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 E |
| Package Name | Abstract | RSICC Tapelist | Title |
| E3LWR | Abstract | D00098 C0000 00 | 45 Neutron, 16 Gamma-Ray and 15 Neutron, 5 Gamma-Ray Group LWR Cross Section Libraries Derived from EURLIB-III using the AGRUKO Optimized Collapsing Scheme. |
| EACRP-D2O-LATTICES | Abstract | D00264 MNYCP 00 | Compilation of Reactor Physics Measurements in HWRs Lattices. |
| EASY-QAD 2.0.1 | Abstract | C00744 PC586 02 | A Visualization Code System for Gamma and Neutron Shielding Calculations. |
| ECIS-12 | Abstract | P00612 MNYCP 00 | Code System to Solve the Coupled Differential Equations Arising in Nuclear Model Calculations. |
| ECPL82 | Abstract | D00106 ALLCP 00 | Evaluated Charged-Particle Data Library. |
| E-DEP-1 | Abstract | C00275 D0VAX 00 | Heavy Ion Energy Deposition Code System. |
| EDISTR | Abstract | P00191 I3033 00 | Prepares a Nuclear Decay Data Base for Internal Radiation Dosimetry Calculations. |
| EDITOR | Abstract | P00035 I0360 00 | Alters Mode, Copies, Merges, Punches, Edits, or Adds to ENDF/B-Formatted Data on Tapes or Cards. |
| EDMULT 6.4 | Abstract | C00430 MNYCP 02 | Evaluates Electron Depth-Dose Distributions in Multilayer Slab Absorbers. |
| EDNA | Abstract | C00104 I7090 00 | Electron Dose and Number Analysis Code by Kernel Integration. |
| EDO | Abstract | C00489 U1110 00 | A Code System in Fortran V for the Evaluation of Dose During Normal Operation of a Nuclear Power Plant. |
EDSFI
USSO | Abstract | D00215 PC486 00 | Electrical Distribution System Functional Inspection Data Base. |
| EEDB | Abstract | P00531 MNYCP 00 | The Energy Economic Data Base. |
| EFDOS | Abstract | C00411 I0360 00 | Calculation of Effective Committed Dose Equivalents by Inhalation of Radioactive Materials Occurring in Routine Atmospheric Releases from Nuclear Fuel Cycle Facilities. |
| EGAD | Abstract | C00206 I0360 00 | Calculation of Dose from External Gamma-Ray Emitters. |
| EGS4 | Abstract | C00331 MNYCP 00 | Monte Carlo Simulation of the Coupled Transport of Electrons and Photons. |
| ELAN | Abstract | P00141 ICL00 00 | Neutron Cross-Section Self-Shielding Code System. |
| ELAST2 | Abstract | D00208 MNYCP 00 | Database of Cross Sections for the Elastic Scattering of Electrons and Positrons by Atoms. |
| ELBA | Abstract | C00119 I0360 00 | Electron and Bremsstrahlung Dose Rate Code. |
| ELECSPEC | Abstract | D00100 DP010 00 | Electron Spectra from Decay of Fission Products. |
| ELEORBIT | Abstract | C00751 PCX86 00 | 3-D Simulation of Electron Orbits in Magnetic Multipole Plasma Source. |
| ELF | Abstract | C00167 I0360 00 | Monte Carlo Neutron Transport Code System for Cylinders and Spheres. |
| ELGATL | Abstract | C00295 C6600 00 | Calculation of Energy Spectra from Coupled Electron-Photon Slowing Down. |
| ELIESE-3 | Abstract | P00003 I0370 00 | Analyses of Elastic and Inelastic Scattering Cross Sections. |
| ELPHO | Abstract | C00301 I0360 00 | Three-Dimensional Monte Carlo Electromagnetic Transport Code System. |
| ELTRAN | Abstract | C00155 C3600 00 | One-Dimensional Monte Carlo Electron Transport Code System. |
| EMERALD | Abstract | C00211 I0360 00 | Calculation of Activity Releases and Potential Doses from a Pressurized Water Reactor Plant. |
| EMERALD-NORMAL | Abstract | C00250 I0370 00 | Calculation of Activity Releases and Potential Doses from the Normal Operation of a Pressurized Water Reactor Plant. |
| EMPIRE-II | Abstract | P00497 PC586 01 | Comprehensive Nuclear Model Code, Nucleons, Ions Induced Cross-Sections. |
| ENBAL2 | Abstract | P00160 I0370 00 | A Program to Generate Multigroup Neutron Kerma Factors. |
| ENDF UTIL. CODES | Abstract | M00008 MNYCP 00 | ENDF Checking and Utility Codes. |
| ENDL82 | Abstract | D00103 ALLCP 00 | Neutron Library in Transmittal Format. |
| ENDLIB-97 | Abstract | D00179 MNYCP 01 | LLNL Libraries of Atomic Data, Electron Data, and Photon Data in Evaluated Nuclear Data Library (ENDL) Type Format. |
| ENDVER/GUI | Abstract | P00572 PCX86 00 | The ENDF File Verification Support Package. |
| ENEDEP | Abstract | C00227 GE400 00 | Energy Deposition Code System for GE 265 Time-Sharing System. |
| ENLOSS | Abstract | P00047 C6600 00 | Calculation of Energy Loss of Charged Particles. |
| ENSL82-CDRL82 | Abstract | D00110 ALLCP 00 | Evaluated Nuclear Structure Libraries. |
| ENTOSAN | Abstract | P00188 C0175 00 | Code System for Calculating Fine-Group Dosimetry Cross Section Values from ENDF/B Data. |
| ENTOSAN | Abstract | P00188 D8810 00 | Code System for Calculating Fine-Group Dosimetry Cross Section Values from ENDF/B Data. |
| ENTREE 1.4.0 | Abstract | P00519 MNYWS 00 | BWR Core Simulation System for Space and Time Dependent Coupled Phenomena. |
| EPICS2014 | Abstract | D00272 MNYCP 00 | Electron Photon Interaction Cross Sections |
| EPICS2017 | Abstract | D00272 MNYCP 01 | Electron Photon Interaction Cross Sections |
EPIPE
USSO | Abstract | P00485 CY000 00 | Code System for Static and Dynamic Piping System Analysis. |
| EPR | Abstract | D00037 I3691 05 | Coupled 100-Group Neutron 21-Group Gamma-ray Cross Sections for EPR Neutronics. |
| EPR MASTER | Abstract | D00052 I3691 00 | 100 Neutron Group Cross Sections in AMPX Master Library Format. |
| EPRI-CINDER | Abstract | C00309 C6600 00 | General Point-Depletion and Fission Product Code System and Four-Group Fission Product Neutron Absorption Chain Data Library Generated from ENDF/B-IV for Thermal Reactors. |
| EQUIVA-1.1 | Abstract | P00323 IMFPC 00 | Generation of Environment-Insensitive Equivalent Diffusion Theory Parameters for PWR Reflector Regions. |
| EQUIVA-2 | Abstract | P00324 IMFPC 00 | Generation of Environment-Insensitive Equivalent Diffusion Theory Parameters for PWR Reflector Regions. |
ERANOS 2.0
OECD | Abstract | C00745 MNYWS 00 | Modular Code and Data System for Fast Reactor Neutronics Analyses |
| ERIC-2 | Abstract | P00119 I0360 00 | Calculator of Resonance Integral and Effective Capture and Fission Cross Sections for Fissile and Non-Fissile Nuclides - Thermal or Fast Reactors. |
| ERINNI | Abstract | P00219 I0360 00 | Optical Model Calculation of Multiple Cascading Particle Emissions. |
| ERPEX | Abstract | C00305 C0073 00 | Monte Carlo Distributions of Energetic Proton Ranges in Silicon. |
| ERRORJ | Abstract | P00526 MNYCP 03 | Multigroup Covariance Matrices Generation from ENDF/B-6 Format. |
| ESDORA | Abstract | C00183 U1108 00 | Fission Product Inventory and Gamma-Ray Dose Rate from a Radioactive Cloud System. |
| ESG | Abstract | D00065 I0360 00 | 56-Group Cross Section Library Based on VITAMIN-C Generated by Using SPHINX and XSDRNPM to Collapse 171 Groups. |
| ESP | Abstract | C00193 I0360 00 | General Purpose Monte Carlo Neutron Transport Code System. |
| ESTIMA | Abstract | P00201 I3033 00 | A Code System for Calculating Average Parameters from Sets of Resolved Resonance Parameters. |
| ETHEL | Abstract | P00217 I0360 00 | Code System for Generating Cross Sections for PSR-128/THERMOS. |
| ETOE-2 | Abstract | P00585 I3033 00 | Cross-Sections Library for Program MC**2 Generator from ENDF/B. |
| ETRAN | Abstract | C00107 I0360 00 | Monte Carlo Code System for Electron and Photon Through Extended Media. |
| EURCYL | Abstract | P00076 I0370 00 | Finite Element Three-Dimensional Mesh Generator for Cylinder - Cylinder Intersections. |
| EURLIB-III | Abstract | D00035 I0360 01 | 100 Neutron, 20 Gamma-Ray Group Cross Section Library for Use in the European Shielding Benchmark Program. |
| EVALPLOT | Abstract | P00211 I3081 00 | A Program to Plot Data in the Evaluated Nuclear Data File/Version B Format. |
| EVAP | Abstract | P00010 I0360 00 | Calculation of Particle Evaporation from Excited Compound Nuclei. |
| EVNTRE | Abstract | P00465 D0VAX 00 | Code System for Event Progression Analysis for PRA. |
| EXCURS-3-RR | Abstract | P00586 D0VAX 00 | Kinetics of Research Reactor Reactivity Transient Analysis. |
| EXIFON2.0 | Abstract | P00305 IPCXT 01 | A Model for Statistical Multistep Direct and Multistep Compound Reactions. |
| EXPALS | Abstract | C00787 C7600 00 | Least Square Fit of Linear Combination of Exponential Decay Function. |
| EXPRESS | Abstract | C00622 MNYCP 00 | Exact Preparedness Supporting System. |
| EXTREME | Abstract | C00440 I3033 00 | Two-Dimensional Discrete-Ordinates Code System with Exponential Expansion of Spatial Variables. |
| EZVIDEO | Abstract | P00237 IBMPC 00 | Graphics Routines for the IBM PC. |