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Merge branch 'mathAndScatt5'

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Paul Romano 2012-11-30 18:54:29 -05:00
commit f333be5fb6
6 changed files with 102 additions and 19 deletions
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14
docs/source/usersguide/input.rst
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@ -798,13 +798,19 @@ The following responses can be tallied.
Total reaction rate
:scatter:
Total scattering rate
Total scattering rate. Can also be identified with the ``scatter-0``
response type.
:nu-scatter:
Total production of neutrons due to scattering. This accounts for
multiplicity from (n,2n), (n,3n), and (n,4n) reactions and should be
slightly higher than the scattering rate.
:scatter-0:
Zeroth scattering moment. Can also be identified with the ``scatter``
response type, but is provided for consistency with the higher order
scattering moments.
:scatter-1:
First scattering moment
@ -813,6 +819,12 @@ The following responses can be tallied.
:scatter-3:
Third scattering moment
:scatter-4:
Fourth scattering moment
:scatter-5:
Fifth scattering moment
:absorption:
Total absorption rate. This accounts for all reactions which do not produce

26
src/constants.F90
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@ -251,7 +251,7 @@ module constants
EVENT_FISSION = 3
! Tally score type
integer, parameter :: N_SCORE_TYPES = 18
integer, parameter :: N_SCORE_TYPES = 20
integer, parameter :: &
SCORE_FLUX = -1, & ! flux
SCORE_TOTAL = -2, & ! total reaction rate
@ -260,17 +260,19 @@ module constants
SCORE_SCATTER_1 = -5, & ! first scattering moment
SCORE_SCATTER_2 = -6, & ! second scattering moment
SCORE_SCATTER_3 = -7, & ! third scattering moment
SCORE_TRANSPORT = -8, & ! transport reaction rate
SCORE_DIFFUSION = -9, & ! diffusion coefficient
SCORE_N_1N = -10, & ! (n,1n) rate
SCORE_N_2N = -11, & ! (n,2n) rate
SCORE_N_3N = -12, & ! (n,3n) rate
SCORE_N_4N = -13, & ! (n,4n) rate
SCORE_ABSORPTION = -14, & ! absorption rate
SCORE_FISSION = -15, & ! fission rate
SCORE_NU_FISSION = -16, & ! neutron production rate
SCORE_CURRENT = -17, & ! partial current
SCORE_EVENTS = -18 ! number of events
SCORE_SCATTER_4 = -8, & ! fourth scattering moment
SCORE_SCATTER_5 = -9, & ! fifth scattering moment
SCORE_TRANSPORT = -10, & ! transport reaction rate
SCORE_DIFFUSION = -11, & ! diffusion coefficient
SCORE_N_1N = -12, & ! (n,1n) rate
SCORE_N_2N = -13, & ! (n,2n) rate
SCORE_N_3N = -14, & ! (n,3n) rate
SCORE_N_4N = -15, & ! (n,4n) rate
SCORE_ABSORPTION = -16, & ! absorption rate
SCORE_FISSION = -17, & ! fission rate
SCORE_NU_FISSION = -18, & ! neutron production rate
SCORE_CURRENT = -19, & ! partial current
SCORE_EVENTS = -20 ! number of events
! Tally map bin finding
integer, parameter :: NO_BIN_FOUND = -1

12
src/input_xml.F90
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@ -1700,6 +1700,8 @@ contains
! Set tally estimator to analog
t % estimator = ESTIMATOR_ANALOG
case ('scatter-0') !does the same as 'scatter', for convenience
t % score_bins(j) = SCORE_SCATTER
case ('scatter-1')
t % score_bins(j) = SCORE_SCATTER_1
@ -1713,6 +1715,16 @@ contains
case ('scatter-3')
t % score_bins(j) = SCORE_SCATTER_3
! Set tally estimator to analog
t % estimator = ESTIMATOR_ANALOG
case ('scatter-4')
t % score_bins(j) = SCORE_SCATTER_4
! Set tally estimator to analog
t % estimator = ESTIMATOR_ANALOG
case ('scatter-5')
t % score_bins(j) = SCORE_SCATTER_5
! Set tally estimator to analog
t % estimator = ESTIMATOR_ANALOG
case('transport')

35
src/math.F90
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@ -112,4 +112,39 @@ contains
end function t_percentile
!===============================================================================
! CALC_PN calculates the n-th order Legendre polynomial at the value of x.
! Since this function is called repeatedly during the neutron transport process,
! neither n or x is checked to see if they are in the applicable range.
! This is left to the client developer to use where applicable. x is to be in
! the domain of [-1,1], and 0<=n<=5. If x is outside of the range, the return
! value will be outside the expected range; if n is outside the stated range,
! the return value will be 1.0.
!===============================================================================
pure function calc_pn(n,x) result(pnx)
integer, intent(in) :: n ! Legendre order requested
real(8), intent(in) :: x ! Independent variable the Legendre is to be
! evaluated at; x must be in the domain [-1,1]
real(8) :: pnx ! The Legendre poly of order n evaluated at x
select case(n)
case(1)
pnx = x
case(2)
pnx = 1.5_8 * x * x - 0.5_8
case(3)
pnx = 2.5_8 * x * x * x - 1.5_8 * x
case(4)
pnx = 4.375_8 * x * x * x * x - 3.75_8 * x * x + 0.375_8
case(5)
pnx = 7.875_8 * x * x * x * x * x - 8.75_8 * x * x * x + 1.875 * x
case default
pnx = ONE
end select
end function calc_pn
end module math

6
src/output.F90
View file

@ -789,6 +789,10 @@ contains
string = trim(string) // ' scatter-2'
case (SCORE_SCATTER_3)
string = trim(string) // ' scatter-3'
case (SCORE_SCATTER_4)
string = trim(string) // ' scatter-4'
case (SCORE_SCATTER_5)
string = trim(string) // ' scatter-5'
case (SCORE_TRANSPORT)
string = trim(string) // ' transport'
case (SCORE_DIFFUSION)
@ -1415,6 +1419,8 @@ contains
score_name(abs(SCORE_SCATTER_1)) = "First Scattering Moment"
score_name(abs(SCORE_SCATTER_2)) = "Second Scattering Moment"
score_name(abs(SCORE_SCATTER_3)) = "Third Scattering Moment"
score_name(abs(SCORE_SCATTER_4)) = "Fourth Scattering Moment"
score_name(abs(SCORE_SCATTER_5)) = "Fifth Scattering Moment"
score_name(abs(SCORE_TRANSPORT)) = "Transport Rate"
score_name(abs(SCORE_DIFFUSION)) = "Diffusion Coefficient"
score_name(abs(SCORE_N_1N)) = "(n,1n) Rate"

28
src/tally.F90
View file

@ -4,7 +4,7 @@ module tally
use datatypes_header, only: ListInt
use error, only: fatal_error
use global
use math, only: t_percentile
use math, only: t_percentile, calc_pn
use mesh, only: get_mesh_bin, bin_to_mesh_indices, get_mesh_indices, &
mesh_indices_to_bin, mesh_intersects
use mesh_header, only: StructuredMesh
@ -178,18 +178,34 @@ contains
! The second scattering moment can be determined in a similar
! manner to the first scattering moment
score = last_wgt * 0.5*(3.0*mu*mu - ONE)
score = last_wgt * calc_pn(2, mu)
case (SCORE_SCATTER_3)
! Skip any event where the particle didn't scatter
if (p % event /= EVENT_SCATTER) cycle SCORE_LOOP
! The first scattering moment can be determined by using the
! rate of scattering reactions multiplied by the cosine of the
! change in neutron's angle due to the collision
! The third scattering moment can be determined in a similar
! manner to the first scattering moment
score = last_wgt * 0.5*(5.0*mu*mu*mu - 3.0*mu)
score = last_wgt * calc_pn(3, mu)
case (SCORE_SCATTER_4)
! Skip any event where the particle didn't scatter
if (p % event /= EVENT_SCATTER) cycle SCORE_LOOP
! The fourth scattering moment can be determined in a similar
! manner to the first scattering moment
score = last_wgt * calc_pn(4, mu)
case (SCORE_SCATTER_5)
! Skip any event where the particle didn't scatter
if (p % event /= EVENT_SCATTER) cycle SCORE_LOOP
! The fifth scattering moment can be determined in a similar
! manner to the first scattering moment
score = last_wgt * calc_pn(5, mu)
case (SCORE_TRANSPORT)
! Skip any event where the particle didn't scatter
if (p % event /= EVENT_SCATTER) cycle SCORE_LOOP