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“CAD-centric” Integrated Multi-physics Simulation Predictive Capability for Plasma
Chamber Nuclear Components
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Others working on separate parts of the subject
M. Abdou, M. Ulrickson (and team), M. Sawan (and team), M. Youssef, B. Merrill
A. Ying (UCLA), R. Reed (graduate student), R. Munipalli (HyPerCom)
Unlike FSP, the integrated modeling is progressed in a smaller scale fashion
FNST meetingAugust 2, 2010
UCLA
Aligned with ReNew Thrust 15
Acknowledgements to graduate(d) students M. Narula, R. Hunt, and H. Zhang (UCLA)
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Integrated Simulation Predictive Capability (ISPC) as a part of ReNeW Thrust 15: Creating integrated models for attractive
fusion power systems
ReNeW Thrust 15 Integrated Model Objectives:
•Develop predictive modeling capability for nuclear components and associated systems that are science-based, well-coupled, and validated by experiments and data collection.•Extend models to cover synergistic physical phenomena for prediction and interpretation of integrated tests and for optimization of systems.•Develop methodologies to integrate with plasma models to jointly supply first wall and divertor temperature and stress levels, electromagnetic responses, surface erosion, etc.
Today’s Trend in Simulation:– Treat complexity of entire
problem• Extreme geometric complexity • Multi-physics, Multi-scales
– Inter-disciplinary approach• Modernize codes & Interpret
phenomena from interrelated scientific disciplines
– High accuracy & thorough understanding at each level
– Interactive visualization and post processing (Intelligent Expert System)
“ITER Baking in progress”
An integrated model tool potentially contributes to more efficient FNST R&D
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0 200 400 600 800 1000 1200
Baking at inlet T increase at 10K/h
TinletToutletT_MaxT_MinCuBeShield-SSFW-SS
Time (s)
FW/BLKT temperature response with time with water inlet temperature at 10K/h ramp-up rate.
• The time-dependent BLKT outlet temperature can be used in RELAP5 system code for heating control analysis.
• The flow pattern and associated heat transfer inside a FW/BLKT is very complex, which RELAP5 cannot model.
• Provide high level of accuracy and substantially reduce risk and cost for the development of complex plasma chamber in-vessel components
• Facilitate simulation of normal and off normal operational scenarios. • Offer capabilities for system optimization
• Allow insight and intuition into the interplay between key multi-physics phenomena (occurring at a level where instruments cannot be installed.)
• Better understand the state of the operation through limited diagnostics
BLKT-12 CATIA model
FW (Be)
Shield Module
CAD-centric modeling tools are being used in the US ITER FW/Blanket Shield Design (design by analysis)
(led by Mike Hechler-ORNL and Mike Ulrickson-SNL)
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Snapshots of velocity magnitudes at different pipes (BLKT-12 SM)
Nuclear heating profile
X-Y plane (8 cm above mid-plane) FW/BLKT-12
CFD/thermo-fluid
Mechanical load under a disruption
Design by analysis incorporating CAD model becomes even more important in regard to first wall panels shaped as local limiters
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• The heat flux profile is extremely non-uniform: heat flux as high as 5 MW/m2 (7.5 MW start-up and ramp down), 40% of wall EHF modules
• A shaped FW design brings forth the importance of using “prototype” in the analysis
location Peak heat fluxRows or panels
affected
Inboard : start-up 4.4 MW/mm² 3,4
Outboard 3.6 MW/m² 14,15,16,17
Shine thru 4.0 MW/m²6 panels on rows
15,16
Top 4.6 MW/m² 7-8-9-10
CuCrZrVon Mises (Pa)
In recent design, slot was removed
CuCrZr
Reference: R. Mitteau et. al., Heat loads and shape design of the ITER first wall, ISFNT-9 (2009)
ITER FW/shield design still evolving
Simulation performed on an engineering CAD model allows practical design assessments
6ISPC can potentially reduce risk and cost of the component development
Mid-plane nuclear heating (gamma: left; neutron: right)
W/cc
• Location of the instrument and the associated perturbation to the data
• Analysis with a detailed geometric drawing with instrumentations in-place needed
Thermomechanics Analysis
Proper manifold designs to provide uniform flow distributions among many parallel flow paths
Adequate cooing to all parts
DCLL He-coolant inlet manifold
He-velocity
High temperature at upper structures
PbLi velocity
PbLi velocity
Velocity :m/s
Stress concentration
Initial results with simplified geometry& operating condition
Inlet to 2nd FW cooling panel
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What numerical software are available for CAD-centric integrated model?
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Attila: Commercial SoftwareTetrahedral mesh
MCNP – MCAMCommunity Developed
Orthogonal mesh
DAG-MCMP
MOAB & CGMCAD Voxels
MCNP(X)MCNPXNative
Geometry (Other)
(many neutronics codes available: deterministic or Monte Carlo)
Hybrid code ADVANTG (MCNP + Denovo)
ITER FW Panel
Attila is now being used to calculate radioactivity of components
ITER 40o A-lite Neutronic model
Total (neutron + photon) flux
ORNL
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Solving individual physics using its optimized numerical technique and running simultaneously with a smart transfer of information
Sample analysis codes and mesh requirements in ISPC
Physics Analysis code Mesh specification
Neutronics MCNP Monte Carlo mesh tally (cell based)
Attila Unstructured tetrahedral mesh (node based)
Electro-magnetics
OPERA(Cubit)
Unstructured tetrahedral (Hex-) mesh (node based)
ANSYS Unstructured Hex/Tet mesh (node based and edge based formulations)
CFD/ Thermo-fluids
SC/Tetra Unstructured hybrid mesh (node based)
Fluent/CFX etc.
Unstructured hybrid mesh (cell based)
MHD HIMAG Unstructured hybrid mesh (cell based)
Structural analysis
ANSYS/ABAQUS
Unstructured second order Hex/Tet mesh (node based)
Species transport
COMSOL or others: TMAP, ASPEN
Unstructured second order mesh (node based)
Safety RELAP5-3DMELOCR
System representation code
Imprinting
AF
BC
ED
Merging
DAG-MCNP (UW)
Overcoming CAD discrepancy (e.g. overlapping) is common source of difficulty for MCNP
• Adopting one numerical technique for all simulations in ISPC can limit the size of the problem and is undesirable.
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A multi-disciplinary effort
Verification & Validation
Material database/Constitutive equations/ Irradiation effect
CAD- Geometry
Mesh services Adaptive mesh/mesh refinement
Visualization Data Management: Interpolation Neutral format
Time step control for transient analysis
Partitioning Parallelism
Neutronics Radiation damage rates
Thermo-fluid
Species (e.g. T2) transport
Electro-magneticsMHD
Coupled effect
Special module
RadioactivityTransmutation
Safety
e.g. source
Structure/thermo-mechanics
• Integration of computational software forms the heart of FNST performance prediction
• Data mapping and interpolation across various analysis meshes/codes has to be fast, accurate and satisfy physical conservation laws
• Large scale simulation, leading-edge high performance computing, advanced computational methods, and the development and application of new mathematical models
• Maintain consistency in the geometric representation among the analysis codes
• The CAD-based solid model is the common element across physical disciplines
specialized user FUNction
Data Mapping Script
CAD ModelNeutronics
Thermo-fluid & LM MHD
Electromagnetics
DMS
FW/Plasma Facing Surface Phenomena
DMS
DMS
FUN
Specialized physics models
FUN
Neutron source profile
q”
FW/PFC Thermo-fluid
profile
Stress/Deformation-Analysis
Species Transport
3-D design iterative assessment important
Safety or Transient events
FUN
*
*Structural Support
ISPC Design Process Flow
Tremendous work for ITER FW/SB at SNL
q
12
Jet impingement
He inlet
He outlet
Need experimental data for code verification & validation
Verification/validation needed on integration methodTemperature and He flow
characteristics under 10 MW/m2
“How to” incorporate a bigger resource into ISPC?
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Similar efforts are being pursued in various fields: •within DOE Vision 21 project (Improved asset optimization by integrating ASPEN PLUS and FLUENT)•Nuclear Energy and Simulation Hub •FSP (Fusion Simulation Project)
“to apply existing modeling and simulation capabilities to create a user environment that allows engineers to create a simulation of a currently operating reactor that will act as a "virtual model" of that reactor.---”
Nuclear Energy Innovation Hub
Advanced computational tools are continuously being developed in various projects:SciDAC, ITAPS, CCA, etc.
• Look for synergism• Not re-inventing the wheel but riding on state-of-the-art methodology
Next StepsHow do you see this moving forward?
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Three activities (ITER FW/shield design, TBM program, and FNSF assessment study) provide mechanism, panorama, and opportunity for the development/ benchmark/test of the idea to the extent possible.
However, a substantial effort requires FSP-like or NESH-like commitmentNear term goal •Continue to build/enhance interface and data management (increase degree of automation)
•Establish test cases to further explore the limit of the capability Example test cases•Enhance existing neutronics computational platform for TBM radioactive dose calculations extended to ITER port cell area •FNSF tritium breeding assessment through a complete 3-D base breeding blanket exploratory design analysis •Develop schemes to link to plasma facing surface phenomena, and address FW tritium inventory and permeation losses
• Periodic recovery of implanted tritium has an impact on the TBR requirement; however, its degree of impact is affected by losses from tritium permeation into FW coolant
15
Plasma
Tro
idal
coi
l
Divertor
First wall/Blanket
6.2m
Test Blanket Module(TBM)
Summary• Adopt the state-of-the-art computer technique, high-powered computing, advanced modeling and simulation that is 3-dimensional, high-resolution
• Develop highly integrated predictive capabilities for many cross-cutting scientific & engineering disciplines and deliver faster and more detailed insights into the R&D of in-vessel FNST components and systems
• The goal of an integrated simulation effort then is to be able to model and design a complete DEMO system including irradiation effects, thermofluid/MHD, temperatures and mechanical loads, tritium accountability in entire system (tritium retention, and tritium production and transport processes), and FW/divertor erosion.
Imagine if critical performance parameters can be projected and examined in advance----