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

From Serpent Wiki

(→Description) |
(→Input) |
||

Line 6: | Line 6: | ||

== 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 ^{235}U, ^{238}U, ^{239}Pu and ^{240}Pu. 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