| Package Name |
Abstract |
RSICC Tapelist |
Title |
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1DX
| Abstract
|
P00096 I0360 00 |
A One-Dimensional Diffusion Code System for Producing Energy Group Collapsed and Self-Shielded Cross Sections. |
1DX
| Abstract
|
P00096 U1108 00 |
A One-Dimensional Diffusion Code System for Producing Energy Group Collapsed and Self-Shielded Cross Sections. |
ABAREX
| Abstract
|
P00248 MNYCP 01 |
Neutron Spherical Optical-Statistical Model Code System. |
ABLEIT-TRANS
| Abstract
|
P00247 C0175 00 |
Error Propagation Analysis for Burnup Calculation. |
ACAT
| Abstract
|
P00257 FM380 00 |
Monte Carlo Simulation of Atomic Collisions in Amorphous Targets in the Binary Collision Approximation. |
ACORNS
| Abstract
|
P00264 IBMPC 01 |
Analysis of Correlations Used in Neutron Spectrometry. |
ACTIV-PC
| Abstract
|
P00287 IBMPC 00 |
A Program to Process Gamma or X-ray Spectra. |
ADASAGE
| Abstract
|
P00426 IBMPC 00 |
Ada Application Development System, Versions 4.02, 4.0 and 3.1. |
ADEFTA 4.0
| Abstract
|
P00543 MNYCP 00 |
Atomic Densities for Transport Analysis Script. |
ADENA
| Abstract
|
P00190 C0000 00 |
Code System for Application of Adjusted Data in Calculating Fission-Product Decay Energies and Spectra. |
ADENA
| Abstract
|
P00190 I3033 00 |
Code System for Application of Adjusted Data in Calculating Fission-Product Decay Energies and Spectra. |
ADLER III
| Abstract
|
P00058 I0360 00 |
A Program to Calculate Cross Sections from Adler-Adler Resonance Parameters. |
ALARM-B2
| Abstract
|
P00218 I0360 00 |
A Computer Code System for Analysis of a Large Break LOCA of a BWR. |
ALICE-2008
| Abstract
|
P00550 PC586 00 |
Statistical Model Code System to Calculate Particle Spectra from HMS Precompound Nucleus Decay. |
ALPHA-M
| Abstract
|
P00169 I0360 00 |
Least-Squares Resolution of Gamma-Ray Spectra in Environmental Samples. |
ALPS
| Abstract
|
P00144 F2307 00 |
Alpha Spectrum Analysis Code System. |
AMARA
| Abstract
|
P00079 I3675 00 |
Nuclear Data Adjustment Using Lagrange's Multipliers Method. |
AMPX 77
| Abstract
|
P00315 CY000 00 |
Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B. |
AMPX-77
| Abstract
|
P00315 ALLMF 01 |
Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B. |
AMUSE
| Abstract
|
P00028 C6600 00 |
Gamma-Ray Spectra Unfolding Code. |
ANA
| Abstract
|
P00356 IBMPC 00 |
Code System for Gamma-Ray Spectra Analyses. |
ANIPLO D50
| Abstract
|
P00213 I0360 00 |
A Digital Computer Program for Plotting Results from Calculations with the Sn Computer Program ANISN. |
ANSIFT
| Abstract
|
P00077 C6600 00 |
ANSI Standard Fortran Sifting Program. |
ANSIFT
| Abstract
|
P00077 I0360 00 |
ANSI Standard Fortran Sifting Program. |
APPLE-2
| Abstract
|
P00111 FM200 00 |
Plotter of Neutron and Gamma-Ray Spectra and Reaction Rates. |
APPLE-2
| Abstract
|
P00111 I3081 00 |
Plotter of Neutron and Gamma-Ray Spectra and Reaction Rates. |
APSAI
| Abstract
|
P00065 I3691 00 |
Activity Calculations and Plotting of Neutron or Gamma-Ray Spectra Generated by Discrete Ordinates Code System ANISN. |
AREAD
| Abstract
|
P00088 I0360 00 |
Input Data Processor for Transport Codes. |
ATHENA_2D
| Abstract
|
P00431 MNYCP 00 |
Code System For Simulation Of Hypothetical Recriticality Accidents in a Thermal Neutron Spectrum. |
AUTOJOM-JOMREAD
| Abstract
|
P00008 C6600 00 |
Computer Programs to Generate or Check Coefficients for Quadratic Equations Describing 3D Geometries. |
AXMIX
| Abstract
|
P00075 CYXMP 00 |
ANISN Cross Section Code System. |
AXMIX
| Abstract
|
P00075 IRISC 01 |
ANISN Cross Section Code System. |
AXMIX-PC
| Abstract
|
P00297 IBMPC 00 |
ANISN Cross Section Mixing Code System. |
BASACF
| Abstract
|
P00285 IBMPC 00 |
Bayesian Approach to Spectrum Adjustment with Covariance Filter. |
BAYES
| Abstract
|
P00205 DP010 00 |
User's Guide for A General-Purpose Computer Code System for Fitting a Functional Form to Experimental Data. |
BEACON MOD3
| Abstract
|
P00402 CDCMF 00 |
Code System for Thermal-Hydraulic Analysis of Nuclear Reactor Containments. |
BFR
USSO
|
Abstract
|
P00449 C0176 00 |
Code System for Common Cause Failure Data Analysis. |
BLOCKAGE V2.5R
| Abstract
|
P00377 IBMPC 00 |
Code System to Calculate Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in a BWR. |
BOB-7 SERIES
| Abstract
|
P00084 F2306 00 |
Theory and Use of Gamma-Ray Spectrum Analysis Codes for Ge(Li) Detectors. |
BON
| Abstract
|
P00173 I0360 00 |
A Code System for Unfolding Multisphere Spectrometer Neutron Measurements. |
BOT3P-5.2
| Abstract
|
P00530 MNYCP 01 |
Code System for 2D and 3D Mesh Generation and Graphical Display of Geometry and Results for Radation Transport Codes. |
BREESE-II
| Abstract
|
P00143 I3033 00 |
Auxiliary Routines for Implementing the Albedo Option in the MORSE Monte Carlo Code System. |
BRMSTK
| Abstract
|
P00044 C6600 00 |
CSEWG Integral Data Testing Shielding Experiment Code System. |
BRMSTK
| Abstract
|
P00044 I3691 00 |
CSEWG Integral Data Testing Shielding Experiment Code System. |
BSPRP2
| Abstract
|
P00372 IRISC 00 |
Code System to Process DORT Boundary-Flux Files. |
BUCORST
| Abstract
|
P00339 PC386 00 |
A Code to Prepare Burnup-Dependent Multigroup Nuclear Reactor Source Terms. |
CALENDF-2005
| Abstract
|
P00539 MNYCP 00 |
Pointwise, Multigroup Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations. |
CARP-82
| Abstract
|
P00131 I3033 00 |
Multigroup Albedo Data Using DOT Angular Flux Results. |
CASKCODES
| Abstract
|
P00262 IBMPC 00 |
CAPSIZE, SCOPE, AND KWIKDOSE for Shipping Cask Optimization, Dose Calculation, Parameter Evaluation, and Shielding Requirements. |
CASTHY
| Abstract
|
P00316 F0230 00 |
Statistical Model Calculation for Neutron Cross Sections and Capture Gamma-Ray Spectra. |
CCRMN
| Abstract
|
P00366 MNYCP 00 |
Monte Carlo Simulation of the Coupled Transport of Electrons and Photons. |
CEAR-PPU
| Abstract
|
P00528 PC586 00 |
Code System for Monte Carlo Simulation of Detector Pulse Pile Up. |
CECP-BWR
| Abstract
|
P00370 PC386 00 |
Estimating Boiling Water Reactor Decomissioning Costs. |
CECP-PWR
| Abstract
|
P00371 PC386 00 |
Estimating Pressurized Water Reactor Decomissioning Costs. |
CEM03.01
| Abstract
|
P00532 MNYCP 00 |
Monte-Carlo Code System to Calculate Nuclear Reactions in the Framework of Improved Cascade-Exciton Model. |
CEMENT 1.02
USSO
|
Abstract
|
P00412 IBMPC 00 |
Computer Code System for the Estimation of Long-Term Performance of Cement-Based Materials. |
CERPI-CEREL
| Abstract
|
P00147 I0360 00 |
Code Systems for Automatic Analysis of Gamma-Ray Spectra Obtained with Ge(Li) Detectors. |
CGS 11.4
| Abstract
|
P00243 MFMWS 03 |
Common Graphics System, Version 11.4. |
CHENDF 7.02
| Abstract
|
P00333 MNYCP 05 |
Codes for Handling ENDF/B-V and ENDF/B-VI Data. |
COAG-II
| Abstract
|
P00070 I0360 00 |
Calculation of the Westcott Epithermal Index and the Westcott 2200 m/s Neutron Flux. |
COBRA-EN
| Abstract
|
P00507 IBMPC 00 |
Code System for Thermal-Hydraulic Transient Analysis of Light Water Reactor Fuel Assemblies and Cores. |
COBRA-SFS CYCLE 3
| Abstract
|
P00472 MNYCP 00 |
Code System for Thermal Hydraulic Analysis of Spent Fuel Casks. |
COBRA4I
| Abstract
|
P00419 MNYCP 00 |
Code Sytem to Calculate Rod-Bundle and Core Thermal-Hydraulics. |
CODAC (2)
| Abstract
|
P00073 I0360 00 |
For TIMOC 72, Monte Carlo Three-Dimensional Neutron Transport Code's Data Generator. |
COGAP
| Abstract
|
P00375 MNYCP 01 |
Nuclear Power Plant Containment Hydrogen Control System Evaluation Code. |
COMAND
| Abstract
|
P00091 I0360 00 |
A Multigroup ANISN Cross Section Data Library Collapsing Code System. |
COMBINE-PC
| Abstract
|
P00286 IBMPC 00 |
Code System to Compute Neutron Spectra and ENDF/B Version 5 Based Multigroup Neutron Constants. |
COMIDA
| Abstract
|
P00343 MNYCP 00 |
Radionuclide Food Chain Model for Acute Fallout Deposition. |
COMMIX-1B
USSO
|
Abstract
|
P00393 DVX11 00 |
3-D Single-Phase Thermal Hydraulics |
COMMIX-1B
USSO
|
Abstract
|
P00393 I3033 00 |
3-D Single-Phase Thermal Hydraulics |
COMMIX-1C
USSO
|
Abstract
|
P00393 MNYCP 00 |
3-D Single-Phase Thermal Hydraulics |
COMNUC3B
| Abstract
|
P00302 CYXMP 00 |
A Compound Nucleus Analysis Program. |
COMPAR
| Abstract
|
P00240 C0170 00 |
Compares Multigroup Cross Sections Generated by NJOY, GROUPIE, FLANGE-II, ETOG-3 and XLACS. |
COMPARE-MOD1A
| Abstract
|
P00410 C7600 00 |
Transient Flow W/Sinks & Doors |
COMPARE-MOD1A
| Abstract
|
P00410 I3033 00 |
Code System to Calculate Transient Flow With Heat Sinks & Doors. |
COMPASS 1.0.0
| Abstract
|
P00520 PC586 00 |
Computerization of MARSSIM for Planning and Assessing Site Surveys. |
COMPBRN3
| Abstract
|
P00389 PC386 00 |
Code System for Modeling Compartment Fires. |
COMPLOT
| Abstract
|
P00259 IBMMF 00 |
Convert EXFOR Format Data to Computation Format and Plot Comparisons of EXFOR and ENDF/B Evaluated Data (Version 86-1). |
CONFOLD
| Abstract
|
P00053 C6600 00 |
Least-Structure Unfolding Code System for Measured Neutron and Gamma-Ray Spectra. |
CONFOLD
| Abstract
|
P00053 I0360 00 |
Least-Structure Unfolding Code System for Measured Neutron and Gamma-Ray Spectra. |
CONTEMPT-LT28B
USSO
|
Abstract
|
P00387 C7600 00 |
Code System to Predict Containment Pressure-Temperature Response To a Loss-Of-Coolant Accident. |
CONTEMPT4
| Abstract
|
P00397 MNYCP 00 |
Code System for PWR & BWR Multicompartment Containment Analysis, Versions MOD5 & MOD6. |
CONVERT
| Abstract
|
P00036 C6600 00 |
An IBM-to-CDC Program Conversion Code. |
COOL-C
| Abstract
|
P00017 I0360 00 |
Spectra Unfolding Codes. |
CORTES
| Abstract
|
P00404 I0360 00 |
Code System for Thermal & Mechanical Analysis of Tees. |
CRECTJ5
| Abstract
|
P00250 D0780 00 |
A Computer Program for Compilation of Evaluated Nuclear Data in ENDF/B Format. |
CRESO
| Abstract
|
P00184 I3081 00 |
Resonance Data-Handling Code System. |
CRRS
| Abstract
|
P00376 DALPU 01 |
Conference Room Reservation System. |
CUPED
| Abstract
|
P00032 I3675 00 |
Scintillation Spectrometer Polyenergetic Gamma Photon Experimental Distributions Unfolding Code. |
D2O
| Abstract
|
P00398 PC486 00 |
Code System for Computing Thermodynamic and Transport Properties of D2O. |
DANCOFF-MC
| Abstract
|
P00509 MNYCP 00 |
Code System for Monte Carlo Calculation of Dancoff Factors in Irregular Geometries. |
DANCOFF3
| Abstract
|
P00279 D8810 00 |
Calculates Dancoff Correction. |
DANTE
| Abstract
|
P00185 I0370 00 |
Unfolding Code System for Energy Spectra Evaluation for Dosimetry Purposes. |
DASQHE
| Abstract
|
P00278 D8810 00 |
Calculates Dancoff Corrections Factors. |
DATINIT
| Abstract
|
P00258 DGMV1 00 |
Interactive Program To Access Photon Interaction Data. |
DENIS
| Abstract
|
P00082 I0360 00 |
Monte Carlo Simulation of the Capture and Detection of Neutrons with Large Liquid Scintillators. |
DEPLETOR
| Abstract
|
P00523 MNYCP 00 |
Code System to Provide Depletion Capability to the U.S. NRC PARCS Code |
DEPOSITION
FEDC
|
Abstract
|
P00420 IBMPC 00 |
Code System to Calculate Particle Penetration Through Aerosol Transport Lines. |
DETAN 95
| Abstract
|
P00361 MNYCP 00 |
Code System to Calculate Spectrum-Averaged Cross Sections and Detector Responses in Neutron Spectra. |
DIFBAS
| Abstract
|
P00334 MNYCP 00 |
A Bayesian Approach to Unfolding a Neutron Spectrum from a Spectrum of Recoiled Protons. |
DIMEN
| Abstract
|
P00341 IBMPC 00 |
Code System for Isotope Identification by Gamma-Ray Analysis. |
DINT
| Abstract
|
P00049 C6600 00 |
Multigroup Coherent-Incoherent Cross Section Data Generator for Photon Transport Calculations. |
DINT
| Abstract
|
P00049 I0360 00 |
Multigroup Coherent-Incoherent Cross Section Data Generator for Photon Transport Calculations. |
DOMINO
| Abstract
|
P00064 I0360 00 |
A General Purpose Code System for Coupling Discrete Ordinates and Monte Carlo Radiation Transport Calculations. |
DOMINO-II
| Abstract
|
P00162 I3033 00 |
General Purpose Code System for Coupling DOT-IV Discrete Ordinates and Monte Carlo Radiation Transport Calculations. |
DOMUS
| Abstract
|
P00301 IPCXT 00 |
A Program for Decomposing A Two-Dimensional Spectrum. |
DOQDP
| Abstract
|
P00110 I0360 00 |
Discrete Ordinates Quadrature Generator. |
DORGLIB
| Abstract
|
P00181 I0360 00 |
An Interactive Program for Displaying Nuclide Decay and Generation Data Based on ORIGEN Data Library. |
DORIAN
| Abstract
|
P00425 IBMPC 00 |
Code System to Implement Bayes Method for Plant Aging Risk Analysis. |
DSNQUAD
| Abstract
|
P00251 IPCXT 00 |
Calculates Angular Quadrature Weights and Cosines. |
DUFOLD
| Abstract
|
P00042 I0360 00 |
Derivative Unfolding Code - Determination of Neutron Spectra from NE-213 Pulse Height Data. |
DWBA07/DWBB07
| Abstract
|
P00338 MNYCP 01 |
Code System for Inelastic and Elastic Scattering with Nucleon-Nucleon Potential |
DWUCK-CHUCK
| Abstract
|
P00546 MNYCP 00 |
Nuclear Model Code System for Distorted Wave Born Approximation and Coupled Channel Calculations. |
ECIS-06
| Abstract
|
P00227 MNYCP 01 |
Code System to Solve the Coupled Differential Equations Arising in Nuclear Model Calculations. |
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. |
EEDB
| Abstract
|
P00531 MNYCP 00 |
The Energy Economic Data Base. |
ELAN
| Abstract
|
P00141 ICL00 00 |
Neutron Cross-Section Self-Shielding Code System. |
ELIESE-3
| Abstract
|
P00003 I0370 00 |
Analyses of Elastic and Inelastic Scattering Cross Sections. |
EMPIRE
| Abstract
|
P00292 IPCAT 00 |
A Pre-equilibrium Compound Nuclear Model Code For Personal Computers. |
EMPIRE-II
| Abstract
|
P00497 PC586 00 |
Statistical Model Code System for Nuclear Reaction Calculations. |
ENBAL2
| Abstract
|
P00160 I0370 00 |
A Program to Generate Multigroup Neutron Kerma Factors. |
ENLOSS
| Abstract
|
P00047 C6600 00 |
Calculation of Energy Loss of Charged Particles. |
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. |
EPIPE
USSO
|
Abstract
|
P00485 CY000 00 |
Code System for Static and Dynamic Piping System Analysis. |
EQUIVA-1.1
| Abstract
|
P00323 IMFPC 00 |
Generation of Few-Group 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. |
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. |
ERRORJ
| Abstract
|
P00526 MNYCP 01 |
Multigroup Covariance Matrices Generation from ENDF/B-6 Format. |
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. |
EURCYL
| Abstract
|
P00076 I0370 00 |
Finite Element Three-Dimensional Mesh Generator for Cylinder - Cylinder Intersections. |
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. |
EXIFON-GAMMA
| Abstract
|
P00305 IPCXT 00 |
A Model For Statistical Multistep Direct and Multistep Compound Reactions. |
EZVIDEO
| Abstract
|
P00237 IBMPC 00 |
Graphics Routines for the IBM PC. |
F5TAB
| Abstract
|
P00221 D0780 00 |
Code System for Converting Energy Distribution Cross Section Data to Tabulated Data. |
FAMREC
| Abstract
|
P00167 C7600 01 |
Fuel Assembly Mechanical Response Code System. |
FANAC
| Abstract
|
P00179 I3033 00 |
A Shape Analysis Code Package for Resonance Parameter Extraction from Neutron Capture Data for Light- and Medium-Weight Nuclei. |
FANAL
| Abstract
|
P00178 I3033 00 |
A Least-Squares Shape Analysis Code System. |
FANG
| Abstract
|
P00140 C0000 00 |
An Angular Folding Code System for Channel Theory Analysis. |
FANG
| Abstract
|
P00140 I0360 00 |
An Angular Folding Code System for Channel Theory Analysis. |
FASTGRASS
| Abstract
|
P00479 MNYCP 00 |
Code System to Predict Fission Product Release in Ubase Fuels. |
FASTPLOT 1.0
| Abstract
|
P00354 IBMPC 00 |
Interface to Microsoft FORTRAN Graphics. |
FATDUD
| Abstract
|
P00080 I0360 00 |
Foil Activation Data Unfolding Code System. |
FBSAM
| Abstract
|
P00103 I0360 00 |
User-Storage - Magnetic Disk Data Manipulator. |
FDMXPC
| Abstract
|
P00322 IPCAT 00 |
Code System for Calculation of Neutron Transmission and Other Functionals from Evaluated Data in ENDF Format. |
FEDGROUP-3
| Abstract
|
P00123 I0360 00 |
Program System for Processing Evaluated Nuclear Data in ENDF/B, KEDAK or UKNDL Format to Constants to be Used in Reactor Physics Calculation. |
FEDGROUP-R
| Abstract
|
P00349 MNYCP 00 |
Multigroup Neutron Cross Section Processing System from Data in ENDF/B Format. |
FEDGROUPC86REV3
| Abstract
|
P00194 MNYCP 01 |
Code System for Processing Evaluated Nuclear in ENDF/B, KEDAK or UKNDL Formats into Constants for Reactor Physics Calculation. |
FEMAXI 6 VER.1
| Abstract
|
P00536 IBMPC 00 |
Code System for Light Water Reactor Fuel Analysis. |
FEP 4.16
| Abstract
|
P00440 IBMPC 00 |
Fault-tree, Event tree, & P&ID Editors. |
FERD-PC
| Abstract
|
P00273 IBMPC 00 |
Interactive Multichannel Neutron and Gamma-Ray Spectrum Matrix Unfolding Code System. |
FERDO/FERD
| Abstract
|
P00102 I3033 00 |
Multichannel Neutron and Gamma-Ray Spectrum Matrix Unfolding Code Systems. |
FERDOR
| Abstract
|
P00017 I7090 00 |
Spectra Unfolding Codes. |
FERDOR
| Abstract
|
P00017 U1108 00 |
Spectra Unfolding Codes. |
FERRET
| Abstract
|
P00145 U0000 00 |
Least-Squares Solution to Nuclear Data and Reactor Physics Problems. |
FIGERO
| Abstract
|
P00149 C0000 00 |
Processing Codes for Generating Multigroup Neutron Cross Sections from ENDF/B for Use in Discrete Ordinates Calculations. |
FIRAC
| Abstract
|
P00444 CY000 00 |
Nuclear Facilities Fire Accident Model |
FITOCO
| Abstract
|
P00189 C0175 00 |
Converter of Fine-Group Flux Density and Cross Section Data to Coarse Group Values. |
FLODIS
| Abstract
|
P00417 I0360 00 |
Code System to Calculate Thermal Response of FSV HTGR Core. |
FLOWPLOT II
| Abstract
|
P00234 I3033 00 |
Fluid Dynamics and Heat Transfer Plotting Package. |
FLUSH
| Abstract
|
P00043 C6600 00 |
Spectral Unfolding Code - Stepwise Regression of System Response Functions. |
FLYSPEC-SHORTS
| Abstract
|
P00196 C7600 00 |
Neutron Unfolding Code System for Reducing Proton-Recoil Pulse-Height Obtained with NE-213 Liquid Scintillator. |
FORECAST V3.0
| Abstract
|
P00384 IBMPC 00 |
Forecast Regulatory Effects Cost Analysis Program. |
FORIST
| Abstract
|
P00092 C0000 00 |
Neutron Spectrum Unfolding Code System - Iterative Smoothing Technique. |
FORIST
| Abstract
|
P00092 I0360 00 |
Neutron Spectrum Unfolding Code System - Iterative Smoothing Technique. |
FORSEN
| Abstract
|
P00170 I0360 00 |
A Multigroup Processing Code for Use with Sensitivity Profiles to Assess the Effect of Cross Section Changes. |
FORSIM VI
| Abstract
|
P00078 C6600 00 |
A Fortran-Oriented Simulation Package for the Automated Solution of Partial and Ordinary Differential Equation Systems. |
FOURACES
| Abstract
|
P00183 I0370 00 |
Code System for Producing Spectrum Weighted, Group Averaged Cross Sections from ENDF/B, KEDAK, or UK Libraries. |
FRANCO
| Abstract
|
P00363 MNYCP 00 |
Finite Element Fuel Rod Analysis Code System. |
FRANTIC3
| Abstract
|
P00406 CDCMF 00 |
Time-Dependent Reliability Analysis. |
FRAPCON2
USSO
|
Abstract
|
P00517 MFMWS 00 |
Fuel Rod Thermal-Mechanical Behavior, Versions FRAPCON2, FRAPCON2/VIM4, & FRAPCON2/VIM5. |
FRAPT6/MOD1
USSO
|
Abstract
|
P00436 C0176 00 |
Code System for Transient Analysis of Fuel Rods. |
FRAPT6/V21
USSO
|
Abstract
|
P00436 C0176 01 |
Code System for Transient Analysis of Fuel Rods. |
FREEFORM
| Abstract
|
P00081 I0360 00 |
Free-Form Input Reading Routines. |
FUELSDATA
| Abstract
|
P00446 C7600 00 |
Code System to Model Verification Fuel Rod Data. |
GABAS
| Abstract
|
P00175 U1108 00 |
A Code System for Generating Composite Time-Dependent Fission Produce Spectra. |
GAINCALB
| Abstract
|
P00056 I0360 00 |
Determination of the Gain Used with Organic Scintillation Detect. |
GALAXY-6
| Abstract
|
P00098 I0370 00 |
Neutron Multigroup Cross Section Processor. |
GAMAN
| Abstract
|
P00083 DP010 00 |
Qualitative and Quantitative Evaluation of Ge(Li) Gamma-Ray Spectra. |
GAMANAL
| Abstract
|
P00506 D0VAX 00 |
Code System for Computerized Quantitative Analysis By Gamma-Ray Spectrometry. |
GAMIDENT
| Abstract
|
P00154 C0000 00 |
A Program to Aid in the Identification of Unknown Materials by Gamma-ray Spectroscopy. |
GAMLEG-75
| Abstract
|
P00086 C7600 00 |
Multigroup Cross Section Generator for Photon Transport Calculations. |
GAMLEG-JR
| Abstract
|
P00116 F2307 00 |
Multigroup Cross-Section Generator for Photon Transport Calculations. |
GAMLEG-JR
| Abstract
|
P00116 I3033 00 |
Multigroup Cross-Section Generator for Photon Transport Calculations. |
GAMMA
| Abstract
|
P00095 I0360 00 |
Monte Carlo Code System for Calculating Efficiencies and Response Functions of NaI(Tl) Crystals for Gamma Rays from Thick Disk Sources. |
GAMX1
| Abstract
|
P00209 I0370 00 |
A Computer Code System for Evaluating Spectra Peak Areas. |
GAPCON-THERMAL
| Abstract
|
P00499 C7600 00 |
Code System to Calculate Fuel Steady State & Transient Behavior. |
GAROL
| Abstract
|
P00033 I7090 00 |
Calculation of Resonance Neutron Absorption in Two-Region Problems. |
GAUSS V
| Abstract
|
P00045 I0360 00 |
A Code system for Analysis of Gamma-Ray Spectra from Ge(Li) Spectrometers. |
GAUSS VII
| Abstract
|
P00045 C0000 00 |
A Code system for Analysis of Gamma-Ray Spectra from Ge(Li) Spectrometers. |
GCI
| Abstract
|
P00421 IBMPC 00 |
Generic Communications Index |
GECINX
| Abstract
|
P00193 H6000 00 |
A Code System for Collapsing Multigroup Cross Sections in CCCC Format. |
GELI2/SPAN2
| Abstract
|
P00094 I0360 00 |
Calculation of Nuclide Abundaces from Multichannel Gamma-ray Spectra. |
GENRD
| Abstract
|
P00040 C6600 00 |
Free Format Card Input Processor. |
GENRD
| Abstract
|
P00040 I0360 00 |
Free Format Card Input Processor. |
GERES
| Abstract
|
P00241 I0370 00 |
A Code to Produce Cross-Section Libraries for ANISN Based on Heterogeneous Fast Reactor Cell Calculations Using MC2II Data. |
GGC-3
| Abstract
|
P00012 I3565 00 |
Multigroup Cross Section Code System for Use in Diffusion and Transport Codes. |
GGC-3 & GGC-4
| Abstract
|
P00012 I3675 00 |
Multigroup Cross Section Code System for Use in Diffusion and Transport Codes. |
GGC-4
| Abstract
|
P00012 U1108 00 |
Multigroup Cross Section Code System for Use in Diffusion and Transport Codes. |
GGTC-ENEL
| Abstract
|
P00128 I0360 00 |
Code System for Producing Few-Group Neutron Cross Sections from Multigroup Data Libraries. |
GIFT
| Abstract
|
P00124 C0076 00 |
A Combinatorial Geometry Code System with Model Testing Routines. |
GIFT
| Abstract
|
P00124 D0VAX 00 |
A Combinatorial Geometry Code System with Model Testing Routines. |
GIFT
| Abstract
|
P00124 U0000 00 |
A Combinatorial Geometry Code System with Model Testing Routines. |
GIP
| Abstract
|
P00229 IBMPC 00 |
Group-Organized Cross-Section Input Program. |
GIRAFFE
| Abstract
|
P00304 I3033 00 |
General Isotope Release Analysis For Failed Elements. |
GLUCS
| Abstract
|
P00192 D0VAX 00 |
A Generalized Least-Squares Code System for Updating Cross Section Evaluations with Correlated Data Sets. |
GMA
| Abstract
|
P00367 MNYCP 00 |
Code System for Calculation of Reactor Accident Consequences. |
GNASH-FKK
| Abstract
|
P00535 MNYCP 00 |
Pre-equilibrium, Statistical Nuclear-Model Code System for Calculation Cross Sections and Emission Spectra, Version gn9cp8. |
GOFRR
| Abstract
|
P00127 I0360 00 |
Generator of Graphical Output of DOT and ANISN Fluxes and Reaction Rates. |
GRASS-SST
| Abstract
|
P00489 MNYCP 00 |
Code System to Predict Fission-Gas Release & Fuel Swelling. |
GRESS 3.0
| Abstract
|
P00231 MFMWS 02 |
Gradient Enhanced Software System. |
GRETEL
| Abstract
|
P00100 I0370 00 |
Analyzer and Processor of Ge(Li) Gamma-Ray Spectrometric Data. |
GRFPAK
| Abstract
|
P00478 I0360 00 |
Code System to Plot CORTES FEM Results. |
GROUPXS
| Abstract
|
P00246 C0740 00 |
Processing of Double-Differential Cross Sections in the New ENDF-VI Format. |
GRPANL
| Abstract
|
P00321 D0VAX 00 |
Code System for Analyzing Ge and Alpha-Particle Detector Spectra. |
GT2R2
| Abstract
|
P00483 ALLMF 00 |
Code System to Calculate Fuel Rod Thermal Performance. |
HAARM-3
| Abstract
|
P00401 CDCMF 00 |
Aerosol Behavior Log-Normal Distribution Model. |
HAUSER*5
| Abstract
|
P00152 U0000 00 |
Code System for Calculating Nuclear Cross Sections. |
HEATING 7.3
| Abstract
|
P00199 MNYCP 06 |
Multidimensional, Finite-Difference Heat Conduction Analysis Code System, Versions 7.2i and 7.3. |
HECTR 1.5+
USSO
|
Abstract
|
P00457 CY000 00 |
Hydrogen Event Containment Response Code System. |
HEITLER
| Abstract
|
P00004 I7030 00 |
Cross Section Generator. |
HSI-DRG
| Abstract
|
P00435 IBMPC 00 |
Code System for Use with Human System Interface Design Review Guidelines. |
HYPERMET
| Abstract
|
P00101 C3800 00 |
Gamma-Ray Spectra Analyzer Germanium Detector. |
HYPERMET
| Abstract
|
P00101 F150F 00 |
Gamma-Ray Spectra Analyzer Germanium Detector. |
HYPERMET
| Abstract
|
P00101 I0360 00 |
Gamma-Ray Spectra Analyzer Germanium Detector. |
ICAR
| Abstract
|
P00291 IPCAT 00 |
A Code For Combinatorial Calculation of Level Densities. |
IER
| Abstract
|
P00024 I3675 00 |
A Gauss-based Quadrature Formula Applied to Sievert's Integral. An Exponential Integral Routine. |
IMPORTANCE
| Abstract
|
P00407 I0370 00 |
FTA Basic Event & Cut Set Ranking. |
INFLTB
| Abstract
|
P00313 ALLCP 00 |
Gamma-Ray Absorption Coefficient Calculation. |
INGEN
| Abstract
|
P00207 C0000 00 |
A General-Purpose Mesh Generator for Finite Element Codes. |
INTRIGUE-II
| Abstract
|
P00054 I0360 00 |
Logarithmic and Semilogarithmic CALCOMP Plot Routines. |
IRRAS 4.16
USSO
|
Abstract
|
P00386 IBMPC 04 |
Code System to Calculate Integrated Reliability and Risk Analysis. |
ITER-2
| Abstract
|
P00148 C0000 00 |
Codes for Unfolding Activation Detector Data and Pulse Height Spectra. |
KAOS-V
| Abstract
|
P00306 CY000 00 |
An Evaluation Tool For Neutron Kerma Factors and Other Nuclear Responses. |
KENO2MCNP
| Abstract
|
P00541 PC586 00 |
Conversion of Input Data between KENO V.a and MCNP File Formats, Version 5L. |
KFIX
| Abstract
|
P00409 C7600 00 |
Code System to Calculate Transient 2-Dimensional 2-Fluid Flow Dynamics. |
KFIX 3D
| Abstract
|
P00383 C7600 00 |
Code System to Calculate Three-Dimensional Extension Two-Phase Flow Dynamics. |
LAPHANO
| Abstract
|
P00020 C6600 00 |
PO Multigroup Photon Production Matrix and Source Vector Code for ENDF Data. |
LAPHANO
| Abstract
|
P00020 I0360 00 |
PO Multigroup Photon Production Matrix and Source Vector Code for ENDF Data. |
LAPUR6
USSO
|
Abstract
|
P00395 PC586 02 |
BWR Core Stability Measurements. |
LEAP-ADDELT
| Abstract
|
P00138 I0360 00 |
Multigroup Thermal Neutron Scattering Data Generator for Hydrogen in Light Water and Deuterium in Heavy Water. |
LEGENDRE FUNCTI
| Abstract
|
P00108 I0360 00 |
Legendre Functions of the First Kind and Legendre Polynomials. |
LEPRICON
| Abstract
|
P00277 IRISC 00 |
PWR Pressure Vessel Surveillance Dosimetry Analysis System. |
LEPRICON
| Abstract
|
P00277 I3033 01 |
PWR Pressure Vessel Surveillance Dosimetry Analysis System. |
LHS
| Abstract
|
P00394 PC386 00 |
Code System to Generate Latin Hypercube and Random Samples. |
LHS
| Abstract
|
P00394 SUN05 00 |
Code System to Generate Latin Hypercube and Random Samples. |
LIBMAK
| Abstract
|
P00087 I0360 00 |
ANISN-Type Binary Data Processing Code System. |
LOGNORML
| Abstract
|
P00307 IPCAT 00 |
Lognormal Probability Analysis Code System for Estimating Doses in Epidemiologic Studies. |
LOOM-P
| Abstract
|
P00153 F2307 00 |
A Finite Element Mesh Generation Code System with On-Line Graphic Display. |
LOUHI82
| Abstract
|
P00236 U1108 00 |
General Purpose Unfolding Program with Linear and Nonlinear Regularizations. |
LPTAU
| Abstract
|
P00340 MNYCP 00 |
Quasi-Random Sequence Generators. |
LSL-M2
| Abstract
|
P00233 D6220 00 |
Least-Squares Logarithmic Adjustment of Neutron Spectra. |
LSL-M2
| Abstract
|
P00233 IBMPC 00 |
Least-Squares Logarithmic Adjustment of Neutron Spectra. |
LSMOD-GLSMOD
| Abstract
|
P00342 IBMPC 00 |
A Least-Squares Computational Tool Kit. |
LTC
| Abstract
|
P00329 IBMPC 00 |
LMR Transient Calculation Code System (version 5). |
MACK-IV
| Abstract
|
P00132 I3691 00 |
Calculation of Nuclear Response Functions from Nuclear Data in ENDF Format. |
MAEROS
| Abstract
|
P00466 C7600 00 |
Code System for Multicomponent Aerosol Time Evolution. |
MAINTAIN
| Abstract
|
P00067 I0360 00 |
Code System for Use in Maintaining and Revising Card Image Files on Tape. |
MANYFILE
| Abstract
|
P00068 I0360 00 |
Utility Routine - Manipulation of Data Sets Between Various I-O Devices. |
MARCH2
| Abstract
|
P00473 CDCMF 00 |
Code System to Model LWR Meltdown Accident Response. |
MARCOPOLO
| Abstract
|
P00225 I0360 00 |
Code System for Calculating the Radial and Axial Neutron Diffusion Coefficients in One-Group and Multigroup Theory. |
MARD 4.16
| Abstract
|
P00448 IBMPC 00 |
Models And Results Database System. |
MARIA SYSTEM
| Abstract
|
P00359 D6000 00 |
Code System to Calculate Cross Sections for PWR Fuel Assembly Calculations. |
MARLOWE 15B
| Abstract
|
P00137 MNYCP 08 |
Computer Simulation of Atomic Collisions in Crystalline Solids (Version 15). |
MARS
| Abstract
|
P00117 I0360 00 |
Collection of Computer Codes for Manipulating Multigroup Cross Section Libraries in AMPX or CCCC Formats. |
MARTHA
| Abstract
|
P00232 I0360 00 |
Monte Carlo Response Function Calculation for Sodium Iodide Photon Detectors. |
MATEXP
| Abstract
|
P00059 I0360 00 |
Matrix Exponential Method Applied to Systems of Ordinary Differential Equations. |
MATXUF
| Abstract
|
P00130 I0360 00 |
On-Line Derivative Method, Spectrum Unfolding Code System for NE-213 Liquid Fast Scintillation Proton Recoil Data. |
MAX-XTREME
| Abstract
|
P00001 C0000 00 |
Generalized Several-Constraint LaGrange Multiplier. |
MAZE II
| Abstract
|
P00041 U1108 00 |
Spectral Unfolding Code. |
MAZE-1
| Abstract
|
P00041 C6600 00 |
Spectral Unfolding Code. |
MC**2-2
| Abstract
|
P00350 SUN05 01 |
Code System for Calculating Fast Neutron Spectra and Multigroup Cross-sections from ENDF/B Data (November 2000 Version). |
MCVIEW
| Abstract
|
P00202 FM780 00 |
View Factor Calculation for Three-Dimensional Geometries. |
MESA
| Abstract
|
P00223 I3033 00 |
Non-Linear Least Squares Spectral Analysis. |
METD
| Abstract
|
P00197 DGMV1 00 |
Computer Code Systems for Use with Meteorological Data. |
METD
| Abstract
|
P00197 I3033 00 |
Computer Code Systems for Use with Meteorological Data. |
MGA8
| Abstract
|
P00542 MNYCP 00 |
Code System to Determine Pu Isotope Abundances from Multichannel Analyzer Gamma Spectra. |
MICAP
| Abstract
|
P00261 I3033 00 |
A Monte Carlo Code System for Analysis of Ionization Chamber Responses. |
MICROX-2
| Abstract
|
P00374 MNYCP 02 |
Code System to Create Broad-Group Cross Sections with Resonance Interference and Self-Shielding from Fine-Group and Pointwise Cross Sections. |
MIGROS3
| Abstract
|
P00265 I0370 00 |
A Code for the Generation of Group Constants for Reactor Calculations from Neutron Nuclear Data in KEDAK Format. |
MINET
| Abstract
|
P00490 CY000 00 |
Momentum Integral Network Method for Thermal-Hydraulic Systems Analysis. |
MINIGAL
| Abstract
|
P00180 I3033 00 |
Neutron Cross Section Processing System for Calculating Average Values from Data in the Standard United Kingdom Nuclear Data Library Format. |
MINTEQ
| Abstract
|
P00494 DVX11 00 |
Code System to Model Aqueous Geochemical Equilibria. |
MINX
| Abstract
|
P00105 C6600 00 |
Multigroup Interpretation of Nuclear X-Sections from ENDF/B Standard CCCC-III Interface Formats. |
MINX
| Abstract
|
P00105 I0360 00 |
Multigroup Interpretation of Nuclear X-Sections from ENDF/B Standard CCCC-III Interface Formats. |
MISSIONARY
| Abstract
|
P00114 I0360 00 |
ENDF/B to NDL Data Format Converter. |
MIXEN
| Abstract
|
P00318 IRISC 00 |
Code System to Replace Files 4 and 6 of ENDF-6 with Files 4 and 5 of ENDF/B-IV. |
MOCUP
| Abstract
|
P00365 DALPU 00 |
MCNP/ORIGEN Coupling Utility Programs. |
MONTEBURNS 2.0
| Abstract
|
P00455 MNYCP 02 |
An Automated, Multi-Step Monte Carlo Burnup Code System. |
MORECA
| Abstract
|
P00411 PC386 00 |
Computer Code System for Simulating Modular High-Temperature Gas Cooled Reactor Core Heatup. |
MORN
| Abstract
|
P00062 I0360 00 |
Calculation of the Response of Sodium Iodide Crystals to Gamma Rays. |
MORSEC-SP2
| Abstract
|
P00142 H6000 00 |
A Multigroup Cross Section Module for the MORSE Monte Carlo Computer Code System. |
MOSRA-LIGHT
| Abstract
|
P00505 MNYWS 00 |
High-Speed Three-Dimensional Nodal Diffusion Code System. |
MOXY-MOD32
| Abstract
|
P00385 I0360 00 |
BWR Core Heat Transfer Code System. |
MRSPAK
| Abstract
|
P00212 DVX11 00 |
A Code System To Generate a Text File Containing Combinatorial Geometry Data Corresponding to PADL2 Geometry. |
MSM-SOURCE
| Abstract
|
P00369 MNYCP 00 |
Code System for Generation of Input Data for MCNP. |
MUP2
| Abstract
|
P00289 I3090 00 |
A Program to Calculate Fast Neutron Data for Medium-Heavy Nuclei. |
MUXS
| Abstract
|
P00187 I3033 00 |
Generator of Multigroup Cross Sections for Charged Particle Transport Problems. |
NAISAP
| Abstract
|
P00085 F2306 00 |
Theory and Use of Gamma-Ray Spectrum Analysis Codes for NaI(Tl) Detectors. |
NANICK
| Abstract
|
P00120 I0360 00 |
Infinitely-Diluted Multigroup Cross-Section Generator - from ENDF/B. |
NASIF-NARES
| Abstract
|
P00121 I0360 00 |
A Code System for Computing Shielding Factors from ENDF/B Tapes. |
NE-SPEC
| Abstract
|
P00150 F2307 00 |
A Code System for Unfolding a Pulse Height Distribution of Neutrons Measured by an NE-213 Organic Scintillator. |
NEUPAC
| Abstract
|
P00177 FM200 00 |
Neutron Unfolding Code System for Calculating Neutron Flux Spectra from Activation Data of Dosimeter Foils. |
NEVEMOR
| Abstract
|
P00026 I3675 00 |
Multigroup-Multiregion Calculation of Flux Spectra and Energy Deposition for Fast Neutrons. |
NJOY-UTIL-EIR
| Abstract
|
P00296 C0825 00 |
Utilities For the NJOY (6/83) Nuclear Data Processing System. |
NJOY91.119
| Abstract
|
P00171 MFMWS 04 |
Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data. |
NJOY94.61
| Abstract
|
P00355 MFMWS 03 |
Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data. |
NJOY97.0
| Abstract
|
P00368 MNYCP 00 |
Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data. |
NJOY99.0
| Abstract
|
P00480 MNYCP 00 |
Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data. |
NONSAP-C
| Abstract
|
P00458 C7600 00 |
Code System for Analysis of 3-D Reinforced Concrete Structures. |
NORMA
| Abstract
|
P00471 PC586 00 |
Code System to Solve Burnup Dependent Neutron Diffusion Equations in Two and Three Dimensions. |
NORMA-FP
| Abstract
|
P00470 PC586 00 |
Code System to Perform Neutronic and Thermal-Hydraulic Subchannel Analysis from Converged Coarse-Mesh Nodal Solutions. |
NPTXS
| Abstract
|
P00090 I0360 00 |
Data Generator: Neutron Point Cross Sections from ENDF/B Resolved and Unresolved Resonance Parameters. |
NRCPAGE
| Abstract
|
P00491 DVX11 00 |
Code System to Detect Recurring Loss of Special Nuclear Materials. |
NRCPIPES 2.0A
| Abstract
|
P00429 IBMPC 00 |
Code System for Fracture Mechanics Analysis of Circumferential Surface Cracks in Pipes. |
NSLINK
| Abstract
|
P00314 D0VAX 00 |
NJOY SCALE LINK. |
NUCHART
| Abstract
|
P00545 IBMPC 00 |
Nuclear Properties and Decay Data Chart of Nuclides. |
NUFACE
| |
