ENDF/B-I Evaluated Nuclear Data Library

The NNDC is looking for copies of both the data summary and the data itself.

If you have any leads, please contact David Brown (dbrown@bnl.gov) or Gustavo Nobre (gnobre@bnl.gov).

Version I of the ENDF/B data file was released in July 1968. The description of the formats and procedures are documented in BNL-50066 (a.k.a. ENDF-102, 1966 edition).

  1. File 1 had a Hollerith description in Section 1, neutron multiplicity in Section 2, radioactive decay data in Section 3 and fission product yield data in Section 4.
  2. File 2 used two energy ranges, one for resolved and one for unresolved parameters.
  3. File 3 limited quantities to 500 points, except for the scattering cross section where 2000 points were allowed. Temperature dependence was ignored, except for thermal cross sections.
  4. File 4 would contain mostly data for elastic scattering. Some data may be given for inelastic or total reaction in the thermal range and may be temperature dependent.
  5. File 5 should have data for inelastic, (n,2n), (n,3n) and fission reactions if smooth cross sections for these reactions are given in File 3.

The evaluations for ENDF/B-I were taken from the existing evaluations of neutron inter- actions for 58 materials and converted into the ENDF format. The emphasis in this version was to create the necessary infrastructure to support the library system.

-- Taken from the ENDF/B-VII format manual, Appendix I "Historic Perspective", By Norman Holden.