| Packages starting with T |
| Package Name | Abstract | RSICC Tapelist | Title |
| TACT-III | Abstract | C00447 I3033 00 | Calculation of the Transport of Radioactivity from a Reactor Core. |
| TALYS-1.2 | Abstract | P00548 PC586 01 | Nuclear Model Code System for Analysis and Prediction of Nuclear Reactions and Generation of Nuclear Data. |
| TAM3 | Abstract | P00308 IBMPC 00 | Demonstrates Monte Carlo Sensitivity and Uncertainty Analysis. |
| 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. |
| TDF | Abstract | D00162 ALLCP 00 | Thermonuclear Data File. |
| TDOWN-IV | Abstract | P00172 H6000 00 | A Code System to Generate Composition- and Spatially-Dependent Neutron Cross Sections for Multigroup Neutronics Analysis. |
| 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. |
| TECALC | Abstract | P00074 DP010 00 | Interactive Calculation of Compton Coherent and Photoelectric Mass Attenuation Coefficients for Photons (E<1 MeV), and the Mass Absorption Coefficient for Known Materials. |
| TEMAC | Abstract | P00468 D0VAX 00 | Top Event Matrix Analysis Code System. |
| TEMPEST-2 | Abstract | P00558 I0360 00 | Thermalization Program for Neutron Spectra and MultiGroup Cross-Sections. |
| TEMPEST-BNW | Abstract | P00559 C7600 00 | Transient 3-D Thermohydraulics for FBR. |
| TENDL-2008-ACE | Abstract | D00243 MNYCP 00 | TALYS-Based Cross Section Library for Use with MCNP(X). |
| TENDL-2010-ACE | Abstract | D00248 MNYCP 00 | TALYS-Based Cross Section Library for Use with MCNP(X). |
| TENDL-2011-ACE | Abstract | D00252 MNYCP 00 | TALYS-Based Cross Section Library for Use with MCNP(X). |
| TENDL-2012-ACE | Abstract | D00266 MNYCP 00 | TALYS-Based Cross Section Library for Use with MCNP(X). |
| TERFOC-N | Abstract | C00596 MFMWS 00 | Terrestrial Food-Chain Model for Normal Operations. |
| TESS | Abstract | C00215 C3600 00 | Multigroup Discrete Ordinates Code System for Slab and Spherical Geometries. |
| THACT-RR | Abstract | P00587 D0VAX 00 | Analysis of Thermal Hydraulics Transients in Research Reactor Core. |
| THERMGAM | Abstract | D00140 ALLCP 00 | Prompt Gamma Rays from Thermal-Neutron Capture. |
| THERMOS-OTA | Abstract | P00107 C0173 00 | Multigroup Integral Transport Code System for Thermal Lattice Calculations using Collision Probability Method for Slabs and Cylinders. |
| THERMOS-OTA | Abstract | P00107 C0740 00 | Multigroup Integral Transport Code System for Thermal Lattice Calculations using Collision Probability Method for Slabs and Cylinders. |
| THERMOS-OTA | Abstract | P00107 U1108 00 | Multigroup Integral Transport Code System for Thermal Lattice Calculations using Collision Probability Method for Slabs and Cylinders. |
| THIDA-2 | Abstract | C00410 FM380 00 | Code System for the Calculation of Transmutation, Activation, Decay Heat and Dose Rate in Fusion Reactors. |
| THRUSH | Abstract | P00276 CYXMP 00 | Calculates Thermal Neutron Scattering Kernel. |
| THT | Abstract | C00480 I0360 00 | Three-Dimensional Neutron Coarse Mesh Code System to Evaluate Average Bundle Fluxes and Power in Light Water Reactors. |
| THYDE-B1/MOD2 | Abstract | P00553 FM200 00 | Computer Code for PWR LOCA Thermohydraulic Transient Analysis. |
| THYDE-P2 | Abstract | P00554 FV100 00 | Computer Code for PWR LOCA Thermohydraulic Transient Analysis. |
| TIBSO | Abstract | C00512 MNYCP 00 | Code System to Calculate Production and Migration of Radionuclides in Nuclear Reactor Systems. |
| TIMED | Abstract | C00292 I0360 00 | Calculation of Cumulated Activity of a Radionuclide in the Organs of the Human Body at a Given Time After Deposition. |
| 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. |
| TIMS-1 | Abstract | P00163 D0780 00 | Processing Code System for Production of Group Constants of Heavy Resonant Nuclei. |
| TIMS-1 | Abstract | P00163 FM200 00 | Processing Code System for Production of Group Constants of Heavy Resonant Nuclei. |
| TIRION 4 | Abstract | C00395 I3033 00 | A Program for Calculating Consequences of a Release of Radioactive Material to the Atmosphere. |
| TITAN 1.29 | Abstract | C00759 PCX86 04 | A Three-Dimensional Deterministic Radiation Transport Code System. |
| TMAP 7 | Abstract | C00858 PCX86 00 | Tritium Migration Analysis Program |
| TMMS | Abstract | C00246 I0360 00 | Gamma-Ray Penetration Shielding Code System, Transmission Matrix Method. |
| TNG1 | Abstract | P00298 D6220 00 | A Multistep Statistical Model Based on the Hauser-Feshbach Theory For The Evaluation Of Neutron Data. |
| TORAC | Abstract | P00459 C0170 00 | Code System to Calculate Tornado-Induced Flow Material Transport. |
| TOTEM-3 | Abstract | P00603 I0370 00 | Demand Assessment for Nuclear Power Plants and Conventional Power Plants. |
| TOXRISK | Abstract | C00692 CDCMF 00 | Code System for Toxic Gas Accident Analysis. |
| TP1 | Abstract | C00465 I3033 00 | A Computer Code System for the Calculation of Reactivity and Kinetic Parameters by One-Dimensional Neutron Transport Perturbation Theory. |
| TP2 | Abstract | C00470 I3033 00 | A Computer Code System for the Calculation of Reactivity and Kinetic Parameters by One-Dimensional Neutron Transport Perturbation Theory. |
| TPASGAM 85 | Abstract | D00088 ALLCP 04 | Radioactive Decay Library of Gamma-Ray Energies, Branching Ratios, and Cross Sections. |
| TPASS | Abstract | P00164 DP010 00 | A Gamma-Ray Spectral Data-Reduction and Analysis Code System. |
| 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. |
| TRANSMIT | Abstract | D00020 I0360 00 | Experimental Neutron Transmission Data Used to Test Total Cross Sections. |
| TRANSPORT | Abstract | C00244 C6600 00 | Charged Particle Beam Transport Systems Design Code System (First- and Second-Order Matrix Multiplication). |
| TRANSPORT | Abstract | C00244 I0360 00 | Charged Particle Beam Transport Systems Design Code System (First- and Second-Order Matrix Multiplication). |
| TRANSX 2.15 | Abstract | P00317 MFMWS 01 | Code system to produce neutron, photon, and particle transport tables for discrete-ordinates and diffusion codes from cross sections in MATXS format. |
| TRANSX-CTR | Abstract | P00206 CY000 00 | Interfaces MATXS Cross-Section Libraries to Nuclear Transport Codes for Fusion Systems Analysis. |
| 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. |
| TRAX | Abstract | P00280 C0720 00 | A Program For Optics of Curved Crystal Neutron Spectrometers. |
| TRD-3 | Abstract | C00362 I3033 00 | Two-Dimensional Removal-Diffusion Neutron Shielding Code System. |
| TRECO | Abstract | C00116 I3675 00 | An Orbital Integration Estimation of Trapped Radiation. |
| TR-EDB | Abstract | D00198 IBMPC 00 | Test Reactor Embrittlement Data Base. |
| TREEDE | Abstract | C00326 C0000 00 | Monte Carlo Neutron Transport Code System Based on the Track Rotation Estimator. |
| TRG-SGD | Abstract | C00025 C0000 00 | Calculation of Secondary Gamma-Ray Dose Rate from a Nuclear Weapon Detonation-Monte Carlo Method. |
| 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. |
| TRIGAP | Abstract | C00600 IBMPC 00 | A Computer Code for TRIGA Type Reactors. |
| TRIGLAV | Abstract | P00495 PC586 00 | Code System to Calculate Mixed Cores in TRIGA Mark II Research Reactor. |
| 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. |
TRIPOLI-4 9S
OECD | Abstract | C00815 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. |
| TRISTAN-IJS | Abstract | P00537 IBMPC 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. |
| TRUMP | Abstract | P00522 MNYCP 01 | Code System for Transient and Steady-State Temperature Distribution in Multidimensional Systems. |
| TSL-ACE/2013 | Abstract | D00270 ALLCP 00 | TSL-ACE/2013 |
| TSORT | Abstract | P00486 IBMPC 00 | Automated Technique for Nuclear Plant Training Task Assignment. |
| TURBINA | Abstract | P00604 I0370 00 | Reheat Steam Turbine Generator Design with Preheater and Condenser. |
| 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. |