Online Catalog
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Click on Abstract to read the package abstract.
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Packages with Keyword: ADJOINT
Package NameAbstractRSICC TapelistTitle
ADJMOMAbstractC00212 I3675 00Adjoint Moments Method Gamma-Ray Transport Code System.
ANISN-ORNLAbstractC00254 MNYCP 02One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering.
ANTE 2AbstractC00131 I3675 00Adjoint Monte Carlo Time-Dependent Neutron Transport Code in Combinatorial Geometry.
BISON 1.5AbstractC00464 HM200 00One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System.
DANTSYS 3.0AbstractC00547 MFMWS 01One-, Two-, and Three-Dimensional, Multigroup, Discrete-Ordinates Transport Code System.
DOORS 3.2AAbstractC00650 MFMWS 04One, Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System.
FOCUSAbstractC00390 I3033 00Adjoint Monte Carlo Neutron Transport Code System.
FORSSAbstractC00334 C0000 00A Sensitivity and Uncertainty Analysis Code System.
FORSSAbstractC00334 I0360 00A Sensitivity and Uncertainty Analysis Code System.
GADJETAbstractC00115 C6600 00Monte Carlo Gamma-Ray Adjoint Energy Transport Code in Complex Three-Dimensional Geometry.
GBANISNAbstractC00628 IRISC 00One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering with the GroupBand Option.
GENP-2AbstractC00575 ALLMF 00Generalized Perturbation Theory Code System.
HAMAbstractC00267 U1108 00Monte Carlo Multigroup Neutron and Photon High Altitude Transport Code System.
JDL-IMPORTANCEAbstractM00005 MNYCP 00Adjoint Function: Physical Basis of Variational & Perturbation Theory in Transport & Diffusion Problems.
MAGIKAbstractC00359 I0360 00A Monte Carlo Code System for Computing Induced Residual Activation Dose Rates.
MORSE-ALBAbstractC00394 FM200 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-ANSI STD.AbstractC00127 I3675 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-BAbstractC00368 I0370 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-CGAbstractC00203 C0000 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-CGAbstractC00203 CY000 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-CGAbstractC00203 D0VAX 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-CGAbstractC00203 I0360 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-CGAbstractC00203 U0000 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-CGAAbstractC00474 ALLCP 03Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-EMPAbstractC00588 IBMPC 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-HAbstractC00471 I3081 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-LAbstractC00261 C6600 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
MORSE-SGCAbstractC00277 C7600 00Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System.
NESTLE 5.2.1AbstractC00641 MNYCP 04Code System to Solve the Few-Group Neutron Diffusion Equation Utilizing the Nodal Expansion Method (NEM) for Eigenvalue, Adjoint, and Fixed-Source
REBEL 3AbstractC00299 I0360 00Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms.
REBEL-2AbstractC00299 C6600 00Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms.
REBEL-2AbstractC00299 ICL00 00Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms.
SAM-CEAbstractC00187 C6600 00Monte Carlo Time-Dependent Complex Geometry (Combinatorial) Code System for the Solution of the Forward Neutron and Forward and Adjoint Gamma-Ray Transport Equations.
SAM-CEAbstractC00187 I0360 00Monte Carlo Time-Dependent Complex Geometry (Combinatorial) Code System for the Solution of the Forward Neutron and Forward and Adjoint Gamma-Ray Transport Equations.
SENSITAbstractC00405 C7600 00One-Dimensional, Multigroup Cross Section and Design Sensitivity and Uncertainty Analysis Code System - Generalized Perturbation Theory.
SNAP-3DAbstractC00434 MNYCP 01Multigroup Complex Geometry Neutron Diffusion Code System.
SUSDAbstractC00501 HM150 00Cross Section Sensitivity and Uncertainty Analysis Including Secondary Neutron Energy and Angular Distributions.
SUSDAbstractC00501 I3090 00Cross Section Sensitivity and Uncertainty Analysis Including Secondary Neutron Energy and Angular Distributions.
TIMEXAbstractC00274 C7600 00One Dimensional, Time Dependent Multigroup Explicit Discrete Ordinates Radiation Transport Code System with Anisotropic Scattering.
TIMEXAbstractC00274 CY000 00One Dimensional, Time Dependent Multigroup Explicit Discrete Ordinates Radiation Transport Code System with Anisotropic Scattering.
TIMEXAbstractC00274 U1106 00One Dimensional, Time Dependent Multigroup Explicit Discrete Ordinates Radiation Transport Code System with Anisotropic Scattering.
VCSAbstractC00262 I0360 00Coupled Discrete Ordinates-Adjoint Monte Carlo Calculation of Radiation Protection Factors in Vehicles.
The Radiation Safety Information Computational Center (RSICC) is a Department of Energy Specialized Information Analysis Center (SIAC) authorized to collect, analyze, maintain, and distribute computer software and data sets in the areas of radiation transport and safety. RSICC resides in the Reactor and Nuclear Systems Division (RNSD) at Oak Ridge National Laboratory.