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
USSO -- US Distribution Only
USUNV -- US Universities Only
Packages with Keyword: GAMMA-RAY CROSS SECTIONS
Package NameAbstractRSICC TapelistTitle
ABBN-90AbstractD00182 MNYCP 00Multigroup Constant Set for Calculation of Neutron and Photon Radiation Fields and Functionals, Including the CONSYST2 Program.
ANS643AbstractD00129 IBMPC 02ANS-6.4.3 Geometric Progression Gamma-Ray Buildup Factor Coefficients.
ANSL-VAbstractD00154 ALLCP 01ENDF/B-V Based Multigroup Cross Section Libraries for Advanced Neutron Source (ANS) Reactor Studies.
DPL-400 GEDT1AbstractD00031 I0360 08Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format.
DPL-401 NEDTAbstractD00031 I0360 09Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format.
DPL-402A/GPDT1AbstractD00031 I0360 10Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format.
DPL-402B/GPDT1AbstractD00031 I0360 11Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format.
E3LWRAbstractD00098 C0000 0045 Neutron, 16 Gamma-Ray and 15 Neutron, 5 Gamma-Ray Group LWR Cross Section Libraries Derived from EURLIB-III using the AGRUKO Optimized Collapsing Scheme.
ENDLIB-97AbstractD00179 MNYCP 01LLNL Libraries of Atomic Data, Electron Data, and Photon Data in Evaluated Nuclear Data Library (ENDL) Type Format.
FEWG1-81AbstractD00031 I0370 06Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format.
FEWG1-85AbstractD00031 I0360 07Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format.
GICX40AbstractD00092 ALLCP 00Coupled 42-Neutron, 21-Gamma-Ray Group Cross Sections for 40 Elements in Group Independent Form for Fusion Reactor Calculations.
HPICEAbstractD00007 I0360 05Evaluated Photon Interaction Library, ENDF/B File 23 Format.
I-R-MANAbstractD00050 ALLCP 00Photon Interaction Data on ICRP Reference Man.
LENDLAbstractD00034 I0360 02Livermore Evaluated Neutron and Secondary Gamma-Ray Production Cross-Section Library in ENDF/B-IV Format.
MATXS1AbstractD00114 C0000 0030-Group Neutron, 12-Group Photon Cross Sections from ENDF/B-IV in MATXS Format.
MATXS10AbstractD00176 ALLCP 0030-Group Neutron, 12-Group Photon Cross Sections from ENDF/B-VI in MATXS Format.
MATXS11AbstractD00177 ALLCP 0080-Group Neutron, 24-Group Photon Cross Sections from ENDF/B-VI in MATXS Format.
MATXS5AAbstractD00115 C0000 0030-Group Neutron, 12-Group Photon Cross Sections from ENDF/B-V in MATSX Format.
MATXS6AAbstractD00116 C0000 0080-Group Neutron, 24-Group Photon Fast-Reactor Cross Section from ENDF/B-V in MATXS Format.
MCNPDATAAbstractD00200 ALLCP 03Standard Neutron, Photon, and Electron Data Libraries for MCNP4C or MCNP-PoliMi.
PHOBIAAbstractD00236 PCX86 00Photon buildup factors to account for angular incidence on shield walls.
PVCAbstractD00048 I3691 0036 Group, P5, Photon Interaction Cross Sections for 38 Materials in ANISN Format.
PVEAbstractD00126 I3033 0038 Group, P8, Photon Interaction Cross Sections in ANISN Format from VITAMIN-E.
STORM-ISRAELAbstractD00015 I0360 01Evaluated Photon Interaction Library, ENDF/B File 23 Format.
VITAMIN-CAbstractD00041 I0360 02171 Neutron, 36 Gamma-Ray Group Cross Sections in AMPX and CCCC Interface Formats for Fusion and LMFBR Neutronics.
VITAMIN-EAbstractD00113 I3033 02174n, 38g Cross-Section Library in AMPX Format.
W-M-NRSMAbstractD00026 U1108 00WANL-MSFC Nuclear Rocket Shielding Methods Data Generator (GAMLEG-W, APPROPOS, NAGS, and SATURN) and Multigroup Neutron and Gamma-ray Cross Section Libraries 1-6.
The Radiation Safety Information Computational Center (RSICC) is a Department of Energy Specialized Information Analysis Center (SIAC) authorized to collect, analyze, maintain, and distribute computer software and data sets in the areas of radiation transport and safety. RSICC resides in the Reactor and Nuclear Systems Division (RNSD) at Oak Ridge National Laboratory.