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Sensitivity and Uncertainty Analysis of LargeScale Systems

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Title: Sensitivity and Uncertainty Analysis of LargeScale Systems


1
Sensitivity and Uncertainty Analysis of
Large-Scale Systems
  • Dan G. Cacuci
  • Commissariat a lÉnergie Atomique, France
    University of Karlsruhe, Germany
  • ACE Workshop, NCSU, Raleigh, NC, May 31 June
    1, 2006

2
OUTLINE
  • Sensitivity and Uncertainty Analysis of Models
    and Data Basic Concepts
  • Paradigm Applications of ASAP to Large-Scale
    Systems
  • QUENCH (Reactor Safety RELAP5/MOD3.3)
  • IFMIF (Reliability Markov Chains)
  • Global Adjoint Sensitivity Analysis Procedure
    (GASAP) for Nonlinear Systems
  • On-Going EURATOM Projects
  • NURESIM (NUclear REactor SIMulation)
  • SNF-TP (Sustainable Nuclear Fission Technology
    Platform)
  • Open Problems (Grand Challenges ?) For Audience
    Discussion

3
Sources of Uncertainties
  • 1. stochastic uncertainty
  • Arises because the system under investigation can
    behave in many different ways
  • 2. subjective (epistemic) uncertainty
  • Arises from the inability to specify an exact
    value for a parameter that is assumed to have a
    constant value in the respective investigation.
  • Epistemic (subjective) uncertainties characterize
    a degree of belief regarding the location of the
    appropriate value of each parameter.
  • In turn, these subjective uncertainties lead to
    subjective uncertainties for the response, thus
    reflecting a corresponding degree of belief
    regarding the location of the appropriate
    response values as the outcome of analyzing the
    model under consideration.

4
Example PSA of Nuclear Power Plants Involve
Both Stochastic and Epistemic Uncertainties
  • Stochastic uncertainties arise due to the
    hypothetical accident scenarios which are
    considered in the respective risk analysis
  • Epistemic uncertainties arise because of
    uncertain parameters that underlie the estimation
    of the probabilities and consequences of the
    respective hypothetical accident scenarios

5
SCOPE of Sensitivity Uncertainty Analysis
  • Scope of local analysis to analyze the behavior
    of the system response locally around a chosen
    point (for static systems) or chosen trajectory
    (for dynamical systems) in the combined phase
    space of parameters and state variables.
  • Scope of global analysis to determine all of the
    system's critical points (bifurcations, turning
    points, response maxima, minima, and/or saddle
    points) in the combined phase space formed by the
    parameters and dependent (state) variables, and
    subsequently analyze these critical points by
    local sensitivity and uncertainty analysis.

6
METHODS Statistical and Deterministic
  • Statistical Methods sampling-based methods
    (random sampling, stratified importance sampling,
    and Latin Hypercube sampling), first- and
    second-order reliability algorithms (FORM and
    SORM, respectively), variance-based methods
    (correlation ratio-based methods, the Fourier
    amplitude sensitivity test, and Sobols method),
    and screening design methods (classical
    one-at-a-time experiments, global one-at-a-time
    design methods, systematic fractional replicate
    designs, and sequential bifurcation designs).
  • Deterministic Methods brute-force method
    based on recalculations, the direct method
    (including the decoupled direct method), the
    Greens function method, the forward sensitivity
    analysis procedure (FSAP), and the adjoint
    sensitivity analysis procedure (ASAP).

7
Important Distinction Statistical vs.
Deterministic Methods
  • Statistical uncertainty and sensitivity analysis
    methods first commence with the uncertainty
    analysis stage, and only subsequently proceed to
    the sensitivity analysis stage.
  • The above conceptual procedural path is the
    reverse of the path underlying the deterministic
    methods of sensitivity and uncertainty analysis,
    where the sensitivities are determined prior to
    using them for uncertainty analysis

8
Uses of local sensitivities
  • Understand the system by highlighting important
    data
  • Eliminate unimportant data
  • Determine effects of parameter variations on the
    systems behavior
  • Design and optimize the system (e.g., maximize
    availability/minimize maintenance)
  • Reduce over-design
  • Prioritize the improvements to be effected in the
    respective system
  • Prioritize introduction of data uncertainties
  • Perform local uncertainty analysis by using the
    method of propagation of errors (also known as
    the propagation of moments, or the
    Taylor-Series). Note the propagation of
    errors method is used both for processing
    experimental data obtained from indirect
    measurements and also for performing uncertainty
    analysis of computational models.

9
Measurements Basic Concepts and Terminology (1)
  • A measurement is the process of finding the value
    of a physical quantity experimentally with the
    help of special devices called measuring
    instruments.
  • The result of a measurement is a numerical value,
    together with a corresponding unit, for a
    physical quantity. Note that a measurement has
    three features
  • The result of a measurement must always be a
    number expressed in sanctioned units of
    measurements. The purpose of a measurement is to
    represent a property of an object by a number.
  • A measurement is always performed with the help
    of some measuring instrument measurement is
    impossible without measuring instruments.
  • A measurement is always an experimental procedure.

10
Measurements Basic Concepts and Terminology (2)
  • The true value of a measurable quantity is the
    value of the measured physical quantity, which,
    if it were known, would ideally reflect, both
    qualitatively and quantitatively, the
    corresponding property of the object.
  • The theory of measurement relies on the following
    three postulates
  • The true value of the measurable quantity exists
  • The true value of the measurable quantity is
    constant (relative to the conditions of the
    measurement)
  • The true value cannot be found.
  • Since measuring instruments are imperfect, and
    since every measurement is an experimental
    procedure, the results of measurements cannot be
    absolutely accurate.

11
Classification of Measurement Errors
  • Methodological errors are caused by
    unavoidable discrepancies between the actual
    quantity to be measured and its model used in the
    measurement.
  • Instrumental measurement errors are
    caused by imperfections of measuring instruments.
  • Personal errors are caused by the
    individual characteristics of the person
    performing the measurement.
  • The general form for the absolute measurement
    error is
  • Since the true value of a measurable quantity is
    always unknown, the errors of measurements must
    be estimated theoretically, by computations,
    using a variety of methods, each with its own
    degree of accuracy.

12
Direct and Indirect Measurements
  • Direct measurement the quantity to be measured
    interacts directly with the measuring instrument,
    and the value of the measured quantity is read
    directly from the instruments indications.
  • Indirect measurement the value of the unknown
    quantity is calculated by using matched
    measurements of other quantities, called measured
    arguments or, briefly, arguments, which are
    related through a known relation to the measured
    quantity.
  • For example, the density of a homogeneous solid
    body is inferred from an indirect measurement, in
    three steps (i) measuring directly the bodys
    mass (ii) measuring directly the bodys volume
    (iii) taking the ratio of the measurements
    obtained in the steps (i) and (ii).

13
The Measurement Equation
  • In an indirect measurement, the true but unknown
    value of the measured quantity or response,
    denoted by R, is related to the true but unknown
    values of the arguments

  • by a known relationship (i.e., function) f.
  • This relationship is called the measurement
    equation, and can be generally represented in the
    form
  • NOTE the measurement equation can be
    interpreted to represent not only results of
    indirect measurements but also results of
    computations.

14
Propagation of Errors (1)
  • In practice, the true values
    are not known they are considered to be random
    variables distributed according to a joint
    probability density function
  • with expectation values
    and covariances
  • The measurement equation becomes

15
Propagation of Errors (2)
  • Expanding R in a Taylor series gives
  • For uncorrelated parameters

16
Propagation of Errors (3)
  • Variance (uncorrelated parameters)
  • When only linear terms are retained, with
    correlated parameters

17
Consistent Combination of Computational and
Experimental Information Data Adjustment/Assimila
tion
  • Computed responses
  • Parameters , with
    covariances
  • To first order
  • Hence, covariance for computed response is
  • Measured responses ,
    with
  • Response deviations
  • Response-parameters covariances

18
Data Adjustment/Assimilation (2)
  • Define adjusted parameters
  • adjusted responses
  • To first order
  • Bayes Theorem yields
  • adjusted parameters
  • adjusted responses
  • adjusted (reduced) parameter covariances
  • adjusted (reduced) response covariances
  • Consistency check test

19
Adjoint Sensitivity/Uncertainty Analysis
Procedure (ASAP)
  • Fundamental Goal of ASAP use Adjoint Operators
  • to compute deterministically the response
    sensitivities
  • exactly and efficiently.
  • ASAP circumvents the need to perform repeatedly
    the expensive Forward Sensitivity calculations.

20
Sensitivity Analysis Implementation Conceptual
Flow Chart
Mathematical Model Select Base-Case
Problem Select Responses
Discretized FSM
Differential FSM
21
Differential FSM
Discretized FSM
Differential Adjoint Sens. Model (ASM)
Discretized Adjoint Sens. Model (DASM)
22
Test Bundle in the QUENCH Facility
23
QUENCH Fuel Rod Bundle RELAP Model
24
THE RELAP5/MOD3.2 Two-Fluid Model (REL/CDE)
  • RELAP5/MOD3.2 simulates a wide variety of
    hydraulic and thermal transients in nuclear and
    non-nuclear systems, concentrating on simulation
    of design basis accidents in LWRs.

25
Sensitivity Analysis Implementation
  • For nominal values Go, solve the RELAP5
    original system to obtain
  • the base-case values co and Ro(co , Go)

26
RELAP5/MOD3.2 Discretized Model
  • Staggered spatial mesh RELAP volumes and
    junctions
  • Time-discretization semi-implicit or nearly
    implicit
  • 13 coupled nonlinear difference equations

27
Adjoint Sensitivity Model for RELAP5/MOD3.2
  • The (Discrete) Adjoint Sensitivity Model for the
    Two-Fluid Equations (ASM-REL/TF)
  • Note The Adjoint System does not depend on G, so
    it must be solved only once for each R.
  • The sensitivity DR becomes

Once F(n) is obtained from the Adjoint System,
DR can be calculated most efficiently for any G.
Thus, ASAP should be used in practice for
large-scale systems with many parameters
variations.
28
Heat Structure Model in RELAP5/MOD3.2
  • 1 heat conduction equation for each heat
    structure
  • Forward Sensitivity System (FSS) for the heat
    conduction equations

29
  • Implement Adjoint Sensitivity Analysis Procedure
    (ASAP)
  • Obtain the Adjoint Sensitivity Model
    (ASM-REL/TFH)
  • where
  • Note The Adjoint System does not depend on
    parameter variations G, so it must be solved only
    once for each response R.
  • The sensitivity DR is

Once FA(n) is obtained from the Adjoint System,
DR can be calculated most efficiently for any G.
30
RELSEN Input Processing
RELAP ADJSEN
  • Schematic representation of the ASAP
    implementation in RELAP

31
  • Quench-04 Sequence of Events

32
Time-evolution of the relative sensitivities of
the inner ring heated rod at 1.3m to the most
important parameters
33
Nomenclature
  • ?1 Nominal power factor 0.7
  • ?2 Nominal power from 0 to 121s 4279W
  • ?3 Nominal power up to 2088.6s 16350W
  • ?4 Nominal power up to 2103s 3874W
  • ?6 Nominal internal source multiplier (axial
    peaking factor) for power of heat structure of
    the heated rod at 0.7m 0.05255. This value is
    multiplied by the power to obtain the total power
    generated in this heat structure
  • ?8 Zircaloy, nominal volumetric heat capacity at
    640K 2168KJ/m³K
  • ?11 ZrO2 Pellets, nominal volumetric heat
    capacity at 700K 3510KJ/m³K
  • ?23 Nominal surface area of volume 0.003007m²,
    volume centre at 1.2m of the pipe height

34
IFMIF Plant
Accelerator D, 32-40MeV, 125mA x 2
Target Liquid Li Jet, Beam Foot Print 5 x 20
cm2 Test Cell 0.5 L (20-50dpa/fpy), 6 L (1-20
dpa/fpy)
35
Accelerator System
RF Tube Cavity Circulator
Crowbar RF Driver Rectifier
Switchgear Transformer Rectifier
50m
Li-Target
5m
100 keV Injector
5-8 MeV RFQ
40 MeV DTL
46 m
High Energy Beam Transport
  • Duty Factor CW
  • Availability gt 88
  • Maintainability hands-on
  • Design Lifetime gt20 years

Ion Source Filament or ECR Type RF Tube and
Windows Low Beam Divergence
36
D-Li Stripping Neutron Source
Typical Reactions 7Li(d,2n)7Be
6Li(d,n)7Be 6Li(n,T)4HeDeuterons 32,
36, 40 MeV 2x 125 mA Beam footprint 5x20
cm2
37
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38
Overall IFMIF System Availability Requirements
  • Availability goal 70 of calendar time
  • 365 days x 24 hrs x 0.70 8760 hrs x 0.70 6132
    hrs
  • Scheduled maintenance 1160 hrs
  • 1 mo shutdown 31x 24 744 hrs
  • 8 hr maint./wk 52 x 8 416 hrs
  • Scheduled operating time 7600 hrs
  • Required inherent availability 6132/7600
    0.8068
  • (This number is a budget, which assumes that on
    the average, over its design life, the machine
    may be down 1468 hours per year in unscheduled
    repairs due to randomly occurring failures that
    cannot be predicted deterministically neither
    from monitoring the wear and tear nor in any
    other way - for these failure modes only a
    statistical estimate is possible. Also, every
    repair leaves the system in exactly the same
    state as it was before the failure, i.e. no
    better or worse)

39
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40
Reliability/Availability/Maintainability/Inspectab
ility RAMI
RAMI
LIFE-CYCLE MANAGEMENT
PRA
Consequences Hazards Releases
Radiological Chemical Exposure Security L
osses Production Budget
Schedule Quality
Event Trees
Fault Trees
Frequencies Initiators Preventors
Mitigators
Specifications
RELIABILITY I/MTBF
AVAILABILITY I-MTTR/MTBF
MAINTAINABILITY I-MTTM/MTBM
INSPECTABILITY I-MTTI/MTBI
TECHNOLOGICAL DEVELOPMENT
EQUIPMENT
OPERATIONS/ COMPLIANCE
41
Illustrative Example Risk analysis process for a
plant, showing relationship of pinch points,
frequency vectors, event trees and transition
matrices.
42
Schematic of an Event Tree (Horizontal), shown
with Fault Trees (Vertical) used to evaluate
probabilities of different events
43
  • The parameters xi, i1,,m, that enter a RAMI
    model are considered random variables distributed
    according to given probability distribution
    function (PDFs)
  • Hence, the Reliability Availability of a system
    will itself be a random variable (since it is a
    function of random variables).

44
RAMI assists designers towards optimum system
design by
  • Establishing reliability and maintainability
    requirements at the subsystem and component
    levels,
  • Identifying system sensitivities to RAMI
    uncertainties,
  • Influencing the level of design redundancy,
  • Estimating the contribution of maintenance to the
    life cycle cost (spares and replacements),
  • Identifying the areas for potential technology
    development.

45
RAMI Modeling Steps
  • a. Top Down Analysis
  • Identify the major subsystems
  • Break up each major subsystem in its constitutive
    assemblies
  • Break up each assembly in sub-assemblies
  • Break up each sub-assembly in its components
  • b. Bottom Up Synthesis
  • Determine RAMI values for individual components
  • Calculate RAMI values for the sub-assembly from
    its components
  • Continue RAMI calculations at successively higher
    order structures, by considering the structures
    at each level as the components of a higher level
    structure
  • Obtain the TOP-level RAMI values for the highest
    level system

NOTE At each level, Markov-type models are
usually used to calculate Dynamic RAMI values for
the respective structures.
46
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48
The First Level of the Fault-Tree for the
Accelerator System
49
The Markov Chain for the First Level of
Accelerator System
50
The Transition Rate Matrix Structure for the
First Level of Accelerator System
51
Calculation of the derivatives (sensitivities)
  • The system under consideration (including event
    and fault trees,
  • Markov-Models, constraints, correlations) can be
    represented as
  • a single system of K equations of the form
  • subject to boundary and/or initial conditions
    represented as
  • where
  • System response (reliability, failure
    probability, etc.)

52
  • First-order derivatives (sensitivities) of Rsys
    with respect to xi are
  • The functions are obtained by
    solving m-times the following differentiated
    Forward Sensitivity System (of K-equations)
  • subject to boundary and/or initial conditions
  • NOTE the above Forward Sensitivity System must
    be solved anew for each of the m system
    parameters. This is computationally very
    expensive!

53
Conceptual Mathematical Procedure underlying ASAP
  • (i) Rewrite the sensitivities
    in inner-product form as
  • where
  • (ii) Construct the adjoint of the Forward
    Sensitivity System by forming the inner product
    of the adjoint function
    with Eq. (4) to obtain

54
  • (iii) Use the mathematical definition of the
    adjoint operator, namely
  • (iv) Obtain the Adjoint Sensitivity Equations
    for ? by setting
  • with ? subject to adjoint boundary and/or
    initial conditions
  • (v) Obtain, finally, the sensitivities
    in terms of the adjoint function ? as

55
Transient Availability of the Accelerator System
and its Main Subsystems
56
Conceptual Framework for Global Optimization and
Sensitivity Analysis
  • Mathematical Model
  • m linear and/or nonlinear equations
  • parameters
  • dependent variables (pressures, temperatures,
    etc.)
  • inequality and/or equality constraints for
    parameters
  • responses to be optimized

57
Objectives of Global Optimization and Sensitivity
Analysis
  • Find all critical (bifurcation, limit, turning)
    points underlying the nonlinear model
  • Find all critical (maxima, minima, saddle points)
    points of responses
  • Perform local sensitivity and uncertainty
    analysis around selected design and critical
    points

58
Global Aims Cannot be Attained by Concepts Based
on Taylor-Series !
  • A functional Taylor-Series
  • is valid only within its convergence radius!
  • Even the second-order terms are impractical to
    compute (the corresponding adjoints would
    depend on the perturbations !)

59
Global Optimization and Sensitivity Analysis
(Cacuci, 1990) Homotopy Path Computed by
Pseudo-Arc-Length Continuation
  • Homotopywhere




  • are the adjoint
    functions.

60
Pseudo-arc-length continuation
  • Impose
  • which implies
  • Thus s becomes the arclength parameter on the
    path in the inflated space
  • Note determines the critical
    points of P
  • determines the
    bifurcation and turning points
  • Computations along the homotopy path are
    performed efficiently using a combined
    Newton-Secant (with regula falsi) method, which
    determines all critical points, globally, with
    probability one.

61
EURATOM Nuclear Reactor Simulations (NURESIM)
Software Platform
  • EU Integrated Project 36 months (2005 - 2007
    7 630 500)
  • Objective to provide a European Standard
    Software Platform for modeling, recording, and
    recovering computer data for the next-generation
    nuclear reactors simulations
  • 18 Partners CEA EDF (F), F. Z. Rossendorf
    GRS Uni-Karlsruhe (D), PSI (CH), ASCOMP (CH),
    TU-Delft (N), KTH (S), Uni-Pisa (I), U.P. Madrid
    (S), Uni-Louvain (B), JSI (Slovenia), VTT LUT
    (Finland), INRNE (Bulgaria), NRI (Czech Rep.),
    KFKI (Hungary)
  • Coordinator CEA
  • 5 Sub-Projects Core Physics, Thermal-Hydraulics,
    Multi-Physics, Sensitivity Uncertainty
    Analysis, Integration
  • Common Software Platform SALOME (CEA)

62
NURESIM Organization
63
The NURESIM Software Platform Architecture
Coupling Solvers through SALOME
64
DESCARTES Architecture
65
KALIF Platform for Sensitivity Uncertainty
Analysis
66
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67
EURATOM Sustainable Nuclear Fission Technology
Platform (SNF-TP)
  • Coordination Action 24 months
  • 22 Partners CEA, CNRS, JRC, PSI, SCK/CEN, FZR,
    FZK, KFKI, NRI, JSI, NRG, CIEMAT, ENEA, U.P.
    Madrid, Uni-Karlsruhe, U-Rome, EDF, AREVA,
    ANSALDO, VTT, Vattenfall, NEXIA
  • Coordinator CEA

68
Sustainable Nuclear Fission Technology Platform
(SNF-TP)
  • Objectives
  • Establish a sustainable, closed fuel cycle for
    electricity production using innovative
    (Generation IV) fast neutron reactor systems in
    conjunction with partitioning and transmutation
    (PT) technologies
  • Establish a commercially viable Very High
    Temperature Reactor (VHTR) for process heat and
    hydrogen production
  • Improve the performance of currently operating
    (Generation II) and future near-term (Generation
    III) LWRs while maintaining a high degree of
    safety, assessment of novel designs (e.g., SCWR),
    and establishing a unified approach of LWR life
    time extension
  • Assure adequate training to preserve and enhance
    the human competence in the nuclear field
    maintain renew the infrastructure necessary for
    achieving sustainability of nuclear energy
    cooperate with other EU-Projects, especially the
    hydrogen platform, geological waste disposal, and
    fusion materials activities.

69
Sustainable Nuclear Fission Technology Platform
(SNF-TP)
LWR (current Gen-3) Competitiveness and Safety
Optimization
VHTR Process Heat, Electricity H2
Materials Fuel Development
Reactor Design Safety
Training and RD Infrastructures
SRA Platform Deployment
System Integration (Economy, non proliferation
)
Fast Neutron Systems Closed Fuel Cycle, PT
Critical Reactors ADS
Geological Disposal Technologies, design, safety
assessment
70
Sustainable Nuclear Fission Technology Platform
(SNF-TP)
71
Road Map for Establishing a Technology Platform
GoP
Vision 2020
Report of the Group of Personalities
CASNF-TP
SRA
The Strategic Research Agenda - Revision every 2
years -
Stakeholders
Research Programs
Public (EU, National, Euro-control,
etc.) and Private (Industry)
Research Projects
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