ENDF-6 Format, ENDF-6 utilities and processing codes

The internationally agreed format for data files of evaluated nuclear reaction data is ENDF-6. The format rules are defined by the U.S. National Nuclear Data Center (NNDC) on behalf of the Cross Section Evaluation Working Group (CSEWG). ENDF was designed primarily for neutron reaction data with allowance for related decay data, fission-product yield data, neutron thermal scattering data, photo-atomic interaction data and others. ENDF-6 also permits the inclusion of data for nuclear reactions induced by photons and charged particles.

ENDF-6 Format Manual

The ENDF-6 manual is the report ENDF-102 produced by CSWEG.

ENDF-6 Checking and Utility Codes

The ENDF Utility Codes are available on the GitHub platform. They can be accessed individually, or they can be downloaded as a ZIP file, or they can be downloaded using git clone.

• CHECKR - Format Checking Code
• FIZCON - Procedures & Simple Physics Checking Code
• PSYCHE - More complicated physics checking code
• INTER - Calculates selected cross sections and integrals
• STANEF - Creates directory, adds tape label & converts numeric fields Converts to binary format
• ENDF2C (*) - Standardizes numeric fields with maximum precision (up to 9 digits, explicit exponent for small numbers). (*) Available as part of the PREPRO Codes.

The original utility codes by C.L. Dunford are described in the Manual (pdf). The ENDF2C code by D.E. Cullen is described in the IAEA-NDS-0217 document. An additional ENDF utility system ENDVER developed and maintained by A. Trkov is provided.

ENDF-6 processing codes: NJOY, PREPRO and ACEMAKER

The following ENDF-6 processing codes are available:

• PREPRO
• NJOY
• ACEMAKER
• GRUCON