DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING...

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DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS L. HENDERSON FINAL PRESENTATION DECEMBER 17, 2010 Variational Methods Applied to the Even-Parity Transport Equation

Transcript of DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING...

Page 1: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

DAVID SIRAJUDDINU N I V E R S I T Y O F W I S C O N S I N - M A D I S O N

D E P T. O F N U C L E A R E N G I N E E R I N G A N D E N G I N E E R I N G P H Y S I C S N E E P 7 0 5 – A D V A N C E D R E A C T O R T H E O R Y, D R . D O U G L A S S L . H E N D E R S O N

F I N A L P R E S E N T A T I O N

D E C E M B E R 1 7 , 2 0 1 0

Variational Methods Applied to the Even-Parity Transport Equation

Page 2: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Outline

Motivation Development of the even-parity transport equation Variational concepts Ritz Procedure Statement of the variational problem 1-D slab transport

Spatial discretization Angular treatment

Discrete Ordinates Collision probability method Legendre polynomial expansion

Conclusions References

Itcanbeshown.comSirajuddin, David

Page 3: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Outline

Motivation Development of the even-parity transport equation Variational concepts Ritz Procedure Statement of the variational problem 1-D slab transport

Spatial discretization Angular treatment

Discrete Ordinates Collision probability method Legendre polynomial expansion

Conclusions References

Itcanbeshown.comSirajuddin, David

Page 4: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Motivation

Computational methods of the raw form of the integrodifferential form of the transport equation are most readily facilitated by:

Discrete ordinates Integral equations (e.g. collision probability methods)

These methods can become computationally expensive

Discrete ordinates

Ray-effects many discrete ordinates must be used Marching scheme, diamond differencing iterative solution

Integral equations

iterating on a scattering source solving matrix equations with a full coefficient matrices Scattering source approximation method only accurate up to order O(D) detrimental for large system size

calculations

Computational expense may be reduced by recasting the transport equation into a variational form

even-parity transport equation gives rise to a variety of approximation techniques solution requires solving a single matrix equation with sparse coefficient matrices

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Page 5: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Outline

Motivation Development of the even-parity transport equation Variational concepts Ritz Procedure Statement of the variational problem 1-D slab transport

Spatial discretization Angular treatment

Discrete Ordinates Collision probability method Legendre polynomial expansion

Conclusions References

Itcanbeshown.comSirajuddin, David

Page 6: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Development of the even-parity transport equation

Transport equation:

Boundary conditions

Define even/odd angular-parity components

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(even)

(odd)

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Development of the even-parity transport equation

The angular flux is defined in terms of the even/odd parity fluxes

where and

Scalar flux

Current

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Development of the even-parity transport equation

The even-parity equation is arrived at by considering the transport equation evaluated at W and -W

Recalling , subtracting both equations allows a

relation between y- and y+

and, by definition

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Calculation of the even-parity flux allows the computation of the scalar flux and the current!

Page 9: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Development of the even-parity transport equation

The even-parity equation is arrived at by considering the transport equation evaluated at W and -W

Adding and subtracting the above equations produces two new equations that may be combined to eliminate y-

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Even-parity transport equation (isotropic scattering)

Page 10: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Remarks on the even-parity transport equation

Even-parity transport equation

Even-parity only need to solve half the angular domain

Isotropic scattering

Cannot be used directly for streaming particles in vacuum (s = 0)

Underdense materials (s small) must check computational algorithm is stable

The equation is self-adjoint variational extremum principleItcanbeshown.comSirajuddin, David

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Outline

Motivation Development of the even-parity transport equation Variational concepts Ritz Procedure Statement of the variational problem 1-D slab transport

Spatial discretization Angular treatment

Discrete Ordinates Collision probability method Legendre polynomial expansion

Conclusions References

Itcanbeshown.comSirajuddin, David

Page 12: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Theory of Calculus of Variations

Variational methods aim to optimize functionals:

Function: , while a functional:

These functionals are often manifest as relevant integrals

Examples: minimum energy, Fermat’s principle, geodesics

Method: Find an appropriate functional that characterizes y +

Introduce a trial function y+ + dy Enforce dy = 0 y+

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Theory of Calculus of Variations: Vladimirov’s functional

y+ is characterized by the even-parity transport eqn.

A relevant functional F[y+] may be computed by the inner product from the self-adjoint extension of the transport operator [2]

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Page 14: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Theory of Calculus of Variations: Stationary solutions

Model as Inputting into the above functional (after much algebra) the

terms may be grouped according to

Where the zeroeth, first, and second variations depend on , (or ),

and , respectively

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“first variation”

“variation”

“second variation”

“zeroeth variation”

Page 15: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Theory of Calculus of Variations: Stationary solutions

The first variation:

Stationary solutions, , require

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“first variation”

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Examine term-by-term

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Theory of Calculus of Variations: Stationary solutions

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Each term must independently vanish

Examine term-by-term

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Theory of Calculus of Variations: Stationary solutions

Page 18: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Examine term-by-term

Recall

Term 1 vanishes if is a solution to the even-parity transport equation.

This is called our Euler-Lagrange Equation

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Theory of Calculus of Variations: Stationary solutions

Page 19: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Examine term-by-term

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Theory of Calculus of Variations: Stationary solutions

Page 20: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Examine term-by-term

must satisfy the vacuum boundary conditionOr, equivalently,

,

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Theory of Calculus of Variations: Stationary solutions

Modified natural boundary condition

Page 21: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Examine term-by-term

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Theory of Calculus of Variations: Stationary solutions

Page 22: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Examine term-by-term

require no variation = 0

or,

on the reflected surface

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Theory of Calculus of Variations: Stationary solutions

Essential Boundary Condition

Modified natural boundary condition (slab geometry)

Page 23: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Outline

Motivation Development of the even-parity transport equation Variational concepts Ritz Procedure Statement of the variational problem 1-D slab transport

Spatial discretization Angular treatment

Discrete Ordinates Collision probability method Legendre polynomial expansion

Conclusions References

Itcanbeshown.comSirajuddin, David

Page 24: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Solution of the variation problem: Ritz procedure

Suppose we approximate the flux:

Where are known even-parity shape functions, , and are unknown coefficients

Inputting the approximation into the functional dsafd , and enforcing a matrix equation whose solution gives the coefficients

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Page 25: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Solution of the variation problem: Ritz procedure

Recasting in terms of matrices Define ,

Inserting into the Vladimirov functional:

where

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and

Page 26: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Note that is an N x N symmetric matrix, since

And

: N x 1 column vector

: 1 x N row vector

: N x N symmetric matrix

: N x N symmetrix matrix

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Solution of the variation problem: Ritz procedure

Page 27: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Introducing a variation in the trial function

Where , stationary solutions then imply

This general procedure is the basis for our solution strategyItcanbeshown.comSirajuddin, David

Solution of the variation problem: Ritz procedure

Page 28: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Outline

Motivation Development of the even-parity transport equation Variational concepts Ritz Procedure Statement of the variational problem 1-D slab transport

Spatial discretization Angular treatment

Discrete Ordinates Collision probability method Legendre polynomial expansion

Conclusions References

Itcanbeshown.comSirajuddin, David

Page 29: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

1-D slab methods

Slab geometry:

Isotropic source distribution: S(x) Reflective boundary at x = 0 Vacuum boundary at x = a The functional

Then becomes

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Page 30: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

1-D slab methods

And

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3-D 1-D

Page 31: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

1-D slab methods

Translating the boundary conditions to 1-D

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3-D 1-D

Page 32: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Outline

Motivation Development of the even-parity transport equation Variational concepts Ritz Procedure Statement of the variational problem 1-D slab transport

Spatial discretization Angular treatment

Discrete Ordinates Collision probability method Legendre polynomial expansion

Conclusions References

Itcanbeshown.comSirajuddin, David

Page 33: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

1-D methods: spatial discretization

A spatial mesh is designated

Each interval xj < x < xj+1 is a finite element. To discretize, segment the independent variables according to

Where the yj approximate y(xj,m), and the hj are shape functions that span the finite the width of one finite element. i.e.

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[1]

Page 34: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

1-D methods: spatial discretization

Linear piecewise trial functions are used for hj(x)

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x ≤ xj-1

xj-1 ≤ x ≤ xj

xj ≤ x ≤ xj+1

xj+1 < x

Page 35: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

1-D methods: spatial discretization

Inserting into the

functional gives

Where

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Page 36: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

1-D methods: spatial discretization

Inserting into the

functional gives

Where

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Each term involves a product of basis

Recall, only neighboring finite elementsAre nonzero A and B are N x N tridiagonal symmetric matrices

Page 37: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

1-D methods: spatial discretization

Introducing a variation in the trial function

into the functional

And enforcing stationary solutions gives a single matrix equation

A number of angular discretization methods may henceforth be employed to facilitate a solution

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Page 38: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Outline

Motivation Development of the even-parity transport equation Variational concepts Ritz Procedure Statement of the variational problem 1-D slab transport

Spatial discretization Angular treatment

Discrete Ordinates Collision probability method Legendre polynomial expansion

Conclusions References

Itcanbeshown.comSirajuddin, David

Page 39: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

1-D methods: Angular discretization

The angular dependence may be handled in a

number of ways

Discrete ordinates

Collision probability methods (integral equations)

Legendre polynomials

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Page 40: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

1-D methods: Angular discretization

The angular dependence may be handled in a

number of ways

Discrete ordinates

Collision probability methods (integral equations)

Legendre polynomials

Itcanbeshown.comSirajuddin, David

Page 41: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Angular discretization: discrete ordinates

Beginning with the result of the spatial discretization

N/2 discrete ordinates are imposed

where the scalar flux may be approximated by a suitable quadrature rule

The solution may be obtained by iterating on the scattering source

The solution requires solving N/2 tridiagonal matrix equations due to evenness of the flux function, while the discrete ordinates equations require N tridiagonal matrix equation solutions at each step

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Page 42: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

1-D methods: Angular discretization

The angular dependence may be handled in a

number of ways

Discrete ordinates

Collision probability methods (integral equations)

Legendre polynomials

Itcanbeshown.comSirajuddin, David

Page 43: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Angular discretization: integral equations

Beginning again with the result of the spatial discretization

Isolating the angular flux and integrating over angle:

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Page 44: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Angular discretization: integral equations

Note the similarities

Collision probabilty method is of order D, even-parity method is order D2

Both have nonsymmetric, dense coefficient matrices Collision method requires analytic integration over kernels, even-parity

could use quadrature rulesItcanbeshown.comSirajuddin, David

Collision Probability Method

Even-parity integral equations

Page 45: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

1-D methods: Angular discretization

The angular dependence may be handled in a

number of ways

Discrete ordinates

Collision probability methods (integral equations)

Legendre polynomials

Itcanbeshown.comSirajuddin, David

Page 46: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Angular discretization: legendre polynomial expansion

In addition to the spatial discretization all ready performed, the angular domain is discretized by a family of known even-parity angular basis functions (e.g. even-order Legendre polynomials)

Consider first the angular domain

Inserting this into our functional, the following is retrieved

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Page 47: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Angular discretization: legendre polynomial expansion

Where

i.e. the angular dependence is contained it these terms

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Page 48: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Angular discretization: legendre polynomial expansion

Enforcing stationary solutions with respect to a variation in the flux gives the spatial Euler-Lagrange operator

Which operates on the spatial dependence of the flux

giving

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where

Page 49: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Remarks on the even-parity transport equation

Writing out the functional shows stationary solutions of the angular flux require solving

The zeroeth moment corresponds to the scalar flux {yj}1 = j(xj)

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Page 50: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Outline

Motivation Development of the even-parity transport equation Variational concepts Ritz Procedure Statement of the variational problem 1-D slab transport

Spatial discretization Angular treatment

Discrete Ordinates Collision probability method Legendre polynomial expansion

Conclusions References

Itcanbeshown.comSirajuddin, David

Page 51: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Conclusions

A variational formalism may be used as a basis for developing algorithms on the neutron transport equation Discrete ordinates Integral transport Legendre polynomial expansion

The even-parity transport equation was shown to facilitate matrix equations that involved sparse coefficient matrices in certain cases (discrete ordinates, legendre polynomial expansion)

Discrete ordinates: Both possess order D2 accuracy The variational structure allowed for the solution of only N/2 tridiagonal matrix equations at each

iteration, while the discrete ordinates demanded N tridiagonal matrix equation solution. Discrete ordinates equations involve lower triangular matrices easier to solve.

Integral transport A similar set of integral equations was arrived at with variational methods as was found in

collision probability methods. Collision probability methods are of order D, while variational approaches allow accuracy of order

D2 Collision probability methods suffer in accuracy for large systems due to the source

approximation, while variational methods may be adapted to fit the needed accuracyItcanbeshown.comSirajuddin, David

Page 52: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Conclusions

Legendre polynomial expansions Both the PN equations and the variational method allow for a diffusion approximation

solution involving tridiagonal coefficient matrices. Higher order PN equations require iterative solutions, higher order variational equations

involve more dense matrices

The methods presented pertained to isotropic scattering and one-dimension. Anisotropic scattering has also been worked into variational formulations, and algorithms have been to two-dimensions with a variety of finite element types, however the treatment is more involved.

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Page 53: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

Outline

Motivation Development of the even-parity transport equation Variational concepts Ritz Procedure Statement of the variational problem 1-D slab transport

Spatial discretization Angular treatment

Discrete Ordinates Collision probability method Legendre polynomial expansion

Conclusions References

Itcanbeshown.comSirajuddin, David

Page 54: DAVID SIRAJUDDIN UNIVERSITY OF WISCONSIN - MADISON DEPT. OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS NEEP 705 – ADVANCED REACTOR THEORY, DR. DOUGLASS.

References

Lewis, E.E. and Miller, W.F. Jr. Computational Methods of Neutron Transport. Wiley-Interscience. January 1993.

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Additional Slides

Vacuum boundary condition

Subtracting both equations, and using the definitions

,

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