| RSICC Tapelist |
Package Name |
Abstract |
Title |
Click on Package Name to get detailed information.
Click on RSICC Tapelist to view list of files.
Note: RESTRICTIONS APPLY to SOME PACKAGES:
"USSO" -- U.S. DISTRIBUTION ONLY
"FEDC" -- For U.S. Government Contractors Only
"USUNV" -- US Universities Only
Go To Order Form
P00001 C0000 00 |
MAX-XTREME
| Abstract
|
Generalized Several-Constraint LaGrange Multiplier. |
P00003 I0370 00 |
ELIESE-3
| Abstract
|
Analyses of Elastic and Inelastic Scattering Cross Sections. |
P00004 I7030 00 |
HEITLER
| Abstract
|
Cross Section Generator. |
P00008 C6600 00 |
AUTOJOM-JOMREAD
| Abstract
|
Computer Programs to Generate or Check Coefficients for Quadratic Equations Describing 3D Geometries. |
P00010 I0360 00 |
EVAP
| Abstract
|
Calculation of Particle Evaporation from Excited Compound Nuclei. |
P00011 I3675 00 |
POPOP4
| Abstract
|
Converter of Gamma-Ray Spectra to Secondary Gamma-Ray Production Cross Sections. |
P00012 I3565 00 |
GGC-3
| Abstract
|
Multigroup Cross Section Code System for Use in Diffusion and Transport Codes. |
P00012 I3675 00 |
GGC-3 & GGC-4
| Abstract
|
Multigroup Cross Section Code System for Use in Diffusion and Transport Codes. |
P00012 U1108 00 |
GGC-4
| Abstract
|
Multigroup Cross Section Code System for Use in Diffusion and Transport Codes. |
P00013 I3691 00 |
SUPERTOG III M2
| Abstract
|
Data Generator--Fine Group Constants and PN Scattering Matrices from ENDF/B. |
P00013 I0360 00 |
SUPERTOG-4
| Abstract
|
Data Generator--Fine Group Constants and PN Scattering Matrices from ENDF/B. |
P00014 DP010 00 |
O5S
| Abstract
|
Response Function Generator--An O5R Monte Carlo Code for Calculating Pulse Height Distributions Due to Monoenergetic Neutrons Incident on Organic Scintillators. |
P00014 I3675 00 |
O5S
| Abstract
|
Response Function Generator--An O5R Monte Carlo Code for Calculating Pulse Height Distributions Due to Monoenergetic Neutrons Incident on Organic Scintillators. |
P00015 I3691 00 |
UKE-III
| Abstract
|
Cross Section Format Translator - UKNDL to ENDF/B. |
P00017 I0360 00 |
COOL-C
| Abstract
|
Spectra Unfolding Codes. |
P00017 I7090 00 |
FERDOR
| Abstract
|
Spectra Unfolding Codes. |
P00017 U1108 00 |
FERDOR
| Abstract
|
Spectra Unfolding Codes. |
P00018 I3675 00 |
PLOTFB
| Abstract
|
ENDF/B Data Plotting Code. |
P00020 C6600 00 |
LAPHANO
| Abstract
|
PO Multigroup Photon Production Matrix and Source Vector Code for ENDF Data. |
P00020 I0360 00 |
LAPHANO
| Abstract
|
PO Multigroup Photon Production Matrix and Source Vector Code for ENDF Data. |
P00022 I0360 00 |
RICE
| Abstract
|
A Program to Calculate Primary Recoil Atom Spectra from ENDF/B Data. |
P00023 I3565 00 |
SPECTER
| Abstract
|
Calculation of Energy Distribution of Nuclear Reaction Products. |
P00024 I3675 00 |
IER
| Abstract
|
A Gauss-based Quadrature Formula Applied to Sievert's Integral. An Exponential Integral Routine. |
P00026 I3675 00 |
NEVEMOR
| Abstract
|
Multigroup-Multiregion Calculation of Flux Spectra and Energy Deposition for Fast Neutrons. |
P00028 C6600 00 |
AMUSE
| Abstract
|
Gamma-Ray Spectra Unfolding Code. |
P00029 I3675 00 |
SCANS
| Abstract
|
Spectra Calculation from Activated Nuclide Sets. |
P00030 C6600 00 |
VIXEN
| Abstract
|
A Code to Check Physical Consistency of Photon-Production Data in Revised ENDF Format. |
P00030 I0360 00 |
VIXEN
| Abstract
|
A Code to Check Physical Consistency of Photon-Production Data in Revised ENDF Format. |
P00031 C6600 00 |
SWIFT
| Abstract
|
Monte Carlo Neutron Spectra Unfolding Code. |
P00032 I3675 00 |
CUPED
| Abstract
|
Scintillation Spectrometer Polyenergetic Gamma Photon Experimental Distributions Unfolding Code. |
P00033 I7090 00 |
GAROL
| Abstract
|
Calculation of Resonance Neutron Absorption in Two-Region Problems. |
P00035 I0360 00 |
EDITOR
| Abstract
|
Alters Mode, Copies, Merges, Punches, Edits, or Adds to ENDF/B-Formatted Data on Tapes or Cards. |
P00036 C6600 00 |
CONVERT
| Abstract
|
An IBM-to-CDC Program Conversion Code. |
P00039 F2307 00 |
REFUM-BROAD
| Abstract
|
Monte Carlo Codes for Calculating Efficiencies and Response Functions of NaI(Tl) Crystals for Thick Disk Gamma-Ray Sources. |
P00040 C6600 00 |
GENRD
| Abstract
|
Free Format Card Input Processor. |
P00040 I0360 00 |
GENRD
| Abstract
|
Free Format Card Input Processor. |
P00041 U1108 00 |
MAZE II
| Abstract
|
Spectral Unfolding Code. |
P00041 C6600 00 |
MAZE-1
| Abstract
|
Spectral Unfolding Code. |
P00042 I0360 00 |
DUFOLD
| Abstract
|
Derivative Unfolding Code - Determination of Neutron Spectra from NE-213 Pulse Height Data. |
P00043 C6600 00 |
FLUSH
| Abstract
|
Spectral Unfolding Code - Stepwise Regression of System Response Functions. |
P00044 C6600 00 |
BRMSTK
| Abstract
|
CSEWG Integral Data Testing Shielding Experiment Code System. |
P00044 I3691 00 |
BRMSTK
| Abstract
|
CSEWG Integral Data Testing Shielding Experiment Code System. |
P00045 I0360 00 |
GAUSS V
| Abstract
|
A Code system for Analysis of Gamma-Ray Spectra from Ge(Li) Spectrometers. |
P00045 C0000 00 |
GAUSS VII
| Abstract
|
A Code system for Analysis of Gamma-Ray Spectra from Ge(Li) Spectrometers. |
P00047 C6600 00 |
ENLOSS
| Abstract
|
Calculation of Energy Loss of Charged Particles. |
P00049 C6600 00 |
DINT
| Abstract
|
Multigroup Coherent-Incoherent Cross Section Data Generator for Photon Transport Calculations. |
P00049 I0360 00 |
DINT
| Abstract
|
Multigroup Coherent-Incoherent Cross Section Data Generator for Photon Transport Calculations. |
P00053 C6600 00 |
CONFOLD
| Abstract
|
Least-Structure Unfolding Code System for Measured Neutron and Gamma-Ray Spectra. |
P00053 I0360 00 |
CONFOLD
| Abstract
|
Least-Structure Unfolding Code System for Measured Neutron and Gamma-Ray Spectra. |
P00054 I0360 00 |
INTRIGUE-II
| Abstract
|
Logarithmic and Semilogarithmic CALCOMP Plot Routines. |
P00055 C6400 00 |
SIR-3
| Abstract
|
Sievert's Integral Routine-Computer Evaluation. |
P00055 I3675 00 |
SIR-3
| Abstract
|
Sievert's Integral Routine-Computer Evaluation. |
P00056 I0360 00 |
GAINCALB
| Abstract
|
Determination of the Gain Used with Organic Scintillation Detect. |
P00057 I3675 00 |
SATURN
| Abstract
|
P1 or Transport Corrected Multigroup Neutron Cross Section Data Processor. |
P00058 I0360 00 |
ADLER III
| Abstract
|
A Program to Calculate Cross Sections from Adler-Adler Resonance Parameters. |
P00059 I0360 00 |
MATEXP
| Abstract
|
Matrix Exponential Method Applied to Systems of Ordinary Differential Equations. |
P00060 I0360 00 |
RESPMG
| Abstract
|
Response Matrix Generation Code System. |
P00062 I0360 00 |
MORN
| Abstract
|
Calculation of the Response of Sodium Iodide Crystals to Gamma Rays. |
P00064 I0360 00 |
DOMINO
| Abstract
|
A General Purpose Code System for Coupling Discrete Ordinates and Monte Carlo Radiation Transport Calculations. |
P00065 I3691 00 |
APSAI
| Abstract
|
Activity Calculations and Plotting of Neutron or Gamma-Ray Spectra Generated by Discrete Ordinates Code System ANISN. |
P00066 I3675 00 |
RNGP
| Abstract
|
Random Number Generator Package. |
P00067 I0360 00 |
MAINTAIN
| Abstract
|
Code System for Use in Maintaining and Revising Card Image Files on Tape. |
P00068 I0360 00 |
MANYFILE
| Abstract
|
Utility Routine - Manipulation of Data Sets Between Various I-O Devices. |
P00069 C7600 00 |
POWER
| Abstract
|
Source Distribution Input Data Generator for ANISN Code. |
P00070 I0360 00 |
COAG-II
| Abstract
|
Calculation of the Westcott Epithermal Index and the Westcott 2200 m/s Neutron Flux. |
P00071 ICL00 00 |
SPECTRANS-2
| Abstract
|
Neutron Spectrum Library Generation. |
P00073 I0360 00 |
CODAC (2)
| Abstract
|
For TIMOC 72, Monte Carlo Three-Dimensional Neutron Transport Code's Data Generator. |
P00074 DP010 00 |
TECALC
| Abstract
|
Interactive Calculation of Compton Coherent and Photoelectric Mass Attenuation Coefficients for Photons (E<1 MeV), and the Mass Absorption Coefficient for Known Materials. |
P00075 CYXMP 00 |
AXMIX
| Abstract
|
ANISN Cross Section Code System. |
P00075 IRISC 01 |
AXMIX
| Abstract
|
ANISN Cross Section Code System. |
P00076 I0370 00 |
EURCYL
| Abstract
|
Finite Element Three-Dimensional Mesh Generator for Cylinder - Cylinder Intersections. |
P00077 C6600 00 |
ANSIFT
| Abstract
|
ANSI Standard Fortran Sifting Program. |
P00077 I0360 00 |
ANSIFT
| Abstract
|
ANSI Standard Fortran Sifting Program. |
P00078 C6600 00 |
FORSIM VI
| Abstract
|
A Fortran-Oriented Simulation Package for the Automated Solution of Partial and Ordinary Differential Equation Systems. |
P00079 I3675 00 |
AMARA
| Abstract
|
Nuclear Data Adjustment Using Lagrange's Multipliers Method. |
P00080 I0360 00 |
FATDUD
| Abstract
|
Foil Activation Data Unfolding Code System. |
P00081 I0360 00 |
FREEFORM
| Abstract
|
Free-Form Input Reading Routines. |
P00082 I0360 00 |
DENIS
| Abstract
|
Monte Carlo Simulation of the Capture and Detection of Neutrons with Large Liquid Scintillators. |
P00083 DP010 00 |
GAMAN
| Abstract
|
Qualitative and Quantitative Evaluation of Ge(Li) Gamma-Ray Spectra. |
P00084 F2306 00 |
BOB-7 SERIES
| Abstract
|
Theory and Use of Gamma-Ray Spectrum Analysis Codes for Ge(Li) Detectors. |
P00085 F2306 00 |
NAISAP
| Abstract
|
Theory and Use of Gamma-Ray Spectrum Analysis Codes for NaI(Tl) Detectors. |
P00086 C7600 00 |
GAMLEG-75
| Abstract
|
Multigroup Cross Section Generator for Photon Transport Calculations. |
P00087 I0360 00 |
LIBMAK
| Abstract
|
ANISN-Type Binary Data Processing Code System. |
P00088 I0360 00 |
AREAD
| Abstract
|
Input Data Processor for Transport Codes. |
P00089 I0360 00 |
SKEWGAUS
| Abstract
|
Skewed-Gaussian Line Peak Fitting Code - Multichannel Analyzer (MCA) Spectra - Ge(Li) and Semiconductor Detectors. |
P00090 I0360 00 |
NPTXS
| Abstract
|
Data Generator: Neutron Point Cross Sections from ENDF/B Resolved and Unresolved Resonance Parameters. |
P00091 I0360 00 |
COMAND
| Abstract
|
A Multigroup ANISN Cross Section Data Library Collapsing Code System. |
P00092 C0000 00 |
FORIST
| Abstract
|
Neutron Spectrum Unfolding Code System - Iterative Smoothing Technique. |
P00092 I0360 00 |
FORIST
| Abstract
|
Neutron Spectrum Unfolding Code System - Iterative Smoothing Technique. |
P00094 I0360 00 |
GELI2/SPAN2
| Abstract
|
Calculation of Nuclide Abundaces from Multichannel Gamma-ray Spectra. |
P00095 I0360 00 |
GAMMA
| Abstract
|
Monte Carlo Code System for Calculating Efficiencies and Response Functions of NaI(Tl) Crystals for Gamma Rays from Thick Disk Sources. |
P00096 I0360 00 |
1DX
| Abstract
|
A One-Dimensional Diffusion Code System for Producing Energy Group Collapsed and Self-Shielded Cross Sections. |
P00096 U1108 00 |
1DX
| Abstract
|
A One-Dimensional Diffusion Code System for Producing Energy Group Collapsed and Self-Shielded Cross Sections. |
P00097 C6600 00 |
PAPER 1
| Abstract
|
Monte Carlo Calculation of Solid Angle and Self-Absorption Factors for an Inclined Cylindrical Source Viewed by a Cylindrical Detector. |
P00098 I0370 00 |
GALAXY-6
| Abstract
|
Neutron Multigroup Cross Section Processor. |
P00099 I0360 00 |
SPEC-4
| Abstract
|
Calculated Recoil Proton Energy Distributions from Monoenergetic and Continuous Spectrum Neutrons. |
P00100 I0370 00 |
GRETEL
| Abstract
|
Analyzer and Processor of Ge(Li) Gamma-Ray Spectrometric Data. |
P00101 C3800 00 |
HYPERMET
| Abstract
|
Gamma-Ray Spectra Analyzer Germanium Detector. |
P00101 F150F 00 |
HYPERMET
| Abstract
|
Gamma-Ray Spectra Analyzer Germanium Detector. |
P00101 I0360 00 |
HYPERMET
| Abstract
|
Gamma-Ray Spectra Analyzer Germanium Detector. |
P00102 I3033 00 |
FERDO/FERD
| Abstract
|
Multichannel Neutron and Gamma-Ray Spectrum Matrix Unfolding Code Systems. |
P00103 I0360 00 |
FBSAM
| Abstract
|
User-Storage - Magnetic Disk Data Manipulator. |
P00104 I0360 00 |
SECA
| Abstract
|
Evaluator of Angular Bounds for a Two-Dimensional Symmetric Gaussian Quadrature Set. |
P00105 C6600 00 |
MINX
| Abstract
|
Multigroup Interpretation of Nuclear X-Sections from ENDF/B Standard CCCC-III Interface Formats. |
P00105 I0360 00 |
MINX
| Abstract
|
Multigroup Interpretation of Nuclear X-Sections from ENDF/B Standard CCCC-III Interface Formats. |
P00106 C6600 00 |
PLASMX
| Abstract
|
A Multigroup Ionization and Charge Exchange Cross-Section Code System for Neutral Hydrogen Transport in Plasmas. |
P00107 C0173 00 |
THERMOS-OTA
| Abstract
|
Multigroup Integral Transport Code System for Thermal Lattice Calculations using Collision Probability Method for Slabs and Cylinders. |
P00107 C0740 00 |
THERMOS-OTA
| Abstract
|
Multigroup Integral Transport Code System for Thermal Lattice Calculations using Collision Probability Method for Slabs and Cylinders. |
P00107 U1108 00 |
THERMOS-OTA
| Abstract
|
Multigroup Integral Transport Code System for Thermal Lattice Calculations using Collision Probability Method for Slabs and Cylinders. |
P00108 I0360 00 |
LEGENDRE FUNCTI
| Abstract
|
Legendre Functions of the First Kind and Legendre Polynomials. |
P00110 I0360 00 |
DOQDP
| Abstract
|
Discrete Ordinates Quadrature Generator. |
P00111 FM200 00 |
APPLE-2
| Abstract
|
Plotter of Neutron and Gamma-Ray Spectra and Reaction Rates. |
P00111 I3081 00 |
APPLE-2
| Abstract
|
Plotter of Neutron and Gamma-Ray Spectra and Reaction Rates. |
P00113 DP010 00 |
STAY'SL
| Abstract
|
Least Squares Dosimetry Unfolding Code System. |
P00114 I0360 00 |
MISSIONARY
| Abstract
|
ENDF/B to NDL Data Format Converter. |
P00115 F2307 00 |
SUPERTOG-JR.
| Abstract
|
A Code System for Generating Transport Group Constants, Energy Deposition Coefficients and Atomic Displacement Constants with ENDF/B. |
P00115 I0360 00 |
SUPERTOG-JR.
| Abstract
|
A Code System for Generating Transport Group Constants, Energy Deposition Coefficients and Atomic Displacement Constants with ENDF/B. |
P00116 F2307 00 |
GAMLEG-JR
| Abstract
|
Multigroup Cross-Section Generator for Photon Transport Calculations. |
P00116 I3033 00 |
GAMLEG-JR
| Abstract
|
Multigroup Cross-Section Generator for Photon Transport Calculations. |
P00117 I0360 00 |
MARS
| Abstract
|
Collection of Computer Codes for Manipulating Multigroup Cross Section Libraries in AMPX or CCCC Formats. |
P00119 I0360 00 |
ERIC-2
| Abstract
|
Calculator of Resonance Integral and Effective Capture and Fission Cross Sections for Fissile and Non-Fissile Nuclides - Thermal or Fast Reactors. |
P00120 I0360 00 |
NANICK
| Abstract
|
Infinitely-Diluted Multigroup Cross-Section Generator - from ENDF/B. |
P00121 I0360 00 |
NASIF-NARES
| Abstract
|
A Code System for Computing Shielding Factors from ENDF/B Tapes. |
P00122 I0360 00 |
RADAK
| Abstract
|
Flux Spectra Unfolding Code System - Neutron or Gamma-Ray Detectors. |
P00123 I0360 00 |
FEDGROUP-3
| Abstract
|
Program System for Processing Evaluated Nuclear Data in ENDF/B, KEDAK or UKNDL Format to Constants to be Used in Reactor Physics Calculation. |
P00124 C0076 00 |
GIFT
| Abstract
|
A Combinatorial Geometry Code System with Model Testing Routines. |
P00124 D0VAX 00 |
GIFT
| Abstract
|
A Combinatorial Geometry Code System with Model Testing Routines. |
P00124 U0000 00 |
GIFT
| Abstract
|
A Combinatorial Geometry Code System with Model Testing Routines. |
P00126 I0360 00 |
RFSP-JUL
| Abstract
|
Unfolding Code System for Neutron Spectra Evaluation from Activation Data. |
P00127 I0360 00 |
GOFRR
| Abstract
|
Generator of Graphical Output of DOT and ANISN Fluxes and Reaction Rates. |
P00128 I0360 00 |
GGTC-ENEL
| Abstract
|
Code System for Producing Few-Group Neutron Cross Sections from Multigroup Data Libraries. |
P00129 C7600 00 |
SPHINX
| Abstract
|
A One-Dimensional Diffusion and Transport Nuclear Cross Section Processing Code System. |
P00129 I0360 00 |
SPHINX
| Abstract
|
A One-Dimensional Diffusion and Transport Nuclear Cross Section Processing Code System. |
P00130 I0360 00 |
MATXUF
| Abstract
|
On-Line Derivative Method, Spectrum Unfolding Code System for NE-213 Liquid Fast Scintillation Proton Recoil Data. |
P00131 I3033 00 |
CARP-82
| Abstract
|
Multigroup Albedo Data Using DOT Angular Flux Results. |
P00132 I3691 00 |
MACK-IV
| Abstract
|
Calculation of Nuclear Response Functions from Nuclear Data in ENDF Format. |
P00133 I0360 00 |
PIXSE
| Abstract
|
A Generator of Multigroup and Multipoint Cross Sections for Thermal Reactor Calculations. |
P00134 I0360 00 |
S1CALC
| Abstract
|
A Multigroup Thermal Neutron Scattering Law Data Generator for Hydrogen and Deuterium. |
P00135 I0360 00 |
SNAKE
| Abstract
|
A Solid Angle Calculational System. |
P00136 I0360 00 |
WINDOWS
| Abstract
|
A Program for the Analysis of Spectral Data Foil Activation Measurements. |
P00137 MNYCP 08 |
MARLOWE 15B
| Abstract
|
Computer Simulation of Atomic Collisions in Crystalline Solids (Version 15). |
P00138 I0360 00 |
LEAP-ADDELT
| Abstract
|
Multigroup Thermal Neutron Scattering Data Generator for Hydrogen in Light Water and Deuterium in Heavy Water. |
P00139 I0360 00 |
SIOB
| Abstract
|
Calculation of Least-Squares Shape Fitting Several Neutron Transmission Measurements Using the Breit-Wigner Multilevel Formula. |
P00140 C0000 00 |
FANG
| Abstract
|
An Angular Folding Code System for Channel Theory Analysis. |
P00140 I0360 00 |
FANG
| Abstract
|
An Angular Folding Code System for Channel Theory Analysis. |
P00141 ICL00 00 |
ELAN
| Abstract
|
Neutron Cross-Section Self-Shielding Code System. |
P00142 H6000 00 |
MORSEC-SP2
| Abstract
|
A Multigroup Cross Section Module for the MORSE Monte Carlo Computer Code System. |
P00143 I3033 00 |
BREESE-II
| Abstract
|
Auxiliary Routines for Implementing the Albedo Option in the MORSE Monte Carlo Code System. |
P00144 F2307 00 |
ALPS
| Abstract
|
Alpha Spectrum Analysis Code System. |
P00145 U0000 00 |
FERRET
| Abstract
|
Least-Squares Solution to Nuclear Data and Reactor Physics Problems. |
P00147 I0360 00 |
CERPI-CEREL
| Abstract
|
Code Systems for Automatic Analysis of Gamma-Ray Spectra Obtained with Ge(Li) Detectors. |
P00148 C0000 00 |
ITER-2
| Abstract
|
Codes for Unfolding Activation Detector Data and Pulse Height Spectra. |
P00149 C0000 00 |
FIGERO
| Abstract
|
Processing Codes for Generating Multigroup Neutron Cross Sections from ENDF/B for Use in Discrete Ordinates Calculations. |
P00150 F2307 00 |
NE-SPEC
| Abstract
|
A Code System for Unfolding a Pulse Height Distribution of Neutrons Measured by an NE-213 Organic Scintillator. |
P00152 U0000 00 |
HAUSER*5
| Abstract
|
Code System for Calculating Nuclear Cross Sections. |
P00153 F2307 00 |
LOOM-P
| Abstract
|
A Finite Element Mesh Generation Code System with On-Line Graphic Display. |
P00154 C0000 00 |
GAMIDENT
| Abstract
|
A Program to Aid in the Identification of Unknown Materials by Gamma-ray Spectroscopy. |
P00156 I0370 00 |
PAPIN
| Abstract
|
A Code System to Calculate Cross Section Probability Tables, Bondarenko and Transmission Self-Shielding Factors for Fertile Isotopes in the Unresolved Resonance Region. |
P00158 MNYCP 12 |
SAMMY-8
| Abstract
|
Code System for Multilevel R-Matrix Fits to Neutron and Charged-Particle Cross-Section Data Using Bayes' Equations. |
P00160 I0370 00 |
ENBAL2
| Abstract
|
A Program to Generate Multigroup Neutron Kerma Factors. |
P00161 I0370 00 |
WINDOWS II
| Abstract
|
A Program for the Analysis of Spectral Data Foil-Activation Measurements. |
P00162 I3033 00 |
DOMINO-II
| Abstract
|
General Purpose Code System for Coupling DOT-IV Discrete Ordinates and Monte Carlo Radiation Transport Calculations. |
P00163 D0780 00 |
TIMS-1
| Abstract
|
Processing Code System for Production of Group Constants of Heavy Resonant Nuclei. |
P00163 FM200 00 |
TIMS-1
| Abstract
|
Processing Code System for Production of Group Constants of Heavy Resonant Nuclei. |
P00164 DP010 00 |
TPASS
| Abstract
|
A Gamma-Ray Spectral Data-Reduction and Analysis Code System. |
P00165 I0360 00 |
REGN
| Abstract
|
Code System for Solving Nonlinear Systems of Equations via the Gauss-Newton Method. |
P00166 C0175 00 |
PREANG
| Abstract
|
Calculation of Pre-equilibrium Angular Distributions with the Exciton Model. |
P00167 C7600 01 |
FAMREC
| Abstract
|
Fuel Assembly Mechanical Response Code System. |
P00168 I0360 00 |
PELINSCA
| Abstract
|
A Code System for Nuclear Elastic and Inelastic Scattering Calculations. |
P00169 I0360 00 |
ALPHA-M
| Abstract
|
Least-Squares Resolution of Gamma-Ray Spectra in Environmental Samples. |
P00170 I0360 00 |
FORSEN
| Abstract
|
A Multigroup Processing Code for Use with Sensitivity Profiles to Assess the Effect of Cross Section Changes. |
P00171 MFMWS 04 |
NJOY91.119
| Abstract
|
Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data. |
P00172 H6000 00 |
TDOWN-IV
| Abstract
|
A Code System to Generate Composition- and Spatially-Dependent Neutron Cross Sections for Multigroup Neutronics Analysis. |
P00173 I0360 00 |
BON
| Abstract
|
A Code System for Unfolding Multisphere Spectrometer Neutron Measurements. |
P00174 I0360 00 |
SORA
| Abstract
|
A Code System for Storage and Retrieval of Data from Radionuclide Analyses. |
P00175 U1108 00 |
GABAS
| Abstract
|
A Code System for Generating Composite Time-Dependent Fission Produce Spectra. |
P00177 FM200 00 |
NEUPAC
| Abstract
|
Neutron Unfolding Code System for Calculating Neutron Flux Spectra from Activation Data of Dosimeter Foils. |
P00178 I3033 00 |
FANAL
| Abstract
|
A Least-Squares Shape Analysis Code System. |
P00179 I3033 00 |
FANAC
| Abstract
|
A Shape Analysis Code Package for Resonance Parameter Extraction from Neutron Capture Data for Light- and Medium-Weight Nuclei. |
P00180 I3033 00 |
MINIGAL
| Abstract
|
Neutron Cross Section Processing System for Calculating Average Values from Data in the Standard United Kingdom Nuclear Data Library Format. |
P00181 I0360 00 |
DORGLIB
| Abstract
|
An Interactive Program for Displaying Nuclide Decay and Generation Data Based on ORIGEN Data Library. |
P00182 I3033 00 |
XLACS-IIA
| Abstract
|
A Modified Version of XLACS-II for Processing ENDF Data into Multigroup Neutron Cross Sections in AMPX Master Library Format. |
P00183 I0370 00 |
FOURACES
| Abstract
|
Code System for Producing Spectrum Weighted, Group Averaged Cross Sections from ENDF/B, KEDAK, or UK Libraries. |
P00184 I3081 00 |
CRESO
| Abstract
|
Resonance Data-Handling Code System. |
P00185 I0370 00 |
DANTE
| Abstract
|
Unfolding Code System for Energy Spectra Evaluation for Dosimetry Purposes. |
P00186 C6600 00 |
SAMPO-LRC
| Abstract
|
Gamma-Ray Spectrum Analysis Code. |
P00187 I3033 00 |
MUXS
| Abstract
|
Generator of Multigroup Cross Sections for Charged Particle Transport Problems. |
P00188 C0175 00 |
ENTOSAN
| Abstract
|
Code System for Calculating Fine-Group Dosimetry Cross Section Values from ENDF/B Data. |
P00188 D8810 00 |
ENTOSAN
| Abstract
|
Code System for Calculating Fine-Group Dosimetry Cross Section Values from ENDF/B Data. |
P00189 C0175 00 |
FITOCO
| Abstract
|
Converter of Fine-Group Flux Density and Cross Section Data to Coarse Group Values. |
P00190 C0000 00 |
ADENA
| Abstract
|
Code System for Application of Adjusted Data in Calculating Fission-Product Decay Energies and Spectra. |
P00190 I3033 00 |
ADENA
| Abstract
|
Code System for Application of Adjusted Data in Calculating Fission-Product Decay Energies and Spectra. |
P00191 I3033 00 |
EDISTR
| Abstract
|
Prepares a Nuclear Decay Data Base for Internal Radiation Dosimetry Calculations. |
P00192 D0VAX 00 |
GLUCS
| Abstract
|
A Generalized Least-Squares Code System for Updating Cross Section Evaluations with Correlated Data Sets. |
P00193 H6000 00 |
GECINX
| Abstract
|
A Code System for Collapsing Multigroup Cross Sections in CCCC Format. |
P00194 MNYCP 01 |
FEDGROUPC86REV3
| Abstract
|
Code System for Processing Evaluated Nuclear in ENDF/B, KEDAK or UKNDL Formats into Constants for Reactor Physics Calculation. |
P00195 C0000 00 |
REPC
| Abstract
|
Estimation of Nuclear Reaction Effects in Proton-Tissue-Dose Calculations. |
P00196 C7600 00 |
FLYSPEC-SHORTS
| Abstract
|
Neutron Unfolding Code System for Reducing Proton-Recoil Pulse-Height Obtained with NE-213 Liquid Scintillator. |
P00197 DGMV1 00 |
METD
| Abstract
|
Computer Code Systems for Use with Meteorological Data. |
P00197 I3033 00 |
METD
| Abstract
|
Computer Code Systems for Use with Meteorological Data. |
P00198 I3033 01 |
SPIRT-NRC
USSO
|
Abstract
|
Computerized Mathematical Models of Spray Washout of Airborne Contaminants (Radioactivity) in Containment Vessels. |
P00199 MNYCP 06 |
HEATING 7.3
| Abstract
|
Multidimensional, Finite-Difference Heat Conduction Analysis Code System, Versions 7.2i and 7.3. |
P00201 I3033 00 |
ESTIMA
| Abstract
|
A Code System for Calculating Average Parameters from Sets of Resolved Resonance Parameters. |
P00202 FM780 00 |
MCVIEW
| Abstract
|
View Factor Calculation for Three-Dimensional Geometries. |
P00203 E1040 00 |
SAIPS
| Abstract
|
Information Processing System for Calculating Neutron Spectra from Measured Reaction Rates. |
P00204 DGNOV 00 |
SAMPO80
| Abstract
|
Gamma-Ray Spectrum Analysis Method for Minicomputers. |
P00205 DP010 00 |
BAYES
| Abstract
|
User's Guide for A General-Purpose Computer Code System for Fitting a Functional Form to Experimental Data. |
P00206 CY000 00 |
TRANSX-CTR
| Abstract
|
Interfaces MATXS Cross-Section Libraries to Nuclear Transport Codes for Fusion Systems Analysis. |
P00207 C0000 00 |
INGEN
| Abstract
|
A General-Purpose Mesh Generator for Finite Element Codes. |
P00208 I3033 00 |
POLLA
| Abstract
|
A Fortran Program to Convert R-MATRIX-Type Multilevel Resonance Parameters for Fissile Nuclei into Equivalent KAPUR-PEIERLS-Type Parameters. |
P00209 I0370 00 |
GAMX1
| Abstract
|
A Computer Code System for Evaluating Spectra Peak Areas. |
P00210 I3033 00 |
SCOPE
| Abstract
|
Computer Code System for Shipping Cask Optimization and Parametric Evaluation. |
P00211 I3081 00 |
EVALPLOT
| Abstract
|
A Program to Plot Data in the Evaluated Nuclear Data File/Version B Format. |
P00212 DVX11 00 |
MRSPAK
| Abstract
|
A Code System To Generate a Text File Containing Combinatorial Geometry Data Corresponding to PADL2 Geometry. |
P00213 I0360 00 |
ANIPLO D50
| Abstract
|
A Digital Computer Program for Plotting Results from Calculations with the Sn Computer Program ANISN. |
P00214 I3033 00 |
PLOTENDF
| Abstract
|
A Program for Producing Graphical Output. |
P00215 C0740 00 |
RESENDD
| Abstract
|
A Code System for Reconstruction of Resonance Cross Sections from Evaluated Nuclear Data in ENDF/B Format. |
P00215 D0780 00 |
RESENDD
| Abstract
|
A Code System for Reconstruction of Resonance Cross Sections from Evaluated Nuclear Data in ENDF/B Format. |
P00216 I3033 00 |
SMOG
| Abstract
|
Code System for Neutron Cross Section Evaluation (Optical Method). |
P00217 I0360 00 |
ETHEL
| Abstract
|
Code System for Generating Cross Sections for PSR-128/THERMOS. |
P00218 I0360 00 |
ALARM-B2
| Abstract
|
A Computer Code System for Analysis of a Large Break LOCA of a BWR. |
P00219 I0360 00 |
ERINNI
| Abstract
|
Optical Model Calculation of Multiple Cascading Particle Emissions. |
P00220 D0780 00 |
X4ECS
| Abstract
|
A Code System to Combine Cross Section Data in EXFOR and/or ENDF/B-IV Format. |
P00221 D0780 00 |
F5TAB
| Abstract
|
Code System for Converting Energy Distribution Cross Section Data to Tabulated Data. |
P00222 DVX11 00 |
X4R
| Abstract
|
Code System for Retrieving EXFOR Cross Section Data According to a Given Target Nucleus. |
P00223 I3033 00 |
MESA
| Abstract
|
Non-Linear Least Squares Spectral Analysis. |
P00224 I0360 00 |
PREM
| Abstract
|
Code System for Pre-equilibrium Process with Multiple Nucleon Emission. |
P00225 I0360 00 |
MARCOPOLO
| Abstract
|
Code System for Calculating the Radial and Axial Neutron Diffusion Coefficients in One-Group and Multigroup Theory. |
P00226 MNYCP 02 |
PRECO2006
| Abstract
|
Exciton Model Code System for Calculating Preequilibrium and Direct Double Differential Cross Sections. |
P00227 MNYCP 01 |
ECIS-06
| Abstract
|
Code System to Solve the Coupled Differential Equations Arising in Nuclear Model Calculations. |
P00228 I0360 00 |
SUPERTOG-LTT
| Abstract
|
A Modification of PSR-13/SUPERTOG-III Applied to Libraries with Tabulated Elastic Scattering and Anistropy Densities. |
P00229 IBMPC 00 |
GIP
| Abstract
|
Group-Organized Cross-Section Input Program. |
P00231 MFMWS 02 |
GRESS 3.0
| Abstract
|
Gradient Enhanced Software System. |
P00232 I0360 00 |
MARTHA
| Abstract
|
Monte Carlo Response Function Calculation for Sodium Iodide Photon Detectors. |
P00233 D6220 00 |
LSL-M2
| Abstract
|
Least-Squares Logarithmic Adjustment of Neutron Spectra. |
P00233 IBMPC 00 |
LSL-M2
| Abstract
|
Least-Squares Logarithmic Adjustment of Neutron Spectra. |
P00234 I3033 00 |
FLOWPLOT II
| Abstract
|
Fluid Dynamics and Heat Transfer Plotting Package. |
P00236 U1108 00 |
LOUHI82
| Abstract
|
General Purpose Unfolding Program with Linear and Nonlinear Regularizations. |
P00237 IBMPC 00 |
EZVIDEO
| Abstract
|
Graphics Routines for the IBM PC. |
P00238 IBMPC 00 |
PICTURE
| Abstract
|
Combinatorial Geometry Printer Plotting. |
P00239 C0170 00 |
RGENDF
| Abstract
|
Format Translation from NJOY GENDF Format to ENDF/B-V and Other Formats. |
P00240 C0170 00 |
COMPAR
| Abstract
|
Compares Multigroup Cross Sections Generated by NJOY, GROUPIE, FLANGE-II, ETOG-3 and XLACS. |
P00241 I0370 00 |
GERES
| Abstract
|
A Code to Produce Cross-Section Libraries for ANISN Based on Heterogeneous Fast Reactor Cell Calculations Using MC2II Data. |
P00242 MFMWS 02 |
SABRINA 3.54
| Abstract
|
Three-Dimensional Geometry Visualization Code System. |
P00243 MFMWS 03 |
CGS 11.4
| Abstract
|
Common Graphics System, Version 11.4. |
P00244 FM380 00 |
SLAROM
| Abstract
|
A Code to Produce Cell Averaged Cross Sections for Fast Critical Assemblies and Fast Power Reactors. |
P00245 ALLCP 01 |
UPEML 3.0
| Abstract
|
A Machine-Portable CDC UPDATE Emulator. |
P00246 C0740 00 |
GROUPXS
| Abstract
|
Processing of Double-Differential Cross Sections in the New ENDF-VI Format. |
P00247 C0175 00 |
ABLEIT-TRANS
| Abstract
|
Error Propagation Analysis for Burnup Calculation. |
P00248 MNYCP 01 |
ABAREX
| Abstract
|
Neutron Spherical Optical-Statistical Model Code System. |
P00249 FM380 00 |
REFERDOU
| Abstract
|
Code System for NE-213 Unfolding of Neutron Spectra up to 100 MeV with Response Function Error Propagation. |
P00250 D0780 00 |
CRECTJ5
| Abstract
|
A Computer Program for Compilation of Evaluated Nuclear Data in ENDF/B Format. |
P00251 IPCXT 00 |
DSNQUAD
| Abstract
|
Calculates Angular Quadrature Weights and Cosines. |
P00252 I3081 00 |
STRADE
| Abstract
|
Stratified Random Design. |
P00257 FM380 00 |
ACAT
| Abstract
|
Monte Carlo Simulation of Atomic Collisions in Amorphous Targets in the Binary Collision Approximation. |
P00258 DGMV1 00 |
DATINIT
| Abstract
|
Interactive Program To Access Photon Interaction Data. |
P00259 IBMMF 00 |
COMPLOT
| Abstract
|
Convert EXFOR Format Data to Computation Format and Plot Comparisons of EXFOR and ENDF/B Evaluated Data (Version 86-1). |
P00261 I3033 00 |
MICAP
| Abstract
|
A Monte Carlo Code System for Analysis of Ionization Chamber Responses. |
P00262 IBMPC 00 |
CASKCODES
| Abstract
|
CAPSIZE, SCOPE, AND KWIKDOSE for Shipping Cask Optimization, Dose Calculation, Parameter Evaluation, and Shielding Requirements. |
P00263 D0VAX 00 |
SPECTER-ANL
| Abstract
|
Neutron Damage Calculations for Materials Irradiations. |
P00264 IBMPC 01 |
ACORNS
| Abstract
|
Analysis of Correlations Used in Neutron Spectrometry. |
P00265 I0370 00 |
MIGROS3
| Abstract
|
A Code for the Generation of Group Constants for Reactor Calculations from Neutron Nuclear Data in KEDAK Format. |
P00266 D8600 00 |
SPUNIT
| Abstract
|
Spectrum Unfolding Using Information Theory. |
P00267 CY0MP 00 |
SCINFUL
| Abstract
|
Scintillator Full Response to Neutron Detection. |
P00267 D8600 00 |
SCINFUL
| Abstract
|
Scintillator Full Response to Neutron Detection. |
P00270 DGMV1 00 |
UPDATE
| Abstract
|
Program to Update Fortran Source Files. |
P00270 I3081 00 |
UPDATE
| Abstract
|
Program to Update Fortran Source Files. |
P00272 ALLCP 02 |
ZOTT99
| Abstract
|
Zero-in On The Truth; Evaluation of Correlated Data Using Partitioned Least Squares. |
P00273 IBMPC 00 |
FERD-PC
| Abstract
|
Interactive Multichannel Neutron and Gamma-Ray Spectrum Matrix Unfolding Code System. |
P00274 ALLCP 00 |
PLOTTAB-89.1
| Abstract
|
Plot Continuous Curves or Discrete Points. |
P00275 IBMPC 00 |
ORMONTE
| Abstract
|
Uncertainty Analysis Code System for Use with User-Developed Systems Models. |
P00276 CYXMP 00 |
THRUSH
| Abstract
|
Calculates Thermal Neutron Scattering Kernel. |
P00277 IRISC 00 |
LEPRICON
| Abstract
|
PWR Pressure Vessel Surveillance Dosimetry Analysis System. |
P00277 I3033 01 |
LEPRICON
| Abstract
|
PWR Pressure Vessel Surveillance Dosimetry Analysis System. |
P00278 D8810 00 |
DASQHE
| Abstract
|
Calculates Dancoff Corrections Factors. |
P00279 D8810 00 |
DANCOFF3
| Abstract
|
Calculates Dancoff Correction. |
P00280 C0720 00 |
TRAX
| Abstract
|
A Program For Optics of Curved Crystal Neutron Spectrometers. |
P00281 D6220 00 |
URR
| Abstract
|
Calculates Resonance Neutron Cross-Section Probability Tables, Bondarenko Self-Shielding Factors and Self-Indication Ratios for Fissile and Fertile Nuclides. |
P00282 IBMPC 00 |
SUPERDAN-PC
| Abstract
|
Calculates Dancoff Factor of Spheres, Cylinders and Slabs. |
P00284 CYXMP 00 |
NUFACE
| Abstract
|
An Interface Code For The Calculation of Nuclear Responses. |
P00285 IBMPC 00 |
BASACF
| Abstract
|
Bayesian Approach to Spectrum Adjustment with Covariance Filter. |
P00286 IBMPC 00 |
COMBINE-PC
| Abstract
|
Code System to Compute Neutron Spectra and ENDF/B Version 5 Based Multigroup Neutron Constants. |
P00287 IBMPC 00 |
ACTIV-PC
| Abstract
|
A Program to Process Gamma or X-ray Spectra. |
P00288 C0170 00 |
UNIFY-ECN
| Abstract
|
A Program to Calculate Fast Neutron Data for Structural Materials. |
P00289 I3090 00 |
MUP2
| Abstract
|
A Program to Calculate Fast Neutron Data for Medium-Heavy Nuclei. |
P00290 D8810 00 |
REX2-87
| Abstract
|
A Code For Calculating Self-Shielded Multigroup Neutron Cross Sections and Self-Shielding Factors From Preprocessed ENDF/B Basic Data Files. |
P00291 IPCAT 00 |
ICAR
| Abstract
|
A Code For Combinatorial Calculation of Level Densities. |
P00292 IPCAT 00 |
EMPIRE
| Abstract
|
A Pre-equilibrium Compound Nuclear Model Code For Personal Computers. |
P00293 IPCAT 00 |
PEQAG-2
| Abstract
|
A Pre-equilibrium Computer Code With Gamma Emission. |
P00294 MNYCP 02 |
SCAT-2B
| Abstract
|
Code System for Calculating Total and Elastic Scattering Cross Sections Based on an Optical Model of the Spherical Nucleus, Versions SCAT-2 and SCAT-2B. |
P00295 IBMPC 00 |
SAIPS-PC
| Abstract
|
Information Processing System for Calculating Neutron Spectra from Measured Reaction Rates. |
P00296 C0825 00 |
NJOY-UTIL-EIR
| Abstract
|
Utilities For the NJOY (6/83) Nuclear Data Processing System. |
P00297 IBMPC 00 |
AXMIX-PC
| Abstract
|
ANISN Cross Section Mixing Code System. |
P00298 D6220 00 |
TNG1
| Abstract
|
A Multistep Statistical Model Based on the Hauser-Feshbach Theory For The Evaluation Of Neutron Data. |
P00300 IPCXT 00 |
UPEAK
| Abstract
|
A Program for Decomposing A One-Dimensional Spectrum. |
P00301 IPCXT 00 |
DOMUS
| Abstract
|
A Program for Decomposing A Two-Dimensional Spectrum. |
P00302 CYXMP 00 |
COMNUC3B
| Abstract
|
A Compound Nucleus Analysis Program. |
P00304 I3033 00 |
GIRAFFE
| Abstract
|
General Isotope Release Analysis For Failed Elements. |
P00305 IPCXT 00 |
EXIFON-GAMMA
| Abstract
|
A Model For Statistical Multistep Direct and Multistep Compound Reactions. |
P00306 CY000 00 |
KAOS-V
| Abstract
|
An Evaluation Tool For Neutron Kerma Factors and Other Nuclear Responses. |
P00307 IPCAT 00 |
LOGNORML
| Abstract
|
Lognormal Probability Analysis Code System for Estimating Doses in Epidemiologic Studies. |
P00308 IBMPC 00 |
TAM3
| Abstract
|
Demonstrates Monte Carlo Sensitivity and Uncertainty Analysis. |
P00309 D0VAX 00 |
SC2N3N
| Abstract
|
Systematics of (n,2n) and (n,3n) Cross Sections. |
P00310 D0VAX 00 |
NX1-NX2
| Abstract
|
Code System to Calculate Excitation Functions for (n,charged particle) Reactions. |
P00311 IBMPC 00 |
VIDEO-PC
| Abstract
|
Super VGA Primitives Graphics System. |
P00312 D0VAX 00 |
RFUNC
| Abstract
|
Code System to Analyze Differential Scattering Data. |
P00313 ALLCP 00 |
INFLTB
| Abstract
|
Gamma-Ray Absorption Coefficient Calculation. |
P00314 D0VAX 00 |
NSLINK
| Abstract
|
NJOY SCALE LINK. |
P00315 CY000 00 |
AMPX 77
| Abstract
|
Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B. |
P00315 ALLMF 01 |
AMPX-77
| Abstract
|
Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B. |
P00316 F0230 00 |
CASTHY
| Abstract
|
Statistical Model Calculation for Neutron Cross Sections and Capture Gamma-Ray Spectra. |
P00317 MFMWS 01 |
TRANSX 2.15
| Abstract
|
Code system to produce neutron, photon, and particle transport tables for discrete-ordinates and diffusion codes from cross sections in MATXS format. |
P00318 IRISC 00 |
MIXEN
| Abstract
|
Code System to Replace Files 4 and 6 of ENDF-6 with Files 4 and 5 of ENDF/B-IV. |
P00319 I3090 00 |
WIMSCORE-ENEA
| Abstract
|
Code System to Process WIMSD4 Interface Output Files and Generate Two-Group Data for Reactor Calculations. |
P00321 D0VAX 00 |
GRPANL
| Abstract
|
Code System for Analyzing Ge and Alpha-Particle Detector Spectra. |
P00322 IPCAT 00 |
FDMXPC
| Abstract
|
Code System for Calculation of Neutron Transmission and Other Functionals from Evaluated Data in ENDF Format. |
P00323 IMFPC 00 |
EQUIVA-1.1
| Abstract
|
Generation of Few-Group Equivalent Diffusion Theory Parameters for PWR Reflector Regions. |
P00324 IMFPC 00 |
EQUIVA-2
| Abstract
|
Generation of Environment-Insensitive Equivalent Diffusion Theory Parameters for PWR Reflector Regions. |
P00325 MNYCP 01 |
STAPRE-H95
| Abstract
|
Code System to Calculate Energy-Averaged Cross Sections of Particle Induced Nuclear Reactions. |
P00328 PC386 00 |
ORPLOT-PC
| Abstract
|
Plotting Package for Data Evaluation Intercomparison. |
P00329 IBMPC 00 |
LTC
| Abstract
|
LMR Transient Calculation Code System (version 5). |
P00330 IBMPC 00 |
STAR CODES
| Abstract
|
Code System for Calculating Stopping-Power and Range Tables for Electrons, Protons, and Helium Ions. |
P00332 PC386 00 |
PRE-ANISN
| Abstract
|
A Preprocessing Code for ANISN and Other Radiation Transport Codes. |
P00333 MNYCP 05 |
CHENDF 7.02
| Abstract
|
Codes for Handling ENDF/B-V and ENDF/B-VI Data. |
P00334 MNYCP 00 |
DIFBAS
| Abstract
|
A Bayesian Approach to Unfolding a Neutron Spectrum from a Spectrum of Recoiled Protons. |
P00336 IBMPC 00 |
PEGAS
| Abstract
|
Pre-Equilibrium-Equilibrium Gamma-and-Spin Code System. |
P00338 MNYCP 01 |
DWBA07/DWBB07
| Abstract
|
Code System for Inelastic and Elastic Scattering with Nucleon-Nucleon Potential |
