Institute for Neutron Physics and Reactor Technology (INR)

Nuclear Data for Fusion Technology

The objective of this activity is to provide cross-section data evaluations required for fusion neutronics calculations (transport and sensitivity/uncertainty) with focus on needs for ITER Test Blanket Modules (TBM), IFMIF neutron source, and high energy accelerator based facilities.



General Cross Section Data Evaluation



Such evaluated nuclear data files are usually treated as a basis for the particle transport calculations in various nuclear facilities. The information included in these files should be as full as possible to make feasible versatile investigations of the nuclear physical processes occurring in such devices.


Evaluated data files up to 200 MeV

 n +  50,52,53,54Cr:   ENDF-6 formatted files

 n +  63,65Cu:         ENDF-6 formatted files

 n+ 90,91,92,94,96Zr:  ENDF-6 formatted files

 n+ 181Ta:  ENDF-6 formatted file

 n+ 182,183,184,186W:  ENDF-6 formatted files

 n+ 180,182,183,184,186W (NEW DATA): KIT SWP Reports 108 and 123


D-Li Cross Sections up to 50 MeV

 d + 6,7Li:   Ref.  NIM B266(2008)3501 .


Cross Section Data Evaluation for Radiation Damage

  • Displacement cross-section for neutron induced reactions for 79 stable targets from Li to Bi at primary energies from thermal to 10 GeV prepared using MD (arc-dpa) and NRT models.
    Release: March 2018.  Data based on: ENDF/B-VIII (, JEFF-3.3 (, and JENDL-4.0 (
    Description and reference: NET 51(2019)170
  • Displacement cross-section for proton induced reactions for 81 targets from Li to U at primary energies from thermal to 10 GeV prepared using MD (arc-dpa) and NRT models.
    Release: May 2018.  Files:
    Explanation of the evaluation method, as an example, for Al, Fe, Cu, and W:  NIM B431(2018)55 
  • Neutron displacement cross-sections with covariances for targets from Li to Bi  at neutron energies up to 200 MeV (preliminary data).
    Release: May 2018. Files:
  • Displacement and gas production cross-sections for Al, Ti, V, Cr, Fe, Ni, Cu, Zr, and W irradiated with neutrons and protons at energies from 10-5 eV to 3 GeV (DXS library).
    Releases 2011-2015:  files
  • Neutron displacement cross-sections for EUROFER prepared using BCA-MD approach and NRT model.
    Release May 2013: file
  • Gas production and NRT-displacement cross-sections for n+9Be irradiation at incident energies up to 200 MeV.
    Release August 2014: file and KIT Scientific Working Papers 37
  • Gas production data library (p-, d-, t-, 3He, α- production cross-sections) for nuclides from Mg to Bi at neutron incident energies up to 200 MeV
    Release August 2014: files and KIT Scientific Working Papers 35
  • Proton-, deuteron-, triton-, 3He, and α-particle production cross-sections for proton induced reactions for 278 targets from Li to Bi for a number of incident proton energies from 62 to 1200 MeV.
    Release 2014: KIT Scientific Reports 7660, page 100
  • (n,α) reaction cross-sections at 14.5 MeV for target nuclei with the atomic number between 18 and 84 with the half-life more than one hour evaluated using an advanced method
    Release September 2015: KIT Scientific Reports 7628 (see Table 4)
  • NRT- and arc-dpa neutron induced cross sections and covariances for elemental Iron: NME 15(2018)244 

Part of the data described above can be also downloaded hier (look DXS files)

Activation Cross Section for p+W reactions at proton energies up to 3 GeV

  •  Evaluated cross-section for proton induced reactions on 180,182,183,184,186W at incident proton energies from threshold up to 3 GeV
    Release 2012: files and KIT Scientific Reports 7628

Cross Section Data Evaluation for (n,x)7Be and (p,x)7Be reactions

  • Calculated (n,x)7Be and (p,x)7Be reaction cross-sections for 274 targets from C to Bi at the primary neutron energies up to 200 MeV.
    Release June 2014: file and KIT Scientific Reports 7684 (format explanations see on page 70)


Benchmarking of the Evaluated Data and Analyses

Each evaluated data file should be validated against available integral measurements. Such usually include rather simple experimental facility containing the samples of the investigated material. The particle transport calculations using newly prepared nuclear data files are compared with the measured nuclear responses from such samples.


Benchmarking in Fusion-like Spectrum


Benchmarking in IFMIF-like Neutron Spectrum