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Click on RSICC Tapelist to view list of files distributed with package.
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| Packages with Keyword: ADJOINT |
| Package Name | Abstract | RSICC Tapelist | Title |
| ADJMOM | Abstract | C00212 I3675 00 | Adjoint Moments Method Gamma-Ray Transport Code System. |
| 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. |
| BISON 1.5 | Abstract | C00464 HM200 00 | One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System. |
| DANTSYS 3.0 | Abstract | C00547 MFMWS 01 | One-, Two-, and Three-Dimensional, Multigroup, Discrete-Ordinates Transport Code System. |
| 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. |
| FOCUS | Abstract | C00390 I3033 00 | Adjoint Monte Carlo Neutron Transport Code System. |
| FORSS | Abstract | C00334 C0000 00 | A Sensitivity and Uncertainty Analysis Code System. |
| FORSS | Abstract | C00334 I0360 00 | A Sensitivity and Uncertainty Analysis Code System. |
| GADJET | Abstract | C00115 C6600 00 | Monte Carlo Gamma-Ray Adjoint Energy Transport Code in Complex Three-Dimensional Geometry. |
| 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. |
| HAM | Abstract | C00267 U1108 00 | Monte Carlo Multigroup Neutron and Photon High Altitude Transport Code System. |
| JDL-IMPORTANCE | Abstract | M00005 MNYCP 00 | Adjoint Function: Physical Basis of Variational & Perturbation Theory in Transport & Diffusion Problems. |
| MAGIK | Abstract | C00359 I0360 00 | A Monte Carlo Code System for Computing Induced Residual Activation Dose Rates. |
| 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-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-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-L | Abstract | C00261 C6600 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. |
| 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 |
| REBEL 3 | Abstract | C00299 I0360 00 | Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms. |
| REBEL-2 | Abstract | C00299 C6600 00 | Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms. |
| REBEL-2 | Abstract | C00299 ICL00 00 | Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms. |
| SAM-CE | Abstract | C00187 C6600 00 | Monte Carlo Time-Dependent Complex Geometry (Combinatorial) Code System for the Solution of the Forward Neutron and Forward and Adjoint Gamma-Ray Transport Equations. |
| SAM-CE | Abstract | C00187 I0360 00 | Monte Carlo Time-Dependent Complex Geometry (Combinatorial) Code System for the Solution of the Forward Neutron and Forward and Adjoint Gamma-Ray Transport Equations. |
| SENSIT | Abstract | C00405 C7600 00 | One-Dimensional, Multigroup Cross Section and Design Sensitivity and Uncertainty Analysis Code System - Generalized Perturbation Theory. |
| SNAP-3D | Abstract | C00434 MNYCP 01 | Multigroup Complex Geometry Neutron Diffusion 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. |
| 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. |
| VCS | Abstract | C00262 I0360 00 | Coupled Discrete Ordinates-Adjoint Monte Carlo Calculation of Radiation Protection Factors in Vehicles. |