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
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Packages with Keyword: EVALUATED NEUTRON CROSS SECTIONS
Package NameAbstractRSICC TapelistTitle
ACTIV87AbstractD00169 ALLCP 00Fast Neutron Activation Cross Section File.
ACTV-FUS/INTAbstractD00170 ALLCP 00International Library of Neutron Activation Cross-Section Data for Fusion Reactor Application.
FSX96AbstractD00190 MNYWS 00Collection of Continuous Energy Cross Section Libraries for MCNP Based on JENDL 3.2, JENDL, Fusion File and Dosimetry File.
FSXJ32AbstractD00244 MNYCP 00A Continuous Energy Cross Section MCNP Nuclear Data Library Based on JENDL-3.2.
FSXLIB-J3AbstractD00165 ALLCP 00MCNP continuous energy neutron cross section library based on JENDL-3.
FSXLIB-J33AbstractD00223 MNYCP 01Continuous Energy Neutron Cross Section Library for MCNP Based on JENDL 3.3.
GRUCONAbstractP00615 MNYCP 00Data Processing for Evaluated Working libraries (transport and shielding)
JENDL-1AbstractD00070 ALLCP 00Japanese Evaluated Neutron Cross Section Data in ENDF/B-IV Format.
JENDL-2AbstractD00122 FM380 00Japanese Evaluated Neutron Cross Section Data in ENDF/B-IV Format.
LA100AbstractD00168 ALLCP 00Evaluated Nuclear Data Library for Transport Calculations Involving Incident Neutrons and Protons of Energy Up to 100 MeV.
LENDL VAbstractD00120 I0360 00Lawrence Livermore National Laboratory Evaluated Nuclear Data Library in ENDF-V Format.
MATXS70-JEF87AbstractD00148 D8810 00JEF/EFF Based 70 Group Neutron Data Library in MATXS Format.
NPCSL-81AbstractD00082 I0370 00Point Neutron Cross Sections Generated from ENDF/B-IV with the NPTXS Modules of PSR-63/AMPX-II.
POINT2015AbstractD00273 MNYCP 00A Temperature-Dependent Linearly Interpolable, Tabulated Cross Section Library Based on ENDF/B
TSL-ACE/2013AbstractD00270 ALLCP 00TSL-ACE/2013
UKFY2AbstractD00171 IBMPC 00UK Fission Product Yield Library.
UKNDLAbstractD00039 I0370 00United Kingdom Evaluated Neutron Cross-Section Data Library.
WIMSLIB-JEF87AbstractD00095 D0VAX 00Extended Version of the WIMS 69-group Library.
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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.