Online Catalog
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810 -- US DOE 10CFR810 Jurisdiction
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Packages with Subject: NUCLEAR PARTICLE TRANSPORT IN MATERIALS
Package NameAbstractRSICC TapelistTitle
1DB-2DB-3DBAbstractC00741 PC586 00One-Dimensional Diffusion Code System for Nuclear Reactor.
ACATAbstractP00257 FM380 00Monte Carlo Simulation of Atomic Collisions in Amorphous Targets in the Binary Collision Approximation.
ACOHAbstractC00191 I3675 00Aerojet COHORT Monte Carlo Code System.
ADJMOMAbstractC00212 I3675 00Adjoint Moments Method Gamma-Ray Transport Code System.
ADOAbstractC00189 I3675 00Aerojet Discrete Ordinates Calculational System.
AIR DATAAbstractD00014 I0360 00Sample Input to ANISN for Calculation of Neutron and Secondary Gamma-Ray Transport in Air.
AIRDIFAbstractC00360 C6600 00A Two-Dimensional Atmospheric Radiation Diffusion Code.
AIRSCATAbstractC00341 DP010 00Calculation of Dose Rate for Gamma-Rays Scattered in Air.
AIRTRANSAbstractC00110 I3675 00Monte Carlo Time and Energy-Dependent Three-Dimensional Radiation Transport Code.
ALGAM-97AbstractC00152 I3675 00Monte Carlo Estimation of Internal Dose from Gamma-Ray Sources in a Phantom Man.
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.
APARNA-IIAbstractC00296 I0360 00Integral Transport Theory Code System Based on Discrete Ordinate Representation in Space and Direction-Slab Geometry.
ARMYL-GAbstractC00297 U1106 00Calculation of Transmission Factors for Gamma Rays from Nuclear Explosions.
ARMYL-NAbstractC00298 U1106 00Calculation of Transmission Factors for Neutrons from Nuclear Explosions.
ASFIT-VARIAbstractC00336 H0000 00Gamma-Ray Transport Code System for One-Dimensional Finite Systems.
ASFIT-VARIAbstractC00336 IBMPC 00Gamma-Ray Transport Code System for One-Dimensional Finite Systems.
ATTOW-KBAbstractC00132 I0370 00Multigroup Two-Dimensional Removal-Diffusion (Spinney Method) Shielding Code System.
AUS98AbstractC00519 MNYWS 01Modular System for Neutronics Calculations of Fission Reactors, Fusion Blankets, and Other Systems.
BALTOROAbstractC00479 C6600 00Code for Coupling of Monte Carlo and Discrete Ordinates Radiation Transport Calculations.
BCGAbstractC00578 C0170 00A Code For Calculating Pointwise Neutron Spectra and Criticality in Fast Reactor Cells.
BERMUDAAbstractC00616 FV260 03Discrete Ordinates Code System for Shielding Analysis for Use with Fusion and Fission Reactors.
BETA IIAbstractC00117 C6600 00Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry.
BETA IIAbstractC00117 I0360 00Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry.
BETA-S 6AbstractC00657 MNYCP 01Code System to Calculate Multigroup Beta-Ray Spectra.
BMC-MGAbstractC00291 C6600 00Multigroup Monte Carlo Neutron and Gamma-Ray Shielding Code System for Plutonium.
BOXERAbstractC00766 MNYWS 00Fine-flux Cross Section Condensation, 2D Few Group Diffusion and Transport Burnup Calculations
BREMRADAbstractC00031 I7090 00External and Internal Bremsstrahlung Calculation Code.
BRHGAMAbstractC00350 I3033 00Monte Carlo Estimation of Absorbed Dose from X-Ray Sources in Phantom Man.
BULK_C-12AbstractC00738 PC586 00Code System to Estimate Neutron and Photon Effective Dose Rates from Medium Energy Protons or Carbon Ions Through Concrete or Concrete/Iron.
CAFDATSAbstractP00549 MNYCP 00Converter of Angular Fluxes of DORT, ANISN and TORT Systems.
CAMERAAbstractC00240 C0074 00Radiation Transport Analysis Code System and the Computerized Man (CAM) Model.
CAMERAAbstractC00240 IBMPC 01Radiation Transport Analysis Code System and the Computerized Man (CAM) Model.
CARL 2.3AbstractC00743 PC586 01Code System to Calculate Radiotoxicity, Activity, Dose and Decay Power Calculations for Spent Fuel.
CARNACAbstractC00238 I3691 00Calculation of Flux and Neutron Spectra in the Case of Criticality Accident.
CASCADEAbstractC00176 C6600 00Monte Carlo Simulation of the Transport of High Energy Electrons and Photons in Matter.
CASCADEAbstractC00176 I0360 00Monte Carlo Simulation of the Transport of High Energy Electrons and Photons in Matter.
CASIMAbstractC00265 I0360 00Monte Carlo Simulation of Transport of Hadron Cascades in Bulk Matter.
CAVEATAbstractC00169 I3675 00General Purpose Monte Carlo Time-Dependent Radiation Transport Code in Complex Geometry.
CCRMNAbstractP00366 MNYCP 00Monte Carlo Simulation of the Coupled Transport of Electrons and Photons.
CEPXS/ONELD 1.0AbstractC00544 MNYCP 02One-Dimensional Coupled Electron-Photon Multigroup Discrete Ordinates Code System.
CHAINT-MCAbstractC00584 CYXMP 00A Two-Dimensional Model for the Analysis of Contaminant Transport in a Fractured Porous Medium.
CNCSN 2009AbstractC00726 PCX86 01One, Two- and Three-Dimensional Coupled Neutral and Charged Particle SN Parallel Multi-Threaded Code System.
COHORT-IIAbstractC00198 I7094 00General Purpose Monte Carlo Radiation Transport Code System.
COLLIMATORAbstractC00136 I7090 00Monte Carlo Calculation of the Spectrum of Gamma Radiation from a Collimated Co-60 Source.
CONSTRIP VAbstractC00139 I3675 00Vertical Barrier-Finite Source Plane Gamma-Ray Penetration Code System.
CYGASAbstractC00317 I3033 00A Gamma-Ray Attenuation Code System for Large Gamma-Ray Sources Shielded by Coaxial Cylinders.
CYGNUS-C SPHEREAbstractC00232 I0360 00Monte Carlo Neutron Transport Code System in Spherical Geometry.
CYLDOSAbstractC00389 I0360 00A Cylindrical Geometry Gamma-Ray Flux Attenuation Code System.
DASH-FPAbstractC00366 C0000 00A One-Dimensional Analytic-Numerical Solution to the Problem of Multicomponent Time-Dependent Diffusion of Fission Products.
DAVEAbstractC00166 I3675 00Monte Carlo Gamma-Ray Transport Code System in One-Dimensional Spherical Geometry.
DCTDOSAbstractC00520 IBMPC 00Neutron and Gamma-Ray Penetration in Composite Duct Systems.
DDXCODESAbstractC00583 FM380 00One-, Two- and Three-Dimensional Transport Codes Using Multigroup Double-Differential Form Cross Sections.
DEMON & DEMON RAbstractC00181 I3675 00Demonstration Monte Carlo Code System in Slab Geometry.
DIAMANT2AbstractC00414 PC386 00Multigroup Two-Dimensional Discrete Ordinates Transport Code System for Triangular Geometry, Release 2.0.
DIPHOAbstractC00140 I3675 00Monte Carlo Gamma-Ray Code System-Infinite Medium, Mono-energetic and Isotropic Point Source.
DOMINOAbstractP00064 I0360 00A General Purpose Code System for Coupling Discrete Ordinates and Monte Carlo Radiation Transport Calculations.
DOORS 3.2AAbstractC00650 MFMWS 04One, Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System.
DRAGON2PARTISNAbstractC00803 PCX86 00Cross-Sections Data Generation for PARTISN4.0.
DRAGON3.05DAbstractC00647 MNYWS 03Lattice Cell Code System.
DTF-INDIAAbstractC00458 I0370 00Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering.
DTF-IVAbstractC00042 C6600 00Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering.
DTF-IV MODIFIEDAbstractC00042 I0370 00Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering.
DTKAbstractC00223 I3675 00One-Dimensional Multigroup Neutron Transport Code System.
DUSTAbstractC00453 I3033 00Albedo Monte Carlo Simulation of Neutron Streaming Through Multilegged Ducts.
EASY-QAD 2.0.1AbstractC00744 PC586 02A Visualization Code System for Gamma and Neutron Shielding Calculations.
EDNAAbstractC00104 I7090 00Electron Dose and Number Analysis Code by Kernel Integration.
EGS4AbstractC00331 MNYCP 00Monte Carlo Simulation of the Coupled Transport of Electrons and Photons.
ELAST2AbstractD00208 MNYCP 00Database of Cross Sections for the Elastic Scattering of Electrons and Positrons by Atoms.
ELFAbstractC00167 I0360 00Monte Carlo Neutron Transport Code System for Cylinders and Spheres.
ELGATLAbstractC00295 C6600 00Calculation of Energy Spectra from Coupled Electron-Photon Slowing Down.
ELPHOAbstractC00301 I0360 00Three-Dimensional Monte Carlo Electromagnetic Transport Code System.
ELTRANAbstractC00155 C3600 00One-Dimensional Monte Carlo Electron Transport Code System.
ENEDEPAbstractC00227 GE400 00Energy Deposition Code System for GE 265 Time-Sharing System.
ENLOSSAbstractP00047 C6600 00Calculation of Energy Loss of Charged Particles.
ERANOS 2.0
OECD
AbstractC00745 MNYWS 00Modular Code and Data System for Fast Reactor Neutronics Analyses
ERINNIAbstractP00219 I0360 00Optical Model Calculation of Multiple Cascading Particle Emissions.
ERPEXAbstractC00305 C0073 00Monte Carlo Distributions of Energetic Proton Ranges in Silicon.
ESPAbstractC00193 I0360 00General Purpose Monte Carlo Neutron Transport Code System.
ETRANAbstractC00107 I0360 00Monte Carlo Code System for Electron and Photon Through Extended Media.
EXTREMEAbstractC00440 I3033 00Two-Dimensional Discrete-Ordinates Code System with Exponential Expansion of Spatial Variables.
FANGAbstractP00140 C0000 00An Angular Folding Code System for Channel Theory Analysis.
FANGAbstractP00140 I0360 00An Angular Folding Code System for Channel Theory Analysis.
FASTER IIIAbstractC00168 U1108 00Monte Carlo Neutron and Photon Transport Code System in Complex Geometries.
FASTER-IIIAbstractC00168 I3675 00Monte Carlo Neutron and Photon Transport Code System in Complex Geometries.
FEM-2DAbstractC00260 C6600 00Two-Dimensional Diffusion Theory Code System Based on the Method of Finite Elements.
FEMBAbstractC00340 B6700 00A Two-Dimensional Diffusion Theory Finite Element Program.
FEMRZAbstractC00342 F2307 00A Finite-Element Method Two-Dimensional Multigroup Neutron Transport Code System, (r,z) Geometry.
FESHAbstractC00676 CDCMF 00X-Y Multigroup Neutron Transport Code System.
FINELMAbstractC00483 MFMWS 00Multigroup Finite Element Diffusion Code System.
FIPDIGAbstractC00251 I0360 00One-Dimensional Time-Dependent Fission Product Diffusion Code System.
FLUKA-TRANKAAbstractC00207 C6600 00Three-Dimensional High-Energy Extranuclear Hadron Cascade Monte Carlo System for Cylindrical Backstop Geometries.
FOCUSAbstractC00390 I3033 00Adjoint Monte Carlo Neutron Transport Code System.
FOTELP-2014AbstractC00581 MNYCP 04Monte Carlo Simulation of Photons, Electrons and Positrons Transport.
FPZDAbstractC00603 PC386 00Code System for Multigroup Neutron Diffusion/Depletion Calculations.
FURNACEAbstractC00615 C0740 00Code System for Neutronic Calculations in Three Dimension Toroidal Geometry.
GADJETAbstractC00115 C6600 00Monte Carlo Gamma-Ray Adjoint Energy Transport Code in Complex Three-Dimensional Geometry.
GAMMOM-IAbstractC00226 I0360 00Gamma-Ray Moments Method Code System.
GASSAbstractC00080 I7090 00Monte Carlo Calculation of Self Shielding by Encapsulated Gamma-Ray Sources.
GBANISNAbstractC00628 IRISC 00One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering with the GroupBand Option.
GENP-2AbstractC00575 ALLMF 00Generalized Perturbation Theory Code System.
GES_MCAbstractC00742 PC586 00Gamma-electron Efficiency Simulator.
GGG-GPAbstractC00564 IBMPC 00Kernel Integration Code System - Multigroup Gamma-Ray Scattering Using the GP Buildup Factor.
GRASS-SSTAbstractP00489 MNYCP 00Code System to Predict Fission-Gas Release & Fuel Swelling.
GREAT-GRASSAbstractC00143 I3675 00Monte Carlo Radiation Transport Code Systems for Fallout Shielding.
HALLMARKAbstractD00005 I0360 00Discrete Ordinates and Monte Carlo Results of Neutron and Secondary Gamma-Ray Transport in Air-Over-Ground Geometry.
HAMAbstractC00267 U1108 00Monte Carlo Multigroup Neutron and Photon High Altitude Transport Code System.
HERMES-KFAAbstractC00687 MNYWS 00Monte Carlo Code System for High-Energy Radiation Transport Calculations.
HIMACAbstractM00001 MNYCP 02Experimental Data of Neutron Yields from Thick Targets Bombarded by 100 to 800 MeV / Nucleon Heavy Ions.
ICOMAbstractC00651 PC386 00Code System for Calculating Ion Track Condensed Collision Model.
IONMIGAbstractC00526 ALLMF 00Code System for Radionuclide Migration Calculations.
ITS6
FEDC
AbstractC00792 PCX86 00Integrated TIGER Series of Coupled Electron/Photon Monte Carlo Transport Codes System.
JDL-IMPORTANCEAbstractM00005 MNYCP 00Adjoint Function: Physical Basis of Variational & Perturbation Theory in Transport & Diffusion Problems.
JN-METD 2&1AbstractC00208 I0370 00Neutron Transport Code System with Isotropic Scattering, Bare Slabs and Homogeneous Slabs (JN Method 1), Multilayer Slabs (JN Method 2).
K009AbstractC00062 I7090 00Solid Angle Integration Charged Particle Penetration Code.
KAMCCOAbstractC00325 I0370 00Three-Dimensional Time Dependent Monte Carlo Code System for Fast Neutron Physics Problems.
KAP-VIAbstractC00094 U1108 00Kernel Integration Code System in Complex Geometry.
KERNELAbstractC00672 IBMPC 00Monte Carlo Code System for Electron (Positron) Dose Kernel Calculations.
KIMAbstractC00376 I3033 00A Two-Dimensional Monte Carlo Code System for Linear Neutron Transport Calculations.
LABAN-PELAbstractC00611 IMFPC 00A Two-Dimensional, Multigroup Diffusion, High-Order Response Matrix Code.
LAHET 2.8AbstractC00696 MFMWS 00Code System for High Energy Particle Transport Calculations.
LASERAbstractC00344 I0360 00A One-Dimensional, Neutron-Thermalization, Lattice-Cell Program Based on MUFT and THERMOS.
LEBCAbstractC00052 I7090 00Electron Bremsstrahlung Code.
LEPAbstractD00001 I0360 02Cascade and Evaporation Particle Results from Low-Energy Intranuclear Cascade Calculations.
LG-HAbstractC00087 I7090 00Ray Analysis Cylindrical Duct Kernel Code for Neutrons and Gamma Rays.
LPPCAbstractC00051 I7090 00Proton Penetration Code.
LPSCAbstractC00064 I7090 00Proton Penetration Code - Multilayer Slab Geometry.
LRSPCAbstractC00050 I7090 00Range and Stopping Power Calculator.
LSHINSEAbstractC00554 IBMPC 00Calculates Flux and Dose Rate from the Scattering of Radiation in Air.
LUIN-IIAbstractC00220 C6600 00Analytical Straight-Ahead Transport Code System-Calculation of Cosmic-Ray Spectra, Fluxes and Ionization in the Earth's Atmosphere.
MAGNAAbstractC00158 C3600 00Multi-Source Gamma-Ray Kernel Integration Code System.
MAPAbstractC00150 I3675 00Kernel Integration Code System in Complex Geometry with Special Application to Surface Sources Determined by Discrete Ordinates Calculations.
MCNP-DSP-EXE
810
AbstractC00699 MNYCP 01Monte Carlo N-Particle Transport Code System with Digital Signal Processing based on MCNP4A.
MCRTOFAbstractC00435 FM200 00Monte Carlo Code System for Calculation of Multiple Scattering of Neutrons in the Resonance Region.
MCRTOFAbstractC00435 I0360 00Monte Carlo Code System for Calculation of Multiple Scattering of Neutrons in the Resonance Region.
MECC-7AbstractC00156 I0360 00Medium-Energy Intranuclear Cascade Code System.
MERCURE 4-82AbstractC00142 I3033 00Three-Dimensional Code System for Integrating Multigroup Line-of-Sight Attenuation Kernels by Monte Carlo Techniques.
MEVDPAbstractC00157 C6600 00Primary Radiation Transport Code System - Complex Geometry - Computerized Anatomical Model Man.
MMCRAbstractC00441 FM200 00Multigroup Monte Carlo Neutron and Photon Transport Code.
MOMENT IAbstractC00188 U1108 00Moments Method Neutron Transport Code System.
MOMGEM-MOMDISAbstractC00085 I7090 00Moments Method Reconstruction of Scattered Gamma-Ray Distributions.
MONK 6.3
FEDC
AbstractC00393 I3033 00A General Purpose Monte Carlo Neutronics Code System.
MURLIAbstractC00378 DP011 00Integral Transport Theory Code System for Thermal Reactor Lattice Cell Calculation.
MVP-GMVP IIAbstractC00739 MNYCP 00General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations based on Continuous Energy and Multigroup Methods.
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
NEVEMORAbstractP00026 I3675 00Multigroup-Multiregion Calculation of Flux Spectra and Energy Deposition for Fast Neutrons.
NITRANAbstractC00582 FM380 00Neutron Transport Code System Based On Anisotropic Scattering.
NMTC/JAERI97AbstractC00694 SUN05 00Monte Carlo Nucleon Meson Transport Code System.
NMTC/JAMAbstractC00717 PC586 00High Energy Particle Transport Code System.
NRNAbstractC00054 C6600 00Multigroup Removal-Diffusion Code System for Planes, Cylinders and Spheres.
NUGAM 2&3 SSLABAbstractC00210 I0360 00Monte Carlo Prediction of Photon Transport Distributions.
O6RAbstractC00128 I3675 00A General-Purpose Monte Carlo Transport Code System.
OGREAbstractC00046 I3675 00A General-Purpose Monte Carlo Gamma-Ray Transport Code System.
OGRE-MINAbstractC00409 DGECL 00A General-Purpose Monte Carlo Gamma-Ray Transport Code System for Minicomputers.
OOSIIAbstractC00324 C0000 00Calculation 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 VIAbstractC00159 I3675 00Kernel Integration Code System - Attenuation of Fast Neutrons in Cylindrical Layers of Water and Dense Material.
PALLAS-1D(VII)AbstractC00380 FM380 00Multigroup Time-Independent Neutron Transport Code System for Plane or Spherical Geometry.
PELSHIEAbstractC00202 C0000 00General Purpose Kernel Integration Shielding Code System-Point and Extended Gamma-Ray Sources.
PELSHIE3AbstractC00202 IBMMF 00General Purpose Kernel Integration Shielding Code System-Point and Extended Gamma-Ray Sources.
PEPINAbstractC00285 I0360 00Methodology for Computing Concentrations, Activities, Gamma-Ray Spectra, and Residual Heat from Fission Products.
PHOEL-2AbstractC00327 I0360 00A Monte Carlo Calculation of Initial Energy of Photoelectrons and Compton Electrons Produced by Photons in Water.
PIPEAbstractC00219 I0360 00Numerical Gamma-Ray Transport Code System for Plane/Spherical Geometry.
PLACIDAbstractC00381 I0370 00Monte Carlo Simulation of Gamma Streaming Through Straight Cylindrical Ducts.
POWERAbstractP00069 C7600 00Source Distribution Input Data Generator for ANISN Code.
PTRANAbstractC00618 PC386 00Proton Monte Carlo Transport Program for the PC.
PUSHLDAbstractC00271 C0074 00Gamma-Ray Three-Dimensional Calculation of Dose Rates from Plutonium in Various Geometries.
QADAbstractC00048 I0360 00Kernel Integration Code System.
QAD-CGGP-AAbstractC00645 MNYCP 00Kernel Integration Code System.
QAD-P5AbstractC00048 C6400 00Kernel Integration Code System.
RAFFLE/2AbstractC00279 C0176 00A General Purpose Monte Carlo Code System for Neutron Transport with Mixed Zone Geometry Option.
RAFFLE/2 MOD 2AbstractC00279 I0360 00A General Purpose Monte Carlo Code System for Neutron Transport with Mixed Zone Geometry Option.
REBUS3/VARIANT8AbstractC00653 MNYWS 01Code System for Analysis of Fast Reactor Fuel Cycles.
REBUS-PC 1.4AbstractC00708 PC586 00Code System for Analysis of Research Reactor Fuel Cycles.
REDIFFUSIONAbstractC00347 I0360 00One-Dimensional Neutron Removal-Diffusion and Gamma-Ray Kernel Integration or Diffusion Theory Calculator.
S3AbstractC00322 C6600 00Kernel Integration Code System--Multigroup Gamma-Ray Scattering.
S3AbstractC00322 DVX11 00Kernel Integration Code System--Multigroup Gamma-Ray Scattering.
S3AbstractC00322 IBMPC 00Kernel Integration Code System--Multigroup Gamma-Ray Scattering.
SAM-CEPAbstractC00192 C6600 00Monte Carlo Code System Correlated to the Simultaneous Solution of Multiple, Perturbed, Time-Dependent Neutron Transport Problems in Complex Three-Dimensional Geometry.
SAMSYAbstractC00315 C0073 00A One-Dimensional Multilayer Multigroup Neutron Removal-Diffusion and Gamma-Ray Point Kernel Calculator.
SANDYLAbstractC00361 C0000 00A Monte Carlo Three-Dimensional Code System for Calculating Combined Photon-Electron Transport in Complex Systems.
SCAP-82AbstractC00418 C7600 00Single Scatter, Albedo Scatter, or Point Kernel Analysis Code System in Complex Geometry.
SHADOKAbstractC00216 C6600 00Transport Code Systems, P1 Scattering in Infinite Cylindrical and Spherical Geometries by Polynomial Approximation.
SHIELDAbstractC00667 MNYCP 01Monte-Carlo Code System to Simulate Interaction of High Energy Hadrons with Complex Macroscopic Targets.
SHREDIAbstractC00284 I0360 00Multigroup Two-Dimensional (x-y, r-o geometry) Neutron Removal-Diffusion (Spinney Method) Shielding Code System.
SKYIII-PCAbstractC00289 IBMPC 01Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air.
SKYSHINE-IIIAbstractC00289 D0VAX 00Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air.
SKYSHINE-KSUAbstractC00646 IBMPC 03Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air.
SNAP-3DAbstractC00434 MNYCP 01Multigroup Complex Geometry Neutron Diffusion Code System.
SNEXAbstractC00353 C0000 00A One-Dimensional Single Group Discrete Ordinates Transport Code System.
SNOWAbstractC00282 I0360 00Two-Dimensional Discrete Ordinates Multigroup Transport Code System in Plane and Cylindrical Geometry with Isotropic and Anisotropic Scattering.
SOURCES-4CAbstractC00661 MNYCP 04Code System for Calculating (alpha,n), Spontaneous Fission, and Delayed Neutron Sources and Spectra.
SPARAbstractC00228 C6600 00Calculation of Stopping Powers and Ranges for Muons, Charged Pions, Protons and Heavy Ions.
SPARAbstractC00228 I0360 00Calculation of Stopping Powers and Ranges for Muons, Charged Pions, Protons and Heavy Ions.
STERNOAbstractC00057 C0000 00Two Dimensional Gamma-Ray Heating Kernel Integration Code.
STRAGLAbstractC00201 C6600 00Calculation of Energy Loss Straggling of Heavy Charged Particles.
STRAINTAbstractC00259 I0360 00One-Dimensional Multigroup Neutron Transport Discrete Ordinates Code System.
STREAMAbstractC00321 C7600 00A Three-Dimensional Cylindrical-Geometry Monte Carlo Ray Tracing Code for Computing Light Transmission.
SURFAbstractC00102 I3675 00Conical and Plane Surface Single Scattering Code.
SUSD3DAbstractC00695 MNYCP 01Multi-Dimensional, Discrete-Ordinates Based Cross Section Sensitivity and Uncertainty Analysis Code System.
SWORD 7.0AbstractC00767 MNYCP 07SoftWare for Optimization of Radiation Detectors.
TART2022AbstractC00638 MNYCP 09Coupled Neutron-Photon, 3-D, Combinatorial Geometry, Time Dependent, Monte Carlo Transport Code System.
TASKAbstractC00184 I0360 00Generalized One-Dimensional Radiation Transport and Diffusion Kinetics Code System.
TDAAbstractC00180 MNYWS 01A Time-Dependent, Multigroup, One-Dimensional, Discrete Ordinates Transport Code System.
TDTAbstractC00256 I0360 00Generalized One-Dimensional Multigroup Time-Dependent Transport and Diffusion Kinetic Code System.
TDTORTAbstractC00709 MNYWS 00Time-Dependent, 3-D, Discrete Ordinates, Neutron Transport Code System.
TESSAbstractC00215 C3600 00Multigroup Discrete Ordinates Code System for Slab and Spherical Geometries.
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.
TIMOC-72AbstractC00144 I0370 00Monte Carlo Three-Dimensional Neutron Transport Code System.
TIMOC-ESPAbstractC00432 U1110 00System for Generating and Analyzing Time Dependent Radiation Transport Results by Monte Carlo.
TITAN 1.29AbstractC00759 PCX86 04A Three-Dimensional Deterministic Radiation Transport Code System.
TMMSAbstractC00246 I0360 00Gamma-Ray Penetration Shielding Code System, Transmission Matrix Method.
TP1AbstractC00465 I3033 00A Computer Code System for the Calculation of Reactivity and Kinetic Parameters by One-Dimensional Neutron Transport Perturbation Theory.
TPHEXAbstractC00421 C0173 00Transmission Probability Code System for Calculating Neutron Flux Distributions in Hexagonal Geometry.
TPHEXAbstractC00421 CYXMP 00Transmission Probability Code System for Calculating Neutron Flux Distributions in Hexagonal Geometry.
TPTRIAAbstractC00550 I3083 00A Computer Program for the Reactivity and Kinetic Parameters for Two-Dimensional Triangular Geometry by Transport Perturbation Theory.
TRANSHEXAbstractC00449 U1108 00Two-dimensional Multigroup Collision Probability Code System for Hexagonal Geometry.
TRANZITAbstractC00172 C7600 00Multigroup Time-Dependent Discrete Ordinates Radiation Transport Code System in (rho,z) Cylindrical Geometry.
TRAPPAbstractC00205 I3691 00Transport of Alpha Particles and Protons with all Nuclear Reaction Products Neglected.
TRD-3AbstractC00362 I3033 00Two-Dimensional Removal-Diffusion Neutron Shielding Code System.
TREEDEAbstractC00326 C0000 00Monte Carlo Neutron Transport Code System Based on the Track Rotation Estimator.
TRIDENTAbstractC00293 C7600 00Two-Dimensional Multigroup Discrete Ordinates Transport Code System-(x,y) and (r,z) Geometries.
TRIDENTAbstractC00293 I0360 00Two-Dimensional Multigroup Discrete Ordinates Transport Code System-(x,y) and (r,z) Geometries.
TRIDENT-CTRAbstractC00377 C0000 00Two-Dimensional x-y and r-z Geometry Multigroup Transport Code System for Large Toroidal Reactors.
TRIGONAbstractC00290 U1108 00Two-Dimensional Multigroup Diffusion Code System-Trigonal or Hexagonal Mesh.
TRIPLETAbstractC00230 C6600 00Two-Dimensional, Multigroup, Triangular Mesh, Planar Geometry, Explicit Discrete Ordinates Code System.
TRIPLETAbstractC00230 C7600 00Two-Dimensional, Multigroup, Triangular Mesh, Planar Geometry, Explicit Discrete Ordinates Code System.
TRIPLETAbstractC00230 I0360 00Two-Dimensional, Multigroup, Triangular Mesh, Planar Geometry, Explicit Discrete Ordinates Code System.
TRIPOLI-4 8.1
OECD
AbstractC00806 MNYCP 00Code System for Coupled Neutron, Photon, Electron, Positron, 3-D, Time Dependent, Monte-Carlo, Transport Calculations.
TRIPOSAbstractC00537 CY00I 00Monte Carlo Ion Transport Analysis Code.
TRISTANAbstractC00511 HM280 00Multigroup Three-Dimensional Direct Integration Method Radiation Transport Analysis Code System.
TRITACAbstractC00560 D8810 00A Three-Dimensional Transport Code For Eigenvalue Problems Using The Diffusion Synthetic Acceleration Method.
TWOTRAN-SPHEREAbstractC00129 C6600 00Multigroup Two-Dimensional Discrete Ordinates Transport Code System in Spherical Geometry.
UNIMUG3AbstractC00407 C0170 00Solves Multigroup Diffusion Equations in One-Dimensional Systems.
USRHYDAbstractC00197 I3675 00Electron and X-Ray Energy Deposition and Hydrodynamics Code System.
VCSAbstractC00262 I0360 00Coupled Discrete Ordinates-Adjoint Monte Carlo Calculation of Radiation Protection Factors in Vehicles.
VESTA 2.1.5-AURORA 1.0AbstractC00769 PCX86 01A Generic Monte Carlo Code and Depletion Module Interface.
VIM 5.1AbstractC00754 MNYWS 01Continuous Energy Neutron and Gamma-ray Transport Code System.
XPORT-PCAbstractC00559 IBMPC 00An Approximation For Black Body X-Ray Transport in Air.
XRAY_AACAbstractC00525 D0750 00X-ray Attenuation and Absorption Calculations.
XSDRNAbstractC00123 C0073 00Multigroup One-Dimensional Discrete Ordinates Spectral Averaging N Transport Code System.
XSDRNAbstractC00123 I0360 00Multigroup One-Dimensional Discrete Ordinates Spectral Averaging N Transport Code System.
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.