Difference between revisions of "Flattop k-eff sensitivity example"

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== Input ==
 
== Input ==
 +
 +
<nowiki>% --- Core outer surface and blanket outer surface
 +
 +
surf s1 sph 0.0 0.0 0.0  4.5332
 +
surf s2 sph 0.0 0.0 0.0 24.1420
 +
 +
% --- Divide space to core, blanket and outside
 +
 +
cell c1 0 core      -s1
 +
cell c3 0 blanket s1 -s2
 +
cell c4 0 outside s2
 +
 +
% --- Core is made from plutonium alloy
 +
 +
mat core sum
 +
94239.03c  3.6697e-2
 +
94240.03c  1.8700e-3
 +
94241.03c  1.1639e-4
 +
31000.03c  1.4755e-3
 +
 +
% --- Blanket is made from natural uranium
 +
 +
mat blanket sum
 +
92234.03c  2.6438e-6
 +
92235.03c  3.4610e-4
 +
92238.03c  4.7721e-2
 +
 +
% --- Cross section libraries
 +
 +
set acelib "/home/tpvtuomas/xsdata/xsss2-beta/sss_endfb71.xsdata"
 +
 +
% --- Neutron population
 +
 +
set pop 10000 100000 50 1 100 100
 +
 +
% --- Write output each 100 cycles
 +
 +
set outp 100
 +
 +
% --- Modify event buffer size to 3 events per neutron
 +
 +
set nbuf 3 3
 +
 +
% --- Use unresolved resonance sampling for the fast system
 +
 +
set ures 1 2
 +
 +
% --- Define Vitamin-J energy grid (one of the defaults)
 +
 +
ene myvit-j 4 nj23
 +
 +
% %%%
 +
% %%% --- Sensitivity options
 +
% %%%
 +
 +
% --- Run sensitivity calculation using Vitamin-J energy grid
 +
 +
sens opt egrid myvit-j
 +
 +
% --- Use 15 latent generations for the sensitivity calculations
 +
 +
sens opt latgen 15
 +
 +
% --- Use 10 generations for Iterated Fission Probability
 +
 +
set ifp 10
 +
 +
% %%%
 +
% %%% --- Sensitivity responses
 +
% %%%
 +
 +
% --- Calculate sensitivity of k-effective to perturbations
 +
 +
sens resp keff
 +
 +
% %%%
 +
% %%% --- Sensitivity perturbations
 +
% %%%
 +
 +
% --- Separate perturbations for the different nuclides and total
 +
 +
sens pert zailist 922350 922380 942390 942400 total
 +
 +
% --- Do not calculate material-wise perturbations (only total)
 +
 +
sens pert matlist total
 +
 +
% --- Perturb cross sections separately for each MT number
 +
 +
sens pert xs all
 +
 +
% --- Score sensitivity results directly to a matrix for each particle
 +
%    Assume 0.2 matrices needed per generation per particle
 +
 +
sens opt direct 0.2</nowiki>
  
 
== Output ==
 
== Output ==

Revision as of 11:28, 20 June 2017

This example demonstrates some basic sensitivity calculation capabilities for the Popsy (Flattop) critical experiment (PU-MET-FAST-006 in the ICSBEP handbook).

Description

The experimental configuration consists of a plutonium alloy sphere (radius 4.5332 cm) reflected by a natural uranium blanket (outer radius 24.1420 cm). The multiplication factor of the system is close to unity (being a critical experiment). This input calculates the sensitivity of the multiplication factor to perturbations applied to the cross sections of 235U, 238U, 239Pu and 240Pu. A processing script for MATLAB/OCTAVE is provided for printing and plotting out the sensitivities.

Input

% --- Core outer surface and blanket outer surface

surf s1 sph 0.0 0.0 0.0  4.5332
surf s2 sph 0.0 0.0 0.0 24.1420

% --- Divide space to core, blanket and outside

cell c1 0 core       -s1
cell c3 0 blanket s1 -s2
cell c4 0 outside s2

% --- Core is made from plutonium alloy

mat core sum
94239.03c  3.6697e-2
94240.03c  1.8700e-3
94241.03c  1.1639e-4
31000.03c  1.4755e-3

% --- Blanket is made from natural uranium

mat blanket sum
92234.03c  2.6438e-6
92235.03c  3.4610e-4
92238.03c  4.7721e-2

% --- Cross section libraries

set acelib "/home/tpvtuomas/xsdata/xsss2-beta/sss_endfb71.xsdata"

% --- Neutron population

set pop 10000 100000 50 1 100 100

% --- Write output each 100 cycles

set outp 100

% --- Modify event buffer size to 3 events per neutron

set nbuf 3 3

% --- Use unresolved resonance sampling for the fast system

set ures 1 2

% --- Define Vitamin-J energy grid (one of the defaults)

ene myvit-j 4 nj23

% %%%
% %%% --- Sensitivity options
% %%%

% --- Run sensitivity calculation using Vitamin-J energy grid

sens opt egrid myvit-j

% --- Use 15 latent generations for the sensitivity calculations

sens opt latgen 15

% --- Use 10 generations for Iterated Fission Probability

set ifp 10

% %%%
% %%% --- Sensitivity responses
% %%%

% --- Calculate sensitivity of k-effective to perturbations

sens resp keff

% %%%
% %%% --- Sensitivity perturbations
% %%%

% --- Separate perturbations for the different nuclides and total

sens pert zailist 922350 922380 942390 942400 total

% --- Do not calculate material-wise perturbations (only total)

sens pert matlist total

% --- Perturb cross sections separately for each MT number

sens pert xs all

% --- Score sensitivity results directly to a matrix for each particle
%     Assume 0.2 matrices needed per generation per particle

sens opt direct 0.2

Output

Data-processing and plotting

Results

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