Transcript PowerPoint

Overview of UCLA Research Activities on
Fusion Nuclear Science and Technology
Briefing to Professor Osamu Motojima
and Japanese delegation from NIFS and MEXT
Signing Ceremony for Agreement on
Scientific Exchange and Cooperation
between Japan (NIFS) and UCLA (HSSEAS and CESTAR)
Mohamed Abdou
November 28, 2006
UCLA Activities in
Fusion Nuclear Science and Technology
•
US ITER Test Blanket Module Activity:
•
•
•
Technical Planning, Design, and Analysis
Modeling Development and Experimental Activities
JUPITER-II (started April 2001)
• Molten Salt Thermofluid MHD Flow Simulation
• Solid Breeder/SiC Material System Thermomechanics
•
Solid breeder blanket research activates under IEA
Collaboration
• Tritium permeation and control
• Interface thermal conductance
•
•
•
ITER Basic Machine and US Procurement Package
Support
Free Surface Liquid Metal MHD Experiments and
Modeling for Liquid Divertors and Melt Layers
Z-pinch Vapor Recombination Dynamics Study
UCLA Leadership in the Development of the US
TBM Technical Plan and Cost Estimate
US ITER TBM
•
A proposed technical plan for US ITER
TBM has been developed over the past 1.5
years.
•
An external review of US DOE technical
and project experts found the cost and plan
“complete and credible” and “ready to be
implemented”
•
The cost averages between $5M to $10M
per year over the next 10 yrs for all the
R&D, Design, Fabrication and Testing
needed for the US H-H Phase TBMs and
supporting systems.
– The exact amount depends on the level of
international collaboration and degree of
integration among ITER Parties
– A significant fraction of the manpower,
facilities, codes and other important
resources already exist in the base program
UCLA Plays a Lead Role on US-TBM
US ITER TBM
UCLA Roles:
• US solid breeder TBM scaling,
test module design
• US DCLL thermofluid MHD
experiments and simulations
• US TBWG representation
Proposed US baseline strategy proposes
different levels of participation for two US
TBM concepts – official US program under
consideration at DOE
DCLL TBM Module
(1660 x 484 x 410 mm)
Poloidal flow
PbLi Channel
He-cooled
RAFS FW
SiC
FCI
HCCB TBM sub-module
(710  389  510 mm)
Ceramic
breeder
pebbles
He-cooled
RAFS FW
Be
Pebbles
HCCB Joint Partnership
Preliminary discussions occurred among US, Japan, and Korea about a possible partnership on HCCB.
US ITER TBM
KO Submodule
JA Submodule
US Submodule The proposed US HCCB
sub-module will occupy
1/3 of an ITER horizontal
half-port
The back plate coolant supply and collection manifold assembly, incorporating
various penetration pipes, flexible supports, and keyways, should be
collaboratively designed by partner Parties.
UCLA MHD group is one of the world’s key
teams working in the area of fusion LM MHD
 Blanket performance is
strongly affected by MHD
DCLL DEMO BLANKET
phenomena
B-field
He
FCI
PbLi
Flow Channel Insert is
the key element of the
DCLL concept, serving
as electric and thermal
insulator
 UCLA group performs MHD
studies under DCLL blanket
conditions for both DEMO
blanket and ITER TBM.
 Strategy encompasses:
• Full 3D simulation tool
development
• Models for specific
phenomena (e.g. natural
convection, MHD turbulence)
• Key EXPERIMENTS to
validate/improve simulations
and understanding
UCLA is collaborating on HIMAG 3D - a complex geometry
simulation code for Closed and Open Channel MHD flows
Simulations are crucial to both understanding
phenomena and exploring possible flow options
for DCLL and FCIs, and NSTX Li module
Problem is challenging from a number of physics
and computational aspects requiring clever
formulation and numerical implementation
Consistent and conservative scheme developed
to conduct the simulation of MHD with high
accuracy at high Hartmann numbers
Bmax = 2.08 T, Ha = 6640
N = 11061, Re = 3986
U = 0.07 m/s
Pipe flow on unstructured
grid in strong field
gradient – good match to
experimental data at high
Ha
Model development focuses on key MHD
phenomena that affect thermal performance via
modification of the MHD velocity field
D
A. Formation of highvelocity near-wall
jets
B. 2-D MHD
turbulence in flows
with M-type velocity
profile
A
B
=5
C. Reduction of
turbulence via Joule
dissipation
E. Strong effects of
MHD flows and FCI
properties on heat
transfer
E
1600
=100
=500
Temperature, C
D. Natural/mixed
convection changes
flow field
dramatically
C
laminar flow model
turbulent flow model
DEMO
1200
800
400
-0.15
-0.1
-0.05
0
0.05
Radial distance, m
0.1
0.15
g
VTBM - Integrated Data/multi-code multi-physics modeling
activities, or Virtual TBM, is key for ITER TBM R&D activity.
• The design of a complex system like the ITER
TBM requires an exhaustive CAE effort
encompassing multiple simulation codes
supporting multi-physics modeling.
CAD Model Input
US ITER TBM
The ferritic structural box
with the first wall helium
coolant channels for the
HCCB TBM. (CAD model
from SolidWorks)
Fix CAD
model
CAD to Analysis Intermediaries
Neutronics
Electromagnetics
Temperature field from
Thermo-Fluid Analysis
using SC/Tetra
Thermo Fluid
Mass Transfer
Structural
Deformation (Thermal
expansion) field from
structural analysis
using ANSYS
UCLA Facilities and Capabilities Utilized in
JUPITER-II Collaboration on Flibe Thermofluid
MHD Research with Japanese Universities
UCLA MTOR MHD Facility
Test section lit by pulsed YAG laser
during Particle Image Velocimetry
measurements
BOB magnet
JUPITER 2 MHD Heat Transfer Exp. in
UCLA FLIHY Electrolyte Loop
JUPITER-II Key Result - Strong MHD effect on turbulence
seen, even at low Ha typical of low conductivity Flibe
velocity fluctuations
severely reduced…
80
60
Near wall temperature
increases…
40
T
+
Ha = 0
Re=9000
Ha=0 (St=0)
Ha=5 (St=0.003)
Ha=10(St=0.01)
Kader
20
0 -1
10
1
y
+
102
10
and global Nu
number decreases…
1
Ha = 20
NuM/Nu
0.9
0.8
0.7
0.6
0.5
0
Re = 5400
NuM=Nu(1-3Ha2/Re)
Present result 30%KOH, circular pipe
Gardner (1970) mercury, circular pipe
Blum (1967) 15% KOH, square duct flow
0.01
0.02
2
interaction parameter Ha /Re
JUPITER-II SiCf/SiC Breeder Pebble Bed
Thermomechanics Interaction Study
1600
A constant force
of 4 N is applied to
each bolt during
the course of the
experiment.
CEA Li2TiO3
pebbles/ CVD
SiC clad
Displacement (um)
1200
800
400
Themex 1
Themex 1 Cooling
Themex 2
0
Themex 2 Cooling
Themex 3
Themex 3 Cooling
-400
with Keyence High Precision Laser position
system for displacement measurement
Kovar
SiC plate
SS-316
Port available for laser
displacement sensors
Capacitance
displacement sensor
Li4SiO4/Li2O pebble bed
0
200
400
600
800
1000
Temperature (C)
Deformation/Stress/Creep Data
were used in conjunction with UCLA
DEM simulation code to develop
temperature dependent stress/strain
constitutive correlations – vital for
accurate finite element analysis
UCLA Research on Liquid Metal Free Surface MHD for
Liquid Divertor: Modeling & Experiments
• The use of fast flowing lithium films as divertor target
will lead to considerable improvement in plasma
performance by gettering of impurities, allowing low
recycling operation and handling of the high heat loads.
• A good understanding of the dynamics of fast flowing
liquid metal streams under spatially varying three
component magnetic fields has to be established.
Divertor design for NSTX
Experiments on film flows show turbulent fluctuations organize
into 2D structures with vorticity along the magnetic field
‘Pinching in’ seen
in HIMAG
simulations and
experiments
Flow
‘Pinching in’
Flow can ‘Pinch-IN’ in field gradients and separate from the
wall. This phenomenon is observed in experiments and
numerical modeling, creating undesireable ‘bare spots’
The free surface structure is affected by the
magnetic field, thus influencing its transport
properties governing the heat and mass
transfer.
A novel double pulse spectroscopic diagnostic was
developed at UCLA to evaluate the feasibility of separating
the Z-Pinch RTL material from the molten flibe
1
Double pulse
spectroscopy
2
Fiber Optics
0.25 m Dual
Monochrometer
Spectrometer
1
Z-box
2
SCR
trigger
circuit
HiCAT
Ignitron
2[kV]
1st pulse (high energy)
used to produce and
excite/ionize Fe & salt vapor
3
0.25 m Dual
Monochrometer
C=55[F]
C=55[F]
Capacitor Bank (5[kJ] Max)
Conceptual Z-pinch power plant
current [kA]
2.5
2
2nd pulse (low energy)
used to re-excite Fe, Na
after a time delay of
140-300 s
1.5
1
0.5
0
0.0E+00
5.0E-05
1.0E-04
time [sec]
1.5E-04
2.0E-04
Initial results suggested that
effective means of separating
either metal halides or precipitated
metal (after hydro-fluoridation)
from liquid flibe will need to be
investigated for Z-IFE.
UCLA Activities in
Fusion Nuclear Science and Technology
•
US ITER Test Blanket Module Activity:
•
•
•
Technical Planning, Design, and Analysis
Modeling Development and Experimental Activities
JUPITER-II (started April 2001)
• Molten Salt Thermofluid MHD Flow Simulation
• Solid Breeder/SiC Material System Thermomechanics
•
Solid breeder blanket research activates under IEA
Collaboration
• Tritium permeation and control
• Interface thermal conductance
•
•
•
ITER Basic Machine and US Procurement Package
Support
Free Surface Liquid Metal MHD Experiments and
Modeling for Liquid Divertors and Melt Layers
Z-pinch Vapor Recombination Dynamics Study