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MSR depletion chain

  • ENDF-B-VII.1_chain_msr.xml
  • ENDF-B-VIII.0_chain_msr.xml

ENDF-B Nuclear reaction, Neutron Induced Fission Product Yields and Decay Reaction libraries downloaded from 👉 nndc.

The xml files are generated using create_chain.py script, including '(n,2n)', '(n,3n)', '(n,4n)', '(n,gamma)', '(n,p)', '(n,a)', '(n,t)','(n,na)' nuclear reactions.

Modified depletion chains

The following chains are retrieved from the OpenMC official depletion data library 👉 Openmc official data library and modified as stated below:

  • chain_endfb71_pwr.xml: added (n,t) reaction of Li6
  • chain_endfb71_pwr_volatile.xml: Only Xe and Kr set to decay to He4
  • chain_endfb71_pwr_fp_removal.xml: All fp set to decay to He4
  • chain_endfb71_pwr_fp_lanth_removal.xml: All fp and lanthanides set to decay to He4

The script modify_xml.py can be used to easly modify the xml depletion chain files.

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Modified depletion chains for OpenMC

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