How to Handle WIMS Reactor Physics Codes for Radial Neutron Flux Analysis?

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SUMMARY

The discussion focuses on performing radial neutron flux analysis using WIMS reactor physics codes, specifically addressing the division of fuel pins into equal-volume sub-regions and the execution of criticality calculations. The user seeks guidance on obtaining the two-group flux output, which is not appearing in the output file. Key parameters include an energy cut-off of 0.615 eV for separating fast and thermal neutron regions and the correct setup of input files, particularly the .pwrpin and .route files, to ensure accurate flux calculations.

PREREQUISITES
  • Familiarity with WIMS reactor physics codes
  • Understanding of neutron flux analysis and criticality calculations
  • Knowledge of input file structures for WIMS, specifically .pwrpin and .route files
  • Experience with energy group splitting in reactor physics
NEXT STEPS
  • Review the WIMS documentation for detailed input file configurations
  • Learn about energy group splitting techniques in neutron transport codes
  • Investigate methods for troubleshooting output file discrepancies in WIMS
  • Explore advanced criticality calculation techniques using WIMS
USEFUL FOR

This discussion is beneficial for nuclear engineers, reactor physicists, and researchers involved in neutron flux analysis and criticality safety assessments using WIMS reactor physics codes.

PhotonEd
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Hello hope someone can help me
I need to do WIMS reactor physics codes analysis for
1) divide fuel pin into radial equal-volume sub regions
2) preform criticality calculations to obtain radial fast and thermal neutron flux (use 0.615eV energy cut off between fast and thermal regions)
I will need advise on obtaining flux for the regions as the output file is not showing the 2 group flux, please see the below for some of the input files, many thanks

regards

1) equal section setup as below in .pwrpin file for wimsbuilder

FUEL MATERIAL 1
DENSITY 10.40
TEMP FUELTEMP
COMPOSITION \
U235 1.0997472E-03 \
U238 2.1525591E-02 \
U234 1.0409077E-05 \
U236 3.2482827E-07 \
O 4.5272144E-02

FUEL MATERIAL 2
DENSITY 10.40
TEMP FUELTEMP
COMPOSITION \
U235 1.0997472E-03 \
U238 2.1525591E-02 \
U234 1.0409077E-05 \
U236 3.2482827E-07 \
O 4.5272144E-02

CLAD MATERIAL 3
DENSITY 6.5
TEMP CLADTEMP
COMPOSITION Zr 100

COOLANT MATERIAL 4
DENSITY COOLDENS
TEMP COOLTEMP
COMPOSITION H 11.18983 O 88.81017

ANNULUS 1 RADIUS 0.40950 MATERIAL 1
ANNULUS 2 RADIUS 0.42950 MATERIAL 2
ANNULUS 3 RADIUS 0.47500 MATERIAL 3
ANNULUS 4 MATERIAL 4

2) for energy cut off and group split in .route file

....
ifelse(BRANCH,YES,[CRITIC 8 5],[CRITIC 2 5])
buckling 6 0.00022314 0.000065641 0.00001 0.0
begin
COND 5 6
energy 0.615 *This is for the Energy cut-off (2-groups)
begin
SMEAR 6 7
newmat 1 allm
begin
EDIT 7
groups SPLIT * this is to print for 2 grroup
nuclides Pu239 Pu241
...
 
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To anyone of interested
EDIT should be on card 6 before SMEAR as otherwise it will just print out the "smeared" 1 group (1 group) and not the 2 groups (fast ad thermal) as required
codes as of the below
:)

...
ifelse(BRANCH,YES,[CRITIC 8 5],[CRITIC 2 5])
buckling 6 0.00022314 0.000065641 0.00001 0.0
begin
COND 5 6 * Energy cut-off (2-groups)
energy 0.615 0 * Energy cut-off (2-groups)
begin * Energy cut-off (2-groups)

EDIT 6
groups SPLIT * print option for 2gr
begin

SMEAR 6 7
newmat 1 mat 1
*newmat 1 allm
begin
...
 
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