Blanket Concepts and Issues
Mohamed Abdou
Distinguished Professor of Engineering and Applied Science
Director, Center for Energy Science and Technology (CESTAR)
Director, Fusion Science and Technology Center
University of California, Los Angeles (UCLA)
web: http://www.fusion.ucla.edu/abdou/
Lecture at the symposium "Towards a Mexican Fusion Programme"
21-22 June, 2007
held at Universidad Nacional Autonoma de Mexico
Blanket (including first wall)
Blanket Functions:
A. Power Extraction
–
Convert kinetic energy of neutrons and secondary gamma rays into heat
–
Absorb plasma radiation on the first wall
–
Extract the heat (at high temperature, for energy conversion)
B. Tritium Breeding
–
Tritium breeding, extraction, and control
–
Must have lithium in some form for tritium breeding
C. Physical Boundary for the Plasma
–
Physical boundary surrounding the plasma, inside the vacuum vessel
–
Provide access for plasma heating, fueling
–
Must be compatible with plasma operation
–
Innovative blanket concepts can improve plasma stability and confinement
D. Radiation Shielding of the Vacuum Vessel
There are Many Blanket Concepts Proposed Worldwide
They all have feasibility issues and attractive features
Material or Configuration
Options
Structural Materials
Reduced Activation Ferritic Steel Alloys (including ODS), Vanadium Alloys, SiC
Composites
Coolant Media
Helium, Water, Liquid Metals, Molten Salts
Breeder Media
Lithium-Bearing: Ceramic Breeders (Li4SiO4, Li2TiO3, Li2O); Liquid Metals (Li, PbLi,
SnLi); Molten Salts (FLiBe, FLiNaBe); Varying enrichments in Li-6
Neutron Multiplier Materials
Beryllium, Be12Ti, Lead
MHD/Thermal Insulator Materials
SiC composites and foams, Al2O3, CaO, AlN, Er2O3, Y2O3
Corrosion and Permeation
Barriers
SiC, Al2O3, others
Plasma Facing Material
Beryllium, Carbon, Tungsten alloys, others
HX or TX Materials
Ferritic Steels, Refractory Alloys, SiC, Direct Gas Contact
Blanket Configurations
He or Water Cooled Ceramic Breeder/Be; Separately Cooled, Self-Cooled, DualCoolant LM or MS
Ceramic Breeder Configurations
Layered, Mixed, Parallel, Edge-On (referenced to FW)
Liquid Breeder Configurations
Radial-Poloidal Flow, Radial-Toroidal Flow, others
MHD/Thermal Insulator Config.
Flow Channel Inserts, Self-Healing Coatings, Multi-Layer Coatings
Structure Fabrication Routes
HIP; TIG, Laser and E-beam Welding; Explosive Bonding; Friction Bonding;
Investment Casting; and others
Blanket Concepts
(many concepts proposed worldwide)
A.
B.
Solid Breeder Concepts
–
Always separately cooled
–
Solid Breeder: Lithium Ceramic (Li2O, Li4SiO4, Li2TiO3, Li2ZrO3)
–
Coolant: Helium or Water
Liquid Breeder Concepts
Liquid breeder can be:
a) Liquid metal (high conductivity, low Pr): Li, or 83Pb 17Li
b) Molten salt (low conductivity, high Pr): Flibe (LiF)n · (BeF2),
Flinabe (LiF-BeF2-NaF)
B.1. Self-Cooled
–
Liquid breeder is circulated at high enough speed to also serve as coolant
B.2. Separately Cooled
–
A separate coolant is used (e.g., helium)
–
The breeder is circulated only at low speed for tritium extraction
B.3. Dual Coolant
–
FW and structure are cooled with separate coolant (He)
–
Breeding zone is self-cooled
Solid Breeder Blanket Concepts
The idea of a solid breeder blanket is to have the lithium-containing
tritium breeder as non-mobile and to reduce lithium and tritium
inventory as described in M.A. Abdou, L.J. Wittenberg, and C.W.
Maynard, "A Fusion Design Study of Nonmobile Blankets with
Low Lithium and Tritium Inventories", Nuclear Technology, 26:
400–419 (1975).
–
Always separately cooled
–
Coolant: Helium or Water
–
Solid Breeder: Lithium Ceramic (Li2O, Li4SiO4, Li2TiO3, Li2ZrO3)
–
A neutron multiplier is always required to achieve TBR > 1 (with the
possible exception of Li2O) because inelastic scattering in non-lithium
elements render Li-7 ineffective
–
Only Beryllium (or Be12Ti) is possible (lead is not practical as a
separate multiplier)
–
Structure is typically Reduced Activation Ferritic Steel (RAFS)
A Helium-Cooled Li-Ceramic Breeder Concept: Example
Material Functions
• Beryllium (pebble bed) for
neutron multiplication
• Ceramic breeder (Li4SiO4,
Li2TiO3, Li2O, etc.) for tritium
breeding
• Helium purge (low pressure)
to remove tritium through
the “interconnected
porosity” in ceramic breeder
• High pressure Helium
cooling in structure (ferritic
steel)
Several configurations exist (e.g. wall parallel or “head on”
breeder/Be arrangements)
“Temperature Window” for Solid Breeders
• The operating temperature of the solid breeder is limited
to an acceptable “temperature window”: Tmin– Tmax
– Tmin, lower temperature limit, is based on acceptable tritium
transport characteristics (typically bulk diffusion). Tritium diffusion
is slow at lower temperatures and leads to unacceptable tritium
inventory retained in the solid breeder
– Tmax, maximum temperature limit, to avoid sintering (thermal and
radiation-induced sintering) which could inhibit tritium release;
also to avoid mass transfer (e.g., LiOT vaporization)
• The limitations on allowable temperature window,
combined with the low thermal conductivity, place limits
on allowable power density and achievable TBR
Liquid Breeders

Many liquid breeder concepts exist, all of which have key
feasibility issues. Selection can not prudently be made before
additional R&D and fusion testing results become available.

Type of Liquid Breeder: Two different classes of materials with
markedly different issues.
a)
Liquid Metal: Li, 83Pb 17Li
High conductivity, low Pr number
Dominant issues: MHD, chemical reactivity for Li, tritium permeation
for LiPb
b)
Molten Salt: Flibe (LiF)n · (BeF2), Flinabe (LiF-BeF2-NaF)
Low conductivity, high Pr number
Dominant Issues: Melting point, chemistry, tritium control
Liquid Breeder Blanket Concepts
1.
Self-Cooled
–
Liquid breeder circulated at high speed to serve as coolant
–
Concepts: Li/V, Flibe/advanced ferritic, flinabe/FS
2.
Separately Cooled
–
A separate coolant, typically helium, is used. The breeder is
circulated at low speed for tritium extraction.
–
Concepts: LiPb/He/FS, Li/He/FS
3.
Dual Coolant
–
First Wall (highest heat flux region) and structure are cooled with a
separate coolant (helium). The idea is to keep the temperature of the
structure (ferritic steel) below 550ºC, and the interface temperature
below 480ºC.
–
The liquid breeder is self-cooled; i.e., in the breeder region, the liquid
serves as breeder and coolant. The temperature of the breeder can
be kept higher than the structure temperature through design, leading
to higher thermal efficiency.
Advantages of Liquid Metal Blankets
LM Blankets have the Potential for:
 High heat removal
 Adequate tritium breeding ratio appears possible without
beryllium neutron multiplier in Li, PbLi (Pb serves as a
multiplier in PbLi). (Note that molten slats, e.g flibe has
beryllium part of the salt and generally requires
additional separate Be.)
 Relatively simple design
 Low pressure, low pumping power (if MHD problems can
be overcome)
See BCSS for review of many possible blanket systems.
Flows of electrically conducting coolants will
experience complicated
magnetohydrodynamic (MHD) effects
What is magnetohydrodynamics (MHD)?
– Motion of a conductor in a magnetic field produces an EMF that can
induce current in the liquid. This must be added to Ohm’s law:
j   (E  V  B )
– Any induced current in the liquid results in an additional body force
in the liquid that usually opposes the motion. This body force must
be included in the Navier-Stokes equation of motion:
V
1
1
 (V  )V   p   2 V  g  j  B
t


– For liquid metal coolant, this body force can have dramatic impact
on the flow: e.g. enormous MHD drag, highly distorted velocity
profiles, non-uniform flow distribution, modified or suppressed
turbulent fluctuations
Main Issue for Flowing Liquid Metal in Blankets:
MHD Pressure Drop
Feasibility issue – Lorentz force resulting from LM
motion across the magnetic field generates MHD
retarding force that is very high for electrically
conducting ducts and complex
geometry flow elements
Thin wall MHD pressure drop formula
p MHD  LJB  LVB
p, pressure
L, flow length
J, current density
B, magnetic induction
V, velocity
, conductivity (LM or wall)
a,t, duct size, wall thickness
2  wt w
a


c
A perfectly insulated “WALL” can eliminate the
MHD pressure drop. But is it practical?
Conducting walls
Insulated walls
Lines of current enter the low
resistance wall – leads to very
high induced current and high
pressure drop
1
0.8
0.6
0.4
1
0.8
0.6
0.4
0.2
0.2
0
0
-0.2
-0.2
All current must close in the
liquid near the wall – net drag
from jxB force is zero
-0.4
-0.6
-0.8
-1
•
•
-0.6
-0.8
-1
-1
-1
•
-0.4
-0.8
-0.6
-0.4
-0.2
0
0.2
0.4
0.6
0.8
-0.8
-0.6
-0.4
-0.2
0
0.2
0.4
0.6
0.8
1
1
Net JxB body force p = cVB2
where c = (tw w)/(a )
For high magnetic field and high
speed (self-cooled LM concepts
in inboard region) the pressure
drop is large
The resulting stresses on the
wall exceed the allowable stress
for candidate structural
materials
•
•
Perfect insulators make the net
MHD body force zero
But insulator coating crack
tolerance is very low (~10-7).
–
•
It appears impossible to develop
practical insulators under fusion
environment conditions with large
temperature, stress, and radiation
gradients
Self-healing coatings have been
proposed but none has yet been
found (research is on-going)
Separately-cooled LM Blanket
Example: PbLi Breeder/ helium Coolant with RAFM



EU mainline blanket design
All energy removed
by separate He stream
The idea is to avoid MHD issues.
But, PbLi must still be circulated to
extract tritium
 ISSUES:
- Low velocity of PbLi leads to high tritium
partial pressure , which leads to
tritium permeation (Serious Problem)
- Tout limited by PbLi compatibility
with RAFM steel structure ~ 500C
(and also by limit on Ferritic, ~550C)
- Possible MHD Issues :
A- MHD pressure drop in the inlet
manifolds
B- Effect of MHD buoyancy-driven flows
on tritium transport
EU-PPCS B
Drawbacks: Tritium Permeation and limited thermal efficiency
EU – The Helium-Cooled Lead Lithium (HCLL) DEMO Blanket
Concept
Module box
(container & surface
heat flux extraction)
Breeder cooling
unit (heat extraction
from PbLi)
[18-54]
mm/s
[0.5-1.5]
mm/s
Stiffening structure
(resistance to accidental in-box
pressurization i.e He leakage)
He collector system
(back)
HCLL PbLi flow scheme
Pathway Toward Higher Temperature Through Innovative
Designs with Current Structural Material (Ferritic Steel):
Dual Coolant Lead-Lithium (DCLL) FW/Blanket Concept
 First wall and ferritic steel structure
cooled with helium
 Breeding zone is self-cooled
 Structure and Breeding zone are
separated by SiCf/SiC composite
flow channel inserts (FCIs) that
 Provide thermal insulation to
decouple PbLi bulk flow
temperature from ferritic steel
wall
 Provide electrical insulation to
reduce MHD pressure drop in
the flowing breeding zone
DCLL Typical Unit Cell
Pb-17Li exit temperature can be significantly higher than the
operating temperature of the steel structure  High Efficiency
Flow Channel Inserts are a critical element
of the high outlet temperature DCLL
 FCIs are roughly box channel
shapes made from some material
with low electrical and thermal
conductivity
– SiC/SiC composites and SiC foams
are primary candidate materials
 They will slip inside the He Cooled
RAFS structure, but not be rigidly
attached
 They will slip fit over each other,
but not be rigidly attached or
sealed
 FCIs may have a thin slot or holes
in one wall to allow better pressure
equalization between the PbLi in the
main flow and in the gap region
 FCIs in front channels, back channels, and access pipes will
be subjected to different thermal and pressure conditions; and
will likely have different designs and thermal and electrical
property optimization
17
DCLL should be effective in reducing
MHD pressure drop to manageable levels
 Higher outlet temperature due
to FCI thermal insulation
allows large coolant delta T
in breeder zone, resulting in
lower mass flow rate
requirements and thus lower
velocity.
 Electrical insulation provided
by insert reduces bare wall
pressure drop by a factor of
10-100.
500
(dP/dx)0 / (dP/dx)
 Low velocity due to
elimination of the need for
FW cooling reduces MHD
pressure drop.
PEH
PES
400
300
200
100
0
1
10
100
1000
Electrical conductivity, S/m
Key DCLL DEMO R&D Items

PbLi Thermofluid MHD
Key impacts on thermal/power extraction performance, FCI load, safety

SiC FCI development including irradiation effects
Key impacts on DCLL lifetime, thermal and power extraction
performance

RAFS/PbLi/SiC compatibility & chemistry control
Impacts DCLL lifetime and thermal performance

Tritium extraction and control
Critical element for PbLi which has low T solubility

High temperature heat exchanger system
Critical element for high temperature DCLL operation

He distribution and heat transfer enhancement
Key impacts on DCLL thermal and power extraction optimization

RAFS fabrication development and materials properties
Critical for any RAFS system

Integrated behavior leading to Test Blanket Module testing in ITER
Critical for any blanket system performance and reliability

Brayton Cycle optimization for DCLL parameters
Key impacts on thermal/power extraction performance
Molten Salt Blanket Concepts
• Lithium-containing molten salts are used as the coolant for the
Molten Salt Reactor Experiment (MSRE)
• Examples of molten salt are:
– Flibe: (LiF)n · (BeF2)
– Flinabe: (LiF-BeF2-NaF)
• The melting point for flibe is high (460ºC for n = 2, 380ºC for n = 1)
• Flinabe has a lower melting point (recent measurement at SNL gives
about 300ºC)
• Flibe has low electrical conductivity, low thermal conductivity
Concepts considered by US for ITER TBM (but were not selected):
– Dual coolant (He-cooled ferritic structures, self-cooled molten salt)
– Self-cooled (only with low-melting-point molten salt)
20
Performing integrated breeding blanket experiments has
been a principal objective of ITER since its inception
 “ITER should test design concepts of tritium breeding blankets relevant
to a reactor. The tests foreseen in modules include the demonstration of
a breeding capability that would lead to tritium self sufficiency in a
reactor, the extraction of high-grade heat, and electricity generation.”
SWG1, reaffirmed by ITER Council, IC-7 Records (14–15 December, 1994), and stated
again in forming the Test Blanket Working Group (TBWG).
The need to test breeding blankets in ITER has been recognized
many times in the US planning efforts for ITER
 “Deliver to ITER for testing the blanket test modules needed to demonstrate
the feasibility of extracting high-temperature heat from burning plasmas and
for a self-sufficient fuel cycle (2013)” A Strategic Program Plan for Fusion
Energy Sciences. http://www.ofes.fusion.doe.gov/News/FusionStrategicPlan.pdf
 “Participate in the [ITER] test blanket module program”, and “Deploy, operate
and study test blanket modules”, Planning for U.S. Fusion Community
Participation in the ITER Program, US BPO Energy Policy Act Task Group,
2006
TBM is an integral part of
ITER Schedule, Safety, and Licensing
ITER Schedule
1st 10 yrs
Early H-H Phase TBM Testing is mandated by ITER IO and licensing team:
1. Optimize plasma control in the presence of Ferritic Steel TBMs
2. Qualify port integration and remote handling procedures
3. License ITER with experimental TBMs for D-T operation
ITER Provides Substantial Hardware Capabilities
for Testing of Blanket System
TBM System (TBM + T-Extrac, Bio-shield
Heat Transport/Exchange…)
A PbLi loop
Transporter located in
the Port Cell Area
2.2 m
ITER has allocated 3
ITER equatorial ports
(1.75 x 2.2 m2) for TBM
testing
Each port can
accommodate only 2
Modules (i.e. 6 TBMs max)
He pipes to
TCWS
Equatorial Port
Plug Assy.
Vacuum Vessel
TBM
Assy
Aggressive competition for space. (Note:
fluence in ITER is limited. We also have to build
another facility, CTF/VNS, for FNT development)
Port
Frame
Blanket Concepts Proposed by 7 Parties for ITER Testing
Concept
Acronym
Materials
Proposing Party
HCCB




RAFS Structure
Be multiplier
Ceramic breeder (Li2TiO3, Li4SiO4, Li2O)
Helium coolant and purge
Water-Cooled
Ceramic Breeder
WCCB



RAFS structure
Be multiplier, Ceramic breeder (Li2TiO3, Li2O)
Water coolant, He purge
Helium-Cooled
Lead-Lithium
HCLL



RAFS structure
Molten Pb-17Li breeder/multiplier
Helium coolant
DCLL




RAFS structure
SiC flow channel inserts
Molten Pb-17Li breeder/coolant/multiplier
Helium coolant
HCML



RAFS structure
Lithium breeder
Helium coolant
KO
Li/V



Vanadium alloy structure
Insulator barrier (e.g., AlN)
Lithium breeder/coolant
RF
LLCB



RAFS structure, PbLi multiplier/breeder/coolant
Dual Helium Coolant
Dual Ceramic Breeder
IN
Helium-Cooled
Ceramic Breeder
Dual-Coolant
Lead-Lithium
Helium-Cooled
Molten Lithium
Self-Cooled
Lithium
Lead-Lithium
Ceramic Breeder
EU, KO, CN
(JA,US, RF, IN)*
*Supporting/Submodule
Role
JA
EU, CN
US, CN
(EU, JA, IN)*
*Supporting Role
- Proposed 12 designs for TBM’s representing 7 classes of concepts
- But there is much common R&D (e.g. for ferritic steel, ceramic breeder, PbLi)
among the concepts
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. A “Lead Party” takes responsibility for fabrication of the back plate and integration of the
three sub modules.
Baseline strategy proposes different levels of
participation for two US TBM concepts
US ITER TBM
After extensive effort two blanket concepts that have
substantially different feasibility issues were selected:
1. The Dual-Coolant PbLi Liquid Breeder Blanket (DCLL)
concept with self-cooled PbLi breeding zone and flow
channel inserts (FCIs) as MHD and thermal insulator.
– Innovative concept (favored by US PC and ARIES, and EU –
DEMO) that provides “pathway” to higher outlet
temperature/higher thermal efficiency while using ferritic steel .
– US lead role in collaboration with other parties. Plan an
independent TBM that will occupy half an ITER test port.
2. The Helium-Cooled Solid Breeder Blanket (HCCB)
concept with ferritic steel structure and beryllium neutron
multiplier, but without an independent TBM.
– ALL parties are interested. HCCB is the most likely candidate
for near-term breeding blankets, e.g. in ITER extended phase.
– Supporting partnership with other parties with shared ancillary
equipment. With modest investment in HCCB, US will gain
access to large international program,
– Contribute submodule test articles that focus on particular
technical issues.
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
R&D, Design, Fabrication and Qualification for TBMs
must proceed Similar to all ITER components
Key Project Milestones
Approve 1st Module
Fabrication, Final TSD
Key early design
decisions, TSD
1st Draft
Approve Prototype
Fabrication, complete
structural design criteria
• TBMs must not affect ITER availability
• TBM systems make up part of the “Safety” boundary
• TBMs must be part of the ITER licensing for HH and DT operation
Framework Proposed for TBM collaboration & responsibilities
(proposed by TBWG DH, July 2006)
 Each 1/2 of a port is dedicated to testing of one TB concept design (one
module or several connected sub-modules).
 Each Concept design is tested by a partnership of a TB concept leader +
supporting partners
 One of the two TB leaders occupying the same port must play a role of the
Port master – responsible for integration of the given port
 Port Master has main responsibility of integration of 2 concepts in the
same port frame and preparation of the integrated testing program
(replacement strategy) for the port ITER has only 3 ports  Only 6 TBMs
can be tested
List of TBM Design Proposals for day-one
 Helium-cooled Lithium-Lead TBM (2
designs)
 Dual-coolant (He+Lithium-Lead) TBM (2
designs)
 He-cooled Ceramic Breeder/Beryllium
multiplier TBM (4 designs)
 Water-cooled Ceramic Breeder/Beryllium
multiplier TBM (1 design)
 He-cooled Liquid Lithium TBM (1 design)
Self-cooled Liquid Lithium TBM (1 design)
1248
750
(DDDs completed by Parties)
524
1700
Horizontal
Vertical
Each Port can hold two vertically or horizontally
oriented half-port size integrated TBMs
ITER TBM is a Necessary First Step in Fusion Environment
Role of CTF (VNS)
Role of ITER TBM
Component Engineering
Development &
Reliability Growth
Fusion “Break-in” &
Scientific Exploration
Engineering Feasibility
& Performance
Verification
Stage I
Stage II
Stage III
1 - 3 MW-y/m2
> 4 - 6 MW-y/m2
1-2 MW/m2,
steady state or long pulse
COT ~ 1-2 weeks
1-2 MW/m2,
steady state or long burn
COT ~ 1-2 weeks
0.1 – 0.3 MW-y/m2
 0.5
MW/m2,
burn > 200 s
Sub-Modules/Modules
• Initial exploration of coupled
phenomena in a fusion environment
• Uncover unexpected synergistic effects,
Calibrate non-fusion tests
• Impact of rapid property changes in
early life
• Integrated environmental data for
model improvement and simulation
benchmarking
• Develop experimental techniques and
test instrumentation
• Screen and narrow the many material
combinations, design choices, and
blanket design concepts
Modules
• Uncover unexpected synergistic
effects coupled to radiation
interactions in materials, interfaces,
and configurations
• Verify performance beyond beginning
of life and until changes in properties
become small (changes are substantial
2
up to ~ 1-2 MW · y/m )
• Initial data on failure modes & effects
• Establish engineering feasibility of
blankets (satisfy basic functions &
performance, up to 10 to 20 % of
lifetime)
• Select 2 or 3 concepts for further
development
Modules/Sectors
• Identify lifetime limiting failure modes
and effects based on full environment
coupled interactions
• Failure rate data: Develop a data base
sufficient to predict mean-timebetween-failure with confidence
• Iterative design / test / fail / analyze /
improve programs aimed at reliability
growth and safety
• Obtain data to predict mean-time-toreplace (MTTR) for both planned
outage and random failure
• Develop a database to predict overall
availability of FNT components in
DEMO
D
E
M
O
Many R&D tasks are highly interactive, and collectively, they provide
information critical to design, procurement specifications,
qualification/acceptance tests, and definition of operating conditions
US ITER TBM
Example:
Flow Channel Insert Function
Decouple PbLi & FS
Thermal insulation
Electric insulation
10
Electrical Conductivity (S/m)
5
0
-5
-10
-15
-20
-25
-30
0
0.0005
0.001
0.0015
0.002
0.0025
0.003
0.0035
0.004
1/T (1/K)
Flow Channel Insert
(FCI) in DCLL
Thermofluid MHD
Effectiveness of FCI as
electric/thermal insulator
MHD pressure drop and
flow distribution
MHD flow and FCI
property effects on T
ITER TBM
Low primary stress
Robust to thermal
stress - T ~200C
Structural Analysis
FCI stresses
FCI deformations
FCI/SiC Devel. & Fabrication
Tailoring k and 
k(T), (T)
Irradiation effect
Fabrication issues
ITER DT
MHD Experiments
 Manifolds
 3D FCI features
ITER DT: Max stress<45 MPa
UCLA Manifold Flow distribution Experiment (~1m length)
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.
US ITER TBM
CAD model of
structure
CAD Model Input
Fix CAD
model
Temperature in
solid domain
CAD to Analysis Intermediaries
Neutronics
Electromagnetics
Thermo Fluid
Mass Transfer
Structural
Stress and Strain in
solid domain