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= update Project.toml
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-8
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3 files changed

+3
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Project.toml

Lines changed: 1 addition & 1 deletion
Original file line numberDiff line numberDiff line change
@@ -1,7 +1,7 @@
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name = "NeutronTransport"
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uuid = "161f4978-d3bb-4696-90f4-058341551711"
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authors = ["Ramiro Vignolo <ramirovignolo@gmail.com>"]
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version = "0.1.0"
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version = "0.2.0"
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[deps]
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Gridap = "56d4f2e9-7ea1-5844-9cf6-b9c51ca7ce8e"

src/NeutronTransport.jl

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Original file line numberDiff line numberDiff line change
@@ -10,8 +10,6 @@ using Gridap.Geometry: get_face_tag, get_tag_from_name
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import Base: show, eltype
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include("cross_section.jl")
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abstract type TransportFormulation end
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struct MethodOfCharacteristics <: TransportFormulation end
@@ -23,6 +21,7 @@ const MoC = MethodOfCharacteristics
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const CP = CollisionProbability
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const SN = DiscreteOrdinates
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include("cross_section.jl")
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include("polar_quad.jl")
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include("quadrature.jl")
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src/mocsolver.jl

Lines changed: 1 addition & 5 deletions
Original file line numberDiff line numberDiff line change
@@ -17,7 +17,7 @@ struct MoCSolution{T<:Real,P<:MoCProblem} <: TransportSolution
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# reduced source
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q::Vector{T}
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# total source (integrated in energy given per region) is used for convergence purposes
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# total source (integrated in energy given per region) used for convergence purposes
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Q::Vector{T}
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# angular flux at boundary
@@ -375,9 +375,7 @@ function residual(sol::MoCSolution{T}, prob::MoCProblem) where {T}
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xs = xss[idx]
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old_qi = Q[i]
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new_qi = zero(T)
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# old_qi = zero(T)
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@unpack νΣf, Σs0 = xs
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fissionable = isfissionable(xs)
@@ -393,7 +391,6 @@ function residual(sol::MoCSolution{T}, prob::MoCProblem) where {T}
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end
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new_qi /= keff
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# old_qi /= keff
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# total scattering source
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for g in 1:NGroups, g′ in 1:NGroups
@@ -402,7 +399,6 @@ function residual(sol::MoCSolution{T}, prob::MoCProblem) where {T}
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new_qi += Σsgg′ * φ[ig′]
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end
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if old_qi > 0
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ϵ += ((new_qi - old_qi) / old_qi)^2
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end

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