Merge pull request #129 from ChasingNeutrons/SABmixing

S(alpha,beta) stochastic mixing
CambridgeNuclear · Sep 4, 2024 · f17e3a0 · f17e3a0
2 parents c2882b1 + 6b9227f
commit f17e3a0
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Showing 38 changed files with 367,315 additions and 678 deletions.
diff --git a/CollisionOperator/CollisionProcessors/neutronCEimp_class.f90 b/CollisionOperator/CollisionProcessors/neutronCEimp_class.f90
@@ -259,7 +259,7 @@ subroutine sampleCollision(self, p, tally, collDat, thisCycle, nextCycle)
     if (.not.associated(self % mat)) call fatalError(Here, 'Failed to retrieve CE Neutron Nuclide')
 
     ! Select Main reaction channel
-    call self % nuc % getMicroXSs(microXss, collDat % E, p % pRNG)
+    call self % nuc % getMicroXSs(microXss, collDat % E, self % mat % kT, p % pRNG)
     r = p % pRNG % get()
     collDat % MT = microXss % invert(r)
 
@@ -297,7 +297,7 @@ subroutine implicit(self, p, tally, collDat, thisCycle, nextCycle)
       rand1 = p % pRNG % get()     ! Random number to sample sites
 
       ! Retrieve cross section at the energy used for reaction sampling
-      call self % nuc % getMicroXSs(microXSs, collDat % E, p % pRNG)
+      call self % nuc % getMicroXSs(microXSs, collDat % E, self % mat % kT, p % pRNG)
 
       sig_nufiss = microXSs % nuFission
       sig_tot    = microXSs % total
@@ -352,7 +352,7 @@ subroutine implicit(self, p, tally, collDat, thisCycle, nextCycle)
     if (self % implicitAbsorption) then
 
       if (.not.fiss_and_implicit) then
-        call self % nuc % getMicroXSs(microXSs, collDat % E, p % pRNG)
+        call self % nuc % getMicroXSs(microXSs, collDat % E, self % mat % kT, p % pRNG)
       end if
 
       sig_scatter  = microXSs % elasticScatter + microXSs % inelasticScatter
@@ -413,7 +413,7 @@ subroutine fission(self, p, tally, collDat, thisCycle, nextCycle)
       rand1 = p % pRNG % get()     ! Random number to sample sites
 
       ! Retrieve cross section at the energy used for reaction sampling
-      call self % nuc % getMicroXSs(microXSs, collDat % E, p % pRNG)
+      call self % nuc % getMicroXSs(microXSs, collDat % E, self % mat % kT, p % pRNG)
 
       sig_nufiss = microXSs % nuFission
       sig_fiss   = microXSs % fission

diff --git a/CollisionOperator/CollisionProcessors/neutronCEstd_class.f90 b/CollisionOperator/CollisionProcessors/neutronCEstd_class.f90
@@ -179,7 +179,7 @@ subroutine sampleCollision(self, p, tally, collDat, thisCycle, nextCycle)
     if (.not.associated(self % nuc)) call fatalError(Here, 'Failed to retrieve CE Neutron Nuclide')
 
     ! Select Main reaction channel
-    call self % nuc % getMicroXSs(microXss, collDat % E, p % pRNG)
+    call self % nuc % getMicroXSs(microXss, collDat % E, self % mat % kT, p % pRNG)
     r = p % pRNG % get()
     collDat % MT = microXss % invert(r)
 
@@ -214,7 +214,7 @@ subroutine implicit(self, p, tally, collDat, thisCycle, nextCycle)
       rand1 = p % pRNG % get()     ! Random number to sample sites
 
       ! Retrieve cross section at the energy used for reaction sampling
-      call self % nuc % getMicroXSs(microXSs, collDat % E, p % pRNG)
+      call self % nuc % getMicroXSs(microXSs, collDat % E, self % mat % kT, p % pRNG)
 
       sig_nufiss = microXSs % nuFission
       sig_tot    = microXSs % total

diff --git a/DataStructures/dictionary_class.f90 b/DataStructures/dictionary_class.f90
@@ -629,7 +629,7 @@ subroutine getChar_new(self,value,keyword)
       case(word)
         ! Check if the content character fits into value
         if( len(value) < len_trim(self % entries(idx) % char0_alloc)) then
-          call fatalError(Here,'value character is to short to store content. Increase its length')
+          call fatalError(Here,'value character is too short to store content. Increase its length')
         end if
 
         value = self % entries(idx) % char0_alloc