iter-d-3g3sqn v1.1 1 thermal & mechanical preliminary analysis elm coil alternate design interim...
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ITER-D-3G3SQN v1.1
1
THERMAL & MECHANICAL PRELIMINARY THERMAL & MECHANICAL PRELIMINARY ANALYSIS ANALYSIS
ELM COIL ALTERNATE DESIGNELM COIL ALTERNATE DESIGN Interim ReviewInterim Review
July 26-28, 2010July 26-28, 2010
In-Vessel Coil System Interim Review – July 26-28, 2010
ITER-D-3G3SQN v1.1 2
OutlineOutline
• BOUNDARY CONDITIONS
• NUCLEAR & RESTISTIVE HEAT GENERATION• LORENTZ & PRESSURE LOADS• RADIATION ; CONDUCTION ; COOLING WATER @ 6 m/sec• MAGNESIUM OXIDE to COIL & JACKETS
• STEADY STATE SANDWICH STRESS RESULTS :
– THERMAL + PRESSURE LOAD RESULTS– THERMAL + PRESSURE + LORENTZ LOAD RESULTS
• DESIGN IMPROVEMENT STRATEGIES
– THERMAL + PRESSURE LOAD RESULTS– THERMAL + PRESSURE + LORENTZ LOAD RESULTS– SUB MODELING ; CORRECTION STRATEGY
• CONCLUSIONS / PLAN:
In-Vessel Coil System Interim Review – July 26-28, 2010
ITER-D-3G3SQN v1.1
Nuclear Heat Operating Modes
ITER-D-3G3SQN v1.1
NUCLEAR HEAT GENERATIONNUCLEAR HEAT GENERATION(W/M^3)(W/M^3)
IVC Interim Design Review – 26-28 July 20104
0.264 m
The Toroidal Leg Nuclear Heat is Applied Based on a Curve fit of data fromUniversity of Wisconsin Team
The Poloidal Leg Applies a Similar Shaped Function
ITER-D-3G3SQN v1.1
IDEALIZED LOAD IDEALIZED LOAD DIAGRAMSDIAGRAMS
Thermal + Pressure Loading
Thermal + Pressure + Lorentz LoadingLo
ad
Time
Time
Load
5 hz
3,000 sec 9,000 sec
30,000 Pulses Unknown Spectrum
STEADY STATE TRANSIENT
ITER-D-3G3SQN v1.1
ELM LORENTZ LOAD VS POSITIONELM LORENTZ LOAD VS POSITION
SECTOR #5 UNIT LOADS ARE MORE CRITICAL IN THE LOWER LEFT QUADRANT
(LFT)
(BOT)(R
HT)
(TRC)
(BLC)
Critical Quadrant
SECTOR 5 FE MODEL LOADS in GLOBAL COORDINATES
Fx Fy Fz
ELM_MD_BOT 132,271 -31,397 -32,429
ELM_MD_BLC 130,406 -8,635 -41,265
ELM_MD_LFT 300,308 -10,272 7,491
ITER-D-3G3SQN v1.1
SANDWICH DESIGNSANDWICH DESIGNSection ViewSection View
IVC Interim Design Review – 26-28 July 20107
Axial Translation Is Allowed
No Hard Mechanical Attachment for tension On the MGO
DESIGN CONCEPT ALLOWS THERMAL DISPLACEMENTWITH SUPPORTS TO REACT LORENTZ LOAD
ITER-D-3G3SQN v1.1
ELEMENT MESHELEMENT MESH
UNIFORM HEXAHEDRAL MESH
Rigid BoundaryRigid Boundary
Flexible Mounts To Facilitate Thermal Growth
Symmetric Boundary
Symmetric Boundary
STEADY STATE TEMPERATURE ANALYSIS
FULL OPERATING CONDITIONS
Resistive Heat Generation
Nuclear Heat Generation
Cooling Water Applied
ITER-D-3G3SQN v1.1
THERMAL BOUNDARY CONDITIONSTHERMAL BOUNDARY CONDITIONS
The Copper Coil Temperature Distribution is an Equilibrium of all Combined Effects
Conduction into Foundation at 100 Cat all foundation interfaces
Radiation Surfaces with View Factor =1 (dark blue surfaces)
Nuclear
HGEN
Temp in =105.7 CTemp out =131.5 C
Unspecified Surface Boundaries are conservatively assumed to be Adiabatic
ITER-D-3G3SQN v1.1
RADIATION ASSUMPTIONSRADIATION ASSUMPTIONS
IVC Interim Design Review – 26-28 July 201012
All Form / View Factors equal to 1.0 Incident Radiation is very small from 100 C Far Field
Emissivity is a Hemispherical AverageAcross all wavelengths and directions
ITER-D-3G3SQN v1.1
Steady State TemperaturesSteady State Temperatures With Heat Generation ; 6 m/s Water Cooling With Heat Generation ; 6 m/s Water Cooling
RadiationRadiation
TEMPERATURES ARE REASONABLE and WITHIN OPERATING LIMITS OF MATERIALS
Max Temp = 476 C on Bracket
ITER-D-3G3SQN v1.1
Max Temperatures ( 472 C ) are within the limits of Stainless SteelWith Cooling Water
Steady State TemperaturesSteady State Temperatures With Heat Generation ; 6 m/s Water Cooling With Heat Generation ; 6 m/s Water Cooling
RadiationRadiation
Stainless Steel Jackets
ITER-D-3G3SQN v1.1
The Coil Temperatures are Consistent with Hand Calculations and the Net Energy Balance of all Applied Thermal Loads
Steady State TemperaturesSteady State Temperatures With Heat Generation ; 6 m/s Water Cooling With Heat Generation ; 6 m/s Water Cooling
RadiationRadiation
Applied Boundary is: Temp in =105.7 CTemp out = 127.2 C
ITER-D-3G3SQN v1.1
Steady State Steady State FaultFault Condition Conditionwith Radiation Coolingwith Radiation Cooling
Fault Condition (No Water Cool or Resistive Heating) with Far Field RadiationResults in Temperatures that are within Material Capacity (316 SS Melt at 1375 C)
Max Temperature Predicted on Surfaces that Exclude Radiation
ITER-D-3G3SQN v1.1
Steady State Steady State Fault Fault ConditionConditionwith Radiation Coolingwith Radiation Cooling
Fault Condition (No Water Cool or Resistive Heating) with Far Field RadiationResults in Temperatures that are within Material Capacity (CuCrZr Melt at 1,078 C)
Conservative Max Copper Temperature= 918 CMelting 1,078 C
ITER-D-3G3SQN v1.1
STEADY STATE STRESS ANALYSIS
THERMAL & DISRUPTION LOADS
ITER-D-3G3SQN v1.1 IVC Interim Design Review – 26-28 July 201019
Steady State Steady State Pressure + Thermal + Lorentz LoadPressure + Thermal + Lorentz Load
Support Reaction Loads Support Reaction Loads
RSYS 12 (Newtons) FX FY FZ14038. -0.16031E+06 -19,761.
.
RSYS 14 (Newtons) FX FY FZ-36461. -0.11263E+06 13456
+Z
+Y
+Z
+Y
Typical Bracket Reaction Loads: FY =36,036 lbs is away from the Reactor on the Toroidal Bracket
FY = 25,178 lbs is away from the Reactor on the Poloidal Bracket
Toroidal
Poloidal
ITER-D-3G3SQN v1.1
Steady State Steady State Pressure + Thermal + Lorentz LoadPressure + Thermal + Lorentz Load
Displacements Displacements
The Displacements are Reasonable for the Specified Boundary ConditionsLorentz Loads Acting Down Toward The Reactor
+Y
+Y0.0066 m = 0.259 in
Note: Local Y displacement is approximately a radial Global Load Coordinates
ITER-D-3G3SQN v1.1
Steady State Steady State Mechanical + Thermal Loads + LorentzMechanical + Thermal Loads + Lorentz
Max Principal StressMax Principal Stress
Stress shows:
1.) Bending across Restraints
2.) Exterior Jackets in Compression
3.) Interior Copper Coil in Tension
Restraint Location
Restraint Location
The Stresses are Excessive However they are ManageableWith the current Strategies in progress
0.19e8 = 2,755 psi
ITER-D-3G3SQN v1.1
Steady State Steady State Mechanical + Thermal LoadsMechanical + Thermal Loads
von Mises Stress von Mises Stress
The Max Copper Coil Stress of 6.5 ksi will be Reduced with Bridge Support The Max Copper Coil Stress of 6.5 ksi will be Reduced with Bridge Support
Copper Coil0.450 e8 Pa = 6,526 Psi
Copper Coil0.185 e8 Pa = 2,683 Psi
ITER-D-3G3SQN v1.1
Steady State Steady State Mechanical + Thermal Loads + LorentzMechanical + Thermal Loads + Lorentz
von Mises Stressvon Mises Stress
Copper Stresses Have Positive Limit Stress Margins and Low Fatigue MarginAdditional Section will be used to Redistribute These stresses
Copper Stresses Have Positive Limit Stress Margins and Low Fatigue MarginAdditional Section will be used to Redistribute These stresses
Max Copper Coil .184e9 Pa = 26,686 psi
20.11184
3.405
61.01184
297
FTU
FTY
M
M
ITER-D-3G3SQN v1.1
REVISED ANALYSISREVISED ANALYSISWith Bridge SupportWith Bridge Support
IVC Interim Design Review – 26-28 July 201024
ITER-D-3G3SQN v1.1 IVC Interim Design Review – 26-28 July 201025
Updated - Steady State TemperaturesUpdated - Steady State Temperatures With Heat Generation ; 6 m/s Water Cooling With Heat Generation ; 6 m/s Water Cooling
RadiationRadiation
Revised Plan July 22, 2010 Inlet Temp 70 C Outlet Temp 120 C
Bridge Support to react outLorentz Loads
ITER-D-3G3SQN v1.1
Sub Modeling PlanSub Modeling Plan
Classical Cut Boundary Displacements applied from Global analysis
Stress to be evaluated forVariable Spring Stiffness and / or applied PreloadsSpringK
Sub Models will be used to test out various strategies in critical areas such as the corners or restraint locations to assure that the best design options are thoroughly investigated
Sub Models will be used to test out various strategies in critical areas such as the corners or restraint locations to assure that the best design options are thoroughly investigated
C0
eTemperatur
ITER-D-3G3SQN v1.1
Steady State Steady State Pressure + Thermal LoadsPressure + Thermal Loads
von Mises Stress von Mises Stress
Bridge Support can be used to Shape and Redistribute Stresses on the CoilAdditional Shaping and Stiffness Changes with Sections changes will be used to React out Stresses
Bridge Support can be used to Shape and Redistribute Stresses on the CoilAdditional Shaping and Stiffness Changes with Sections changes will be used to React out Stresses
Copper Coil0.37 e8 Pa = 5,366 Psi
ITER-D-3G3SQN v1.1
Steady State Steady State Pressure + Thermal + Lorentz Loads Pressure + Thermal + Lorentz Loads
Von Mises StressVon Mises Stress
50.01270
3.405
1.01270
297
FTU
FTY
M
M
Max Copper Coil= 0.18e8 Pa = 2,465 psi
Bridge Support can be used to Shape and Redistribute Stresses on the CoilAdditional Shaping, Stiffness Changes and Sections changes will be used to React out Stresses
Bridge Support can be used to Shape and Redistribute Stresses on the CoilAdditional Shaping, Stiffness Changes and Sections changes will be used to React out Stresses
ITER-D-3G3SQN v1.1
ConclusionsConclusions
• The Sandwich Design can be a viable option with the design changes and analysis options in progress.
• The MGO / Jacket Interface is critical to understand the load sharing between the components.
• This Design will survive Fault Operation without Water Cooling.
• An analysis methodology / plan is in place to resolve stress issues.
IVC Interim Design Review – 26-28 July 201029
ITER-D-3G3SQN v1.1 IVC Interim Design Review – 26-28 July 201030
STRESS RESOLUTION TABLE
ITEM Reference Slides in Presentation Dated 7-26-10 STATUS
ISSUE RESOLUTION PRE or POST Column1
1.)Update on Thermal Boundary Conditions
M. Kalish / L. Bryant to Work this Issue PRE
IN PROGRESS
Using FCOOL Program
2.)Nuclear Heat Generation Functions are outdated
Update Curve Fits for Nuclear Heating from data PRE
IN PROGRESS
Provided last week
3.)Stress on Coil Corner too High Complete Sub-models to react load reduce stress PRE
IN PROGRESS
4.)Stress Adjacent to Brackets too high
Complete Sub-models to react load reduce stress PRE
5.) Design the Bolt & Clamp Interface Concept
Complte Hand Calculations & Recommend to Design POST
6.)Complete Transient Stress evaluation; PRE
IN PROGRESS
500 MW, 400 MW, 356 MW Power Levels
7.)Optimize Design Cooling Water Flow Rate
Run Multiple Temperature Data Sets POST
Evaluate Stresses and compare to erosion rates
ISSUE / RESOLUTIONISSUE / RESOLUTION
ITER-D-3G3SQN v1.1
ISSUE / RESOLUTIONISSUE / RESOLUTION
IVC Interim Design Review – 26-28 July 201031
STRESS RESOLUTION TABLE
ITEM Reference Slides in Presentation Dated 7-26-10 STATUS
ISSUE RESOLUTION PRE or POST Column1
8.)Upade Mechanical Properties on MGO Completion of Mechanical Testing PRE
IN PROGRESS
9.)Determine Proper MGO Interface Boundary
Calibrate Parametric Model with Test data PRE
IN PROGRESS
Condition
10.)Complete Stress Pass on Fault Temperatures
Update Stress Model with Temperatures PRE
NO STARTED
With Radiation Cooling Run Fault Stress Pass on Restraints
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