Nuclear Data Validation Group
The Nuclear Data Validation Group of KAERI/NDC has been producing several kinds of cross section libraries for general purpose radiation transport/depletion programs such as MCNP/MCNPX, McCARD, DANTSYS/PARTISN, DOORS, WIMS, SCALE/ORIGEN, etc. The cross section libraries have been widely used in many research areas by domestic and foreign researchers, while fulfilling the nuclear data needs for R&D activities on the advanced reactors.

ACE-Format Nuclear Data Library
  • KNE
  • ENDF/B-based library
  • KNF
  • JEFF-based library
  • KNJ
  • JENDL-based library
The Monte Carlo transport codes such as MCNP/MCNPX and McCARD adopt ACE-formatted continuous-energy cross section libraries for the radiation transport calculations. The libraries have been generated through NJOY99/NJOY2012 code processing with the source evaluated nuclear data files. The MCLIB-E6, which was the first ACE-format library officially disseminated by the KAERI/NDC, contained continuous-energy neutron data at 300K, 600K, and 900K for 332 nuclides mainly from ENDF/B-VI.5. This library can be obtained from the OECD/NEA Data Bank.

MATXS-Format Nuclear Data Library
  • KASHIL
  • Neutron/photon shielding library
  • KAFAX
  • Fast reactor library
The MATXS-format multi-group cross section library is considered as the master library for applications to the SN transport codes such as DANTSYS/PARTISN and DOORS. The libraries have been generated through NJOY99/NJOY2012 code processing with the source evaluated nuclear data files. The MATXS-format libraries can be converted to other formats such as ISOTXS- and ANISN-formats through the utility code TRANSX.

COVFIL-Format Covariance Data Library
  • GCov-E
  • ENDF/B-based library
  • GCov-F
  • JEFF-based library
  • GCov-J
  • JENDL-based library

SCALE Library
  • YLD
  • Fission-product yield library
  • Dec
  • Nuclear decay library
The SCALE code package includes the fission product yield data and decay data, which are essential for various burnup and depletion analyses. The generation of new SCALE/ORIGEN-S fission product yield and decay data libraries based on the recently available evaluated files has been carried out. In addition, the libraries have been validated through the decay heat analysis after a fission event of actinides.
Nuclear Data Center, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 34057, KOREA
Tel: +82-42-868-8651, Fax: +82-42-868-2636, E-mail: kimdh@kaeri.re.kr