FENDL-2.0:
Activation
Decay
Dosimetry
Fusion
Transport
Benchmarks

Pointwise and processed neutron activation cross sections below 20 MeV for 13006 neutron reactions on 739 target nuclides (including metastable states with half-lives longer than 1/2 day).
One of the most comprehensive libraries of that type available.

   view list of reactions             download list of reactions

• POINTWISE neutron activation cross sections assembled by the Culham/ECN team at UKAEA Culham in March 1996.

view documentation

view plots

Data in
EAF format:

H-1     -    Ge-73

Ge-74   -    Ru-99

Ru-100   -   Te-123g

Te-123m   -   Ne-144

Ne-145   -   Lu-170

Lu-171   -   Bi-205

Bi-206   -   Cm-248

entire data

Data in
ENDF format:

H-1    -    Ge-73

Ge-74  -   Ru-99

Ru-100   -  Te-123g

Te-123m -   Ne-144

Ne-145    -  Lu-170

Lu-171    -   Bi-205

Bi-206    -   Cm-248

• PROCESSED neutron activation cross section data

  view documentation
  

  MCNP -  data processed into continuous energy format for input to the Monte Carlo neutron/photon transport code MCNP

  download ACTXS1

  view XSDIR

   

  • VITJ_E - data processed into VITAMIN-J 175 multigroup structure (ASCII) weighted with the VITAMIN-E weighting spectrum

    • LIBOUT - data in LIBOUT format for the code FOUR ACES (ENEA Bologna)

      download LIBOUT data

    • REAC - data in the input format for the REAC*2/3 transmutation code

      download REAC data

      TRANREAC source and header files of the FORTRAN code , which collapses the REAC (ASCII) groupwise data files and/or converts them into the format needed for input to the FISPACT and RACC codes

      download TRANREAC

  • VITJ_FLAT - data processed into Vitamin-J 175 structure (ASCII) weighted with a flat (constant) weighting spectrum in ENDF-6 format (click below to download):

    H-1 -  Ge-73	Ge-74  -  Ru-99	Ru-100 - Te-123g
    Te-123m - Ne-144	Ne-145 - Lu-170	Lu-171 - Bi-205
    Bi-206 - Cm-248