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: ENDF/B-V
Package NameAbstractRSICC TapelistTitle
ADENAAbstractP00190 C0000 00Code System for Application of Adjusted Data in Calculating Fission-Product Decay Energies and Spectra.
ADENAAbstractP00190 I3033 00Code System for Application of Adjusted Data in Calculating Fission-Product Decay Energies and Spectra.
AMPX-77AbstractP00315 ALLMF 01Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B.
COMPARAbstractP00240 C0170 00Compares Multigroup Cross Sections Generated by NJOY, GROUPIE, FLANGE-II, ETOG-3 and XLACS.
CRECTJ5AbstractP00250 D0780 00A Computer Program for Compilation of Evaluated Nuclear Data in ENDF/B Format.
ENTOSANAbstractP00188 C0175 00Code System for Calculating Fine-Group Dosimetry Cross Section Values from ENDF/B Data.
ENTOSANAbstractP00188 D8810 00Code System for Calculating Fine-Group Dosimetry Cross Section Values from ENDF/B Data.
GLUCSAbstractP00192 D0VAX 00A Generalized Least-Squares Code System for Updating Cross Section Evaluations with Correlated Data Sets.
NJOY91.119AbstractP00171 MFMWS 04Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
NJOY94.61AbstractP00355 MFMWS 03Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
NJOY97.0AbstractP00368 MNYCP 00Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
NJOY99.0AbstractP00480 MNYCP 00Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data.
NJOY-UTIL-EIRAbstractP00296 C0825 00Utilities For the NJOY (6/83) Nuclear Data Processing System.
NSLINKAbstractP00314 D0VAX 00NJOY SCALE LINK.
RGENDFAbstractP00239 C0170 00Format Translation from NJOY GENDF Format to ENDF/B-V and Other Formats.
SAIPSAbstractP00203 E1040 00Information Processing System for Calculating Neutron Spectra from Measured Reaction Rates.
SAIPS-PCAbstractP00295 IBMPC 00Information Processing System for Calculating Neutron Spectra from Measured Reaction Rates.
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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.