Online Catalog
Click on Package Name to get detailed information.
Click on Abstract to read the package abstract.
Click on RSICC Tapelist to view list of files distributed with package.

Note: RESTRICTIONS APPLY TO SOME PACKAGES -
810 -- US DOE 10CFR810 Jurisdiction
FEDC -- US Government Agencies and Their Contractors Only
OECD -- Restricted/See Abstract
RUGA -- Restricted Use Government Authorized
USSO -- US Distribution Only
USUNV -- US Universities Only
Packages with Keyword: REACTION CROSS SECTIONS
Package NameAbstractRSICC TapelistTitle
ACTIV87AbstractD00169 ALLCP 00Fast Neutron Activation Cross Section File.
ACTV-F/HAbstractD00155 ALLCP 00Neutron Activation Cross Section Library for Fusion Reactor Design.
ACTV-FUS/INTAbstractD00170 ALLCP 00International Library of Neutron Activation Cross-Section Data for Fusion Reactor Application.
DOSDAM81-82AbstractD00097 C0000 00Multigroup Cross Sections in SAND-II Format for Spectral, Integral, and Damage Analyses.
DOSDAM84AbstractD00131 IBMMF 00Multigroup Cross Sections in SAND-II Format for Spectral, Integral, and Damage Analyses.
GAMMONAbstractD00071 ALLCP 00Gamma-Ray Moments Method Code System.
GEAF-1AbstractD00158 D8810 00100 Group Cross Sections for Neutron Activation.
IEAF-2001AbstractD00217 MNYCP 00Intermediate Energy Activation File - 2001.
IRDF-2002AbstractD00229 MNYCP 01The International Reactor Dosimetry File.
IRDF82AbstractD00094 I0360 00The International Reactor Dosimetry File.
KAOS/LIB-VAbstractD00160 CY000 00A Library of Nuclear Response Functions Generated by KAOS-V Code From ENDF/B-V and Other Data Files.
LAFPX-VAbstractD00054 C0000 01A Multigroup Reaction Cross-Section Collapsing Code and Library of 154-Group Fission-Product Cross Sections.
LAFPX-VAbstractD00054 C0000 02A Multigroup Reaction Cross-Section Collapsing Code and Library of 154-Group Fission-Product Cross Sections.
LAHIMACKAbstractD00128 I0360 00A Multigroup Library of Neutron and Gamma Cross Sections and Response Functions in the Energy Range up to 800 MeV.
MACKLIBAbstractD00029 I3675 00A Library of Nuclear Response Functions Generated with the MACK-V Computer Program from ENDF/B-IV.
MACKLIB-IV-82AbstractD00060 I0360 01A Library of Nuclear Response Functions Generated with the MACK-V Computer Program from ENDF/B-IV.
MCB63NEA.BOLIBAbstractD00216 MNYCP 00ENDF/B-VI Release 3 Cross Section Library for Use with the MCNP Monte Carlo Code.
MCJEF22NEA.BOLIBAbstractD00203 MNYCP 01JEF 2.2 Cross Section Library for the MCNP Monte Carlo Code.
MENDL-2PAbstractD00207 MNYCP 00Proton Reaction Data Library for Nuclear Activation (Medium Energy Nuclear Data Library.)
MONTUK-80AbstractD00072 ALLCP 01UKCTR III Transmutation and Activation Data, 100-Group Neutron Activation Cross-Section Data for Fusion Reactor Structure and Coolant Materials.
ORYX-EAbstractD00038 I0360 00ORIGEN Yields and Cross Sections Nuclear Transmutation and Decay Data from ENDF/B-IV.
ORYX-EAbstractD00038 I0360 01ORIGEN Yields and Cross Sections Nuclear Transmutation and Decay Data from ENDF/B-IV.
SNLRMLAbstractD00178 ALLCP 00Recommended Dosimetry Cross Section Compendium.
TDFAbstractD00162 ALLCP 00Thermonuclear Data File.
UKCTRI-81AbstractD00064 I0370 0146-Group Neutron Cross Sections and Kerma Factors for Fusion Reactor Calculations.
UTXS6AbstractD00211 MNYCP 00MCNP Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1365K.
VITAMIN-CAbstractD00041 I0360 02Broad-Group and Fine-Group and Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data.
VITAMIN-EAbstractD00113 I3033 02Broad-Group and Fine-Group and Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data.
VITAMIN-J/KERMAAbstractD00150 I3090 00Broad-Group and Fine-Group and Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data.
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The Radiation Safety Information Computational Center (RSICC) collects, analyzes, maintains, and distributes software in the areas of radiation transport and safety. RSICC resides in the Nuclear Energy and Fuel Cycle Division (NEFCD) at Oak Ridge National Laboratory.