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 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 00Code System for Assessing 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.
VERA 4.3-EXE
810		AbstractC00855 PCX86 05Virtual Environment for Reactor Applications
VESTA 2.1.5-AURORA 1.0AbstractC00769 PCX86 01A Generic Monte Carlo Code and Depletion Module Interface.
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 Gamma-ray Transport Code System.
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.
VISUAL EDITOR 61AbstractP00618 PCX86 00MCNPX/6 Visual Editor Computer Code 61
VITAMIN-4CAbstractD00053 I3691 00Broad-Group and Fine-Group and Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data.
VITAMIN-B6AbstractD00184 ALLCP 00Broad-Group and Fine-Group and Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data.
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 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/COVAAbstractD00157 D8810 00Broad-Group and Fine-Group and Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data.
VITAMIN-J/COVA/EFFAbstractD00197 ALLCP 00Broad-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.
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 00AMPX 175-n,42-g Multigroup X-section Library for Nuclear Fusion Applications.
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 00Computer Code System for Reactor Physics and Fuel Cycle Simulation.
VVER-BENCHMARKSAbstractM00003 MNYCP 00Collection of Neutronic VVER Reactor Benchmarks.
123ABCDEFGHIJKLMNOPQRSTUVWXYZ
FAQ | ORNL Home | DOE | Site Map | Security Notice
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.