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 L
Package NameAbstractRSICC TapelistTitle
L26P3S34AbstractD00112 IBMMF 00ENDL 26-Group up to P3 Library Prepared by SUPERTOG for 34 Materials.
LA100AbstractD00168 ALLCP 00Evaluated Nuclear Data Library for Transport Calculations Involving Incident Neutrons and Protons of Energy Up to 100 MeV.
LABAN-PELAbstractC00611 IMFPC 00A Two-Dimensional, Multigroup Diffusion, High-Order Response Matrix Code.
LADTAP IIAbstractC00363 C7600 00Code System for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents.
LADTAP IIAbstractC00363 D0780 00Code System for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents.
LADTAP IIAbstractC00363 I3033 00Code System for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents.
LAFPX-VAbstractD00054 C0000 01A Multigroup Reaction Cross-Section Collapsing Code and Library of 154-Group Fission-Product Cross Sections.
LAFPX-VAbstractD00054 C0000 02A Multigroup Reaction Cross-Section Collapsing Code and Library of 154-Group Fission-Product Cross Sections.
LAHET 2.8AbstractC00696 MFMWS 00Code System for High Energy Particle Transport Calculations.
LAHIMACKAbstractD00128 I0360 00A Multigroup Library of Neutron and Gamma Cross Sections and Response Functions in the Energy Range up to 800 MeV.
LAPHANOAbstractP00020 C6600 00PO Multigroup Photon Production Matrix and Source Vector Code for ENDF Data.
LAPHANOAbstractP00020 I0360 00PO Multigroup Photon Production Matrix and Source Vector Code for ENDF Data.
LAPUR6
USSO
AbstractP00395 PC586 02BWR Core Stability Measurements.
LAS CRUCES
USSO
AbstractD00194 ALLCP 00Las Cruces Trench Site Database, Vadose Model.
LASERAbstractC00344 I0360 00A One-Dimensional, Neutron-Thermalization, Lattice-Cell Program Based on MUFT and THERMOS.
LAZYAbstractP00595 I0360 00General Experimental Data Processing Program.
LEAFAbstractC00312 C6600 00Fission Product Release Calculator-From a Reactor Containment Building for Arbitrary Radioactive Decay Chains.
LEAP-ADDELTAbstractP00138 I0360 00Multigroup Thermal Neutron Scattering Data Generator for Hydrogen in Light Water and Deuterium in Heavy Water.
LEBCAbstractC00052 I7090 00Electron Bremsstrahlung Code.
LEGENDRE FUNCTIAbstractP00108 I0360 00Legendre Functions of the First Kind and Legendre Polynomials.
LENDLAbstractD00034 I0360 02Livermore Evaluated Neutron and Secondary Gamma-Ray Production Cross-Section Library in ENDF/B-IV Format.
LENDL VAbstractD00120 I0360 00Lawrence Livermore National Laboratory Evaluated Nuclear Data Library in ENDF-V Format.
LEOPARDAbstractC00343 C0000 00A Spectrum-Dependent Non-Spatial Fuel Depletion Code System.
LEOPARDAbstractC00343 IBMPC 00A Spectrum-Dependent Non-Spatial Fuel Depletion Code System.
LEPAbstractD00001 I0360 02Cascade and Evaporation Particle Results from Low-Energy Intranuclear Cascade Calculations.
LEPRICONAbstractP00277 I3033 01PWR Pressure Vessel Surveillance Dosimetry Analysis System.
LEPRICONAbstractP00277 IRISC 00PWR Pressure Vessel Surveillance Dosimetry Analysis System.
LG-HAbstractC00087 I7090 00Ray Analysis Cylindrical Duct Kernel Code for Neutrons and Gamma Rays.
LGH-GAbstractC00239 I0360 00Calculation of Gamma Radiation through Partially Shielded Gaps (Buildup Factor Method in Taylors Approximation).
LHSAbstractP00394 PC386 00Code System to Generate Latin Hypercube and Random Samples.
LHSAbstractP00394 SUN05 00Code System to Generate Latin Hypercube and Random Samples.
LIB123AbstractD00153 ALLCP 00AMPX-II P3 123-Group Neutron Cross Section Master Interface Library.
LIBMAKAbstractP00087 I0360 00ANISN-Type Binary Data Processing Code System.
LIE-PNAbstractC00816 I0360 00Pn Neutron Transport in Radial Geometry Cell with Source Problems Calculation.
LINEDOSEAbstractC00468 IBMPC 00A Line Source Shielding Code for Personal Computers.
LINSEDAbstractC00673 I0360 001D Multireach Sediment Transport Model
LIONSAbstractC00247 I0360 00Calculation of Fission Product Inventory, Gamma-Ray Dose Rates and Gamma-Ray Doses by Kernel Integration.
LOGNORMLAbstractP00307 IPCAT 00Lognormal Probability Analysis Code System for Estimating Doses in Epidemiologic Studies.
LOOM-PAbstractP00153 F2307 00A Finite Element Mesh Generation Code System with On-Line Graphic Display.
LOUHI82AbstractP00236 U1108 00General Purpose Unfolding Program with Linear and Nonlinear Regularizations.
LPGSAbstractC00385 I3033 00Code System for Calculating Radiation Exposure Resulting from Accidental Radioactive Releases to the Hydrosphere.
LPPCAbstractC00051 I7090 00Proton Penetration Code.
LPSCAbstractC00064 I7090 00Proton Penetration Code - Multilayer Slab Geometry.
LPTAUAbstractP00340 MNYCP 00Quasi-Random Sequence Generators.
LRSPCAbstractC00050 I7090 00Range and Stopping Power Calculator.
LSHINSEAbstractC00554 IBMPC 00Calculates Flux and Dose Rate from the Scattering of Radiation in Air.
LSL-M2AbstractP00233 D6220 00Least-Squares Logarithmic Adjustment of Neutron Spectra.
LSL-M2AbstractP00233 IBMPC 00Least-Squares Logarithmic Adjustment of Neutron Spectra.
LSMOD-GLSMODAbstractP00342 IBMPC 00A Least-Squares Computational Tool Kit.
LSVDCAbstractC00053 I7090 00Space Vehicle Dose Calculation.
LSVDCAbstractC00053 I7090 01Space Vehicle Dose Calculation.
LTCAbstractP00329 IBMPC 00LMR Transient Calculation Code System (version 5).
LUIN-IIAbstractC00220 C6600 00Analytical Straight-Ahead Transport Code System-Calculation of Cosmic-Ray Spectra, Fluxes and Ionization in the Earth's Atmosphere.
LUMPAbstractD00089 I0360 00Evaluated Lumped Fission Product Cross Sections for Fast Reactor Analysis--Based on ENDF/B-V Data.
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.