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program monte_carlo

    use omp_lib
    use, intrinsic :: iso_fortran_env
    implicit none

    !> Initialize some variables for neutrons
    integer(int64), parameter :: n = 1e8
    integer(int64), parameter :: bins = 800
    real(real64), parameter :: eps = 1.0e-12_real64

    !> And for geometry
    real(real64), parameter :: L = 8.0_real64
    real(real64), parameter :: dx = L / bins
    real(real64), dimension(6), parameter :: boundaries = [0.0_real64, 2.0_real64, 3.0_real64, 5.0_real64, 6.0_real64, 8.0_real64]

    !> These will contain the x-position and cosine of angle for each neutron
    real(real64), dimension(n) :: px, mu
    !> Track whether or not the neutron is alive
    logical, dimension(n) :: is_alive = .true.
    !> And for tallying the flux
    real(real64), dimension(bins) :: flux_tally = 0.0_real64
    real(real64), dimension(bins) :: thread_tally = 0.0_real64

    !> Some local trackers to be updated via subroutine call
    real(real64) :: sigma_t, sigma_s, q, d_flight, d_boundary, d_step, xi, next_boundary
    integer(int64) :: i, region

    !> Initialize RNG to be actually random
    call random_seed()
    call random_init(.false., .true.)

    !> Provide all neutrons an initial location/angle
    call initialize_neutrons(n, px, mu)

    !$OMP PARALLEL PRIVATE(thread_tally, sigma_t, sigma_s, q, d_flight, d_boundary, d_step, xi, region, i)
    thread_tally=0.0_real64

    !> The main monte carlo loop 
    !$OMP DO
    main: do i = 1,n

        !> Skip if the neutron is already lost
        if(.not. is_alive(i)) cycle main

        !> Otherwise, simulate it until it is lost
        single: do while(is_alive(i))

            !> Find what region the neutron is in and get XS
            region = count(px(i) .ge. boundaries)
            call get_region_info(region, sigma_t, sigma_s, q)

            !> Determine the distance before collision
            if(sigma_t .eq. 0.0_real64) then
                !> If we are in a void, make it huge
                d_flight = huge(real64)
            else
                !> Else, calculate with d = -ln(xi)/sigma_t
                call random_number(xi)
                d_flight = -log(xi) / sigma_t
            end if

            !> Determine where the next boundary is and the distance
            if(mu(i) .gt. 0.0_real64) then
                d_boundary = (boundaries(region + 1) - px(i)) / mu(i)
            else if(mu(i) .lt. 0.0_real64) then
                d_boundary = (boundaries(region) - px(i)) / mu(i)
            else
                !> In the rare chance it is perfectly parallel with the walls
                d_boundary = huge(real64)
                is_alive(i) = .false.
            end if

            !> How far we will actually go
            d_step = min(d_flight,d_boundary)

            !> Tally the track-length in the bin
            call tally_segment(px(i), mu(i), d_step, bins, dx, thread_tally)

            !> Update the neutron position
            px(i) = px(i) + d_step * mu(i)

            !> If the neutron crosses a boundary, restart the simulation at the new location
            if(d_boundary .le. d_flight) then
                !> We cross a boundary
                if(mu(i) .gt. 0.0_real64 .and. boundaries(region+1) .eq. L ) then
                    !> Bin neutron at vacuum boundary at x=8.0
                    is_alive(i) = .false.
                    cycle main
                else if(mu(i) .lt. 0.0_real64 .and. boundaries(region) .eq. 0.0_real64) then
                    !> Reflect on specular boundary at x=0.0
                    mu(i) = -mu(i)
                    px(i) = eps
                    cycle single
                else
                    !> Internal boundary
                    if(mu(i) .gt. 0.0_real64) then
                        px(i) = boundaries(region+1) + eps
                    else
                        px(i) = boundaries(region) - eps
                    end if
                    cycle single
                end if
            end if

            !> If not, determine what type of interaction happens
            call random_number(xi)
            if(xi .le. sigma_s / sigma_t) then
                !> Scattering interaction
                !> Sample new isotropic angle
                call random_number(xi)
                mu(i) = 2.0_real64 * xi - 1.0_real64
            else
                !> Absorption interaction
                is_alive(i) = .false.
            end if

        end do single


    end do main
    !$OMP END DO

    !$OMP CRITICAL
    flux_tally = flux_tally + thread_tally
    !$OMP END CRITICAL
    !$OMP END PARALLEL
    flux_tally = flux_tally / flux_tally(bins/8)
    !flux_tally = flux_tally / (real(n, real64) * dx)

    open(unit=10, file='flux.out', status='replace')
    write: do i = 1,bins
        write(10,'(2E15.7)') (i-0.5_real64)*dx, flux_tally(i)
    end do write


contains
        
    pure elemental subroutine get_region_info(region, sigma_t, sigma_s, q)
        integer(int64), intent(in) :: region
        real(real64), intent(out) :: sigma_t, sigma_s, q

        if(region .eq. 1) then
            sigma_t = 50.0_real64; sigma_s = 0.0_real64; q = 50.0_real64
        else if(region .eq. 2) then
            sigma_t = 5.0_real64; sigma_s = 0.0_real64; q = 5.0_real64
        else if(region .eq. 3) then
            sigma_t = 0.0_real64; sigma_s = 0.0_real64; q = 0.0_real64
        else if(region .eq. 4) then
            sigma_t = 1.0_real64; sigma_s = 0.9_real64; q = 1.0_real64
        else if(region .eq. 5) then
            sigma_t = 1.0_real64; sigma_s = 0.9_real64; q = 0.0_real64
        end if
    end subroutine get_region_info

    impure subroutine initialize_neutrons(n, px, mu)
        integer(int64), intent(in) :: n
        real(real64), intent(out), dimension(n) :: px, mu
        real(real64), dimension(n) :: r_region, r_position, r_mu

        !> Make some uniform random numbers
        call random_number(r_region)
        call random_number(r_position)
        call random_number(r_mu)

        !> Consider the total integrated source-distance for regions
        r_region = r_region * 106.0_real64

        !> Assign a random position in each source region
        where(r_region .lt. 100.0_real64)
            px = eps + r_position * (2.0_real64 - 2.0_real64*eps)
        else where(r_region .lt. 105.0_real64)
            px = 2.0_real64 + eps + r_position * (1.0_real64 - 2.0_real64*eps)
        else where(r_region .lt. 106.0_real64)
            px = 5.0_real64 + eps + r_position * (1.0_real64 - 2.0_real64*eps)
        end where

        !> Assign random angles to each particle
        mu = 2.0_real64 * r_mu - 1.0_real64

    end subroutine initialize_neutrons

    pure subroutine tally_segment(px, mu, d_step, bins, dx, thread_tally)
        integer(int64), intent(in) :: bins
        real(real64), intent(in) :: px, mu, d_step, dx
        real(real64), intent(in out), dimension(bins) :: thread_tally
        real(real64) :: x_start, x_end, x_left, x_right
        integer(int64) :: i_start, i_end, i

        !> If no distance was travelled
        if (d_step <= 0.0_real64) return

        !> Start and end position
        x_start = px
        x_end = px + mu * d_step

        if (x_start > x_end) call swap(x_start, x_end)

        i_start = floor(x_start / dx) + 1
        i_end   = floor(x_end / dx) + 1

        i_start = max(1, min(bins, i_start))
        i_end   = max(1, min(bins, i_end))

        if (i_start == i_end) then
            thread_tally(i_start) = thread_tally(i_start) + d_step
        else
            ! First partial bin
            x_right = i_start * dx
            thread_tally(i_start) = thread_tally(i_start) + (x_right - x_start)

            ! Full interior bins
            do i = i_start+1, i_end-1
                thread_tally(i) = thread_tally(i) + dx
            end do

            ! Last partial bin
            x_left = (i_end - 1) * dx
            thread_tally(i_end) = thread_tally(i_end) + (x_end - x_left)
        end if
    end subroutine tally_segment

    pure elemental subroutine swap(x,y)
        real(real64), intent(in out) :: x,y
        real(real64) :: temp
        temp = x
        x = y
        y = temp
    end subroutine swap

end program monte_carlo