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Catalog of Programs in Category J

J. Gamma Heating and Shield Design

nea-1839 ACAB-2008, ACtivation ABacus Code
iaea1432 AL-SHIELDER, calculates shielding thickness of aluminum for any photon emitting radionuclide between 0.5 to 10 MeV
nea-1353 ALBEDO ALBEZ, Gamma and Neutron Attenuation in Air Ducts
psr-0315 AMPX-77, Modular System for Coupled Neutron-Gamma MultiGroup Cross-Sections from ENDF/B-5
ccc-0082 ANISN-E, 1-D Transport Program ANISN with Exponential Model
nea-0363 ANISN-FONTENAY, 1-D Planar, Spherical, Cylindrical Neutron Transport and Gamma Transport with Deep Penetration
ccc-0082 ANISN-JR, 1-D Transport Program ANISN with ZZ JSD Data and Flux Plot
ccc-0254 ANISN-ORNL, 1-D Neutron Transport & Gamma Transport in Slab, Cylindrical, Spherical Geometry with Anisotropic Scattering
ccc-0255 ANISN-W, 1-D Transport Calculation for Deep Penetration Problems
ccc-0514 ANISN/PC, MultiGroup 1-D Discrete Ordinates Transport with Anisotropic Scattering
ccc-0126 ASOP, Shield Calculation, 1-D, Discrete Ordinates Transport
nea-0949 BERMUDA, 1-D, 2-D, 3-D Neutron and Gamma Transport for Shielding
ccc-0117 BETA-2B, Time-Dependent Bremsstrahlung Transport, Electron Transport by Monte-Carlo Method
nea-0188 BIGGI-4T, Gamma Transport in Multi-Region Shield in Planar or Spherical Geometry
psr-0143 BREESE, Distribution Function for Program MORSE from Albedo Data
nea-0390 BRIGITTE, Dose Rate and Heat Source and Energy Flux for Self-Absorbing Rods
nea-1727 BULK-I, Radiation Shielding Tool for Proton Accelerator Facilities
nea-1771 BULK_C-12, N & photon effective dose rates from medium energy protons or carbon ions through concrete or concrete/iron
iaea1403 C-SHIELDER, Gamma shielding calculations of radionuclides emitting photons 0.5 to 10 MeV by different concretes
nea-1800 CAFDATS, Converter of Angular Fluxes of DORT, ANISN and TORT Systems
psr-0131 CARP-82, Multigroup Albedo Data using DOT Angular Flux Results
ccc-0024 CARSTEP, Particle Flux on Space Vehicle in Van Allen Zone
psr-0262 CASKCODES, Program CAPSIZE Scope KWIKDOSE for Shipping Cask Shielding
ccc-0544 CEPXS ONELD, 1-D Coupled Electron Photon MultiGroup System
ccc-0837 CEPXS, Coupled Electron-Photon Cross Section
ccc-0070 CHARGE-2/C, Flux and Dose Behind Shield from Electron, Proton, Heavy Particle Irradiation
ccc-0726 CNCSN 2009, One, Two- and Three-Dimensional Coupled Neutral and Charged Particle Sn Parallel Multi-Threaded Code System
ccc-0829 COG11.1, Multiparticle Monte Carlo Code System for Shielding and Criticality Use
nea-1126 COLLI-PTB, Neutron Fluence Spectra for 3-D Collimator System by Monte-Carlo
nea-0383 COSANI-2, Gamma Doses from SABINE Calculation, Activity from ANISN Flux Calculation
nea-0247 CYGAS, 3-D Gamma Flux in Axial or Cylindrical Shields from Cylindrical Source
nea-0494 CYLDOS, Dose Rate in Cylindrical Shield from Cylindrical Source
ccc-0547 DANTSYS3.0, 1-D, 2-D, 3-D MultiGroup Discrete Ordinate Method Transport
ccc-0366 DASH, Void Tracing Sn and Monte-Carlo Coupling Program with Angular Fluxes from DOT Program
nea-1603 DCHAIN-SP 2001, Code System for Analyzing Decay and Build-up Characteristics of Spallation Products
ccc-0520 DCTDOS, Neutron and Gamma Penetration in Composite Duct System
nea-0667 DIFFAX, Axial Streaming for Hexagonal Lattices in Gas Cooled FBR, Slab Geometry Diffusion
nea-0625 DINE, Neutron Flux, Neutron Dose Rate in Multi-Region Slab Reactor Shield by Removal Diffusion
nea-0391 DLS, 2-D Diffusion with Line-of-Sight Method for Cavities
psr-0155 DOGS, Flux Plots of Radiation Transport Program Using DISSPLA
psr-0064 DOMINO, Coupling of Discrete Ordinate Program DOT with Monte-Carlo Program MORSE
ccc-0650 DOORS, 1-,2-,3-dimensional discrete-ordinates system for deep-penetration neutron and photon transport
ccc-0543 DORT, 1-D 2-D Discrete Ordinate Neutron and Photon Transport with Deep Penetration
ccc-0532 DORT-PC, 2-D Discrete Ordinates Transport System
nea-1711 DORTDAT2, Input-Making Support System for a Two-Dimensional SN Code, DORT
ccc-0276 DOT-3.5, 2-D Neutron Transport, Gamma Transport Program DOT with New Space-Scaling
ccc-0320 DOT-4.2, 2-D Neutron Transport, Gamma Transport with Space Dependent Mesh and Quadrature
psr-0251 DSNQUAD, Angular Quadrature Weights and Cosines for ANISN
nea-1671 DUCT-III, Design Code for Duct-Streaming Radiations
ccc-0453 DUST, Albedo Monte-Carlo Simulation of Neutron Streaming in Multilegged Square Concrete Ducts
nea-1813 EASYQAD 2.0, Visualization for Gamma and Neutron Shielding Calculations
nea-0969 EDMULT-6.4, Electron Depth Dose Distribution in Multilayer Slab Absorbers
ccc-0331 EGS4, Electron Photon Shower Simulation by Monte-Carlo
ccc-0119 ELBA, Bremsstrahlung Dose from Isotropic Electron Flux on Plane Al Shield
ccc-0301 ELPHO, Muon, Electron, Positron Generator from Pions by Monte-Carlo with HETC Collision Data
nea-1683 ERANOS 2.3, Modular code and data system for fast reactor neutronics analyses
ccc-0107 ETRAN, Electron Transport and Gamma Transport with Secondary Radiation in Slab by Monte-Carlo
psr-0617 F-SCORE, F-Score Nuclide ID Scoring Applications
nesc9578 FACET, Radiation View Factor with Shadowing
ccc-0351 FALSTF, Neutron Flux and Gamma Flux Detector Response Outside Cylindrical Shields
iaea1438 FE-SHIELDER, shielding thickness of Iron for any photon emitting radionuclide between 0.5 and 10 MeV
nea-0566 FEM-RZ, 2-D MultiGroup Neutron Transport in R-Z Geometry, Eigenvalue and Fixed Source Problems
nea-1833 FLUKA2011.2X.4, Monte Carlo general purpose tool for calculations of particle transport and interactions with matter
nea-0596 FOCUS, Neutron Transport System for Complex Geometry Reactor Core and Shielding Problems by Monte-Carlo
iaea1388 FOTELP-2014, Photons, Electrons and Positrons Transport in 3D by Monte Carlo Techniques
nea-1846 FSKY4C, Gamma Ray Skyshine Analysis Code
ccc-0494 G33-GP, Multigroup Gamma Scattering Using Geometric Progression Buildup Factors
nea-1175 GAMFIL, Photon Production Cross-Sections in ENDF/B Format
ccc-0042 GAMLEG-JR, MultiGroup Gamma Cross-Sections, Energy Absorption Coefficient Generator for Transport Calculation
nea-0268 GAMMONE, Multi-Region Shield Gamma Penetration from Various Geometries Source by Monte-Carlo
nea-0584 GFX/GAMP1, Above-Ground Radiation Field from Terrestrial K, U, Th Gamma Emitters
nea-1690 GRTUNCL-3D/R-THETA-Z, Code to Calculate Semi Analytic First Collision Source and Uncollided Flux in an R-theta-Z grid
ccc-0721 GRTUNCL3D, Code to Calculate Semi Analytic First Collision Source and Uncollided Flux (X, Y, Z)
ccc-0276 GRUNCLE, 1st Collision Source Calculation for Program DOT
ccc-0697 GUI2QAD, Graphical Interface for QAD-CGPIC, Point Kernel for Shielding Calculations
nea-1265 HERMES-KFA, High-Energy Radiation Transport by Monte-Carlo
ccc-0651 ICOM, Ion Radiation Transport Calculation for Shielding and Dosimetry
ccc-0636 ISO-PC, X-Ray, Gamma-Bremsstrahlung Dose-Rates
ccc-0079 ISOSHLD, Decay Gamma Dose, Bremsstrahlung Dose Behind Shield, Fission Products Source Strength
ccc-0467 ITS, TIGER System of Coupled Electron Photon Transport by Monte-Carlo
ccc-0696 LAHET 2.8, Code System for High Energy Particle Transport Calculations
psr-0020 LAPHAN0, P0 Gamma Production Matrices from ENDF/B
nea-0124 LGH, Gamma Streaming and Neutron Streaming for Duct
ccc-0064 LPSC, Protons and Neutron Flux, Spectra Behind Slab Shield from Protons Irradiation
nea-1306 LSHINSE, Air Scattering Neutron and Gamma Doserates for Complex Shielding Geometry
ccc-0220 LUIN-II, Cosmic Ray Cascade Generator and Particle Fluxes
nea-1047 MANYCASK, Radiation Dose Rate Around Many Casks
nea-1307 MARMER, Point-Kernel Shielding Calculation with Nuclide Concentrations from ORIGEN-S
nea-1643 MCB1C, Monte-Carlo Continuous Energy Burnup Code
nea-1733 MCNP4B-GN, Monte Carlo Code System for (gamma,n) production and transport in high-Z materials
ests1678 MCSLTT, Monte Carlo Simulation of Light Transport in Tissue
nea-1166 MCVIEW, 3-D Radiation View Factor by Monte-Carlo Method
nea-0351 MERCURE, 3-D Gamma Heating and Gamma Dose Rate and Fast Flux by Monte-Carlo
nea-0194 MERCURE-3, Gamma Attenuation by Line-of-Flight in 3-D Heterogeneous Geometry
nea-1747 MONTE-CARLO-WS-2005, Proceedings of Monte Carlo Criticality Calculations & TRIPOLI-IV Workshops 2005
ccc-0127 MORSE, MultiGroup Neutron Transport and Gamma Transport for Complex Geometry Shields by Monte-Carlo
ccc-0431 MORSE-C, Neutron Transport, Gamma Transport for Criticality Calculation by Monte-Carlo Method
ccc-0474 MORSE-CGA, Monte-Carlo Neutron and Gamma MultiGroup Transport with Array Geometry
nea-1181 MORSE-DD, Monte-Carlo Neutron Transport with Combinatorial Geometry Using DDL Cross-Sections Library
ccc-0127 MORSE-E, Program MORSE with Uniform Source for Various Geometry
ccc-0588 MORSE-EMP, Monte-Carlo Neutron and Gamma MultiGroup Transport with Array Geometry, for PC
nea-1673 MVP/GMVP V.3, MC Codes for Neutron & Photon Transport Calc. based on Continuous Energy and Multigroup Methods
ccc-0164 NAC, Neutron Activation Analysis and Isotope Inventory
ccc-0462 NCRP49, X-Ray Shielding for Radiographic and Fluoroscopic Diagnostic Units
nea-0125 NRN, Removal-Diffusion for Squares and Cylindrical Geometry with Energy Transfer Matrix
ccc-0046 OGRE, Monte-Carlo System for Gamma Transport Problems
psr-0275 ORMONTE, Uncertainty Analysis for User-Developed System Models
nea-1008 PALLAS-1D(VII), Direct Integration of Transport Equation in 1-D Planar and Spherical Geometry
nea-0702 PALLAS-2DY, 2-D Neutron Transport, Gamma Transport with Anisotropic Scattering for Fixed Source
ccc-0842 PARTISN 8.29, Time-Dependent, Parallel Neutral Particle Transport Code System
nea-1238 PASC-1, Petten AMPX-II/SCALE-3 Code System for Reactor Neutronics Calculation
iaea0855 PELSHIE, Dose Rates from Gamma Source by Point-Kernel Integration
nea-1525 PENELOPE2014, A Code System for Monte-Carlo Simulation of Electron and Photon Transport
nea-1886 PENGEOM, tools for handling complex quadric geometries in Monte Carlo simulations of radiation transport
nea-1339 PEPIN, Methodology for Computing Concentrations, Activities, Gamma-Ray Spectra, and Residual Heat from Fission Products.
nea-1857 PHITS-2.88, Particle and Heavy Ion Transport code System
ccc-0160 PICA, Photon-Induced Medium-Range Nuclear Cascade Analysis by Monte-Carlo
psr-0238 PICTURE, 2-D Slices Through 3-D CG of MORSE, QAD-CG
nea-0416 PIPE, 1-D Gamma Transport for Slab, Spherical Shields with Compton Scattering Calculation
iaea1172 PKI, Gamma Radiation Reactor Shielding Calculation by Point-Kernel Method
ccc-0381 PLACID, Gamma Streaming in Cylindrical Duct Shields by Monte-Carlo
ccc-0618 PTRAN, Proton Transport for 50 to 250 MeV by Monte-Carlo
ccc-0595 PUTZ, Point-Kernel 3-D Gamma Shielding
nea-1679 PVIS-4, Pressure vessel irradiation, source preparation
ccc-0493 QAD-CGGP, Fast Neutron and Gamma Penetration in Shields with Combinatorial Geometry
ccc-0645 QAD-CGGP-A, Fast Neutron, Gamma Penetration in Shields with Combinatorial Geometry
ccc-0396 QADMOD-G, Point-Kernel Gamma-Ray Shielding Program
ccc-0617 QBF, Radiation Dose Distribution Around Spent Fuel Shipping Casks
nea-0467 RADHEAT, Transport, Heat Generator, Radiation Damage Cross-Sections in Reactor and Shield
ccc-0083 RAID, Gamma, Neutron Scattering into Cylindrical or Multibend Duct
nea-0519 REDIFFUSION, 1-D Neutron Removal-Diffusion and Gamma Point-Kernel Calculation for Shielding
psr-0482 REMIT5.1, Radiation exposure monitoring and information transmittal system
nea-0598 RSYST, Modular System for Reactor Core and Shielding Problems
nea-0402 SABINE-3, Neutron Penetration and Gamma Penetration in Reactor Shield for Planar, Spherical, Cylindrical Geometry
nea-1884 SACALC-ELLIPSOID, Calculates the average solid angle subtended by a ellipsoid solid or surface
nea-1688 SACALC3, Calculates the average solid angle subtended by a volume
ccc-0187 SAM-CE, Time-Dependent 3-D Neutron Transport, Gamma Transport in Complex Geometry by Monte-Carlo
iaea0837 SAMSY, Neutron and Gamma Dose Rates and Heat Source for Multilayer Shields
ccc-0361 SANDYL, 3-D Time-Dependent and Space-Dependent Gamma Electron Cascade Transport by Monte-Carlo
ccc-0834 SCALE 6.2.3, A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design
ccc-0418 SCAP-82, Single Scattering, Albedo Scattering, Point-Kernel Analysis in Complex Geometry
psr-0210 SCOPE, Shipping Cask Optimization and Parametric Evaluation
ccc-0729 SERA-1C1, Simulation environment for radiotherapy applications
iaea1287 SHIELD, Monte-Carlo Code for Simulating Interaction of High Energy Hadrons with Complex Macroscopic Targets
ccc-0379 SHIELDOSE, Doses from Electron and Proton Irradiation in Space Vehicle Al Shields
nea-0466 SHREDI, Neutron Flux and Neutron Activation in 2-D Shields by Removal Diffusion
ccc-0289 SKYSHINE, Dose Rate Outside Concrete Steel Building from 6 MeV Gamma by Monte-Carlo
nea-1046 SMART, Radiation Dose Rates on Cask Surface
ccc-0120 SPACETRAN, Radiation Leakage from Cylinder with ANISN Flux Calculation
ccc-0228 SPAR, High-Energy Muon, Pion, Heavy Ion Stopping-Powers and Ranges
ccc-0148 SPARES, Program System for Space Radiation Environment and Shielding System Evaluation
nea-0468 SPARK, Time-Dependent 1-D, 2-D, 3-D Diffusion with Heat Transfer and Feedback
psr-0263 SPECTER-ANL, Neutron Damage for Material Irradiation
ccc-0460 SPOT1, Gamma-Ray Dose Rate from Cylindrical Source Volume
nea-0919 SRIM-2008, Stopping Power and Range of Ions in Matter
iaea1382 SRNA-2K5, Proton Transport Using 3-D by Monte Carlo Techniques
psr-0330 STARCODES, Stopping Power and Ranges for Electrons, Protons, He
iaea0970 STOPOW, Stopping Power of Fast Ions in Matter
ccc-0067 STORM, Radiation Hazard of Solar Flares for Space Vehicles
psr-0282 SUPERDAN-PC, Dancoff Factor for Spherical, Cylindrical, Slab Geometry
iaea1437 SUPERMC, Super Monte Carlo simulation program for nuclear and radiation process
ccc-0248 SWAN-PPL, Fusion Reactor 1-D Particle Transport Optimization
ccc-0638 TART2016, 3D Coupled Neutron-Photon Combinatorial Geometry, Time Dependent, Monte Carlo Transport Code
nea-0619 TIMOC-ESP, Time-Dependent Response Function by Monte-Carlo with Interface to Program TIMOC-72
ccc-0759 TITAN 1.29, A Three-Dimensional Deterministic Radiation Transport Code System
ccc-0543 TORT, 2-D 3-D Discrete Ordinate Neutron and Photon Transport with Deep Penetration
nea-0668 TRD-3, In-Core and Out-Core Neutron Flux, Gamma Flux by 2-D Removal Diffusion in Cylindrical Geometry
nea-1716 TRIPOLI-4 version 8.1, 3D general purpose continuous energy Monte Carlo Transport code
nea-1878 TRIPOLI-4 version 9S, Coupled Neutron, Photon, Electron, Positron 3-D, Time Dependent Monte-Carlo Transport Calculation
ccc-0537 TRIPOS, Monte Carlo Ion Transport Analysis Code
nea-1086 TRISTAN, 3-D fixed source radiation transport
ccc-0195 TWOTRAN-GG-FC, General Geometry 2-D Transport with 1st Collision Source Calculation
ccc-0195 TWOTRAN-GG-VW, General Geometry 2-D Transport, Variable-Weight Diamond Difference
iaea1434 U-SHIELDER, Estimates Shielding Thickness of Depleted Uranium for Photons from 0.5 to 10 MeV
psr-0281 URR, Cross-Sections, Selfshielding for Fertile and Fissile Isotopes in Unresolved Region
ccc-0262 VCS, Radiation Protection Factors in Vehicles by Monte-Carlo
nea-1856 VESTA 2.1.5, Monte Carlo depletion interface code and AURORA 1.0.0, Depletion analysis tool
ccc-0754 VIM 5.1, Steady-State 3-D Neutron Transport Using ENDF/B or Multigroup Cross Sections
iaea1417 W-SHIELDER, calculates shielding thickness of water for photon emitting radionuclide between 0.5 to 10 MeV
ccc-0525 XRAY-AAC, X-Ray Attenuation and Absorption
nea-1251 ZYLIND, Gamma Penetration for Cylindrical Source and Shield Geometry
iaea0870 ZZ L26P3S34, 26-Group Constants Library of 34 Materials for Neutron Shielding Calculations
nea-1740 ZZ MATJEF22.BOLIB, JEF-2.2 Multigr Coupled (199n + 42gamma) X-Section Lib. in MATXS Fmt for Nuclear Fission Applications
nea-1847 ZZ MATJEFF31.BOLIB, JEFF-3.1 Multigr Coupled(199n + 42gamma) X-Section MATXS Fmt for Nuclear Fission Applications
iaea1217 ZZ N-SPECT/DET-RESP, Neutron Spectra and Detector Responses for Radiation Protection
dlc-0136 ZZ PHOTX, Photon Interaction Cross-Section Library for 100 Elements
dlc-0256 ZZ VIP-MAN, Computational Phantom
dlc-0184 ZZ VITAMIN-B6, Fine-Group Cross-Section Library from ENDF/B-VI.3 for Radiation Transport
dlc-0245 ZZ VITAMINB7/BUGLEB7, Broad-Grp, Fine-Grp, Coupled N/Gamma Cross-Sec Lib derived from ENDF/B-VII.0 Nuclear Data
nea-1870 ZZ VITENDF70.BOLIB, ENDF/B-VII.0 Multi-Grp Coupled (199n +42gamma) AMPX Fmt for Nuclear Fission Applications
nea-1699 ZZ VITJEF22.BOLIB, JEF-2.2 Multigr Coupled (199n + 42gamma) X-Section Lib. in AMPX Fmt for Nuclear Fission Applications
nea-1801 ZZ VITJEFF31.BOLIB,JEFF-3.1 Multigr Coupled (199n + 42gamma) X-Section Lib. in AMPX Fmt for Nuclear Fission Applications
nea-1869 ZZ VITJEFF311.BOLIB, JEFF-3.1.1 Multi-Group Coupled (199n + 42gamma) X-Sec Lib in AMPX Fmt for Nuclear Fission Applic.
nea-1891 ZZ VITJEFF32.BOLIB, JEFF-3.2 Multi-Grp Coupled (199n+ 42gamma) X-Sec. Lib. In AMPX Fmt for Nuclear Fission Applications