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 U
Package NameAbstractRSICC TapelistTitle
UDAD IXAbstractC00685 I0370 00Uranium Dispersion & Dosimetry Model.
UHSAbstractP00390 IPS70 00Ultimate Heat Sink Cooling Pond and Spray Pond Analysis Models.
UKCTRI-81AbstractD00064 I0370 0146-Group Neutron Cross Sections and Kerma Factors for Fusion Reactor Calculations.
UKE-IIIAbstractP00015 I3691 00Cross Section Format Translator - UKNDL to ENDF/B.
UKFY2AbstractD00171 IBMPC 00UK Fission Product Yield Library.
UKNDLAbstractD00039 I0370 00United Kingdom Evaluated Neutron Cross-Section Data Library.
UKNDL-81AbstractD00107 I3033 00The Aldermaston Nuclear Data Library.
UMG 3.3AbstractP00529 PC586 00Unfolding with Maxed and Gravel.
UMIBIOAbstractC00680 I3033 00Code System to Model Uranium Mills Bioassay Dosimetry.
UNFAbstractP00521 PC586 00Code System to Calculate Multistep Compound Nucleus Neutron Cross-Sections and Spectra for Structural Materials.
UNGERAbstractD00164 PC386 00Effective Dose Equivalent for Specific Radionuclides.
UNIFY-ECNAbstractP00288 C0170 00A Program to Calculate Fast Neutron Data for Structural Materials.
UNIMUG3AbstractC00407 C0170 00Solves Multigroup Diffusion Equations in One-Dimensional Systems.
UPDATEAbstractP00270 DGMV1 00Program to Update Fortran Source Files.
UPDATEAbstractP00270 I3081 00Program to Update Fortran Source Files.
UPEAKAbstractP00300 IPCXT 00A Program for Decomposing A One-Dimensional Spectrum.
UPEML 3.0AbstractP00245 ALLCP 01A Machine-Portable CDC UPDATE Emulator.
URRAbstractP00281 D6220 00Calculates Resonance Neutron Cross-Section Probability Tables, Bondarenko Self-Shielding Factors and Self-Indication Ratios for Fissile and Fertile Nuclides.
USINTAbstractP00415 MNYCP 00Code System to Calculate Heat and Mass Transfer In Concrete
USRHYDAbstractC00197 I3675 00Electron and X-Ray Energy Deposition and Hydrodynamics Code System.
UTMTOXAbstractC00500 D8600 00Unified Transport Model for Toxic Materials.
UTSGAbstractP00379 I3033 00Code System for Calculating the Nonlinear Transient Behavior of a Natural Circulation U-Tube Steam Generator with Its Main Steam System.
UTXS6AbstractD00211 MNYCP 00MCNP Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1365K.
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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.