Online Catalog
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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 starting with V
Package NameAbstractRSICC TapelistTitle
VALE 1.1AbstractC00613 IRISC 01A Multigroup Diffusion Theory Neutronics Code System for Solving Two- and Three-Dimensional Problems for Triagonal Geometries.
VALE 1.1AbstractC00613 PC386 01A Multigroup Diffusion Theory Neutronics Code System for Solving Two- and Three-Dimensional Problems for Triagonal Geometries.
VARSKIN 4AbstractC00781 PCX86 00Computer Code System to Assess Skin Dose from Skin Contamination
VCSAbstractC00262 I0360 00Coupled Discrete Ordinates-Adjoint Monte Carlo Calculation of Radiation Protection Factors in Vehicles.
VELMAbstractD00133 I0360 00Multigroup Cross-Section Libraries Based on ENDF/B-V Data for Sodium-Cooled Reactor Shield Analysis.
VENTEASYAbstractC00776 PCX86 00Criticality search for a desired Keffective by adjusting dimensions, nuclide concentrations, or buckling
VENTURE-PCAbstractC00654 PC586 02A Reactor Analysis Code System.
VESTA 2.1.5-AURORA 1.0
OECD
AbstractC00769 PCX86 01VESTA 2.1.5 - Monte Carlo Depletion Interface Code; AURORA 1.0.0 - Depletion Analysis Tool.
VIDEO-PCAbstractP00311 IBMPC 00Super VGA Primitives Graphics System.
VIEWCXSAbstractP00514 PC586 00Interactive Graphic User Interface to View Neutron and Gamma-Ray Interaction Cross Sections.
VIM 5.1AbstractC00754 MNYWS 01Continuous Energy Neutron and Photon Transport Code System, April 2009 Release.
VIM_NCAbstractC00794 PCX86 00VIM Color Syntax for Nuclear Codes: NJOY, DRAGON, PARTISN, TORT, MONK, and MCNP.
VIP-MANAbstractD00256 MNYCP 00Computational Phantom.
VISA2AbstractP00445 MNYCP 00Code System to Calculate Probability of Reactor Vessel Failure.
VITAMIN-4CAbstractD00053 I3691 00171 Neutron Group Cross Sections and Bondarenko Factors in CCCC Interface Formats for Fusion and LMFBR Neutronics.
VITAMIN-B6AbstractD00184 ALLCP 00A Fine-Group Cross Section Library Based on ENDF/B-VI Release 3 for Radiation Transport Applications.
VITAMIN-B7/BUGLE-B7AbstractD00245 MNYCP 01Broad-Group and Fine-Group and Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data.
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.
VITAMIN-J/COVAAbstractD00157 D8810 00Neutron Cross-Section Covariance Data in Multigroup Form.
VITAMIN-J/COVA/EFFAbstractD00197 ALLCP 00Neutron Cross-Section Covariance Data in Multigroup Form.
VITAMIN-J/KERMAAbstractD00150 I3090 00VITAMIN-J 175-Neutron and 38-Photon Kerma And Gas Production Cross Sections.
VITENDF70.BOLIBAbstractD00261 PCX86 00ENDF/B-VII.0 Multi-Group Coupled (199n +42gamma) Cross Section Library in AMPX Format for Nuclear Fission Applications.
VITENEA-EAbstractD00240 MNYCP 00VITENEA-E, AMPX 174-N,38-Gamma Multigroup X-sec. Library for Multidimensional Radiation Transport and Dose Evaluation.
VITENEA-JAbstractD00238 MNYCP 00AMPX 175-n,42-g Multigroup X-section Library for Nuclear Fusion Applications.
VITJEF22.BOLIBAbstractD00241 MNYCP 00JEF-2.2 Multigroup Coupled (199n + 42?) Cross-Section Library in AMPX Format for Nuclear Fission Applications.
VITJEFF31.BOLIBAbstractD00235 MNYCP 00A JEFF-3.1 Multigr Coupled (199n + 42gamma) X-Section Lib. in AMPX Fmt for Nuclear Fission Applications.
VITJEFF311.BOLIBAbstractD00257 MNYCP 01JEFF-3.1.1 Multi-Group Coupled (199n + 42gamma) X-Section Library in AMPX Format for Nuclear Fission Applications.
VIXENAbstractP00030 C6600 00A Code to Check Physical Consistency of Photon-Production Data in Revised ENDF Format.
VIXENAbstractP00030 I0360 00A Code to Check Physical Consistency of Photon-Production Data in Revised ENDF Format.
VPI-NECMAbstractC00481 C0740 00Nuclear Engineering Computer Models for In-Core Fuel Management Analysis.
VPI-NECMAbstractC00481 D0VAX 00Nuclear Engineering Computer Models for In-Core Fuel Management Analysis.
VPI-NECMAbstractC00481 PC486 00Nuclear Engineering Computer Models for In-Core Fuel Management Analysis.
VSOP94AbstractC00670 MNYWS 00Code System for Reactor Physics and Fuel Cycle Simulation.
VVER-BENCHMARKSAbstractM00003 MNYCP 00Collection of Neutronic VVER Reactor Benchmarks.
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.