 TS後TE46 CL直前流量
温度[deg C]
流量[L/min]
経過時間[hr]0 5 10 15 20 250
100
200
300
400
500
600
700
800
900
1000
0
0.2
0.4
0.6
0.8
1
1.2
1.4
1.6
1.8
2
LiPb/SiC loop operated at 900C
Glovebox for LiPb experimentKyoto University Institute of Advanced Energy
He-LiPb loop
EMP
T
T
Dump tank
T
T
T
hygrometer
cooler
HEATER
GC
断熱材
T
Used forOther project He loop
P
F
F
P
MSB
Zr
GC
T
T
Heater
9 00℃
9 00℃
7 00℃
7 00℃
~200℃
耐熱合金Testmodule
Vacuum vessel
He loop for LiPb blanketExpansion tank
Original LiPb loop
MHDsection
SiC tube
IHX
• MHD measurement with SiC/LiPb.• Compatibility test at various flow velocity.• Hydrogen/Tritium permeation through composite.• Hydrogen isotherm with LiPb.• Better purity and precise composition with
controlled atmosphere (glovebox).• Instrumentation:EM flowmeter, emf sensor.• Secondary 900C He loop and heat transfer test.• Development of RAFM enclosure , square
SiC duct and flange.• 3-D neutronics and module design.
Kyoto University Institute of Advanced EnergyPlanned test in 2007
• Ultimate goal of this program in Kyoto is to develop a concept of high temperature blanket.
• Small scale blanket module will be demonstrated in 4 years.
• System and component design will be made.• Small neutron source will be used for tritium
transfer experiment.• Possible collaboration on DCLL and further SiC-
LiPb configuration under TBM programs.• Reactor design with near term high temperature
blanket.
Kyoto University Institute of Advanced EnergyLong term plan
• LiPb-SiC blanket concept is now actively studied in Japan at Kyoto University.
• Both experimental and design studies are open for international collaboration.
• Some of the experiments are unique and valuable
for international efforts for liquid blanket
development.
Kyoto University Institute of Advanced EnergyConclusion