| Package Name |
Abstract |
RSICC Tapelist |
Title |
Click on Package Name to get detailed information.
Click on RSICC Tapelist to view list of files.
Note: RESTRICTIONS APPLY to SOME PACKAGES:
"USSO" -- U.S. DISTRIBUTION ONLY
"FEDC" -- For U.S. Government Contractors Only
"OECD" -- Restricted/See Abstract
"USUNV" -- US Universities Only
Go To Order Form
1DB-2DB-3DB
|
Abstract
|
C00741 PC586 00 |
One-Dimensional Diffusion Code System for Nuclear Reactor. |
3DDT
|
Abstract
|
C00605 C6600 00 |
Multigroup Diffusion Code System for Use in Fast Reactor Analysis. |
ACAB-2008
|
Abstract
|
C00758 MNYCP 00 |
ACtivation ABacus Inventory Code System for Nuclear Applications. |
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. |
ACRO
|
Abstract
|
C00354 I0360 00 |
Calculation of Organ Dose from Acute or Chronic Inhalation and Ingestion of Radionuclides. |
ACT-ARA
|
Abstract
|
C00372 CYXMP 00 |
Code System for the Calculation of Changes in Radiological Source Terms with Time. |
ADJMOM
|
Abstract
|
C00212 I3675 00 |
Adjoint Moments Method Gamma-Ray Transport Code System. |
ADO
|
Abstract
|
C00189 I3675 00 |
Aerojet Discrete Ordinates Calculational System. |
AIRBORNE
|
Abstract
|
C00263 I0360 00 |
Airborne Contaminants Dispersion Code. |
AIRDIF
|
Abstract
|
C00360 C6600 00 |
A Two-Dimensional Atmospheric Radiation Diffusion Code. |
AIRDOS-PC
|
Abstract
|
C00551 IBMPC 00 |
Clean Air Act Compliance Software for Personal Computers. See C00542/CAP-88. |
AIREM
|
Abstract
|
C00242 I3691 00 |
Calculation of Doses, Population Doses, and Ground Depositions Due to Atmospheric Emissions of Radionuclides. |
AIRGAMMA
|
Abstract
|
C00567 FM380 00 |
A Program For The Calculation Of External Exposure To Gamma Rays From A Radioactive Cloud. |
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. |
AISITE II
|
Abstract
|
C00286 I0360 00 |
Reactor Siting Code System. |
AKERN
|
Abstract
|
C00190 C0000 00 |
Aerojet Point Kernel Integration Calculational System. |
AKERN
|
Abstract
|
C00190 U1108 00 |
Aerojet Point Kernel Integration Calculational System. |
AKTIV
|
Abstract
|
C00339 I0360 00 |
An Evaluation of Activity, Afterheat and Biological Hazard Potential of Stainless Steel Structures in Fusion Reactor Blankets. |
ALARA 2.7.8
|
Abstract
|
C00723 MNYCP 00 |
Code System for Analytic and Laplacian Adaptive Radioactivity Analysis. |
ALBEMO
|
Abstract
|
C00268 C6600 00 |
Albedo Monte Carlo Code System. |
ALDOSE
|
Abstract
|
C00577 IBMPC 00 |
Dose Calculation for Alpha Disc Source. |
ALGAM-97
|
Abstract
|
C00152 I3675 00 |
Monte Carlo Estimation of Internal Dose from Gamma-Ray Sources in a Phantom Man. |
ALKASYS-PC
|
Abstract
|
C00558 IBMPC 00 |
A Computer Program For Studies of Rankine-Cycle Space Nuclear Power Systems. |
ALPHN
|
Abstract
|
C00612 IBMPC 00 |
Code System for Calculating (alpha,n) Neutron Production in Canisters of High-Level Waste. |
AMC
|
Abstract
|
C00090 I3675 00 |
Monte Carlo Albedo Code for Neutron and Capture Gamma-Ray Distributions in Rectangular Concrete Ducts. |
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. RSIC recommends CCC-650/DOORS3.2a for most applications. |
ANITA-2000
|
Abstract
|
C00693 MNYCP 00 |
Code System to Calculate Isotope Inventories from Neutron Irradiation for Fusion Applications. |
ANITA-4
|
Abstract
|
C00606 MNYCP 01 |
Analysis of Neutron Induced Transmutation and Activation. See ANITA-2000 (CCC-693). |
ANTE 2
|
Abstract
|
C00131 I3675 00 |
Adjoint Monte Carlo Time-Dependent Neutron Transport Code in Combinatorial Geometry. |
APARNA-II
|
Abstract
|
C00296 I0360 00 |
Integral Transport Theory Code System Based on Discrete Ordinate Representation in Space and Direction-Slab Geometry. |
APUD 3.0
|
Abstract
|
C00637 IBMPC 00 |
Code System for Analyzing, Predicting Consequences of, and Guiding the Response to Nuclear Emergencies. |
ARC
|
Abstract
|
C00224 C6600 00 |
Aircraft Radiation Transport Code System, Crew Dose Calculation. |
ARCON96
|
Abstract
|
C00664 IBMPC 00 |
Code System to Calculate Atmospheric Relative Concentrations in Building Wakes. |
AREAC
|
Abstract
|
C00438 I3033 00 |
Radiological Emission Analysis Code System. |
ARMYL-G
|
Abstract
|
C00297 U1106 00 |
Calculation of Transmission Factors for Gamma Rays from Nuclear Explosions. |
ARMYL-N
|
Abstract
|
C00298 U1106 00 |
Calculation of Transmission Factors for Neutrons from Nuclear Explosions. |
ARRRG
|
Abstract
|
C00404 U1100 00 |
Calculation of Radiation Dose to Man from Radionuclides in the Environment. |
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. |
ASTROS
|
Abstract
|
C00073 I7090 00 |
Calculation of Primary and Secondary Proton Dose Rates in Spheres and Slabs of Tissue. |
AT123D
|
Abstract
|
C00417 I0360 00 |
Analytical Transient One-, Two-, and Three-Dimensional Simulation of Waste Transport in an Aquifer System. |
ATM-TOX
|
Abstract
|
C00472 I3033 00 |
An Atmospheric Transport Model for Toxic Substances. |
ATTOW-KB
|
Abstract
|
C00132 I0370 00 |
Multigroup Two-Dimensional Removal-Diffusion (Spinney Method) Shielding Code System. |
AUS98
|
Abstract
|
C00519 MNYWS 01 |
Modular System for Neutronics Calculations of Fission Reactors, Fusion Blankets, and Other Systems. |
BALTORO
|
Abstract
|
C00479 C6600 00 |
Code for Coupling of Monte Carlo and Discrete Ordinates Radiation Transport Calculations. |
BCG
|
Abstract
|
C00578 C0170 00 |
A Code For Calculating Pointwise Neutron Spectra and Criticality in Fast Reactor Cells. |
BEBC
|
Abstract
|
C00077 I7090 00 |
Electron Bremsstrahlung Penetration Code for Space Vehicles. |
BED
|
Abstract
|
C00078 I7090 00 |
Electron Penetration Code for Space Vehicles. |
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. |
BETA-S 6
|
Abstract
|
C00657 MNYCP 01 |
Code System to Calculate Multigroup Beta-Ray Spectra. |
BIGGI
|
Abstract
|
C00066 I3675 00 |
Numerical Gamma-Ray Transport Code for Plane or Spherical Multilayer Geometry, Versions 3P &4T. |
BIGGI
|
Abstract
|
C00066 U1108 00 |
Numerical Gamma-Ray Transport Code for Plane or Spherical Multilayer Geometry, Versions 3P and 4T. |
BISON 1.5
|
Abstract
|
C00464 HM200 00 |
A One-dimensional Discrete Ordinate Transport and Burnup Calculation Code. (Burnup of Isotopes and One-Dimensional Transport). |
BISON-C
|
Abstract
|
C00659 MNYWS 00 |
One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System. |
BLT-FEMWATER
USSO
|
Abstract
|
C00633 PC386 00 |
Code System to Solve for Release and Transport of Contaminants through Saturated/Unsaturated Media. |
BMC-MG
|
Abstract
|
C00291 C6600 00 |
Multigroup Monte Carlo Neutron and Gamma-Ray Shielding Code System for Plutonium. |
BOLD VENTURE IV
|
Abstract
|
C00459 I3033 00 |
A Reactor Analysis Code System. |
BPPC
|
Abstract
|
C00076 I7090 00 |
Proton Penetration Codes for Space Vehicles. |
BREMRAD
|
Abstract
|
C00031 I7090 00 |
External and Internal Bremsstrahlung Calculation Code. |
BRHGAM
|
Abstract
|
C00350 I3033 00 |
Monte Carlo Estimation of Absorbed Dose from X-Ray Sources in Phantom Man. |
BULK_C-12
|
Abstract
|
C00738 PC586 00 |
Code System to Estimate Neutron and Photon Effective Dose Rates from Medium Energy Protons or Carbon Ions Through Concrete or Concrete/Iron. |
BURP-2
|
Abstract
|
C00237 C6600 00 |
Calculation of Buildup and Decay of Radioactive Fission Products. |
BUSH
|
Abstract
|
C00333 I0360 00 |
A Code to Calculate Radiation Doses Inside Buildings from Routine Releases of Radionuclides to the Atmosphere. |
BWR-LTAS
|
Abstract
|
C00485 I3033 01 |
Code System for Boiling Water Reactor Long-Term Accident Simulation. |
CAAC
|
Abstract
|
C00476 D0VAX 00 |
Code System for Implementation of Atmospheric Dispersion Assessment Required by the Clear Air Act. See CCC-542/CAP-88. |
CAAC
|
Abstract
|
C00476 I3033 00 |
Code System for Implementation of Atmospheric Dispersion Assessment Required by the Clear Air Act. See CCC-542/CAP-88. |
CACA-2
|
Abstract
|
C00302 I0360 00 |
Heavy Isotope and Fission-Product Concentration Calculation Code System. |
CALKUX
|
Abstract
|
C00594 IBMPC 00 |
Code System to Calculate Exposure Transmission of Medical X-ray Beams Through Barrier Materials. |
CALOR95
|
Abstract
|
C00610 MNYWS 00 |
Monte Carlo Code System for Design and Analysis of Calorimeter Systems, Spallation Neutron Source (SNS) Target Systems, etc. |
CAMERA
|
Abstract
|
C00240 C0074 00 |
Radiation Transport Analysis Code System and the Computerized Man (CAM) Model. |
CAMERA
|
Abstract
|
C00240 IBMPC 01 |
Radiation Transport Analysis Code System and the Computerized Man (CAM) Model. |
CAP-88
|
Abstract
|
C00542 D0VAX 00 |
Clean Air Act Assessment Package. |
CAP-88
|
Abstract
|
C00542 I3090 00 |
Clean Air Act Assessment Package. |
CAP88-PC
|
Abstract
|
C00542 IBMPC 01 |
Clean Air Act Assessment Package. |
CAPS-2
|
Abstract
|
C00074 CDCMF 00 |
Analysis of Structures for Fallout Radiation Shielding. |
CARL-2.2
|
Abstract
|
C00743 PC586 00 |
Code System to Calculate Radiotoxicity, Activity, Dose and Decay Power Calculations for Spent Fuel. |
CARMEN SYSTEM
|
Abstract
|
C00487 U1110 00 |
A Code System for Neutronics PWR Calculation by Diffusion Theory with Space-Dependent Feedback Effects. |
CARNAC
|
Abstract
|
C00238 I3691 00 |
Calculation of Flux and Neutron Spectra in the Case of Criticality Accident. |
CARSTEP
|
Abstract
|
C00024 I7090 00 |
Trajectory and Environment Code-Electron and Proton Fluxes Impinging on Spacecraft in Orbit. |
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. |
CASIM
|
Abstract
|
C00265 I0360 00 |
Monte Carlo Simulation of Transport of Hadron Cascades in Bulk 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/ONELD 1.0
|
Abstract
|
C00544 MNYCP 02 |
One-Dimensional Coupled Electron-Photon Multigroup Discrete Ordinates Code System. |
CHAINS-PC
|
Abstract
|
C00604 IBMPC 00 |
Code System to Compute Atom Density of Members of a Single Decay Chain. |
CHAINT-MC
|
Abstract
|
C00584 CYXMP 00 |
A Two-Dimensional Model for the Analysis of Contaminant Transport in a Fractured Porous Medium. |
CHARGE II
|
Abstract
|
C00070 C6500 00 |
Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres. |
CHARGE II
|
Abstract
|
C00070 I3675 00 |
Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres. |
CHARGE-PC
|
Abstract
|
C00070 IBMPC 00 |
Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres. |
CHNSED
|
Abstract
|
C00671 I0360 00 |
Code System to Model Sediment & Containment Transport. |
CINDER 1.05
|
Abstract
|
C00755 PC586 00 |
Code System for Actinide Transmutation Calculations |
CITATION-LDI 2
|
Abstract
|
C00643 PC386 02 |
Nuclear Reactor Core Analysis Code System. |
CLOUD-M
|
Abstract
|
C00032 I3565 00 |
Gamma-Ray Dose Rate from a Radioactive Cloud-Kernel Integration Code. |
CNCSN
|
Abstract
|
C00726 PC586 00 |
One, Two- and Three-Dimensional Coupled Neutral and Charged Particle SN Code System. |
COG 10
|
Abstract
|
C00724 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. |
COLLIMATOR
|
Abstract
|
C00136 I7090 00 |
Monte Carlo Calculation of the Spectrum of Gamma Radiation from a Collimated Co-60 Source. |
COLUMN2
|
Abstract
|
C00534 ALLMF 00 |
Calculation of Effects of Physicochemical Processes on Migration. |
COMPRASH
|
Abstract
|
C00072 I3675 00 |
Spinney Removal-Diffusion Shielding Code. |
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. |
CRAC2
|
Abstract
|
C00419 C0000 00 |
Code System for Calculating Reactor Accident Consequences. |
CRAC2
|
Abstract
|
C00419 I3033 00 |
Code System for Calculating Reactor Accident Consequences. |
CRRIS
|
Abstract
|
C00518 I3033 00 |
Computerized Radiological Risk Investigation System for Assessing Doses and Health Risks from Atmospheric Releases of Radionuclides. |
CRRIS
|
Abstract
|
C00518 PC586 00 |
Computerized Radiological Risk Investigation System for Assessing Doses and Health Risks from Atmospheric Releases of Radionuclides. |
CRYSTAL BALL
|
Abstract
|
C00233 C6600 00 |
Code System for Determining Neutron Spectra from Activation Measurements. |
CRYSTAL BALL
|
Abstract
|
C00233 I0360 00 |
Code System for Determining Neutron Spectra from Activation Measurements. |
CYGAS
|
Abstract
|
C00317 I3033 00 |
A Gamma-Ray Attenuation Code System for Large Gamma-Ray Sources Shielded by Coaxial Cylinders. |
CYGNUS-C SPHERE
|
Abstract
|
C00232 I0360 00 |
Monte Carlo Neutron Transport Code System in Spherical Geometry. |
CYLDOS
|
Abstract
|
C00389 I0360 00 |
A Cylindrical Geometry Gamma-Ray Flux Attenuation Code System. |
DACRIN
|
Abstract
|
C00273 U1100 00 |
Airborne Radionuclide Organ Dose Calculational System. |
DASH-FP
|
Abstract
|
C00366 C0000 00 |
A One-Dimensional Analytic-Numerical Solution to the Problem of Multicomponent Time-Dependent Diffusion of Fission Products. |
DAVE
|
Abstract
|
C00166 I3675 00 |
Monte Carlo Gamma-Ray Transport Code System in One-Dimensional Spherical Geometry. |
DCHAIN 1.3
|
Abstract
|
C00640 MNYCP 01 |
Code System for Radioactive Decay and Reaction Chain Calculations. |
DCHAIN-SP2001
|
Abstract
|
C00712 MNYWS 01 |
Code System for Analyzing Decay and Build-up Characteristics of Spallation Products. |
DCHAIN2
|
Abstract
|
C00370 PC486 00 |
A Code System for Calculation of Transmutation of Nuclides. |
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. |
DEIS
|
Abstract
|
C00455 C6600 00 |
Draft Environmental Impact Statement on Licensing Requirements for Land Disposal of Radioactive Waste. |
DELFIC-TES
|
Abstract
|
C00257 I3033 00 |
Multigroup Kernel Integration Code System for Calculating Gamma-Ray Exposure from a Radioactive Airborne Cloud. |
DELFIC-TES
|
Abstract
|
C00257 U1108 00 |
Multigroup Kernel Integration Code System for Calculating Gamma-Ray Exposure from a Radioactive Airborne Cloud. |
DEMON & DEMON R
|
Abstract
|
C00181 I3675 00 |
Demonstration Monte Carlo Code System in Slab Geometry. |
DIAMANT2
|
Abstract
|
C00414 PC386 00 |
Multigroup Two-Dimensional Discrete Ordinates Transport Code System for Triangular Geometry, Release 2.0. |
DIF3D8-VARIANT8
|
Abstract
|
C00649 MFMWS 01 |
Code System Using Variational Nodal Methods and Finite Difference Methods to Solve Neutron Diffusion and Transport Problems. |
DIFMOD
|
Abstract
|
C00572 I3083 00 |
A Computer Program To Calculate The Leaching of Radionuclides and the Corrosion of Cemented Waste Forms in Water or Brine. |
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. |
DISPERS
|
Abstract
|
C00454 MNYCP 00 |
Mathematical Models for Dispersion of Radionuclides |
DKR
|
Abstract
|
C00323 CY000 00 |
A Radioactivity and Dose Rate Calculation Code System for Fusion Reactors. |
DLS
|
Abstract
|
C00264 C6600 00 |
Two-Dimensional Shielding Calculational System with Diffusion Theory and Line-of-Sight Method. |
DOORS 3.2A
|
Abstract
|
C00650 MFMWS 04 |
One, Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System. |
DOPEX
|
Abstract
|
C00177 I3675 00 |
Laminated Shield Weight Optimization Code System-Steepest Descent Calculational Model. |
DOPEX
|
Abstract
|
C00177 U1108 00 |
Laminated Shield Weight Optimization Code System-Steepest Descent Calculational Model. |
DOPEX-1D2C
|
Abstract
|
C00214 I0360 00 |
A One-Dimensional, Two-Constraint Radiation Shield Optimization Code System. |
DOSE 1
|
Abstract
|
C00165 I3675 00 |
Gamma-Radiation Dosimetry for Arbitrary Source and Target Geometry. |
DOSE-SGTR
|
Abstract
|
C00624 IBMPC 00 |
Code System to Calculate the Integrated Iodine Release to the Environment During a Steam Generator Tube Rupture in a PWR. |
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. |
DPCT
|
Abstract
|
C00580 CYXMP 00 |
A Deterministic-Probabilistic Model For Contaminant Transport. |
DRAGON3.05D
|
Abstract
|
C00647 MNYWS 03 |
Lattice Cell Code System. |
DTF-69
|
Abstract
|
C00130 C6600 00 |
One-Dimensional Multigroup Photon Transport Discrete Ordinates 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 |
One-Dimensional Multigroup Neutron Transport Discrete Ordinates Code System. |
DTK
|
Abstract
|
C00223 I3675 00 |
One-Dimensional Multigroup Neutron Transport Code System. |
DUST
|
Abstract
|
C00453 I3033 00 |
Albedo Monte Carlo Simulation of Neutron Streaming Through Multilegged Ducts. |
DUST-BNL
|
Abstract
|
C00634 PC386 00 |
Disposal Unit Source Term by One-Dimensional, Transient, Finite-Difference, Subsurface Release and Transport of Contaminants. |
DWNWND
|
Abstract
|
C00383 DP010 00 |
Interactive Gaussian Plume Atmospheric Transport Model. |
E-DEP-1
|
Abstract
|
C00275 D0VAX 00 |
Heavy Ion Energy Deposition Code System. |
EASY-2005.1
|
Abstract
|
C00735 MNYCP 01 |
Inventory Code System for Neutron Activation Analysis. |
EASY-QAD 1.0
|
Abstract
|
C00744 PC586 00 |
Visualization Code System for Gamma and Neutron Shielding Calculations. |
EDMULT 6.4
|
Abstract
|
C00430 MNYCP 02 |
Evaluates Electron Depth-Dose Distributions in Multilayer Slab Absorbers. |
EDNA
|
Abstract
|
C00104 I7090 00 |
Electron Dose and Number Analysis Code by Kernel Integration. |
EDO
|
Abstract
|
C00489 U1110 00 |
A Code System in Fortran V for the Evaluation of Dose During Normal Operation of a Nuclear Power Plant. |
EFDOS
|
Abstract
|
C00411 I0360 00 |
Calculation of Effective Committed Dose Equivalents by Inhalation of Radioactive Materials Occurring in Routine Atmospheric Releases from Nuclear Fuel Cycle Facilities. |
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. |
ELBA
|
Abstract
|
C00119 I0360 00 |
Electron and Bremsstrahlung Dose Rate Code. |
ELF
|
Abstract
|
C00167 I0360 00 |
Monte Carlo Neutron Transport Code System for Cylinders and Spheres. |
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. |
ELTRAN
|
Abstract
|
C00155 C3600 00 |
One-Dimensional Monte Carlo Electron Transport Code System. |
EMERALD
|
Abstract
|
C00211 I0360 00 |
Calculation of Activity Releases and Potential Doses from a Pressurized Water Reactor Plant. |
EMERALD-NORMAL
|
Abstract
|
C00250 I0370 00 |
Calculation of Activity Releases and Potential Doses from the Normal Operation of a Pressurized Water Reactor Plant. |
ENEDEP
|
Abstract
|
C00227 GE400 00 |
Energy Deposition Code System for GE 265 Time-Sharing System. |
EPRI-CINDER
|
Abstract
|
C00309 C6600 00 |
General Point-Depletion and Fission Product Code System and Four-Group Fission Product Neutron Absorption Chain Data Library Generated from ENDF/B-IV for Thermal Reactors. |
ERANOS 2.0
OECD
|
Abstract
|
C00745 MNYWS 00 |
Modular Code and Data System for Fast Reactor Neutronics Analyses |
ERPEX
|
Abstract
|
C00305 C0073 00 |
Monte Carlo Distributions of Energetic Proton Ranges in Silicon. |
ESDORA
|
Abstract
|
C00183 U1108 00 |
Fission Product Inventory and Gamma-Ray Dose Rate from a Radioactive Cloud System. |
ESP
|
Abstract
|
C00193 I0360 00 |
General Purpose Monte Carlo Neutron Transport Code System. |
ETRAN
|
Abstract
|
C00107 I0360 00 |
Monte Carlo Code System for Electron and Photon Through Extended Media. |
EXPRESS
|
Abstract
|
C00622 MNYCP 00 |
Exact Preparedness Supporting System. |
EXTREME
|
Abstract
|
C00440 I3033 00 |
Two-Dimensional Discrete-Ordinates Code System with Exponential Expansion of Spatial Variables. |
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. |
FE3DGW
|
Abstract
|
C00531 D0780 00 |
Code System for Finite-Element, Three-Dimensional Ground-Water Flow Analysis. |
FEM-2D
|
Abstract
|
C00260 C6600 00 |
Two-Dimensional Diffusion Theory Code System Based on the Method of Finite Elements. |
FEMB
|
Abstract
|
C00340 B6700 00 |
A Two-Dimensional Diffusion Theory Finite Element Program. |
FEMRZ
|
Abstract
|
C00342 F2307 00 |
A Finite-Element Method Two-Dimensional Multigroup Neutron Transport Code System, (r,z) Geometry. |
FEMWASTE/FEMWATER
|
Abstract
|
C00451 C7600 00 |
A Finite-Element Model of Waste and Water Transport through Porous Saturated-Unsaturated Media. |
FEMWASTE/FEMWATER
|
Abstract
|
C00451 PC386 00 |
A Finite-Element Model of Waste and Water Transport through Porous Saturated-Unsaturated Media. |
FESH
|
Abstract
|
C00676 CDCMF 00 |
X-Y Multigroup Neutron Transport Code System. |
FEWA-FEMA
|
Abstract
|
C00477 I3033 00 |
A Finite Element Model of Water and Other Material through Aquifers. |
FINELM
|
Abstract
|
C00483 MFMWS 00 |
Multigroup Finite Element Diffusion Code System. |
FIPDIG
|
Abstract
|
C00251 I0360 00 |
One-Dimensional Time-Dependent Fission Product Diffusion Code System. |
FISP-6
|
Abstract
|
C00538 I3090 00 |
An Enhanced Code for the Evaluation of Fission Product Inventories and Decay Heat. |
FISPIN
|
Abstract
|
C00413 ICL00 00 |
Nuclide Inventory Calculation System. |
FISSP & CLOUD
|
Abstract
|
C00163 MNYCP 01 |
Fission Product Inventory, Release, Transport and Dose Calculation. |
FLUKA-TRANKA
|
Abstract
|
C00207 C6600 00 |
Three-Dimensional High-Energy Extranuclear Hadron Cascade Monte Carlo System for Cylindrical Backstop Geometries. |
FOCUS
|
Abstract
|
C00390 I3033 00 |
Adjoint Monte Carlo Neutron Transport Code System. |
FONTA
|
Abstract
|
C00423 S4044 00 |
Code System For Calculating Individual And Collective Doses From Reactor Accidents Using Pasquill's Plume Model. |
FOOD
|
Abstract
|
C00403 U1108 00 |
Calculation of Radiation Dose to Man from Radionuclides in the Environment. |
FORSS
|
Abstract
|
C00334 C0000 00 |
A Sensitivity and Uncertainty Analysis Code System. |
FORSS
|
Abstract
|
C00334 I0360 00 |
A Sensitivity and Uncertainty Analysis Code System. |
FOTELP-2K6
|
Abstract
|
C00581 MNYCP 03 |
Monte Carlo Simulation of Photons, Electrons and Positrons Transport. |
FPGAM
|
Abstract
|
C00386 F2307 00 |
Calculation of Fission-Product Gamma-Ray Spectra. |
FPIC
|
Abstract
|
C00028 I3675 00 |
Fission Product Inventory Code. |
FPIP
|
Abstract
|
C00162 C6600 00 |
Fission Product Inventory Code System. |
FPZD
|
Abstract
|
C00603 PC386 00 |
Code System for Multigroup Neutron Diffusion/Depletion Calculations. |
FRCRL2
|
Abstract
|
C00231 C6400 00 |
Calculation of Fission-Product Release in Reactor Accident Analyses. |
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. |
FURNACE
|
Abstract
|
C00615 C0740 00 |
Code System for Neutronic Calculations in Three Dimension Toroidal Geometry. |
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. |
G33-GP
|
Abstract
|
C00494 IBMPC 01 |
Kernel Integration Code System - Multigroup Gamma-Ray Scattering Using the GP Buildup Factor. |
GADJET
|
Abstract
|
C00115 C6600 00 |
Monte Carlo Gamma-Ray Adjoint Energy Transport Code in Complex Three-Dimensional Geometry. |
GALE BWR
|
Abstract
|
C00335 U1100 00 |
Boiling Water and Pressurized Water Reactors Gaseous and Liquid Effluents Radiological Assessment Code System. |
GALE PWR & BWR
|
Abstract
|
C00335 I3033 00 |
Boiling Water and Pressurized Water Reactors Gaseous and Liquid Effluents Radiological Assessment Code System. |
GALE86
|
Abstract
|
C00506 C0000 01 |
Calculation of Routine Radioactive Releases in Gaseous and Liquid Effluents from Boiling Water and Pressurized Water Reactors. |
GAMMOM
|
Abstract
|
C00135 ALLMF 00 |
Gamma-Ray Moments Method Codes--GRMM and SPENCER. |
GAMMOM-I
|
Abstract
|
C00226 I0360 00 |
Gamma-Ray Moments Method Code System. |
GANAPOL-ABNTT
|
Abstract
|
C00753 MNYCP 00 |
Analytical Benchmarks; Case Studies in Neutron Transport Theory. |
GASPAR
|
Abstract
|
C00463 I3033 01 |
Calculates Radiation Exposure to Man from Routine Air Releases of Nuclear Reactor Effluents. |
GASPAR II
|
Abstract
|
C00463 D0780 00 |
Calculates Radiation Exposure to Man from Routine Air Releases of Nuclear Reactor Effluents. |
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. |
GENII 2.06
|
Abstract
|
C00737 PC586 00 |
Environmental Radiation Dosimetry Software System. |
GENII-LIN 2.1
|
Abstract
|
C00728 PC586 01 |
GENII-LIN Multipurpose Health Physics Code System with a New Object-Oriented Interface, Release 2.0. |
GENP-2
|
Abstract
|
C00575 ALLMF 00 |
Generalized Perturbation Theory Code System. |
GES_MC
|
Abstract
|
C00742 PC586 00 |
Gamma-electron Efficiency Simulator, Version 3.1 |
GETOUT
|
Abstract
|
C00461 C0176 00 |
A Computer Code System for Predicting One-Dimensional Radionuclide Decay Chain Transport through Geologic Media. |
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. |
GNOMER
|
Abstract
|
C00625 MNYCP 01 |
Multigroup 3-Dimensional Neutron Diffusion Nodal Code System with Thermohydraulic Feedbacks. |
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. |
GRENADE
|
Abstract
|
C00516 C1787 00 |
Green's Function Nodal Algorithm for the Diffusion Equation. |
GRENADE
|
Abstract
|
C00516 D0780 00 |
Green's Function Nodal Algorithm for the Diffusion Equation. |
GRTUNCL3D
|
Abstract
|
C00721 MNYCP 01 |
Code to Calculate Semi-Analytic First Collision Source and Uncollided Flux. |
GUI2QAD-3D
|
Abstract
|
C00697 PC586 01 |
Point Kernel Code System for Neutron and Gamma-Ray Shielding Calculations in Complex Geometry, Including a Graphical User Interface. |
HABIT 1.1
|
Abstract
|
C00665 IBMPC 01 |
Code System for Evaluation of Control Room Habitability. |
HADOC
|
Abstract
|
C00452 U1100 00 |
Calculates External and Inhalation Doses from Acute Radionuclide Releases on the Hanford Site. |
HAM
|
Abstract
|
C00267 U1108 00 |
Monte Carlo Multigroup Neutron and Photon High Altitude Transport Code System. |
HARAD
|
Abstract
|
C00387 I0360 00 |
Calculation of Daughter Concentrations in Air Following the Atmospheric Release of a Parent Radionuclide. |
HERAD
|
Abstract
|
C00444 CY00I 00 |
Three-Dimensional Monte Carlo Computer Code System for Calculating Radiation Damage from Ion Beams. |
HERMES-KFA
|
Abstract
|
C00687 MNYWS 00 |
Monte Carlo Code System for High-Energy Radiation Transport Calculations. |
HEXAB-3D
|
Abstract
|
C00593 I0370 00 |
Three-Dimensional Few-Group Coarse Mesh Diffusion Code for Neutron Physics Calculation of Reactor Core in Hexagonal Geometry. |
HIC-1
|
Abstract
|
C00249 I0360 00 |
Monte Carlo Code System for Calculating Heavy Ion Reactions at Energies > 50 MeV/Nucleon. |
HORN
|
Abstract
|
C00568 I3083 00 |
A Computer Code To Analyze The Gas-Phase Transport of Fission Products In Reactor Cooling System Under Severe Accidents. |
HOTSPOT 2.05
|
Abstract
|
C00644 IBMPC 03 |
Health Physics Code System for Evaluating Accidents Involving Radioactive Materials. |
HYACINTH
|
Abstract
|
C00294 I0360 00 |
Fast Heavy Isotope Point Burnup and Decay Code System - Analytical Solution. |
ICOM
|
Abstract
|
C00651 PC386 00 |
Code System for Calculating Ion Track Condensed Collision Model. |
IDC
|
Abstract
|
C00384 I0360 00 |
ICRP Dosimetric Calculational System. |
IMPACTS-BRC2.1
|
Abstract
|
C00666 IBMPC 00 |
Code System for Analysis of Potential Radiological Impacts. |
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. |
INDOSE V2.1.1
|
Abstract
|
C00720 PC586 00 |
Internal Dosimetry Code System Using Biokinetics Models |
INDRA
|
Abstract
|
C00303 I0360 00 |
A Modular System for Calculating the Neutronics and Photonics Characteristics of a Fusion Reactor Blanket. |
INGDOS
|
Abstract
|
C00408 DP010 00 |
A Conversational Code System Designed to Implement NRC Reg-Guide 1.109 Models for Estimation of Annual Doses from Ingestion of Atmospherically Released Radionuclides in Foods. |
INREM II
|
Abstract
|
C00392 I3033 00 |
Computer Implementation of Recent Models for Estimating the Dose Equivalent to Organs of Man from an Inhaled or Ingested Radionuclide. |
INREM/EXREM
|
Abstract
|
C00185 I0360 00 |
Beta and Gamma Radiation Environmental Dose Code Systems. |
INTERTRAN I
|
Abstract
|
C00473 ALLMF 00 |
A Code System for Assessing the Impact from Transporting Radioactive Material. |
INTRUDE-ANS
|
Abstract
|
C00539 D8810 00 |
A Repository Intrusion Risk Evaluation Code. |
INVENT
|
Abstract
|
C00540 D8810 00 |
A Radionuclide Inventory and Hazard Index Code. |
IODES
|
Abstract
|
C00365 I0360 00 |
A Code System for Calculating the Estimation of Dose to the World Population from Releases of Iodine-129 to the Environment. |
IONMIG
|
Abstract
|
C00526 ALLMF 00 |
Code System for Radionuclide Migration Calculations. |
IRDAM
|
Abstract
|
C00524 IPCXT 00 |
Interactive Rapid Dose Assessment Model. |
ISO-PC 2.1
|
Abstract
|
C00636 IBMPC 01 |
Kernel Integration Code System for General Purpose Isotope Shielding Analyses. |
ISOGEN II
|
Abstract
|
C00055 I3675 00 |
Radioisotope Generator Code. |
ITS 3.0
|
Abstract
|
C00467 MNYCP 02 |
Integrated TIGER Series of Coupled Electron/Photon Monte Carlo Transport Codes System. |
JN-METD 2&1
|
Abstract
|
C00208 I0370 00 |
Neutron Transport Code System with Isotropic Scattering, Bare Slabs and Homogeneous Slabs (JN Method 1), Multilayer Slabs (JN Method 2). |
K009
|
Abstract
|
C00062 I7090 00 |
Solid Angle Integration Charged Particle Penetration Code. |
K019
|
Abstract
|
C00100 I0360 00 |
Shield Thickness Calculation Program for Space Vehicles. |
KAMCCO
|
Abstract
|
C00325 I0370 00 |
Three-Dimensional Time Dependent Monte Carlo Code System for Fast Neutron Physics Problems. |
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. |
KIM
|
Abstract
|
C00376 I3033 00 |
A Two-Dimensional Monte Carlo Code System for Linear Neutron Transport Calculations. |
KORIGEN
|
Abstract
|
C00457 I3033 00 |
A Modification of the Isotope Generation and Depletion Code System ORIGEN. CCC-702/ORIGEN-ARP is recommended for new ORIGEN users. |
KRONIC
|
Abstract
|
C00229 I0360 00 |
Calculation of Annual Average External (Beta and Gamma Radiation) Doses from Chronic Atmospheric Releases of Radionuclides. |
KRONIC
|
Abstract
|
C00229 U1108 00 |
Calculation of Annual Average External (Beta and Gamma Radiation) Doses from Chronic Atmospheric Releases of Radionuclides. |
KUX
|
Abstract
|
C00515 ALLCP 00 |
Medical X-Ray Shielding Calculation. |
LABAN-PEL
|
Abstract
|
C00611 IMFPC 00 |
A Two-Dimensional, Multigroup Diffusion, High-Order Response Matrix Code. |
LADTAP II
|
Abstract
|
C00363 C7600 00 |
Code System for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents. |
LADTAP II
|
Abstract
|
C00363 D0780 00 |
Code System for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents. |
LADTAP II
|
Abstract
|
C00363 I3033 00 |
Code System for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents. |
LAHET 2.8
|
Abstract
|
C00696 MFMWS 00 |
Code System for High Energy Particle Transport Calculations. |
LASER
|
Abstract
|
C00344 I0360 00 |
A One-Dimensional, Neutron-Thermalization, Lattice-Cell Program Based on MUFT and THERMOS. |
LEAF
|
Abstract
|
C00312 C6600 00 |
Fission Product Release Calculator-From a Reactor Containment Building for Arbitrary Radioactive Decay Chains. |
LEBC
|
Abstract
|
C00052 I7090 00 |
Electron Bremsstrahlung Code. |
LEOPARD
|
Abstract
|
C00343 C0000 00 |
A Spectrum-Dependent Non-Spatial Fuel Depletion Code System. |
LEOPARD
|
Abstract
|
C00343 IBMPC 00 |
A Spectrum-Dependent Non-Spatial Fuel Depletion Code System. |
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). |
|
