| Packages with Keyword: MULTIGROUP |
| Package Name | Abstract | RSICC Tapelist | Title |
| ACDOS3 | Abstract | C00442 C7600 00 | Calculation of Activities and Dose Rates Produced by Neutron Activation. |
| ADO | Abstract | C00189 I3675 00 | Aerojet Discrete Ordinates Calculational System. |
| ADS-LIB/V2.0 | Abstract | D00250 MNYCP 00 | Test Library for Accelerator Driven Systems V2.0 |
| AIRDIF | Abstract | C00360 C6600 00 | A Two-Dimensional Atmospheric Radiation Diffusion Code. |
| ALARA 2.7.8 | Abstract | C00723 MNYCP 00 | Code System for Analytic and Laplacian Adaptive Radioactivity Analysis. |
| ANISN-ORNL | Abstract | C00254 MNYCP 02 | One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering. |
| ANISN-PC | Abstract | C00514 IBMPC 00 | Multigroup One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering. |
| APARNA-II | Abstract | C00296 I0360 00 | Integral Transport Theory Code System Based on Discrete Ordinate Representation in Space and Direction-Slab Geometry. |
ARC 11.2892
FEDC | Abstract | C00824 MNYCP 02 | Code System for Analysis of Nuclear Reactors. |
| ASOP | Abstract | C00126 IRISC 00 | Multigroup One-Dimensional Discrete Ordinates Transport Code System for Shield Optimization. |
| ATHENA_2D | Abstract | P00431 MNYCP 00 | Code System For Simulation Of Hypothetical Recriticality Accidents in a Thermal Neutron Spectrum. |
| 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. |
| BISON 1.5 | Abstract | C00464 HM200 00 | One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System. |
| BISON-C | Abstract | C00659 MNYWS 00 | One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System. |
| BMC-MG | Abstract | C00291 C6600 00 | Multigroup Monte Carlo Neutron and Gamma-Ray Shielding Code System for Plutonium. |
| BOLD VENTURE IV | Abstract | C00459 I3033 00 | A Reactor Analysis Code System. |
| BOREHOLE-EB6.8-MG | Abstract | D00268 MNYCP 00 | Multi-Group Cross-Section Library for Deterministic and Monte Carlo Codes. |
| BUGENDF70.BOLIB | Abstract | D00262 PCX86 00 | ENDF/B-VII.0 Broad-Group Coupled Cross Section Library for LWR Shielding & Pressure Vessel Dosimetry Applications. |
| BUGJEFF311.BOLIB | Abstract | D00254 MNYCP 01 | JEFF-3.1.1 Broad-Group Coupled Cross Section Library For LWR Shielding & Pressure Vessel Dosimetry Applications. |
| CAFDATS | Abstract | P00549 MNYCP 00 | Converter of Angular Fluxes of DORT, ANISN and TORT Systems. |
| CARMEN SYSTEM | Abstract | C00487 U1110 00 | A Code System for Neutronics PWR Calculation by Diffusion Theory with Space-Dependent Feedback Effects. |
| CEPXS | Abstract | C00837 MNYCP 00 | Coupled Electron-Photon Cross Section |
| CEPXS/ONELD 1.0 | Abstract | C00544 MNYCP 02 | One-Dimensional Coupled Electron-Photon Multigroup Discrete Ordinates Code System. |
| CNCSN 2009 | Abstract | C00726 PCX86 01 | One, Two- and Three-Dimensional Coupled Neutral and Charged Particle SN Parallel Multi-Threaded Code System. |
| CRESO | Abstract | P00184 I3081 00 | Resonance Data-Handling Code System. |
| DANTSYS 3.0 | Abstract | C00547 MFMWS 01 | One-, Two-, and Three-Dimensional, Multigroup, Discrete-Ordinates Transport Code System. |
| DDXCODES | Abstract | C00583 FM380 00 | One-, Two- and Three-Dimensional Transport Codes Using Multigroup Double-Differential Form Cross Sections. |
| DIAMANT2 | Abstract | C00414 PC386 00 | Multigroup Two-Dimensional Discrete Ordinates Transport Code System for Triangular Geometry, Release 2.0. |
DIF3D 11.2892
FEDC | Abstract | C00784 MNYCP 02 | Code System Using Variational Nodal Methods and Finite Difference Methods to Solve Neutron Diffusion and Transport Theory Problems. |
| DIXY-2 | Abstract | C00812 I0370 00 | 2-D Homogeneous and Inhomogeneous Neutron Diffusion N X-Z, R-Z, R-Theta Geometry with Perturbation. |
| DKR | Abstract | C00323 CY000 00 | A Radioactivity and Dose Rate Calculation Code System for Fusion Reactors. |
| DOORS 3.2A | Abstract | C00650 MFMWS 04 | One, Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System. |
| DOT 3.5 | Abstract | C00276 I0360 00 | Two-Dimensional Discrete Ordinates Radiation Transport Code System. |
| DTF-69 | Abstract | C00130 C6600 00 | Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering. |
| DTF-TRACA | Abstract | C00412 U1100 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. |
| EXTREME | Abstract | C00440 I3033 00 | Two-Dimensional Discrete-Ordinates Code System with Exponential Expansion of Spatial Variables. |
| FDKR | Abstract | C00541 I4381 00 | Radioactivity and Dose Rate Calculation Code for Fission, Fusion and Hybrid Reactors. |
| 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. |
| FLUKA05-PRE-LIB | Abstract | D00260 PCX86 00 | FLUKA05 Multi-Group, Multi-Purpose Nuclear Data Library, Neutrons, Photons, Charged Particles. |
| FORSS | Abstract | C00334 C0000 00 | A Sensitivity and Uncertainty Analysis Code System. |
| FORSS | Abstract | C00334 I0360 00 | A Sensitivity and Uncertainty Analysis Code System. |
| FPZD | Abstract | C00603 PC386 00 | Code System for Multigroup Neutron Diffusion/Depletion Calculations. |
| FSCATT | Abstract | C00186 I3033 00 | Discrete Ordinates Gamma-Ray Transport Code System in Plane Geometry. |
| FSCATT | Abstract | C00186 U1108 00 | Discrete Ordinates Gamma-Ray Transport Code System in Plane Geometry. |
| GBANISN | Abstract | C00628 IRISC 00 | One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering with the GroupBand Option. |
| GNOMER | Abstract | C00625 MNYCP 01 | Multigroup 3-Dimensional Neutron Diffusion Nodal Code System with Thermohydraulic Feedbacks. |
| HAM | Abstract | C00267 U1108 00 | Monte Carlo Multigroup Neutron and Photon High Altitude Transport Code System. |
| HEXAB-3D | Abstract | C00593 I0370 00 | Three-Dimensional Few-Group Coarse Mesh Diffusion Code for Neutron Physics Calculation of Reactor Core in Hexagonal Geometry. |
| INDRA | Abstract | C00303 I0360 00 | A Modular System for Calculating the Neutronics and Photonics Characteristics of a Fusion Reactor Blanket. |
| KASY | Abstract | C00814 I0370 00 | 3-D Homogeneous Neutron Diffusion in X-Y-Z, R-Theta, Hexagonal-Z Geometry by Synthesis Method. |
| KORIGEN | Abstract | C00457 I3033 00 | A Modification of the Isotope Generation and Depletion Code System ORIGEN. |
| LIE-PN | Abstract | C00816 I0360 00 | Pn Neutron Transport in Radial Geometry Cell with Source Problems Calculation. |
| MADONNA | Abstract | C00425 I0370 00 | Two-dimensional Neutron Streaming Coupled Removal-Diffusion-Albedo-Transport Code System. |
| MARC-PN | Abstract | C00311 D8810 00 | A Neutron Diffusion Code System with Spherical Harmonics Option. |
| MATXSLIBJ33 | Abstract | D00258 MNYCP 01 | JENDL-3.3 Based, 175 Neutron-42 Photon Groups (VITAMIN-J) MATXS Library for Discrete Ordinates Multi-Group Transport Codes. |
| MKENO-DAR | Abstract | C00513 FM380 00 | Direct Angular Representation Monte Carlo Code for Criticality Safety Analysis |
| MMCR | Abstract | C00441 FM200 00 | Multigroup Monte Carlo Neutron and Photon Transport Code. |
| MORSE-ALB | Abstract | C00394 FM200 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-ANSI STD. | Abstract | C00127 I3675 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-B | Abstract | C00368 I0370 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-C | Abstract | C00431 C7600 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-CG | Abstract | C00203 C0000 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-CG | Abstract | C00203 CY000 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-CG | Abstract | C00203 D0VAX 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-CG | Abstract | C00203 I0360 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-CG | Abstract | C00203 U0000 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-CGA | Abstract | C00474 ALLCP 03 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-CV | Abstract | C00535 HM280 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-E | Abstract | C00258 I0360 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-EMP | Abstract | C00588 IBMPC 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-H | Abstract | C00471 I3081 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-SGC | Abstract | C00277 C7600 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MULTI-KENO2 | Abstract | C00492 FM380 00 | A Monte Carlo Code System for Criticality Safety Analysis. |
| MURLI | Abstract | C00378 DP011 00 | Integral Transport Theory Code System for Thermal Reactor Lattice Cell Calculation. |
| MUSPALB | Abstract | C00171 ICL00 00 | Albedo Calculation of Multigroup Spectra of Neutrons Transmitted Through Multilayer Slab Shielding. |
| NAP | Abstract | C00101 I7090 00 | Multigroup Time-Dependent Neutron Activation Prediction Code. |
| NITRAN | Abstract | C00582 FM380 00 | Neutron Transport Code System Based On Anisotropic Scattering. |
| ONETRAN | Abstract | C00266 C7600 00 | A One-Dimensional Multigroup Discrete Ordinates Finite Element Transport Code System. |
| ONETRAN | Abstract | C00266 CY000 00 | A One-Dimensional Multigroup Discrete Ordinates Finite Element Transport Code System. |
| ONETRAN | Abstract | C00266 I3033 00 | A One-Dimensional Multigroup Discrete Ordinates Finite Element Transport Code System. |
| ORIGEN2.2 | Abstract | C00371 ALLCP 03 | Isotope Generation and Depletion Code - Matrix Exponential Method. |
| ORIGEN-JENDL32 | Abstract | C00703 MNYWS 00 | Isotope Generation and Depletion Code - Matrix Exponential Method. |
| OZMA | Abstract | C00406 I0370 00 | Calculation of Resonance Reaction Rates in Reactor Lattices Using Resonance Profile Tabulations. |
| PALLAS-1D(VII) | Abstract | C00380 FM380 00 | Multigroup Time-Independent Neutron Transport Code System for Plane or Spherical Geometry. |
| PALLAS-2DCY-FX | Abstract | C00391 FM380 00 | Multigroup Time-Independent Neutron Transport Code System for Plane or Spherical Geometry. |
PERSENT 11.2892
FEDC | Abstract | C00823 MNYCP 02 | Perturbation and Sensitivity Code for Assembly Homogenized Multi-group Transport Problems |
| PIGG | Abstract | C00138 C3600 00 | A Multigroup One-Dimensional P-1 Radiation Transport Code System. |
| PN | Abstract | C00818 I0370 00 | MultiGroup Neutron Transport. |
| PREMOR | Abstract | C00369 I0360 00 | A Point Reactor Exposure Code System for Survey Nuclear Analysis of Power Plant Performance. |
| PROB | Abstract | C00287 I0370 00 | Multigroup One-Dimensional Transport Code System, Collision Probability Method. |
| RADHEAT-V4 | Abstract | C00300 FM380 00 | A Code System To Generate Multigroup Constants and Analyze Radiation Transport for Shielding Safety Evaluation. |
| 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. |
| RASC-2D | Abstract | C00318 I0370 00 | Two-Dimensional Removal Diffusion Code Reactor Shielding Design Code System. |
| 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. |
| SAMSY | Abstract | C00315 C0073 00 | A One-Dimensional Multilayer Multigroup Neutron Removal-Diffusion and Gamma-Ray Point Kernel Calculator. |
| SANDOR | Abstract | C00364 C7600 00 | Isotope Generation and Depletion Code Matrix Exponential Method. |
SCEPTRE 1.1
FEDC | Abstract | C00807 PCX86 00 | Sandia Computational Engine for Particle Transport for Radiation Effects. |
SCEPTRE 1.7
FEDC | Abstract | C00826 PCX86 01 | Sandia Computational Engine for Particle Transport for Radiation Effects. |
| SCORE-4 | Abstract | C00234 I0370 00 | Two-Dimensional Multigroup Removal-Diffusion Shielding Code System. |
| SENSIT | Abstract | C00405 C7600 00 | One-Dimensional, Multigroup Cross Section and Design Sensitivity and Uncertainty Analysis Code System - Generalized Perturbation Theory. |
| SHADOK | Abstract | C00216 C6600 00 | Transport Code Systems, P1 Scattering in Infinite Cylindrical and Spherical Geometries by Polynomial Approximation. |
| SHREDI | Abstract | C00284 I0360 00 | Multigroup Two-Dimensional (x-y, r-o geometry) Neutron Removal-Diffusion (Spinney Method) Shielding Code System. |
| SIXTUS-3 | Abstract | C00609 MFMWS 00 | Three-Dimensional, Nodal, Neutron Diffusion Criticality Code System in Hex-Z Geometry. |
| SLDN | Abstract | C00221 A1000 00 | Code System for Shielding Calculations by the Method of Invariant Imbedding. |
| SLDN | Abstract | C00221 F2307 00 | Code System for Shielding Calculations by the Method of Invariant Imbedding. |
| SLDN | Abstract | C00221 FM200 00 | Code System for Shielding Calculations by the Method of Invariant Imbedding. |
| SLDN | Abstract | C00221 GE625 00 | Code System for Shielding Calculations by the Method of Invariant Imbedding. |
| SLDN | Abstract | C00221 I0360 00 | Code System for Shielding Calculations by the Method of Invariant Imbedding. |
| SNAP-3D | Abstract | C00434 MNYCP 01 | Multigroup Complex Geometry Neutron Diffusion 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. |
| SOLTRAN | Abstract | C00763 PCX86 00 | Solving Multi-Dimensional Simplified P2 Transport and Diffusion Problems of Hexagonal Geometry in Fast Reactors. |
| STRAINT | Abstract | C00259 I0360 00 | One-Dimensional Multigroup Neutron Transport Discrete Ordinates Code System. |
| SUSD | Abstract | C00501 HM150 00 | Cross Section Sensitivity and Uncertainty Analysis Including Secondary Neutron Energy and Angular Distributions. |
| SUSD | Abstract | C00501 I3090 00 | Cross Section Sensitivity and Uncertainty Analysis Including Secondary Neutron Energy and Angular Distributions. |
| SUSD3D | Abstract | C00695 MNYCP 01 | Multi-Dimensional, Discrete-Ordinates Based Cross Section Sensitivity and Uncertainty Analysis 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. |
| TESS | Abstract | C00215 C3600 00 | Multigroup Discrete Ordinates Code System for Slab and Spherical Geometries. |
| THIDA-2 | Abstract | C00410 FM380 00 | Code System for the Calculation of Transmutation, Activation, Decay Heat and Dose Rate in Fusion Reactors. |
| 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. |
| 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. |
| TRD-3 | Abstract | C00362 I3033 00 | Two-Dimensional Removal-Diffusion Neutron Shielding Code System. |
| 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. |
| TRISTAN | Abstract | C00511 HM280 00 | Multigroup Three-Dimensional Direct Integration Method Radiation Transport Analysis Code System. |
| TWOTRAN | Abstract | C00195 C6600 00 | Two-Dimensional Multigroup Discrete Ordinates Transport C System in (x,y), (r,theta), and (r,z) Geometries. |
| TWOTRAN II | Abstract | C00222 C7600 00 | Two-Dimensional Multigroup Discrete Ordinates Transport C System in (x,y), (r,theta), and (r,z) Geometries. |
| TWOTRAN II | Abstract | C00222 I3691 00 | Two-Dimensional Multigroup Discrete Ordinates Transport C System in (x,y), (r,theta), and (r,z) Geometries. |
| 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. |
| VALE 1.1 | Abstract | C00613 IRISC 01 | A Multigroup Diffusion Theory Neutronics Code System for Solving Two- and Three-Dimensional Problems for Triagonal Geometries. |
| VALE 1.1 | Abstract | C00613 PC386 01 | A Multigroup Diffusion Theory Neutronics Code System for Solving Two- and Three-Dimensional Problems for Triagonal Geometries. |
| VENTURE-PC | Abstract | C00654 PC586 02 | A Reactor Analysis Code System. |
| VESTA 2.1.5-AURORA 1.0 | Abstract | C00769 PCX86 01 | A Generic Monte Carlo Code and Depletion Module Interface. |
| VITENDF70.BOLIB | Abstract | D00261 PCX86 00 | ENDF/B-VII.0 Multi-Group Coupled (199n +42gamma) Cross Section Library in AMPX Format for Nuclear Fission Applications. |
| VITJEFF311.BOLIB | Abstract | D00257 MNYCP 01 | JEFF-3.1.1 Multi-Group Coupled (199n + 42gamma) X-Section Library in AMPX Format for Nuclear Fission Applications. |
| WLUP 3.0 | Abstract | D00231 MNYCP 01 | 69- and 172- Group Cross Section Libraries for WIMS. |
| 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. |