Intro to Task 3: Core Instrumentationresearch.engr.oregonstate.edu/treat-irp/sites/... · Task 3:...
Transcript of Intro to Task 3: Core Instrumentationresearch.engr.oregonstate.edu/treat-irp/sites/... · Task 3:...
MIT NUCLEAR REACTOR LABORATORYan MIT Interdepartmental Center
Intro to Task 3: Core InstrumentationDavid Carpenter and Kaichao Sun
11/19/2015 – DOE NE IRP Kickoff Meeting, INL
Research Scientists
Task 3 Overview
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Instrumentation Plano Identify TREAT core monitoring needso Select sensors and requirementso Develop instrumentation plan
Benchmarkingo Design and selection of in-reactor instrumentation testso Modeling (performance and safety)o Validation experiments
—Steady-state and transient testso Analyze data and develop instrumentation report
Task 3: Core Instrumentation
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3.1 Instrumentation Plano 3.1.1 Review TREAT core design and test plans MITo 3.1.2 Identify core parameter monitoring needs MITo 3.1.3 Determine applicable flux/measurement range MITo 3.1.4 Select TREAT core instrumentation MITo 3.1.5 Identify instrumentation calibration requirements MITo 3.1.6 Develop TREAT core instrumentation plan MIT
3.2 Initial Benchmark Evaluationo 3.2.1 Develop Benchmark experimental plan using the MITR MITo 3.2.2 Select test instrumentation MITo 3.2.3 Design test assembly for OSTR and MITR MITo 3.2.4 Conduct experiment safety review and approval MITo 3.2.5 Perform core analysis with MCODE MITo 3.2.6 Assemble and test data acquisition systems MITo 3.2.7 Perform steady-state experiments at MITR MITo 3.2.8 Perform steady-state experiments at OSTR OSUo 3.2.9 Perform transient experiments at MITR MITo 3.2.10 Perform transient experiments at OSTR OSUo 3.2.11 Analyze experimental data MITo 3.2.12 Evaluate core analysis and instrumentation measurement uncertainties MIT
Task 3.1 Instrumentation Plan
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Review of TREAT core design & test planso Conditionso Geometryo Facilities
What are the parameter monitoring needs?o Existing instrumentation vs. requirementso Opportunities for increasing technology readinesso Redundancy, complimentary techniques, advanced
methods
Task 3.1 Instrumentation Plan (2)
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Create plano Develop instrumentation list & down select
—Operations—Experiments
o Calibration requirements (QA)o Placement Sensor technologies
o Fission & ion chamberso SPDso Thermometryo Other?
Size (miniaturization)Range & resolutionTemporal responseCost & availability
Task 3.2 Initial Benchmark Evaluation
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Development of Instrumentation Experimentso Benchmarking plan for steady-state and transientso Selection of test instrumentationo Design and review of experiments for MITR and OSTR
Irradiations and Model Validationo Core analysis (MCODE)o Bench sensor data acquisition testingo Conduct experiments and MITR and OSTRo Analysis of experiment data vs. predictionso Uncertainty analysis
Reactor Irradiations
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Leveraging strengths for combination of:
o Expert review and selection o Experiment data generationo Explicit modeling
Opportunity to test proposed instrumentation (sensors + data acquisition)
Opportunity to evaluate new technology
In-Core Options
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Variety of test variableso Neutronic impacto Range & sensitivityo Temporal responseo Thermal effectso Repeatability / activation effects
1-to-1 instrument comparisons
MITRo Steady-state 0-6 MWo Transient T≥20s (<1kW)
OSTRo Steady-state 0-1MWo Transient ≤$2.25
ICSA thimble
MITR Irradiation Locations
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Facility Size Neutron Flux (n/cm2‐s)
In‐core
3 availableMax in‐core volume ~ 1.8” ID x 24” long
Thermal: 3.6x1013Fast: up to 1.2x1014(E>0.1 MeV)
Beam ports Various radial: 4” to 12” ID
Thermal: 1x1010 ‐1x1013 (source)
Vertical irradiation position
2 vertical (3GV) 3” ID x 24” long
Thermal: 4x1012 ‐1x1013
Through ports One 4” port (4TH)One 6” port (6TH).
Avg thermal: 2.5x1012to 5.5x1012
Pneumatic Tubes
One 1” ID tube* (1PH1) Thermal: up to 8x1012
One 2” ID tube* (2PH1) Thermal: up to 5x1013
Fission Converter BeamFacility (FCB)
Beam aperture ~ 6” ID Epithermal: ~ 5x109
Thermal Beam Facility (TNB)
Beam aperture ~ 6” ID Thermal: up to 1x1010
Recent In-Core Experiments
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ACI (Water Loop)o SiC LWR cladding in PWR conditions
BSiC (Water Loop)o SiC channel box and guide tubes
WATF (Water Loop)o Accident-tolerant cladding and coatings
HYFIo U-Zr-H LWR fuel rods with liquid metal
bonding
AFTRo Internally- and Externally-Cooled Annular
Fuel
HTIFo Very high-temperature gas irradiation
Drexel (ICSA)o MAX-phase materials at 300-700°C in
inert gas
LUNA (ICSA)o Fiber optics at 700°C in inert gas
FS-1 (ICSA)o FHR coupons in flibe salt at 700°C
FS-2o FHR coupons in flibe salt at 700°C
ULTRA (ICSA)o Ultrasonic transducer and self-powered
detector test
ICCGMo Actively-loaded real-time crack growth
monitor
In-Core Sample Assembly
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Reactor core tank ICSA thimble In‐core region
MIT Nuclear Reactor
Laboratory
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ICSA Thimble in MITR Core
MIT Nuclear Reactor
Laboratory
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Fiber-Optic Sensors in ICSA
Ultrasonic Sensors (INL & PSU)
Magnetostrictive and Piezoelectric ultrasonic sensors operating in-core
o Particularly interested in fast neutron damageo Real-time monitoring throughout irradiationo Two types of magnetostrictive magnetso Three types of piezoelectric crystals
Self-powered detectors included for local power monitoring
o Vanadium neutron detector (SPND)o Platinum gamma detector (SPGD)
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ULTRA Design
AlN‐1
BiTi
AlN‐2
ZnO
TC2
TC1Galfenol‐1 and Remendur‐1
Piezo Drop‐Ins
Meltwires
ULTRA Capsule Axial Layout
Magnetostrictive Drop‐Insand Flux Wires
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Reactor Physics Code System
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Fuel Cycle Part
Static Part
Dynamic Part
NeutronicsMCNP
Core Thermal‐HydraulicsRELAP5 / StarCCM+
DepletionMCODE (ORIGEN)
MITR Fuel ManagementMCODE‐FM
Uncertainty QuantificationDAKOTA
Calculation of X‐sections and Reactivity Coefficients
System Thermal‐Hydraulics RELAP5 (LOF)
1D Reactor Kinetics PARET (RIA)
Design Basis Accident SCALE
Power Distribution
OpenMC
MCNP/MCODE Model and Validation
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Core center-line~5 cm below
Uncertainty Quantification
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Fuel peak temperature satisfy K-S normal distribution test Rank correlation coefficients adopts Pearson model
1 1 1
2 22 2
1 1 1 1
1
ˆ1 1
n n n
i i i ii i i
n n n n
i i i ii i i i
x y x yn
x x y yn n
1360 1400 1440 1480 1520 1560 16000.00
0.05
0.10
0.15
0.20
0.25
0.30
Prob
abili
ty
Temperature (K)
Peak fuel temperature
Temperature limit 1573K
Sensitivity Analysis95/95 Criteria UQ