| Packages with Keyword: GAMMA-RAY |
| Package Name | Abstract | RSICC Tapelist | Title |
| ACDOS3 | Abstract | C00442 C7600 00 | Calculation of Activities and Dose Rates Produced by Neutron Activation. |
| ACFA | Abstract | C00478 I3033 00 | A Versatile Activation Code for Coolant and Structural Materials. |
| ACOH | Abstract | C00191 I3675 00 | Aerojet COHORT Monte Carlo Code System. |
| ACRA-II | Abstract | C00213 I0360 00 | Kernel Integration Code System for Estimation of Radiation Doses Caused by a Hypothetical Reactor Accident. |
| ACRA-TRIT | Abstract | C00283 I0360 00 | The Tritium Version of ACRA-II, Estimation of Radiation Doses Caused by a Hypothetical Reactor Accident. |
| ADJMOM | Abstract | C00212 I3675 00 | Adjoint Moments Method Gamma-Ray Transport Code System. |
| ADO | Abstract | C00189 I3675 00 | Aerojet Discrete Ordinates Calculational System. |
| AIRDIF | Abstract | C00360 C6600 00 | A Two-Dimensional Atmospheric Radiation Diffusion Code. |
| AIRSCAT | Abstract | C00341 DP010 00 | Calculation of Dose Rate for Gamma-Rays Scattered in Air. |
| AIRTRANS | Abstract | C00110 I3675 00 | Monte Carlo Time and Energy-Dependent Three-Dimensional Radiation Transport Code. |
| AKERN | Abstract | C00190 C0000 00 | Aerojet Point Kernel Integration Calculational System. |
| AKERN | Abstract | C00190 U1108 00 | Aerojet Point Kernel Integration Calculational System. |
| ALARA 2.7.8 | Abstract | C00723 MNYCP 00 | Code System for Analytic and Laplacian Adaptive Radioactivity Analysis. |
| ALBEDO/ALBEZ | Abstract | C00555 IBMPC 00 | Calculates Attenuation of Radiation in Single and Double Bends. |
| ALBEMO | Abstract | C00268 C6600 00 | Albedo Monte Carlo Code System. |
| ALGAM-97 | Abstract | C00152 I3675 00 | Monte Carlo Estimation of Internal Dose from Gamma-Ray Sources in a Phantom Man. |
| AMC | Abstract | C00090 I3675 00 | Monte Carlo Albedo Code for Neutron and Capture Gamma-Ray Distributions in Rectangular Concrete Ducts. |
| ANIPLO D50 | Abstract | P00213 I0360 00 | A Digital Computer Program for Plotting Results from Calculations with the Sn Computer Program ANISN. |
| 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. |
| ARC | Abstract | C00224 C6600 00 | Aircraft Radiation Transport Code System, Crew Dose Calculation. |
| ARMYL-G | Abstract | C00297 U1106 00 | Calculation of Transmission Factors for Gamma Rays from Nuclear Explosions. |
| ASFIT-VARI | Abstract | C00336 H0000 00 | Gamma-Ray Transport Code System for One-Dimensional Finite Systems. |
| ASFIT-VARI | Abstract | C00336 IBMPC 00 | Gamma-Ray Transport Code System for One-Dimensional Finite Systems. |
| ASOP | Abstract | C00126 IRISC 00 | Multigroup One-Dimensional Discrete Ordinates Transport Code System for Shield Optimization. |
| AUS98 | Abstract | C00519 MNYWS 01 | Modular System for Neutronics Calculations of Fission Reactors, Fusion Blankets, and Other Systems. |
| BERMUDA | Abstract | C00616 FV260 03 | Discrete Ordinates Code System for Shielding Analysis for Use with Fusion and Fission Reactors. |
| BETA II | Abstract | C00117 C6600 00 | Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry. |
| BETA II | Abstract | C00117 I0360 00 | Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry. |
| BIGGI | Abstract | C00066 I3675 00 | Numerical Gamma-Ray Transport Code for Plane or Spherical Multilayer Geometry. |
| BIGGI | Abstract | C00066 U1108 00 | Numerical Gamma-Ray Transport Code for Plane or Spherical Multilayer Geometry. |
| BIGGI-4T | Abstract | C00780 I0360 00 | Gamma Transport in Multi-Region Shield in Planar or Spherical Geometry. |
| 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. |
| BOT3P-5.3 | Abstract | P00530 MNYCP 02 | Code System for 2D and 3D Mesh Generation and Graphical Display of Geometry and Results for Radiation Transport Codes. |
| BREMRAD | Abstract | C00031 I7090 00 | External and Internal Bremsstrahlung Calculation Code. |
| BUSH | Abstract | C00333 I0360 00 | A Code to Calculate Radiation Doses Inside Buildings from Routine Releases of Radionuclides to the Atmosphere. |
| BUTTERCUP | Abstract | C00779 MNYCP 00 | A Dual-Layer Photon Buildup Factor Code. |
| CAFDATS | Abstract | P00549 MNYCP 00 | Converter of Angular Fluxes of DORT, ANISN and TORT Systems. |
| CALKUX | Abstract | C00594 IBMPC 00 | Code System to Calculate Exposure Transmission of Medical X-ray Beams Through Barrier Materials. |
| CARL 2.3 | Abstract | C00743 PC586 01 | Code System to Calculate Radiotoxicity, Activity, Dose and Decay Power Calculations for Spent Fuel. |
| CASCADE | Abstract | C00176 C6600 00 | Monte Carlo Simulation of the Transport of High Energy Electrons and Photons in Matter. |
| CASCADE | Abstract | C00176 I0360 00 | Monte Carlo Simulation of the Transport of High Energy Electrons and Photons in Matter. |
| CAVEAT | Abstract | C00169 I3675 00 | General Purpose Monte Carlo Time-Dependent Radiation Transport Code in Complex Geometry. |
| CDR | Abstract | C00182 C6600 00 | A Constant Dose Range Code System, Using the LANL-NWEF Neutron-Gamma-Ray Air Flux Tape. |
| CDR | Abstract | C00182 I0360 00 | A Constant Dose Range Code System, Using the LANL-NWEF Neutron-Gamma-Ray Air Flux Tape. |
| 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. |
| CLOUD-M | Abstract | C00032 I3565 00 | Gamma-Ray Dose Rate from a Radioactive Cloud-Kernel Integration Code. |
| CNCSN 2009 | Abstract | C00726 PCX86 01 | One, Two- and Three-Dimensional Coupled Neutral and Charged Particle SN Parallel Multi-Threaded Code System. |
| COG11.1 | Abstract | C00829 MNYCP 00 | Multiparticle Monte Carlo Code System for Shielding and Criticality Use. |
| COHORT-II | Abstract | C00198 I7094 00 | General Purpose Monte Carlo Radiation Transport Code System. |
| COMNUC3B | Abstract | P00302 CYXMP 00 | A Compound Nucleus Analysis Program. |
| COMRADEX4 | Abstract | C00332 I0360 00 | Evaluator of Potential Radiological Doses in the Near (< 10 km) Environment of Radioactive Release. |
| CONDOS-II | Abstract | C00416 I0360 00 | Code for Estimating Radiation Doses from Radionuclide-Containing Consumer Products. |
| CONSTRIP V | Abstract | C00139 I3675 00 | Vertical Barrier-Finite Source Plane Gamma-Ray Penetration Code System. |
| CRESO | Abstract | P00184 I3081 00 | Resonance Data-Handling Code System. |
| CYGAS | Abstract | C00317 I3033 00 | A Gamma-Ray Attenuation Code System for Large Gamma-Ray Sources Shielded by Coaxial Cylinders. |
| CYLDOS | Abstract | C00389 I0360 00 | A Cylindrical Geometry Gamma-Ray Flux Attenuation Code System. |
| DANTSYS 3.0 | Abstract | C00547 MFMWS 01 | One-, Two-, and Three-Dimensional, Multigroup, Discrete-Ordinates Transport Code System. |
| DAVE | Abstract | C00166 I3675 00 | Monte Carlo Gamma-Ray Transport Code System in One-Dimensional Spherical Geometry. |
| DCHAIN-SP2001 | Abstract | C00712 MNYWS 01 | Code System for Analyzing Decay and Build-up Characteristics of Spallation Products. |
| DCTDOS | Abstract | C00520 IBMPC 00 | Neutron and Gamma-Ray Penetration in Composite Duct Systems. |
| DDXCODES | Abstract | C00583 FM380 00 | One-, Two- and Three-Dimensional Transport Codes Using Multigroup Double-Differential Form Cross Sections. |
| DINT-YAEC | Abstract | C00306 ALLMF 00 | Evaluator of I1 and I2 Integrals as Used in Long-Term External Gamma-Ray Doses from Routine Atmospheric Releases. |
| DIPHO | Abstract | C00140 I3675 00 | Monte Carlo Gamma-Ray Code System-Infinite Medium, Mono-energetic and Isotropic Point Source. |
| DISDOS | Abstract | C00170 I0360 00 | Calculation of Dose Distribution in Human Phantoms Irradiated by External Photon Sources. |
| DISKTRAN | Abstract | C00533 CYXMP 00 | Dose Calculations at Detectors from the End of a Cylinder Using DOT IV Scalar Flux Data. |
| DISKTRAN | Abstract | C00533 I3033 00 | Dose Calculations at Detectors from the End of a Cylinder Using DOT IV Scalar Flux Data. |
| 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. |
| DOSE 1 | Abstract | C00165 I3675 00 | Gamma-Radiation Dosimetry for Arbitrary Source and Target Geometry. |
| DOSFACTER II | Abstract | C00400 D0750 00 | Calculation of Dose-Rate Conversion Factors for Exposure to Photons and Electrons. |
| DOSFACTER II | Abstract | C00400 I0360 00 | Calculation of Dose-Rate Conversion Factors for Exposure to Photons and Electrons. |
| DOSFACTER-DOE | Abstract | C00536 I3033 00 | Calculation of Dose-Rate Conversion Factors for Exposure to Photons and Electrons. |
| DOT 3.5 | Abstract | C00276 I0360 00 | Two-Dimensional Discrete Ordinates Radiation Transport Code System. |
| DTF-INDIA | Abstract | C00458 I0370 00 | Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering. |
| DTF-IV | Abstract | C00042 C6600 00 | Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering. |
| DTF-IV MODIFIED | Abstract | C00042 I0370 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. |
| EASY-QAD 2.0.1 | Abstract | C00744 PC586 02 | A Visualization Code System for Gamma and Neutron Shielding Calculations. |
| EGAD | Abstract | C00206 I0360 00 | Calculation of Dose from External Gamma-Ray Emitters. |
| EGS4 | Abstract | C00331 MNYCP 00 | Monte Carlo Simulation of the Coupled Transport of Electrons and Photons. |
| ELGATL | Abstract | C00295 C6600 00 | Calculation of Energy Spectra from Coupled Electron-Photon Slowing Down. |
| ELPHO | Abstract | C00301 I0360 00 | Three-Dimensional Monte Carlo Electromagnetic Transport Code System. |
| EMPIRE-II | Abstract | P00497 PC586 01 | Comprehensive Nuclear Model Code, Nucleons, Ions Induced Cross-Sections. |
| ENEDEP | Abstract | C00227 GE400 00 | Energy Deposition Code System for GE 265 Time-Sharing System. |
| ESDORA | Abstract | C00183 U1108 00 | Fission Product Inventory and Gamma-Ray Dose Rate from a Radioactive Cloud System. |
| ETRAN | Abstract | C00107 I0360 00 | Monte Carlo Code System for Electron and Photon Through Extended Media. |
| FANTOM | Abstract | C00375 BESM6 00 | Monte Carlo Calculation of the Response of an External Detector to a Photon Source in the Lungs of a Heterogeneous Phantom. |
| FASTER III | Abstract | C00168 U1108 00 | Monte Carlo Neutron and Photon Transport Code System in Complex Geometries. |
| FASTER-III | Abstract | C00168 I3675 00 | Monte Carlo Neutron and Photon Transport Code System in Complex Geometries. |
| FDKR | Abstract | C00541 I4381 00 | Radioactivity and Dose Rate Calculation Code for Fission, Fusion and Hybrid Reactors. |
| FISSP & CLOUD | Abstract | C00163 MNYCP 01 | Fission Product Inventory, Release, Transport and Dose Calculation. |
| FOTELP-2014 | Abstract | C00581 MNYCP 04 | Monte Carlo Simulation of Photons, Electrons and Positrons Transport. |
| FPIC | Abstract | C00028 I3675 00 | Fission Product Inventory Code. |
| 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. |
| FSKY4C | Abstract | C00771 PCX86 00 | Gamma Ray Skyshine Analysis Code. |
| G3-6ED | Abstract | C00075 C6600 00 | Kernel Integration Code System - Multigroup Gamma Ray Scattering. |
| G3-6ED | Abstract | C00075 I3033 00 | Kernel Integration Code System - Multigroup Gamma Ray Scattering. |
| GADJET | Abstract | C00115 C6600 00 | Monte Carlo Gamma-Ray Adjoint Energy Transport Code in Complex Three-Dimensional Geometry. |
| GAMMOM | Abstract | C00135 ALLMF 00 | Gamma-Ray Moments Method Code System. |
| GAMMOM-I | Abstract | C00226 I0360 00 | Gamma-Ray Moments Method Code System. |
| GASS | Abstract | C00080 I7090 00 | Monte Carlo Calculation of Self Shielding by Encapsulated Gamma-Ray Sources. |
| GBANISN | Abstract | C00628 IRISC 00 | One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering with the GroupBand Option. |
| GES_MC | Abstract | C00742 PC586 00 | Gamma-electron Efficiency Simulator. |
| GFX-GAMIX | Abstract | C00397 I3033 00 | A Spherical Harmonics Code System for Evaluation of Terrestrial Gamma-Radiation Fields. |
| GGG-GP | Abstract | C00564 IBMPC 00 | Kernel Integration Code System - Multigroup Gamma-Ray Scattering Using the GP Buildup Factor. |
| GRACE-II | Abstract | C00026 I3675 00 | Gamma Ray Kernel Integration Dose Rate and Heating Code-Cylinders and Spheres. |
| GREAT-GRASS | Abstract | C00143 I3675 00 | Monte Carlo Radiation Transport Code Systems for Fallout Shielding. |
| GUI2QAD-3D | Abstract | C00697 PC586 01 | A Graphical User Interface for QAD-CGPIC, a Point Kernal Code for Neutron and Gamma-Ray Shielding Calculations in Complex Geometry. |
| HAM | Abstract | C00267 U1108 00 | Monte Carlo Multigroup Neutron and Photon High Altitude Transport Code System. |
| IDC | Abstract | C00384 I0360 00 | ICRP Dosimetric Calculational System. |
| INAP | Abstract | C00235 U1108 00 | Improved Neutron Activation Prediction Code Systems. |
| INDOS | Abstract | C00236 DP010 00 | Conversational Computer Code Systems to Implement ICRP-10-10A Models for Estimation of Internal Radiation Dose to Man. |
| INDRA | Abstract | C00303 I0360 00 | A Modular System for Calculating the Neutronics and Photonics Characteristics of a Fusion Reactor Blanket. |
| INREM/EXREM | Abstract | C00185 I0360 00 | Beta and Gamma Radiation Environmental Dose Code Systems. |
| INTRUDE-ANS | Abstract | C00539 D8810 00 | A Repository Intrusion Risk Evaluation Code. |
| INVENT | Abstract | C00540 D8810 00 | A Radionuclide Inventory and Hazard Index Code. |
| ISO-PC 2.1 | Abstract | C00636 IBMPC 01 | Kernel Integration Code System for General Purpose Isotope Shielding Analyses. |
ITS6
FEDC | Abstract | C00792 PCX86 00 | Integrated TIGER Series of Coupled Electron/Photon Monte Carlo Transport Codes System. |
| KAP-VI | Abstract | C00094 U1108 00 | Kernel Integration Code System in Complex Geometry. |
| KDLIBE | Abstract | C00124 I3675 00 | Kernel-Diffusion Shielding Analysis System. |
| KERNEL | Abstract | C00672 IBMPC 00 | Monte Carlo Code System for Electron (Positron) Dose Kernel Calculations. |
| KUX | Abstract | C00515 ALLCP 00 | Medical X-Ray Shielding Calculation. |
| LG-H | Abstract | C00087 I7090 00 | Ray Analysis Cylindrical Duct Kernel Code for Neutrons and Gamma Rays. |
| LGH-G | Abstract | C00239 I0360 00 | Calculation of Gamma Radiation through Partially Shielded Gaps (Buildup Factor Method in Taylors Approximation). |
| LINEDOSE | Abstract | C00468 IBMPC 00 | A Line Source Shielding Code for Personal Computers. |
| LIONS | Abstract | C00247 I0360 00 | Calculation of Fission Product Inventory, Gamma-Ray Dose Rates and Gamma-Ray Doses by Kernel Integration. |
| LSHINSE | Abstract | C00554 IBMPC 00 | Calculates Flux and Dose Rate from the Scattering of Radiation in Air. |
| MAGIK | Abstract | C00359 I0360 00 | A Monte Carlo Code System for Computing Induced Residual Activation Dose Rates. |
| MAGNA | Abstract | C00158 C3600 00 | Multi-Source Gamma-Ray Kernel Integration Code System. |
| MAP | Abstract | C00150 I3675 00 | Kernel Integration Code System in Complex Geometry with Special Application to Surface Sources Determined by Discrete Ordinates Calculations. |
| MARMER | Abstract | C00579 D8350 00 | A Flexible Point-Kernel Shielding Code System. |
| MARMER | Abstract | C00579 PC486 00 | A Flexible Point-Kernel Shielding Code System. |
MCNP6.3-EXE
810 | Abstract | C00870 MNYCP 01 | Monte Carlo N-Particle Transport Code System. |
MCNP-DSP-EXE
810 | Abstract | C00699 MNYCP 01 | Monte Carlo N-Particle Transport Code System with Digital Signal Processing based on MCNP4A. |
MCNPX-POLIMI-EXE
810 | Abstract | C00791 MNYCP 01 | Monte Carlo N-Particle Transport Code System To Simulate Time-Analysis Quantities. |
| MERCURE 4-82 | Abstract | C00142 I3033 00 | Three-Dimensional Code System for Integrating Multigroup Line-of-Sight Attenuation Kernels by Monte Carlo Techniques. |
| MMCR | Abstract | C00441 FM200 00 | Multigroup Monte Carlo Neutron and Photon Transport Code. |
| MOMGEM-MOMDIS | Abstract | C00085 I7090 00 | Moments Method Reconstruction of Scattered Gamma-Ray Distributions. |
| 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. |
| MORSEC-SP2 | Abstract | P00142 H6000 00 | 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-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. |
MRIPP 1.0
810 | Abstract | C00655 PC386 00 | Magnetic Resonance Image Phantom Code System to Calibrate in vivo Measurement Systems. |
| MVP-GMVP II | Abstract | C00739 MNYCP 00 | General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations based on Continuous Energy and Multigroup Methods. |
| NUCCON | Abstract | C00439 S7800 00 | A Code System for Calculation of Time-Dependent Nuclide Concentrations, Activity, Gamma-Ray Dose Rate and Biological Hazard Potential of Fusion Reactor Materials Due to Neutron Irradiation. |
| NUCWIZ | Abstract | P00616 PCX86 00 | NucWiz |
| NUGAM 2&3 SSLAB | Abstract | C00210 I0360 00 | Monte Carlo Prediction of Photon Transport Distributions. |
| OGRE | Abstract | C00046 I3675 00 | A General-Purpose Monte Carlo Gamma-Ray Transport Code System. |
| OGRE-MIN | Abstract | C00409 DGECL 00 | A General-Purpose Monte Carlo Gamma-Ray Transport Code System for Minicomputers. |
| 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. |
| ORIP_XXI | Abstract | C00731 PC586 02 | Computer Programs for Isotope Transmutation Simulations. |
| PABLM | Abstract | C00402 U1100 00 | Calculation of Accumulated Radiation Doses to Man from Radionuclides Found in Food Products and from Radionuclides in the Environment. |
| PALLAS-2DCY-FX | Abstract | C00391 FM380 00 | Multigroup Time-Independent Neutron Transport Code System for Plane or Spherical Geometry. |
| PELSHIE | Abstract | C00202 C0000 00 | General Purpose Kernel Integration Shielding Code System-Point and Extended Gamma-Ray Sources. |
| PELSHIE3 | Abstract | C00202 IBMMF 00 | General Purpose Kernel Integration Shielding Code System-Point and Extended Gamma-Ray Sources. |
| PENELOPE2014 | Abstract | C00782 PCX86 01 | Code System for Monte Carlo Simulation of Electron and Photon Transport. |
| PENELOPE-MPI | Abstract | C00713 IBMSP 00 | Code System for Monte Carlo Simulation of Electron and Photon Transport. |
| PF-COMP | Abstract | C00106 C3600 00 | Building Fallout Radiation Protection Factor Analysis. |
| PHOEL-2 | Abstract | C00327 I0360 00 | A Monte Carlo Calculation of Initial Energy of Photoelectrons and Compton Electrons Produced by Photons in Water. |
| PIGG | Abstract | C00138 C3600 00 | A Multigroup One-Dimensional P-1 Radiation Transport Code System. |
| PIPE | Abstract | C00219 I0360 00 | Numerical Gamma-Ray Transport Code System for Plane/Spherical Geometry. |
| PKI | Abstract | C00573 C0830 00 | A Point Kernel Integration Code For Radiation Shielding of Loop System. |
| PLUDOS | Abstract | C00313 I0360 00 | Calculator of Ground Level External Gamma-Ray Dose from a Radioactive Plume. |
| PLUMEX | Abstract | C00356 I0360 00 | A Computer Program to Evaluate External Exposures to a Gaussian Plume by Point Kernel Integration. |
| PRESTO | Abstract | C00549 D8810 00 | Point Kernel Calculation for Complex and Time-Dependent Gamma-Ray Source Spectra. |
| PROCIV | Abstract | C00488 U1110 00 | A Code System for Calculating the Protection Factors Against Radioactive Fallout for Apartment Buildings. |
| PUSHLD | Abstract | C00271 C0074 00 | Gamma-Ray Three-Dimensional Calculation of Dose Rates from Plutonium in Various Geometries. |
| PUTZ 2.1 | Abstract | C00595 IBMPC 00 | A Point-Kernel Photon Shielding Code. |
| QAD | Abstract | C00048 I0360 00 | Kernel Integration Code System. |
| QAD-BSA | Abstract | C00346 C0000 00 | Kernel Integration Code System. |
| QAD-CGGP-A | Abstract | C00645 MNYCP 00 | Kernel Integration Code System. |
| QADMOD-G | Abstract | C00396 I3033 00 | Point Kernel Gamma-Ray Shielding Code With Geometric Progression Buildup Factors. |
| QADMOD-GP | Abstract | C00565 IBMPC 00 | Point Kernel Gamma-Ray Shielding Code With Geometric Progression Buildup Factors. |
| QAD-P5 | Abstract | C00048 C6400 00 | Kernel Integration Code System. |
| QAD-QC | Abstract | C00401 C0000 00 | Kernel Integration Code System. |
| QAD-QC | Abstract | C00401 I0360 00 | Kernel Integration Code System. |
| QAD-UE | Abstract | C00448 H6000 00 | Kernel Integration Code System. |
| QBSHIELD | Abstract | C00599 IBMPC 00 | Spherical Shield Design for Gamma-Ray Sources Using the Buildup Factor Method. |
| RADHEAT-V4 | Abstract | C00300 FM380 00 | A Code System To Generate Multigroup Constants and Analyze Radiation Transport for Shielding Safety Evaluation. |
| RADOS | Abstract | C00088 I3675 00 | Gamma-Ray Dose Estimation from Cloud of Radioactive Gases by Kernel Integration. |
| RAID | Abstract | C00083 I7090 00 | Monte Carlo Multibend Duct Shielding Code. |
| REACTORSHIELDING-NMS | Abstract | M00014 MNYCP 00 | REACTORSHIELDING-NMS, Reactor Shielding for Nuclear Engineers. |
| 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. |
| REDIFFUSION | Abstract | C00347 I0360 00 | One-Dimensional Neutron Removal-Diffusion and Gamma-Ray Kernel Integration or Diffusion Theory Calculator. |
| RSYST | Abstract | C00269 I0360 00 | Integrated Modular Code System for Shielding and Reactor Physics Calculations. |
| 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. |
| 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. |
| SAMSY | Abstract | C00315 C0073 00 | A One-Dimensional Multilayer Multigroup Neutron Removal-Diffusion and Gamma-Ray Point Kernel Calculator. |
| SANDYL | Abstract | C00361 C0000 00 | A Monte Carlo Three-Dimensional Code System for Calculating Combined Photon-Electron Transport in Complex Systems. |
| SAP N-G | Abstract | C00092 I7094 00 | Neutron and Gamma-Ray Albedo Model Scatter Shield Analysis Code System. |
| SCAP-82 | Abstract | C00418 C7600 00 | Single Scatter, Albedo Scatter, or Point Kernel Analysis Code System in Complex Geometry. |
| SDC | Abstract | C00060 I3675 00 | Kernel Integration Shield Design Code for Radioactive Fuel Handling Facilities. |
| SENSIT | Abstract | C00405 C7600 00 | One-Dimensional, Multigroup Cross Section and Design Sensitivity and Uncertainty Analysis Code System - Generalized Perturbation Theory. |
| SERA-1C1 | Abstract | C00729 MNYCP 01 | Simulation Environment for Radiotherapy Applications. |
| SFAK | Abstract | C00437 I3033 00 | Code System for Calculation of the Self-Absorption of Unscattered Gamma Radiation from Fuel Assemblies. |
| SHARDA | Abstract | C00521 C0740 00 | Sample Heat, Activity, Reactivity, and Dose Analysis for Safety Analysis of Irradiations in a Research Reactor. |
| SKYIII-PC | Abstract | C00289 IBMPC 01 | Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air. |
| SKYSHINE-III | Abstract | C00289 D0VAX 00 | Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air. |
| SKYSHINE-KSU | Abstract | C00646 IBMPC 03 | Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air. |
| 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. |
| SMAUG-13 | Abstract | C00194 C6600 00 | Calculation of Neutron and Prompt Gamma-Ray Doses Resulting from an Atmospheric Nuclear Detonation. |
| SNAP-3D | Abstract | C00434 MNYCP 01 | Multigroup Complex Geometry Neutron Diffusion Code System. |
| SNEX | Abstract | C00353 C0000 00 | A One-Dimensional Single Group Discrete Ordinates Transport 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. |
| SOSUM | Abstract | C00109 I3675 00 | Multigroup Beta and Gamma-Ray Energy Sources from Activities. |
| SPACETRAN 1;2;3 | Abstract | C00120 I3675 00 | Dose Calculations at Detectors at Various Distances from the Surface of a Cylinder. |
| SPOT1 | Abstract | C00460 I3033 00 | Shielding Problem Code Based on Methods of Ono and Tsuruo. |
| STERNO | Abstract | C00057 C0000 00 | Two Dimensional Gamma-Ray Heating Kernel Integration Code. |
| SUBDOSA-II | Abstract | C00270 U1100 00 | Calculation of External Gamma-Ray and Beta-Ray Doses from Accidental Atmospheric Releases of Radionuclides. |
| SURF | Abstract | C00102 I3675 00 | Conical and Plane Surface Single Scattering Code. |
| SWAN | Abstract | C00248 C0000 00 | Code System for Analysis and Optimization of Fusion Reactor Nucleonic Characteristics. |
| SWAN | Abstract | C00248 CY000 00 | Code System for Analysis and Optimization of Fusion Reactor Nucleonic Characteristics. |
| SWAN | Abstract | C00248 I0360 00 | Code System for Analysis and Optimization of Fusion Reactor Nucleonic Characteristics. |
| SWANLAKE | Abstract | C00204 C6600 00 | Cross Section Sensitivity Analysis Code System for One-Dimensional Discrete Ordinates Calculations. |
| SWANLAKE | Abstract | C00204 I3033 00 | Cross Section Sensitivity Analysis Code System for One-Dimensional Discrete Ordinates Calculations. |
| TALYS-1.2 | Abstract | P00548 PC586 01 | Nuclear Model Code System for Analysis and Prediction of Nuclear Reactions and Generation of Nuclear Data. |
| TART2022 | Abstract | C00638 MNYCP 09 | Coupled Neutron-Photon, 3-D, Combinatorial Geometry, Time Dependent, Monte Carlo Transport Code System. |
| TDA | Abstract | C00180 MNYWS 01 | A Time-Dependent, Multigroup, One-Dimensional, Discrete Ordinates Transport Code System. |
| TESS | Abstract | C00215 C3600 00 | Multigroup Discrete Ordinates Code System for Slab and Spherical Geometries. |
| TMMS | Abstract | C00246 I0360 00 | Gamma-Ray Penetration Shielding Code System, Transmission Matrix Method. |
| TRANZIT | Abstract | C00172 C7600 00 | Multigroup Time-Dependent Discrete Ordinates Radiation Transport Code System in (rho,z) Cylindrical Geometry. |
| TRD-3 | Abstract | C00362 I3033 00 | Two-Dimensional Removal-Diffusion Neutron Shielding Code System. |
| 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. |
| 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. |
| 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. |
| VCS | Abstract | C00262 I0360 00 | Coupled Discrete Ordinates-Adjoint Monte Carlo Calculation of Radiation Protection Factors in Vehicles. |
| VIEWCXS | Abstract | P00514 PC586 00 | Interactive Graphic User Interface to View Neutron and Gamma-Ray Interaction Cross Sections. |
| VIM 5.1 | Abstract | C00754 MNYWS 01 | Continuous Energy Neutron and Gamma-ray Transport Code System. |
| XPORT-PC | Abstract | C00559 IBMPC 00 | An Approximation For Black Body X-Ray Transport in Air. |
| XRAY_AAC | Abstract | C00525 D0750 00 | X-ray Attenuation and Absorption Calculations. |
| ZYLIND-PC | Abstract | C00557 IBMPC 00 | An Interactive Point Kernel Program For Photon Dose Rate Prediction of Cylindrical Source/Shield Arrangements. |