| Packages with Subject: NUCLEAR PARTICLE TRANSPORT IN MATERIALS |
| Package Name | Abstract | RSICC Tapelist | Title |
| 1DB-2DB-3DB | Abstract | C00741 PC586 00 | One-Dimensional Diffusion Code System for Nuclear Reactor. |
| ACAT | Abstract | P00257 FM380 00 | Monte Carlo Simulation of Atomic Collisions in Amorphous Targets in the Binary Collision Approximation. |
| ACOH | Abstract | C00191 I3675 00 | Aerojet COHORT Monte Carlo Code System. |
| ADJMOM | Abstract | C00212 I3675 00 | Adjoint Moments Method Gamma-Ray Transport Code System. |
| ADO | Abstract | C00189 I3675 00 | Aerojet Discrete Ordinates Calculational System. |
| AIR DATA | Abstract | D00014 I0360 00 | Sample Input to ANISN for Calculation of Neutron and Secondary Gamma-Ray Transport in Air. |
| AIRDIF | Abstract | C00360 C6600 00 | A Two-Dimensional Atmospheric Radiation Diffusion Code. |
| AIRSCAT | Abstract | C00341 DP010 00 | Calculation of Dose Rate for Gamma-Rays Scattered in Air. |
| AIRTRANS | Abstract | C00110 I3675 00 | Monte Carlo Time and Energy-Dependent Three-Dimensional Radiation Transport Code. |
| ALGAM-97 | Abstract | C00152 I3675 00 | Monte Carlo Estimation of Internal Dose from Gamma-Ray Sources in a Phantom Man. |
| ANISN-ORNL | Abstract | C00254 MNYCP 02 | One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering. |
| ANTE 2 | Abstract | C00131 I3675 00 | Adjoint Monte Carlo Time-Dependent Neutron Transport Code in Combinatorial Geometry. |
| APARNA-II | Abstract | C00296 I0360 00 | Integral Transport Theory Code System Based on Discrete Ordinate Representation in Space and Direction-Slab Geometry. |
| ARMYL-G | Abstract | C00297 U1106 00 | Calculation of Transmission Factors for Gamma Rays from Nuclear Explosions. |
| ARMYL-N | Abstract | C00298 U1106 00 | Calculation of Transmission Factors for Neutrons from Nuclear Explosions. |
| ASFIT-VARI | Abstract | C00336 H0000 00 | Gamma-Ray Transport Code System for One-Dimensional Finite Systems. |
| ASFIT-VARI | Abstract | C00336 IBMPC 00 | Gamma-Ray Transport Code System for One-Dimensional Finite Systems. |
| ATTOW-KB | Abstract | C00132 I0370 00 | Multigroup Two-Dimensional Removal-Diffusion (Spinney Method) Shielding Code System. |
| AUS98 | Abstract | C00519 MNYWS 01 | Modular System for Neutronics Calculations of Fission Reactors, Fusion Blankets, and Other Systems. |
| BALTORO | Abstract | C00479 C6600 00 | Code for Coupling of Monte Carlo and Discrete Ordinates Radiation Transport Calculations. |
| BCG | Abstract | C00578 C0170 00 | A Code For Calculating Pointwise Neutron Spectra and Criticality in Fast Reactor Cells. |
| BERMUDA | Abstract | C00616 FV260 03 | Discrete Ordinates Code System for Shielding Analysis for Use with Fusion and Fission Reactors. |
| BETA II | Abstract | C00117 C6600 00 | Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry. |
| BETA II | Abstract | C00117 I0360 00 | Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry. |
| BETA-S 6 | Abstract | C00657 MNYCP 01 | Code System to Calculate Multigroup Beta-Ray Spectra. |
| BMC-MG | Abstract | C00291 C6600 00 | Multigroup Monte Carlo Neutron and Gamma-Ray Shielding Code System for Plutonium. |
| BOXER | Abstract | C00766 MNYWS 00 | Fine-flux Cross Section Condensation, 2D Few Group Diffusion and Transport Burnup Calculations |
| BREMRAD | Abstract | C00031 I7090 00 | External and Internal Bremsstrahlung Calculation Code. |
| BRHGAM | Abstract | C00350 I3033 00 | Monte Carlo Estimation of Absorbed Dose from X-Ray Sources in Phantom Man. |
| BULK_C-12 | Abstract | C00738 PC586 00 | Code System to Estimate Neutron and Photon Effective Dose Rates from Medium Energy Protons or Carbon Ions Through Concrete or Concrete/Iron. |
| CAFDATS | Abstract | P00549 MNYCP 00 | Converter of Angular Fluxes of DORT, ANISN and TORT Systems. |
| CAMERA | Abstract | C00240 C0074 00 | Radiation Transport Analysis Code System and the Computerized Man (CAM) Model. |
| CAMERA | Abstract | C00240 IBMPC 01 | Radiation Transport Analysis Code System and the Computerized Man (CAM) Model. |
| CARL 2.3 | Abstract | C00743 PC586 01 | Code System to Calculate Radiotoxicity, Activity, Dose and Decay Power Calculations for Spent Fuel. |
| CARNAC | Abstract | C00238 I3691 00 | Calculation of Flux and Neutron Spectra in the Case of Criticality Accident. |
| CASCADE | Abstract | C00176 C6600 00 | Monte Carlo Simulation of the Transport of High Energy Electrons and Photons in Matter. |
| CASCADE | Abstract | C00176 I0360 00 | Monte Carlo Simulation of the Transport of High Energy Electrons and Photons in Matter. |
| CASIM | Abstract | C00265 I0360 00 | Monte Carlo Simulation of Transport of Hadron Cascades in Bulk Matter. |
| CAVEAT | Abstract | C00169 I3675 00 | General Purpose Monte Carlo Time-Dependent Radiation Transport Code in Complex Geometry. |
| CCRMN | Abstract | P00366 MNYCP 00 | Monte Carlo Simulation of the Coupled Transport of Electrons and Photons. |
| CEPXS/ONELD 1.0 | Abstract | C00544 MNYCP 02 | One-Dimensional Coupled Electron-Photon Multigroup Discrete Ordinates Code System. |
| CHAINT-MC | Abstract | C00584 CYXMP 00 | A Two-Dimensional Model for the Analysis of Contaminant Transport in a Fractured Porous Medium. |
| CNCSN 2009 | Abstract | C00726 PCX86 01 | One, Two- and Three-Dimensional Coupled Neutral and Charged Particle SN Parallel Multi-Threaded Code System. |
| COHORT-II | Abstract | C00198 I7094 00 | General Purpose Monte Carlo Radiation Transport Code System. |
| COLLIMATOR | Abstract | C00136 I7090 00 | Monte Carlo Calculation of the Spectrum of Gamma Radiation from a Collimated Co-60 Source. |
| CONSTRIP V | Abstract | C00139 I3675 00 | Vertical Barrier-Finite Source Plane Gamma-Ray Penetration Code System. |
| CYGAS | Abstract | C00317 I3033 00 | A Gamma-Ray Attenuation Code System for Large Gamma-Ray Sources Shielded by Coaxial Cylinders. |
| CYGNUS-C SPHERE | Abstract | C00232 I0360 00 | Monte Carlo Neutron Transport Code System in Spherical Geometry. |
| CYLDOS | Abstract | C00389 I0360 00 | A Cylindrical Geometry Gamma-Ray Flux Attenuation Code System. |
| DASH-FP | Abstract | C00366 C0000 00 | A One-Dimensional Analytic-Numerical Solution to the Problem of Multicomponent Time-Dependent Diffusion of Fission Products. |
| DAVE | Abstract | C00166 I3675 00 | Monte Carlo Gamma-Ray Transport Code System in One-Dimensional Spherical Geometry. |
| DCTDOS | Abstract | C00520 IBMPC 00 | Neutron and Gamma-Ray Penetration in Composite Duct Systems. |
| DDXCODES | Abstract | C00583 FM380 00 | One-, Two- and Three-Dimensional Transport Codes Using Multigroup Double-Differential Form Cross Sections. |
| DEMON & DEMON R | Abstract | C00181 I3675 00 | Demonstration Monte Carlo Code System in Slab Geometry. |
| DIAMANT2 | Abstract | C00414 PC386 00 | Multigroup Two-Dimensional Discrete Ordinates Transport Code System for Triangular Geometry, Release 2.0. |
| DIPHO | Abstract | C00140 I3675 00 | Monte Carlo Gamma-Ray Code System-Infinite Medium, Mono-energetic and Isotropic Point Source. |
| DOMINO | Abstract | P00064 I0360 00 | A General Purpose Code System for Coupling Discrete Ordinates and Monte Carlo Radiation Transport Calculations. |
| DOORS 3.2A | Abstract | C00650 MFMWS 04 | One, Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System. |
| DRAGON2PARTISN | Abstract | C00803 PCX86 00 | Cross-Sections Data Generation for PARTISN4.0. |
| DRAGON3.05D | Abstract | C00647 MNYWS 03 | Lattice Cell Code System. |
| DTF-INDIA | Abstract | C00458 I0370 00 | Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering. |
| DTF-IV | Abstract | C00042 C6600 00 | Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering. |
| DTF-IV MODIFIED | Abstract | C00042 I0370 00 | Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering. |
| DTK | Abstract | C00223 I3675 00 | One-Dimensional Multigroup Neutron Transport Code System. |
| DUST | Abstract | C00453 I3033 00 | Albedo Monte Carlo Simulation of Neutron Streaming Through Multilegged Ducts. |
| EASY-QAD 2.0.1 | Abstract | C00744 PC586 02 | A Visualization Code System for Gamma and Neutron Shielding Calculations. |
| EDNA | Abstract | C00104 I7090 00 | Electron Dose and Number Analysis Code by Kernel Integration. |
| EGS4 | Abstract | C00331 MNYCP 00 | Monte Carlo Simulation of the Coupled Transport of Electrons and Photons. |
| ELAST2 | Abstract | D00208 MNYCP 00 | Database of Cross Sections for the Elastic Scattering of Electrons and Positrons by Atoms. |
| 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. |
| 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. |
| 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. |
ERANOS 2.0
OECD | Abstract | C00745 MNYWS 00 | Modular Code and Data System for Fast Reactor Neutronics Analyses |
| 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. |
| ESP | Abstract | C00193 I0360 00 | General Purpose Monte Carlo Neutron Transport Code System. |
| ETRAN | Abstract | C00107 I0360 00 | Monte Carlo Code System for Electron and Photon Through Extended Media. |
| EXTREME | Abstract | C00440 I3033 00 | Two-Dimensional Discrete-Ordinates Code System with Exponential Expansion of Spatial Variables. |
| 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. |
| FASTER III | Abstract | C00168 U1108 00 | Monte Carlo Neutron and Photon Transport Code System in Complex Geometries. |
| FASTER-III | Abstract | C00168 I3675 00 | Monte Carlo Neutron and Photon Transport Code System in Complex Geometries. |
| FEM-2D | Abstract | C00260 C6600 00 | Two-Dimensional Diffusion Theory Code System Based on the Method of Finite Elements. |
| FEMB | Abstract | C00340 B6700 00 | A Two-Dimensional Diffusion Theory Finite Element Program. |
| FEMRZ | Abstract | C00342 F2307 00 | A Finite-Element Method Two-Dimensional Multigroup Neutron Transport Code System, (r,z) Geometry. |
| FESH | Abstract | C00676 CDCMF 00 | X-Y Multigroup Neutron Transport Code System. |
| FINELM | Abstract | C00483 MFMWS 00 | Multigroup Finite Element Diffusion Code System. |
| FIPDIG | Abstract | C00251 I0360 00 | One-Dimensional Time-Dependent Fission Product Diffusion Code System. |
| FLUKA-TRANKA | Abstract | C00207 C6600 00 | Three-Dimensional High-Energy Extranuclear Hadron Cascade Monte Carlo System for Cylindrical Backstop Geometries. |
| FOCUS | Abstract | C00390 I3033 00 | Adjoint Monte Carlo Neutron Transport Code System. |
| FOTELP-2014 | Abstract | C00581 MNYCP 04 | Monte Carlo Simulation of Photons, Electrons and Positrons Transport. |
| FPZD | Abstract | C00603 PC386 00 | Code System for Multigroup Neutron Diffusion/Depletion Calculations. |
| FURNACE | Abstract | C00615 C0740 00 | Code System for Neutronic Calculations in Three Dimension Toroidal Geometry. |
| GADJET | Abstract | C00115 C6600 00 | Monte Carlo Gamma-Ray Adjoint Energy Transport Code in Complex Three-Dimensional Geometry. |
| GAMMOM-I | Abstract | C00226 I0360 00 | Gamma-Ray Moments Method Code System. |
| GASS | Abstract | C00080 I7090 00 | Monte Carlo Calculation of Self Shielding by Encapsulated Gamma-Ray Sources. |
| GBANISN | Abstract | C00628 IRISC 00 | One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering with the GroupBand Option. |
| GENP-2 | Abstract | C00575 ALLMF 00 | Generalized Perturbation Theory Code System. |
| GES_MC | Abstract | C00742 PC586 00 | Gamma-electron Efficiency Simulator. |
| GGG-GP | Abstract | C00564 IBMPC 00 | Kernel Integration Code System - Multigroup Gamma-Ray Scattering Using the GP Buildup Factor. |
| GRASS-SST | Abstract | P00489 MNYCP 00 | Code System to Predict Fission-Gas Release & Fuel Swelling. |
| GREAT-GRASS | Abstract | C00143 I3675 00 | Monte Carlo Radiation Transport Code Systems for Fallout Shielding. |
| HALLMARK | Abstract | D00005 I0360 00 | Discrete Ordinates and Monte Carlo Results of Neutron and Secondary Gamma-Ray Transport in Air-Over-Ground Geometry. |
| HAM | Abstract | C00267 U1108 00 | Monte Carlo Multigroup Neutron and Photon High Altitude Transport Code System. |
| HERMES-KFA | Abstract | C00687 MNYWS 00 | Monte Carlo Code System for High-Energy Radiation Transport Calculations. |
| HIMAC | Abstract | M00001 MNYCP 02 | Experimental Data of Neutron Yields from Thick Targets Bombarded by 100 to 800 MeV / Nucleon Heavy Ions. |
| ICOM | Abstract | C00651 PC386 00 | Code System for Calculating Ion Track Condensed Collision Model. |
| IONMIG | Abstract | C00526 ALLMF 00 | Code System for Radionuclide Migration Calculations. |
ITS6
FEDC | Abstract | C00792 PCX86 00 | Integrated TIGER Series of Coupled Electron/Photon Monte Carlo Transport Codes System. |
| JDL-IMPORTANCE | Abstract | M00005 MNYCP 00 | Adjoint Function: Physical Basis of Variational & Perturbation Theory in Transport & Diffusion Problems. |
| JN-METD 2&1 | Abstract | C00208 I0370 00 | Neutron Transport Code System with Isotropic Scattering, Bare Slabs and Homogeneous Slabs (JN Method 1), Multilayer Slabs (JN Method 2). |
| K009 | Abstract | C00062 I7090 00 | Solid Angle Integration Charged Particle Penetration Code. |
| KAMCCO | Abstract | C00325 I0370 00 | Three-Dimensional Time Dependent Monte Carlo Code System for Fast Neutron Physics Problems. |
| KAP-VI | Abstract | C00094 U1108 00 | Kernel Integration Code System in Complex Geometry. |
| KERNEL | Abstract | C00672 IBMPC 00 | Monte Carlo Code System for Electron (Positron) Dose Kernel Calculations. |
| KIM | Abstract | C00376 I3033 00 | A Two-Dimensional Monte Carlo Code System for Linear Neutron Transport Calculations. |
| LABAN-PEL | Abstract | C00611 IMFPC 00 | A Two-Dimensional, Multigroup Diffusion, High-Order Response Matrix Code. |
| LAHET 2.8 | Abstract | C00696 MFMWS 00 | Code System for High Energy Particle Transport Calculations. |
| LASER | Abstract | C00344 I0360 00 | A One-Dimensional, Neutron-Thermalization, Lattice-Cell Program Based on MUFT and THERMOS. |
| LEBC | Abstract | C00052 I7090 00 | Electron Bremsstrahlung Code. |
| LEP | Abstract | D00001 I0360 02 | Cascade and Evaporation Particle Results from Low-Energy Intranuclear Cascade Calculations. |
| LG-H | Abstract | C00087 I7090 00 | Ray Analysis Cylindrical Duct Kernel Code for Neutrons and Gamma Rays. |
| LPPC | Abstract | C00051 I7090 00 | Proton Penetration Code. |
| LPSC | Abstract | C00064 I7090 00 | Proton Penetration Code - Multilayer Slab Geometry. |
| LRSPC | Abstract | C00050 I7090 00 | Range and Stopping Power Calculator. |
| LSHINSE | Abstract | C00554 IBMPC 00 | Calculates Flux and Dose Rate from the Scattering of Radiation in Air. |
| LUIN-II | Abstract | C00220 C6600 00 | Analytical Straight-Ahead Transport Code System-Calculation of Cosmic-Ray Spectra, Fluxes and Ionization in the Earth's Atmosphere. |
| MAGNA | Abstract | C00158 C3600 00 | Multi-Source Gamma-Ray Kernel Integration Code System. |
| MAP | Abstract | C00150 I3675 00 | Kernel Integration Code System in Complex Geometry with Special Application to Surface Sources Determined by Discrete Ordinates Calculations. |
MCNP-DSP-EXE
810 | Abstract | C00699 MNYCP 01 | Monte Carlo N-Particle Transport Code System with Digital Signal Processing based on MCNP4A. |
| MCRTOF | Abstract | C00435 FM200 00 | Monte Carlo Code System for Calculation of Multiple Scattering of Neutrons in the Resonance Region. |
| MCRTOF | Abstract | C00435 I0360 00 | Monte Carlo Code System for Calculation of Multiple Scattering of Neutrons in the Resonance Region. |
| MECC-7 | Abstract | C00156 I0360 00 | Medium-Energy Intranuclear Cascade Code System. |
| MERCURE 4-82 | Abstract | C00142 I3033 00 | Three-Dimensional Code System for Integrating Multigroup Line-of-Sight Attenuation Kernels by Monte Carlo Techniques. |
| MEVDP | Abstract | C00157 C6600 00 | Primary Radiation Transport Code System - Complex Geometry - Computerized Anatomical Model Man. |
| MMCR | Abstract | C00441 FM200 00 | Multigroup Monte Carlo Neutron and Photon Transport Code. |
| MOMENT I | Abstract | C00188 U1108 00 | Moments Method Neutron Transport Code System. |
| MOMGEM-MOMDIS | Abstract | C00085 I7090 00 | Moments Method Reconstruction of Scattered Gamma-Ray Distributions. |
MONK 6.3
FEDC | Abstract | C00393 I3033 00 | A General Purpose Monte Carlo Neutronics Code System. |
| MURLI | Abstract | C00378 DP011 00 | Integral Transport Theory Code System for Thermal Reactor Lattice Cell Calculation. |
| MVP-GMVP II | Abstract | C00739 MNYCP 00 | General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations based on Continuous Energy and Multigroup Methods. |
| NESTLE 5.2.1 | Abstract | C00641 MNYCP 04 | Code System to Solve the Few-Group Neutron Diffusion Equation Utilizing the Nodal Expansion Method (NEM) for Eigenvalue, Adjoint, and Fixed-Source |
| NEVEMOR | Abstract | P00026 I3675 00 | Multigroup-Multiregion Calculation of Flux Spectra and Energy Deposition for Fast Neutrons. |
| NITRAN | Abstract | C00582 FM380 00 | Neutron Transport Code System Based On Anisotropic Scattering. |
| NMTC/JAERI97 | Abstract | C00694 SUN05 00 | Monte Carlo Nucleon Meson Transport Code System. |
| NMTC/JAM | Abstract | C00717 PC586 00 | High Energy Particle Transport Code System. |
| NRN | Abstract | C00054 C6600 00 | Multigroup Removal-Diffusion Code System for Planes, Cylinders and Spheres. |
| NUGAM 2&3 SSLAB | Abstract | C00210 I0360 00 | Monte Carlo Prediction of Photon Transport Distributions. |
| O6R | Abstract | C00128 I3675 00 | A General-Purpose Monte Carlo Transport Code System. |
| OGRE | Abstract | C00046 I3675 00 | A General-Purpose Monte Carlo Gamma-Ray Transport Code System. |
| OGRE-MIN | Abstract | C00409 DGECL 00 | A General-Purpose Monte Carlo Gamma-Ray Transport Code System for Minicomputers. |
| OOSII | Abstract | C00324 C0000 00 | Calculation of Isotropic Scattering by Particles for One-Dimensional and Three-Dimensional Transport in Slabs by Invariant Imbedding, Orders-of-Scattering Method, Including Check Calculations by Integral Transport Theory and Monte Carlo. |
| ORPHEE VI | Abstract | C00159 I3675 00 | Kernel Integration Code System - Attenuation of Fast Neutrons in Cylindrical Layers of Water and Dense Material. |
| PALLAS-1D(VII) | Abstract | C00380 FM380 00 | Multigroup Time-Independent Neutron Transport Code System for Plane or Spherical Geometry. |
| PELSHIE | Abstract | C00202 C0000 00 | General Purpose Kernel Integration Shielding Code System-Point and Extended Gamma-Ray Sources. |
| PELSHIE3 | Abstract | C00202 IBMMF 00 | General Purpose Kernel Integration Shielding Code System-Point and Extended Gamma-Ray Sources. |
| PEPIN | Abstract | C00285 I0360 00 | Methodology for Computing Concentrations, Activities, Gamma-Ray Spectra, and Residual Heat from Fission Products. |
| PHOEL-2 | Abstract | C00327 I0360 00 | A Monte Carlo Calculation of Initial Energy of Photoelectrons and Compton Electrons Produced by Photons in Water. |
| PIPE | Abstract | C00219 I0360 00 | Numerical Gamma-Ray Transport Code System for Plane/Spherical Geometry. |
| PLACID | Abstract | C00381 I0370 00 | Monte Carlo Simulation of Gamma Streaming Through Straight Cylindrical Ducts. |
| POWER | Abstract | P00069 C7600 00 | Source Distribution Input Data Generator for ANISN Code. |
| PTRAN | Abstract | C00618 PC386 00 | Proton Monte Carlo Transport Program for the PC. |
| PUSHLD | Abstract | C00271 C0074 00 | Gamma-Ray Three-Dimensional Calculation of Dose Rates from Plutonium in Various Geometries. |
| QAD | Abstract | C00048 I0360 00 | Kernel Integration Code System. |
| QAD-CGGP-A | Abstract | C00645 MNYCP 00 | Kernel Integration Code System. |
| QAD-P5 | Abstract | C00048 C6400 00 | Kernel Integration Code System. |
| RAFFLE/2 | Abstract | C00279 C0176 00 | A General Purpose Monte Carlo Code System for Neutron Transport with Mixed Zone Geometry Option. |
| RAFFLE/2 MOD 2 | Abstract | C00279 I0360 00 | A General Purpose Monte Carlo Code System for Neutron Transport with Mixed Zone Geometry Option. |
| REBUS3/VARIANT8 | Abstract | C00653 MNYWS 01 | Code System for Analysis of Fast Reactor Fuel Cycles. |
| REBUS-PC 1.4 | Abstract | C00708 PC586 00 | Code System for Analysis of Research Reactor Fuel Cycles. |
| REDIFFUSION | Abstract | C00347 I0360 00 | One-Dimensional Neutron Removal-Diffusion and Gamma-Ray Kernel Integration or Diffusion Theory Calculator. |
| S3 | Abstract | C00322 C6600 00 | Kernel Integration Code System--Multigroup Gamma-Ray Scattering. |
| S3 | Abstract | C00322 DVX11 00 | Kernel Integration Code System--Multigroup Gamma-Ray Scattering. |
| S3 | Abstract | C00322 IBMPC 00 | Kernel Integration Code System--Multigroup Gamma-Ray Scattering. |
| SAM-CEP | Abstract | C00192 C6600 00 | Monte Carlo Code System Correlated to the Simultaneous Solution of Multiple, Perturbed, Time-Dependent Neutron Transport Problems in Complex Three-Dimensional Geometry. |
| SAMSY | Abstract | C00315 C0073 00 | A One-Dimensional Multilayer Multigroup Neutron Removal-Diffusion and Gamma-Ray Point Kernel Calculator. |
| SANDYL | Abstract | C00361 C0000 00 | A Monte Carlo Three-Dimensional Code System for Calculating Combined Photon-Electron Transport in Complex Systems. |
| SCAP-82 | Abstract | C00418 C7600 00 | Single Scatter, Albedo Scatter, or Point Kernel Analysis Code System in Complex Geometry. |
| SHADOK | Abstract | C00216 C6600 00 | Transport Code Systems, P1 Scattering in Infinite Cylindrical and Spherical Geometries by Polynomial Approximation. |
| SHIELD | Abstract | C00667 MNYCP 01 | Monte-Carlo Code System to Simulate Interaction of High Energy Hadrons with Complex Macroscopic Targets. |
| SHREDI | Abstract | C00284 I0360 00 | Multigroup Two-Dimensional (x-y, r-o geometry) Neutron Removal-Diffusion (Spinney Method) Shielding Code System. |
| SKYIII-PC | Abstract | C00289 IBMPC 01 | Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air. |
| SKYSHINE-III | Abstract | C00289 D0VAX 00 | Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air. |
| SKYSHINE-KSU | Abstract | C00646 IBMPC 03 | Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air. |
| SNAP-3D | Abstract | C00434 MNYCP 01 | Multigroup Complex Geometry Neutron Diffusion Code System. |
| SNEX | Abstract | C00353 C0000 00 | A One-Dimensional Single Group Discrete Ordinates Transport Code System. |
| SNOW | Abstract | C00282 I0360 00 | Two-Dimensional Discrete Ordinates Multigroup Transport Code System in Plane and Cylindrical Geometry with Isotropic and Anisotropic Scattering. |
| SOURCES-4C | Abstract | C00661 MNYCP 04 | Code System for Calculating (alpha,n), Spontaneous Fission, and Delayed Neutron Sources and Spectra. |
| SPAR | Abstract | C00228 C6600 00 | Calculation of Stopping Powers and Ranges for Muons, Charged Pions, Protons and Heavy Ions. |
| SPAR | Abstract | C00228 I0360 00 | Calculation of Stopping Powers and Ranges for Muons, Charged Pions, Protons and Heavy Ions. |
| STERNO | Abstract | C00057 C0000 00 | Two Dimensional Gamma-Ray Heating Kernel Integration Code. |
| STRAGL | Abstract | C00201 C6600 00 | Calculation of Energy Loss Straggling of Heavy Charged Particles. |
| STRAINT | Abstract | C00259 I0360 00 | One-Dimensional Multigroup Neutron Transport Discrete Ordinates Code System. |
| STREAM | Abstract | C00321 C7600 00 | A Three-Dimensional Cylindrical-Geometry Monte Carlo Ray Tracing Code for Computing Light Transmission. |
| SURF | Abstract | C00102 I3675 00 | Conical and Plane Surface Single Scattering Code. |
| SUSD3D | Abstract | C00695 MNYCP 01 | Multi-Dimensional, Discrete-Ordinates Based Cross Section Sensitivity and Uncertainty Analysis Code System. |
| SWORD 7.0 | Abstract | C00767 MNYCP 07 | SoftWare for Optimization of Radiation Detectors. |
| TART2022 | Abstract | C00638 MNYCP 09 | Coupled Neutron-Photon, 3-D, Combinatorial Geometry, Time Dependent, Monte Carlo Transport Code System. |
| TASK | Abstract | C00184 I0360 00 | Generalized One-Dimensional Radiation Transport and Diffusion Kinetics Code System. |
| TDA | Abstract | C00180 MNYWS 01 | A Time-Dependent, Multigroup, One-Dimensional, Discrete Ordinates Transport Code System. |
| TDT | Abstract | C00256 I0360 00 | Generalized One-Dimensional Multigroup Time-Dependent Transport and Diffusion Kinetic Code System. |
| TDTORT | Abstract | C00709 MNYWS 00 | Time-Dependent, 3-D, Discrete Ordinates, Neutron Transport Code System. |
| TESS | Abstract | C00215 C3600 00 | Multigroup Discrete Ordinates Code System for Slab and Spherical Geometries. |
| TIMEX | Abstract | C00274 C7600 00 | One Dimensional, Time Dependent Multigroup Explicit Discrete Ordinates Radiation Transport Code System with Anisotropic Scattering. |
| TIMEX | Abstract | C00274 CY000 00 | One Dimensional, Time Dependent Multigroup Explicit Discrete Ordinates Radiation Transport Code System with Anisotropic Scattering. |
| TIMEX | Abstract | C00274 U1106 00 | One Dimensional, Time Dependent Multigroup Explicit Discrete Ordinates Radiation Transport Code System with Anisotropic Scattering. |
| TIMOC-72 | Abstract | C00144 I0370 00 | Monte Carlo Three-Dimensional Neutron Transport Code System. |
| TIMOC-ESP | Abstract | C00432 U1110 00 | System for Generating and Analyzing Time Dependent Radiation Transport Results by Monte Carlo. |
| TITAN 1.29 | Abstract | C00759 PCX86 04 | A Three-Dimensional Deterministic Radiation Transport Code System. |
| TMMS | Abstract | C00246 I0360 00 | Gamma-Ray Penetration Shielding Code System, Transmission Matrix Method. |
| TP1 | Abstract | C00465 I3033 00 | A Computer Code System for the Calculation of Reactivity and Kinetic Parameters by One-Dimensional Neutron Transport Perturbation Theory. |
| TPHEX | Abstract | C00421 C0173 00 | Transmission Probability Code System for Calculating Neutron Flux Distributions in Hexagonal Geometry. |
| TPHEX | Abstract | C00421 CYXMP 00 | Transmission Probability Code System for Calculating Neutron Flux Distributions in Hexagonal Geometry. |
| TPTRIA | Abstract | C00550 I3083 00 | A Computer Program for the Reactivity and Kinetic Parameters for Two-Dimensional Triangular Geometry by Transport Perturbation Theory. |
| TRANSHEX | Abstract | C00449 U1108 00 | Two-dimensional Multigroup Collision Probability Code System for Hexagonal Geometry. |
| TRANZIT | Abstract | C00172 C7600 00 | Multigroup Time-Dependent Discrete Ordinates Radiation Transport Code System in (rho,z) Cylindrical Geometry. |
| TRAPP | Abstract | C00205 I3691 00 | Transport of Alpha Particles and Protons with all Nuclear Reaction Products Neglected. |
| TRD-3 | Abstract | C00362 I3033 00 | Two-Dimensional Removal-Diffusion Neutron Shielding Code System. |
| TREEDE | Abstract | C00326 C0000 00 | Monte Carlo Neutron Transport Code System Based on the Track Rotation Estimator. |
| TRIDENT | Abstract | C00293 C7600 00 | Two-Dimensional Multigroup Discrete Ordinates Transport Code System-(x,y) and (r,z) Geometries. |
| TRIDENT | Abstract | C00293 I0360 00 | Two-Dimensional Multigroup Discrete Ordinates Transport Code System-(x,y) and (r,z) Geometries. |
| TRIDENT-CTR | Abstract | C00377 C0000 00 | Two-Dimensional x-y and r-z Geometry Multigroup Transport Code System for Large Toroidal Reactors. |
| TRIGON | Abstract | C00290 U1108 00 | Two-Dimensional Multigroup Diffusion Code System-Trigonal or Hexagonal Mesh. |
| TRIPLET | Abstract | C00230 C6600 00 | Two-Dimensional, Multigroup, Triangular Mesh, Planar Geometry, Explicit Discrete Ordinates Code System. |
| TRIPLET | Abstract | C00230 C7600 00 | Two-Dimensional, Multigroup, Triangular Mesh, Planar Geometry, Explicit Discrete Ordinates Code System. |
| TRIPLET | Abstract | C00230 I0360 00 | Two-Dimensional, Multigroup, Triangular Mesh, Planar Geometry, Explicit Discrete Ordinates Code System. |
TRIPOLI-4 8.1
OECD | Abstract | C00806 MNYCP 00 | Code System for Coupled Neutron, Photon, Electron, Positron, 3-D, Time Dependent, Monte-Carlo, Transport Calculations. |
| TRIPOS | Abstract | C00537 CY00I 00 | Monte Carlo Ion Transport Analysis Code. |
| TRISTAN | Abstract | C00511 HM280 00 | Multigroup Three-Dimensional Direct Integration Method Radiation Transport Analysis Code System. |
| TRITAC | Abstract | C00560 D8810 00 | A Three-Dimensional Transport Code For Eigenvalue Problems Using The Diffusion Synthetic Acceleration Method. |
| TWOTRAN-SPHERE | Abstract | C00129 C6600 00 | Multigroup Two-Dimensional Discrete Ordinates Transport Code System in Spherical Geometry. |
| UNIMUG3 | Abstract | C00407 C0170 00 | Solves Multigroup Diffusion Equations in One-Dimensional Systems. |
| USRHYD | Abstract | C00197 I3675 00 | Electron and X-Ray Energy Deposition and Hydrodynamics Code System. |
| VCS | Abstract | C00262 I0360 00 | Coupled Discrete Ordinates-Adjoint Monte Carlo Calculation of Radiation Protection Factors in Vehicles. |
| VESTA 2.1.5-AURORA 1.0 | Abstract | C00769 PCX86 01 | A Generic Monte Carlo Code and Depletion Module Interface. |
| VIM 5.1 | Abstract | C00754 MNYWS 01 | Continuous Energy Neutron and Gamma-ray Transport Code System. |
| XPORT-PC | Abstract | C00559 IBMPC 00 | An Approximation For Black Body X-Ray Transport in Air. |
| XRAY_AAC | Abstract | C00525 D0750 00 | X-ray Attenuation and Absorption Calculations. |
| XSDRN | Abstract | C00123 C0073 00 | Multigroup One-Dimensional Discrete Ordinates Spectral Averaging N Transport Code System. |
| XSDRN | Abstract | C00123 I0360 00 | Multigroup One-Dimensional Discrete Ordinates Spectral Averaging N Transport Code System. |