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Title |
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C00017 I3675 00 |
O5R
|
Abstract
|
A General-Purpose Monte Carlo Neutron Transport Code System. |
C00023 I7090 00 |
MAVRAC
|
Abstract
|
Model Astronaut and Vehicle Radiation Analysis Code. |
C00024 I7090 00 |
CARSTEP
|
Abstract
|
Trajectory and Environment Code-Electron and Proton Fluxes Impinging on Spacecraft in Orbit. |
C00025 C0000 00 |
TRG-SGD
|
Abstract
|
Calculation of Secondary Gamma-Ray Dose Rate from a Nuclear Weapon Detonation-Monte Carlo Method. |
C00026 I3675 00 |
GRACE-II
|
Abstract
|
Gamma Ray Kernel Integration Dose Rate and Heating Code-Cylinders and Spheres. |
C00028 I3675 00 |
FPIC
|
Abstract
|
Fission Product Inventory Code. |
C00031 I7090 00 |
BREMRAD
|
Abstract
|
External and Internal Bremsstrahlung Calculation Code. |
C00032 I3565 00 |
CLOUD-M
|
Abstract
|
Gamma-Ray Dose Rate from a Radioactive Cloud-Kernel Integration Code. |
C00042 C6600 00 |
DTF-IV
|
Abstract
|
Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering. |
C00042 I0370 00 |
DTF-IV MODIFIED
|
Abstract
|
Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering. |
C00046 I3675 00 |
OGRE
|
Abstract
|
A General-Purpose Monte Carlo Gamma-Ray Transport Code System. |
C00048 I0360 00 |
QAD
|
Abstract
|
Kernel Integration Code System. |
C00048 C6400 00 |
QAD-P5
|
Abstract
|
Kernel Integration Code System. |
C00050 I7090 00 |
LRSPC
|
Abstract
|
Range and Stopping Power Calculator. |
C00051 I7090 00 |
LPPC
|
Abstract
|
Proton Penetration Code. |
C00052 I7090 00 |
LEBC
|
Abstract
|
Electron Bremsstrahlung Code. |
C00053 I7090 00 |
LSVDC
|
Abstract
|
Space Vehicle Dose Calculation. |
C00053 I7090 01 |
LSVDC
|
Abstract
|
Space Vehicle Dose Calculation. |
C00054 C6600 00 |
NRN
|
Abstract
|
Multigroup Removal-Diffusion Code System for Planes, Cylinders and Spheres. |
C00055 I3675 00 |
ISOGEN II
|
Abstract
|
Radioisotope Generator Code. |
C00056 C0000 00 |
MYRA
|
Abstract
|
Calculation of Shipping Costs and Cask Designs for Irradiated Fuel Elements. |
C00056 I7090 00 |
MYRA
|
Abstract
|
Calculation of Shipping Costs and Cask Designs for Irradiated Fuel Elements. |
C00057 C0000 00 |
STERNO
|
Abstract
|
Two Dimensional Gamma-Ray Heating Kernel Integration Code. |
C00060 I3675 00 |
SDC
|
Abstract
|
Kernel Integration Shield Design Code for Radioactive Fuel Handling Facilities. |
C00062 I7090 00 |
K009
|
Abstract
|
Solid Angle Integration Charged Particle Penetration Code. |
C00064 I7090 00 |
LPSC
|
Abstract
|
Proton Penetration Code - Multilayer Slab Geometry. |
C00066 I3675 00 |
BIGGI
|
Abstract
|
Numerical Gamma-Ray Transport Code for Plane or Spherical Multilayer Geometry, Versions 3P &4T. |
C00066 U1108 00 |
BIGGI
|
Abstract
|
Numerical Gamma-Ray Transport Code for Plane or Spherical Multilayer Geometry, Versions 3P and 4T. |
C00067 I7090 00 |
STORM
|
Abstract
|
Solar Flare Radiation Hazard to Earth Orbiting Vehicles. |
C00070 C6500 00 |
CHARGE II
|
Abstract
|
Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres. |
C00070 I3675 00 |
CHARGE II
|
Abstract
|
Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres. |
C00070 IBMPC 00 |
CHARGE-PC
|
Abstract
|
Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres. |
C00072 I3675 00 |
COMPRASH
|
Abstract
|
Spinney Removal-Diffusion Shielding Code. |
C00073 I7090 00 |
ASTROS
|
Abstract
|
Calculation of Primary and Secondary Proton Dose Rates in Spheres and Slabs of Tissue. |
C00074 CDCMF 00 |
CAPS-2
|
Abstract
|
Analysis of Structures for Fallout Radiation Shielding. |
C00075 C6600 00 |
G3-6ED
|
Abstract
|
Kernel Integration Code System - Multigroup Gamma Ray Scattering. |
C00075 I3033 00 |
G3-6ED
|
Abstract
|
Kernel Integration Code System - Multigroup Gamma Ray Scattering. |
C00076 I7090 00 |
BPPC
|
Abstract
|
Proton Penetration Codes for Space Vehicles. |
C00077 I7090 00 |
BEBC
|
Abstract
|
Electron Bremsstrahlung Penetration Code for Space Vehicles. |
C00078 I7090 00 |
BED
|
Abstract
|
Electron Penetration Code for Space Vehicles. |
C00080 I7090 00 |
GASS
|
Abstract
|
Monte Carlo Calculation of Self Shielding by Encapsulated Gamma-Ray Sources. |
C00083 I7090 00 |
RAID
|
Abstract
|
Monte Carlo Multibend Duct Shielding Code. |
C00084 I7090 00 |
SHADRAC(G-30)
|
Abstract
|
Kernel Integration Code - Shield Heating and Dose Rate Calculation in Complex Geometry. |
C00085 I7090 00 |
MOMGEM-MOMDIS
|
Abstract
|
Moments Method Reconstruction of Scattered Gamma-Ray Distributions. |
C00087 I7090 00 |
LG-H
|
Abstract
|
Ray Analysis Cylindrical Duct Kernel Code for Neutrons and Gamma Rays. |
C00088 I3675 00 |
RADOS
|
Abstract
|
Gamma-Ray Dose Estimation from Cloud of Radioactive Gases by Kernel Integration. |
C00090 I3675 00 |
AMC
|
Abstract
|
Monte Carlo Albedo Code for Neutron and Capture Gamma-Ray Distributions in Rectangular Concrete Ducts. |
C00092 I7094 00 |
SAP N-G
|
Abstract
|
Neutron and Gamma-Ray Albedo Model Scatter Shield Analysis Code System. |
C00093 I7090 00 |
MCFLARE
|
Abstract
|
Monte Carlo Code to Simulate Solar Flare Events and Estimate Probable Doses Encountered on Interplanetary Missions. |
C00094 U1108 00 |
KAP-VI
|
Abstract
|
Kernel Integration Code System in Complex Geometry. |
C00100 I0360 00 |
K019
|
Abstract
|
Shield Thickness Calculation Program for Space Vehicles. |
C00101 I7090 00 |
NAP
|
Abstract
|
Multigroup Time-Dependent Neutron Activation Prediction Code. |
C00102 I3675 00 |
SURF
|
Abstract
|
Conical and Plane Surface Single Scattering Code. |
C00103 I7090 00 |
OPEX-II
|
Abstract
|
Radiation Shield Optimization Code. |
C00104 I7090 00 |
EDNA
|
Abstract
|
Electron Dose and Number Analysis Code by Kernel Integration. |
C00106 C3600 00 |
PF-COMP
|
Abstract
|
Building Fallout Radiation Protection Factor Analysis. |
C00107 I0360 00 |
ETRAN
|
Abstract
|
Monte Carlo Code System for Electron and Photon Through Extended Media. |
C00108 C0000 00 |
SPECTRA
|
Abstract
|
Determination of Neutron Spectra from Activation. |
C00108 C0073 00 |
SPECTRA
|
Abstract
|
Determination of Neutron Spectra from Activation. |
C00108 C3600 00 |
SPECTRA
|
Abstract
|
Determination of Neutron Spectra from Activation. |
C00109 I3675 00 |
SOSUM
|
Abstract
|
Multigroup Beta and Gamma-Ray Energy Sources from Activities. |
C00110 I3675 00 |
AIRTRANS
|
Abstract
|
Monte Carlo Time and Energy-Dependent Three-Dimensional Radiation Transport Code. |
C00112 MNYCP 03 |
SAND-II
|
Abstract
|
Neutron Flux Spectra Determination by Multiple Foil Activation Method. We recommend PSR-345/SNL-SAND-II. |
C00115 C6600 00 |
GADJET
|
Abstract
|
Monte Carlo Gamma-Ray Adjoint Energy Transport Code in Complex Three-Dimensional Geometry. |
C00116 I3675 00 |
TRECO
|
Abstract
|
An Orbital Integration Estimation of Trapped Radiation. |
C00117 C6600 00 |
BETA II
|
Abstract
|
Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry. |
C00117 I0360 00 |
BETA II
|
Abstract
|
Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry. |
C00118 C6000 00 |
SIGMA II
|
Abstract
|
Space Radiation Dose Analysis Within Complex Configurations. |
C00118 PC486 00 |
SIGMA II
|
Abstract
|
Space Radiation Dose Analysis Within Complex Configurations. |
C00119 I0360 00 |
ELBA
|
Abstract
|
Electron and Bremsstrahlung Dose Rate Code. |
C00120 I3675 00 |
SPACETRAN 1;2;3
|
Abstract
|
Dose Calculations at Detectors at Various Distances from the Surface of a Cylinder. |
C00121 C7600 00 |
SABINE-3
|
Abstract
|
Spinney (Removal-Diffusion) Shielding Code System in One-Dimensional Geometry. |
C00121 I0370 00 |
SABINE-3
|
Abstract
|
Spinney (Removal-Diffusion) Shielding Code System in One-Dimensional Geometry. |
C00121 U1106 00 |
SABINE-3
|
Abstract
|
Spinney (Removal-Diffusion) Shielding Code System in One-Dimensional Geometry. |
C00121 IBMPC 00 |
SABINE-PC
|
Abstract
|
Spinney (Removal-Diffusion) Shielding Code System in One-Dimensional Geometry. |
C00122 I7090 00 |
RAD 2
|
Abstract
|
Fission Product Radioactivities Calculation. |
C00123 C0073 00 |
XSDRN
|
Abstract
|
Multigroup One-Dimensional Discrete Ordinates Spectral Averaging N Transport Code System. |
C00123 I0360 00 |
XSDRN
|
Abstract
|
Multigroup One-Dimensional Discrete Ordinates Spectral Averaging N Transport Code System. |
C00124 I3675 00 |
KDLIBE
|
Abstract
|
Kernel-Diffusion Shielding Analysis System. |
C00125 PC586 03 |
RSAC6.2
|
Abstract
|
Radiological Safety Analysis Code System. |
C00126 IRISC 00 |
ASOP
|
Abstract
|
Multigroup One-Dimensional Discrete Ordinates Transport Code System for Shield Optimization. |
C00127 I3675 00 |
MORSE-ANSI STD.
|
Abstract
|
A General Purpose Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. We recommend C00474/ALLCP/02 MORSE-CGA. |
C00128 I3675 00 |
O6R
|
Abstract
|
A General-Purpose Monte Carlo Transport Code System. |
C00129 C6600 00 |
TWOTRAN-SPHERE
|
Abstract
|
Multigroup Two-Dimensional Discrete Ordinates Transport Code System in Spherical Geometry. |
C00130 C6600 00 |
DTF-69
|
Abstract
|
One-Dimensional Multigroup Photon Transport Discrete Ordinates Code System. |
C00131 I3675 00 |
ANTE 2
|
Abstract
|
Adjoint Monte Carlo Time-Dependent Neutron Transport Code in Combinatorial Geometry. |
C00132 I0370 00 |
ATTOW-KB
|
Abstract
|
Multigroup Two-Dimensional Removal-Diffusion (Spinney Method) Shielding Code System. |
C00135 ALLMF 00 |
GAMMOM
|
Abstract
|
Gamma-Ray Moments Method Codes--GRMM and SPENCER. |
C00136 I7090 00 |
COLLIMATOR
|
Abstract
|
Monte Carlo Calculation of the Spectrum of Gamma Radiation from a Collimated Co-60 Source. |
C00137 C6600 00 |
RIBD-II
|
Abstract
|
Radioisotope Buildup and Decay Code System. |
C00137 I0360 00 |
RIBD-II
|
Abstract
|
Radioisotope Buildup and Decay Code System. |
C00138 C3600 00 |
PIGG
|
Abstract
|
A Multigroup One-Dimensional P-1 Radiation Transport Code System. |
C00139 I3675 00 |
CONSTRIP V
|
Abstract
|
Vertical Barrier-Finite Source Plane Gamma-Ray Penetration Code System. |
C00140 I3675 00 |
DIPHO
|
Abstract
|
Monte Carlo Gamma-Ray Code System-Infinite Medium, Mono-energetic and Isotropic Point Source. |
C00142 I3033 00 |
MERCURE 4-82
|
Abstract
|
Three-Dimensional Code System for Integrating Multigroup Line-of-Sight Attenuation Kernels by Monte Carlo Techniques. |
C00143 I3675 00 |
GREAT-GRASS
|
Abstract
|
Monte Carlo Radiation Transport Code Systems for Fallout Shielding. |
C00144 I0370 00 |
TIMOC-72
|
Abstract
|
Monte Carlo Three-Dimensional Neutron Transport Code System. |
C00148 I3675 00 |
SPARES
|
Abstract
|
Space Radiation Environment and Shielding Code System. |
C00150 I3675 00 |
MAP
|
Abstract
|
Kernel Integration Code System in Complex Geometry with Special Application to Surface Sources Determined by Discrete Ordinates Calculations. |
C00152 I3675 00 |
ALGAM-97
|
Abstract
|
Monte Carlo Estimation of Internal Dose from Gamma-Ray Sources in a Phantom Man. |
C00155 C3600 00 |
ELTRAN
|
Abstract
|
One-Dimensional Monte Carlo Electron Transport Code System. |
C00156 I0360 00 |
MECC-7
|
Abstract
|
Medium-Energy Intranuclear Cascade Code System. |
C00157 C6600 00 |
MEVDP
|
Abstract
|
Primary Radiation Transport Code System - Complex Geometry - Computerized Anatomical Model Man. |
C00158 C3600 00 |
MAGNA
|
Abstract
|
Multi-Source Gamma-Ray Kernel Integration Code System. |
C00159 I3675 00 |
ORPHEE VI
|
Abstract
|
Kernel Integration Code System - Attenuation of Fast Neutrons in Cylindrical Layers of Water and Dense Material. |
C00160 D0VAX 00 |
PICA
|
Abstract
|
Monte Carlo Medium-Energy Photon-Induced Intranuclear Cascade Anal Code System. |
C00160 I0360 00 |
PICA
|
Abstract
|
Monte Carlo Medium-Energy Photon-Induced Intranuclear Cascade Anal Code System. |
C00162 C6600 00 |
FPIP
|
Abstract
|
Fission Product Inventory Code System. |
C00163 MNYCP 01 |
FISSP & CLOUD
|
Abstract
|
Fission Product Inventory, Release, Transport and Dose Calculation. |
C00164 C0000 00 |
NAC
|
Abstract
|
Neutron Activation Analysis and Product Isotope Inventory Code System. |
C00164 IBMMF 00 |
NAC
|
Abstract
|
Neutron Activation Analysis and Product Isotope Inventory Code System. |
C00164 IBMPC 00 |
NAC-PC
|
Abstract
|
Neutron Activation Analysis and Product Isotope Inventory Code System. |
C00165 I3675 00 |
DOSE 1
|
Abstract
|
Gamma-Radiation Dosimetry for Arbitrary Source and Target Geometry. |
C00166 I3675 00 |
DAVE
|
Abstract
|
Monte Carlo Gamma-Ray Transport Code System in One-Dimensional Spherical Geometry. |
C00167 I0360 00 |
ELF
|
Abstract
|
Monte Carlo Neutron Transport Code System for Cylinders and Spheres. |
C00168 U1108 00 |
FASTER III
|
Abstract
|
Monte Carlo Neutron and Photon Transport Code System in Complex Geometries. |
C00168 I3675 00 |
FASTER-III
|
Abstract
|
Monte Carlo Neutron and Photon Transport Code System in Complex Geometries. |
C00169 I3675 00 |
CAVEAT
|
Abstract
|
General Purpose Monte Carlo Time-Dependent Radiation Transport Code in Complex Geometry. |
C00170 I0360 00 |
DISDOS
|
Abstract
|
Calculation of Dose Distribution in Human Phantoms Irradiated by External Photon Sources. |
C00171 ICL00 00 |
MUSPALB
|
Abstract
|
Albedo Calculation of Multigroup Spectra of Neutrons Transmitted Through Multilayer Slab Shielding. |
C00172 C7600 00 |
TRANZIT
|
Abstract
|
Multigroup Time-Dependent Discrete Ordinates Radiation Transport Code System in (rho,z) Cylindrical Geometry. |
C00174 U1108 00 |
RACER
|
Abstract
|
Calculation of Potential External Dose from Airborne Fission Products Following Postulated Reactor Accident. |
C00175 I3675 00 |
PICFEE
|
Abstract
|
Fission Product Inventory Code System. |
C00176 C6600 00 |
CASCADE
|
Abstract
|
Monte Carlo Simulation of the Transport of High Energy Electrons and Photons in Matter. |
C00176 I0360 00 |
CASCADE
|
Abstract
|
Monte Carlo Simulation of the Transport of High Energy Electrons and Photons in Matter. |
C00177 I3675 00 |
DOPEX
|
Abstract
|
Laminated Shield Weight Optimization Code System-Steepest Descent Calculational Model. |
C00177 U1108 00 |
DOPEX
|
Abstract
|
Laminated Shield Weight Optimization Code System-Steepest Descent Calculational Model. |
C00180 MNYWS 01 |
TDA
|
Abstract
|
A Time-Dependent, Multigroup, One-Dimensional, Discrete Ordinates Transport Code System. |
C00181 I3675 00 |
DEMON & DEMON R
|
Abstract
|
Demonstration Monte Carlo Code System in Slab Geometry. |
C00182 C6600 00 |
CDR
|
Abstract
|
A Constant Dose Range Code System, Using the LANL-NWEF Neutron-Gamma-Ray Air Flux Tape. |
C00182 I0360 00 |
CDR
|
Abstract
|
A Constant Dose Range Code System, Using the LANL-NWEF Neutron-Gamma-Ray Air Flux Tape. |
C00183 U1108 00 |
ESDORA
|
Abstract
|
Fission Product Inventory and Gamma-Ray Dose Rate from a Radioactive Cloud System. |
C00184 I0360 00 |
TASK
|
Abstract
|
Generalized One-Dimensional Radiation Transport and Diffusion Kinetics Code System. |
C00185 I0360 00 |
INREM/EXREM
|
Abstract
|
Beta and Gamma Radiation Environmental Dose Code Systems. |
C00186 I3033 00 |
FSCATT
|
Abstract
|
Discrete Ordinates Gamma-Ray Transport Code System in Plane Geometry. |
C00186 U1108 00 |
FSCATT
|
Abstract
|
Discrete Ordinates Gamma-Ray Transport Code System in Plane Geometry. |
C00187 C6600 00 |
SAM-CE
|
Abstract
|
Monte Carlo Time-Dependent Complex Geometry (Combinatorial) Code System for the Solution of the Forward Neutron and Forward and Adjoint Gamma-Ray Transport Equations. |
C00187 I0360 00 |
SAM-CE
|
Abstract
|
Monte Carlo Time-Dependent Complex Geometry (Combinatorial) Code System for the Solution of the Forward Neutron and Forward and Adjoint Gamma-Ray Transport Equations. |
C00188 U1108 00 |
MOMENT I
|
Abstract
|
Moments Method Neutron Transport Code System. |
C00189 I3675 00 |
ADO
|
Abstract
|
Aerojet Discrete Ordinates Calculational System. |
C00190 C0000 00 |
AKERN
|
Abstract
|
Aerojet Point Kernel Integration Calculational System. |
C00190 U1108 00 |
AKERN
|
Abstract
|
Aerojet Point Kernel Integration Calculational System. |
C00191 I3675 00 |
ACOH
|
Abstract
|
Aerojet COHORT Monte Carlo Code System. |
C00192 C6600 00 |
SAM-CEP
|
Abstract
|
Monte Carlo Code System Correlated to the Simultaneous Solution of Multiple, Perturbed, Time-Dependent Neutron Transport Problems in Complex Three-Dimensional Geometry. |
C00193 I0360 00 |
ESP
|
Abstract
|
General Purpose Monte Carlo Neutron Transport Code System. |
C00194 C6600 00 |
SMAUG-13
|
Abstract
|
Calculation of Neutron and Prompt Gamma-Ray Doses Resulting from an Atmospheric Nuclear Detonation. |
C00195 C6600 00 |
TWOTRAN
|
Abstract
|
Two-Dimensional Discrete Ordinates. We recommend CCC-547/TWODANT-SYS. |
C00196 I0360 00 |
RRR
|
Abstract
|
Radiation Transport in Air-Analysis of Routine Releases of Short-Lived Radioactive Nuclides. |
C00197 I3675 00 |
USRHYD
|
Abstract
|
Electron and X-Ray Energy Deposition and Hydrodynamics Code System. |
C00198 I7094 00 |
COHORT-II
|
Abstract
|
General Purpose Monte Carlo Radiation Transport Code System. |
C00201 C6600 00 |
STRAGL
|
Abstract
|
Calculation of Energy Loss Straggling of Heavy Charged Particles. |
C00202 C0000 00 |
PELSHIE
|
Abstract
|
General Purpose Kernel Integration Shielding Code System-Point and Extended Gamma-Ray Sources. |
C00202 IBMMF 00 |
PELSHIE3
|
Abstract
|
General Purpose Kernel Integration Shielding Code System-Point and Extended Gamma-Ray Sources. |
C00203 C0000 00 |
MORSE-CG
|
Abstract
|
A General Purpose Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System with Combinatorial Geometry. We recommend C00474/ALLCP/02 MORSE-CGA. |
C00203 CY000 00 |
MORSE-CG
|
Abstract
|
A General Purpose Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System with Combinatorial Geometry. We recommend C00474/ALLCP/02 MORSE-CGA. |
C00203 D0VAX 00 |
MORSE-CG
|
Abstract
|
A General Purpose Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System with Combinatorial Geometry. We recommend C00474/ALLCP/02 MORSE-CGA. |
C00203 I0360 00 |
MORSE-CG
|
Abstract
|
A General Purpose Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System with Combinatorial Geometry. We recommend C00474/ALLCP/02 MORSE-CGA. |
C00203 U0000 00 |
MORSE-CG
|
Abstract
|
A General Purpose Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System with Combinatorial Geometry. We recommend C00474/ALLCP/02 MORSE-CGA. |
C00204 C6600 00 |
SWANLAKE
|
Abstract
|
Cross Section Sensitivity Analysis Code System for One-Dimensional Discrete Ordinates Calculations. |
C00204 I3033 00 |
SWANLAKE
|
Abstract
|
Cross Section Sensitivity Analysis Code System for One-Dimensional Discrete Ordinates Calculations. |
C00205 I3691 00 |
TRAPP
|
Abstract
|
Transport of Alpha Particles and Protons with all Nuclear Reaction Products Neglected. |
C00206 I0360 00 |
EGAD
|
Abstract
|
Calculation of Dose from External Gamma-Ray Emitters. |
C00207 C6600 00 |
FLUKA-TRANKA
|
Abstract
|
Three-Dimensional High-Energy Extranuclear Hadron Cascade Monte Carlo System for Cylindrical Backstop Geometries. |
C00208 I0370 00 |
JN-METD 2&1
|
Abstract
|
Neutron Transport Code System with Isotropic Scattering, Bare Slabs and Homogeneous Slabs (JN Method 1), Multilayer Slabs (JN Method 2). |
C00210 I0360 00 |
NUGAM 2&3 SSLAB
|
Abstract
|
Monte Carlo Prediction of Photon Transport Distributions. |
C00211 I0360 00 |
EMERALD
|
Abstract
|
Calculation of Activity Releases and Potential Doses from a Pressurized Water Reactor Plant. |
C00212 I3675 00 |
ADJMOM
|
Abstract
|
Adjoint Moments Method Gamma-Ray Transport Code System. |
C00213 I0360 00 |
ACRA-II
|
Abstract
|
Kernel Integration Code System for Estimation of Radiation Doses Caused by a Hypothetical Reactor Accident. |
C00214 I0360 00 |
DOPEX-1D2C
|
Abstract
|
A One-Dimensional, Two-Constraint Radiation Shield Optimization Code System. |
C00215 C3600 00 |
TESS
|
Abstract
|
Multigroup Discrete Ordinates Code System for Slab and Spherical Geometries. |
C00216 C6600 00 |
SHADOK
|
Abstract
|
Transport Code Systems, P1 Scattering in Infinite Cylindrical and Spherical Geometries by Polynomial Approximation. |
C00219 I0360 00 |
PIPE
|
Abstract
|
Numerical Gamma-Ray Transport Code System for Plane/Spherical Geometry. |
C00220 C6600 00 |
LUIN-II
|
Abstract
|
Analytical Straight-Ahead Transport Code System-Calculation of Cosmic-Ray Spectra, Fluxes and Ionization in the Earth's Atmosphere. |
C00221 A1000 00 |
SLDN
|
Abstract
|
Code System for Shielding Calculations by the Method of Invariant Imbedding. |
C00221 F2307 00 |
SLDN
|
Abstract
|
Code System for Shielding Calculations by the Method of Invariant Imbedding. |
C00221 FM200 00 |
SLDN
|
Abstract
|
Code System for Shielding Calculations by the Method of Invariant Imbedding. |
C00221 GE625 00 |
SLDN
|
Abstract
|
Code System for Shielding Calculations by the Method of Invariant Imbedding. |
C00221 I0360 00 |
SLDN
|
Abstract
|
Code System for Shielding Calculations by the Method of Invariant Imbedding. |
C00222 C7600 00 |
TWOTRAN II
|
Abstract
|
Two-Dimensional Multigroup Discrete Ordinates Transport C System in (x,y), (r,theta), and (r,z) Geometries. |
C00222 I3691 00 |
TWOTRAN II
|
Abstract
|
Two-Dimensional Multigroup Discrete Ordinates Transport C System in (x,y), (r,theta), and (r,z) Geometries. |
C00223 I3675 00 |
DTK
|
Abstract
|
One-Dimensional Multigroup Neutron Transport Code System. |
C00224 C6600 00 |
ARC
|
Abstract
|
Aircraft Radiation Transport Code System, Crew Dose Calculation. |
C00225 I0360 00 |
REST 1;2;3
|
Abstract
|
Fission Product Inventory Code System with Fission Product Escape Model. |
C00226 I0360 00 |
GAMMOM-I
|
Abstract
|
Gamma-Ray Moments Method Code System. |
C00227 GE400 00 |
ENEDEP
|
Abstract
|
Energy Deposition Code System for GE 265 Time-Sharing System. |
C00228 C6600 00 |
SPAR
|
Abstract
|
Calculation of Stopping Powers and Ranges for Muons, Charged Pions, Protons and Heavy Ions. |
C00228 I0360 00 |
SPAR
|
Abstract
|
Calculation of Stopping Powers and Ranges for Muons, Charged Pions, Protons and Heavy Ions. |
C00229 I0360 00 |
KRONIC
|
Abstract
|
Calculation of Annual Average External (Beta and Gamma Radiation) Doses from Chronic Atmospheric Releases of Radionuclides. |
C00229 U1108 00 |
KRONIC
|
Abstract
|
Calculation of Annual Average External (Beta and Gamma Radiation) Doses from Chronic Atmospheric Releases of Radionuclides. |
C00230 C6600 00 |
TRIPLET
|
Abstract
|
Two-Dimensional, Multigroup, Triangular Mesh, Planar Geometry, Explicit Discrete Ordinates Code System. |
C00230 C7600 00 |
TRIPLET
|
Abstract
|
Two-Dimensional, Multigroup, Triangular Mesh, Planar Geometry, Explicit Discrete Ordinates Code System. |
C00230 I0360 00 |
TRIPLET
|
Abstract
|
Two-Dimensional, Multigroup, Triangular Mesh, Planar Geometry, Explicit Discrete Ordinates Code System. |
C00231 C6400 00 |
FRCRL2
|
Abstract
|
Calculation of Fission-Product Release in Reactor Accident Analyses. |
C00232 I0360 00 |
CYGNUS-C SPHERE
|
Abstract
|
Monte Carlo Neutron Transport Code System in Spherical Geometry. |
C00233 C6600 00 |
CRYSTAL BALL
|
Abstract
|
Code System for Determining Neutron Spectra from Activation Measurements. |
C00233 I0360 00 |
CRYSTAL BALL
|
Abstract
|
Code System for Determining Neutron Spectra from Activation Measurements. |
C00234 I0370 00 |
SCORE-4
|
Abstract
|
Two-Dimensional Multigroup Removal-Diffusion Shielding Code System. |
C00235 U1108 00 |
INAP
|
Abstract
|
Improved Neutron Activation Prediction Code Systems. |
C00236 DP010 00 |
INDOS
|
Abstract
|
Conversational Computer Code Systems to Implement ICRP-10-10A Models for Estimation of Internal Radiation Dose to Man. |
C00237 C6600 00 |
BURP-2
|
Abstract
|
Calculation of Buildup and Decay of Radioactive Fission Products. |
C00238 I3691 00 |
CARNAC
|
Abstract
|
Calculation of Flux and Neutron Spectra in the Case of Criticality Accident. |
C00239 I0360 00 |
LGH-G
|
Abstract
|
Calculation of Gamma Radiation through Partially Shielded Gaps (Buildup Factor Method in Taylors Approximation). |
C00240 C0074 00 |
CAMERA
|
Abstract
|
Radiation Transport Analysis Code System and the Computerized Man (CAM) Model. |
C00240 IBMPC 01 |
CAMERA
|
Abstract
|
Radiation Transport Analysis Code System and the Computerized Man (CAM) Model. |
C00242 I3691 00 |
AIREM
|
Abstract
|
Calculation of Doses, Population Doses, and Ground Depositions Due to Atmospheric Emissions of Radionuclides. |
C00243 C0074 00 |
PATCH-7
|
Abstract
|
Three-Dimensional Kernel Integration Code-Explicit Single Scattering Option. |
C00244 C6600 00 |
TRANSPORT
|
Abstract
|
Charged Particle Beam Transport Systems Design Code System (First- and Second-Order Matrix Multiplication). |
C00244 I0360 00 |
TRANSPORT
|
Abstract
|
Charged Particle Beam Transport Systems Design Code System (First- and Second-Order Matrix Multiplication). |
C00246 I0360 00 |
TMMS
|
Abstract
|
Gamma-Ray Penetration Shielding Code System, Transmission Matrix Method. |
C00247 I0360 00 |
LIONS
|
Abstract
|
Calculation of Fission Product Inventory, Gamma-Ray Dose Rates and Gamma-Ray Doses by Kernel Integration. |
C00248 C0000 00 |
SWAN
|
Abstract
|
Code System for Analysis and Optimization of Fusion Reactor Nucleonic Characteristics. |
C00248 CY000 00 |
SWAN
|
Abstract
|
Code System for Analysis and Optimization of Fusion Reactor Nucleonic Characteristics. |
C00248 I0360 00 |
SWAN
|
Abstract
|
Code System for Analysis and Optimization of Fusion Reactor Nucleonic Characteristics. |
C00249 I0360 00 |
HIC-1
|
Abstract
|
Monte Carlo Code System for Calculating Heavy Ion Reactions at Energies > 50 MeV/Nucleon. |
C00250 I0370 00 |
EMERALD-NORMAL
|
Abstract
|
Calculation of Activity Releases and Potential Doses from the Normal Operation of a Pressurized Water Reactor Plant. |
C00251 I0360 00 |
FIPDIG
|
Abstract
|
One-Dimensional Time-Dependent Fission Product Diffusion Code System. |
C00254 MNYCP 02 |
ANISN-ORNL
|
Abstract
|
One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering. |
C00256 I0360 00 |
TDT
|
Abstract
|
Generalized One-Dimensional Multigroup Time-Dependent Transport and Diffusion Kinetic Code System. |
C00257 I3033 00 |
DELFIC-TES
|
Abstract
|
Multigroup Kernel Integration Code System for Calculating Gamma-Ray Exposure from a Radioactive Airborne Cloud. |
C00257 U1108 00 |
DELFIC-TES
|
Abstract
|
Multigroup Kernel Integration Code System for Calculating Gamma-Ray Exposure from a Radioactive Airborne Cloud. |
C00258 I0360 00 |
MORSE-E
|
Abstract
|
Special Purpose Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. We recommend C00474/ALLCP/02 MORSE-CGA. |
C00259 I0360 00 |
STRAINT
|
Abstract
|
One-Dimensional Multigroup Neutron Transport Discrete Ordinates Code System. |
C00260 C6600 00 |
FEM-2D
|
Abstract
|
Two-Dimensional Diffusion Theory Code System Based on the Method of Finite Elements. |
C00261 C6600 00 |
MORSE-L
|
Abstract
|
Multigroup Neutron and Gamma-Ray Transport Code System for the Solution of Penetration Problems. We recommend C00474/ALLCP/02 MORSE-CGA. |
C00262 I0360 00 |
VCS
|
Abstract
|
Coupled Discrete Ordinates-Adjoint Monte Carlo Calculation of Radiation Protection Factors in Vehicles. |
C00263 I0360 00 |
AIRBORNE
|
Abstract
|
Airborne Contaminants Dispersion Code. |
C00264 C6600 00 |
DLS
|
Abstract
|
Two-Dimensional Shielding Calculational System with Diffusion Theory and Line-of-Sight Method. |
C00265 I0360 00 |
CASIM
|
Abstract
|
Monte Carlo Simulation of Transport of Hadron Cascades in Bulk Matter. |
C00266 C7600 00 |
ONETRAN
|
Abstract
|
A One-Dimensional Multigroup Discrete Ordinates Finite Element Transport Code System. We recommend CCC-547/TWODANT-SYS. |
C00266 CY000 00 |
ONETRAN
|
Abstract
|
A One-Dimensional Multigroup Discrete Ordinates Finite Element Transport Code System. We recommend CCC-547/TWODANT-SYS. |
C00266 I3033 00 |
ONETRAN
|
Abstract
|
A One-Dimensional Multigroup Discrete Ordinates Finite Element Transport Code System. We recommend CCC-547/TWODANT-SYS. |
C00267 U1108 00 |
HAM
|
Abstract
|
Monte Carlo Multigroup Neutron and Photon High Altitude Transport Code System. |
C00268 C6600 00 |
ALBEMO
|
Abstract
|
Albedo Monte Carlo Code System. |
C00269 I0360 00 |
RSYST
|
Abstract
|
Integrated Modular Code System for Shielding and Reactor Physics Calculations. |
C00270 U1100 00 |
SUBDOSA-II
|
Abstract
|
Calculation of External Gamma-Ray and Beta-Ray Doses from Accidental Atmospheric Releases of Radionuclides. |
C00271 C0074 00 |
PUSHLD
|
Abstract
|
Gamma-Ray Three-Dimensional Calculation of Dose Rates from Plutonium in Various Geometries. |
C00273 U1100 00 |
DACRIN
|
Abstract
|
Airborne Radionuclide Organ Dose Calculational System. |
C00274 C7600 00 |
TIMEX
|
Abstract
|
One Dimensional, Time Dependent Multigroup Explicit Discrete Ordinates Radiation Transport Code System with Anisotropic Scattering. |
C00274 CY000 00 |
TIMEX
|
Abstract
|
One Dimensional, Time Dependent Multigroup Explicit Discrete Ordinates Radiation Transport Code System with Anisotropic Scattering. |
C00274 U1106 00 |
TIMEX
|
Abstract
|
One Dimensional, Time Dependent Multigroup Explicit Discrete Ordinates Radiation Transport Code System with Anisotropic Scattering. |
C00275 D0VAX 00 |
E-DEP-1
|
Abstract
|
Heavy Ion Energy Deposition Code System. |
C00277 C7600 00 |
MORSE-SGC
|
Abstract
|
A Super Grouped Cross Section Version of the MORSE Code System. We recommend either C00474/ALLCP/02 MORSE-CGA, or C00545/IRISC/01 SCALE 4.2. |
C00278 C7600 00 |
SPOOR
|
Abstract
|
Monte Carlo Simulation of the Turbulent Transport of Airborne Contaminants. |
C00279 C0176 00 |
RAFFLE/2
|
Abstract
|
A General Purpose Monte Carlo Code System for Neutron Transport with Mixed Zone Geometry Option. |
C00279 I0360 00 |
RAFFLE/2 MOD 2
|
Abstract
|
A General Purpose Monte Carlo Code System for Neutron Transport with Mixed Zone Geometry Option. |
C00281 I0360 00 |
MUSCAT
|
Abstract
|
Calculation of Neutron Currents in Spherical and Cylindrical Cavities by Means of View Factors. |
C00282 I0360 00 |
SNOW
|
Abstract
|
Two-Dimensional Discrete Ordinates Multigroup Transport Code System in Plane and Cylindrical Geometry with Isotropic and Anisotropic Scattering. |
C00283 I0360 00 |
ACRA-TRIT
|
Abstract
|
The Tritium Version of ACRA-II, Estimation of Radiation Doses Caused by a Hypothetical Reactor Accident. |
C00284 I0360 00 |
SHREDI
|
Abstract
|
Multigroup Two-Dimensional (x-y, r-o geometry) Neutron Removal-Diffusion (Spinney Method) Shielding Code System. |
C00285 I0360 00 |
PEPIN
|
Abstract
|
Methodology for Computing Concentrations, Activities, Gamma-Ray Spectra, and Residual Heat from Fission Products. |
C00286 I0360 00 |
AISITE II
|
Abstract
|
Reactor Siting Code System. |
C00287 I0370 00 |
PROB
|
Abstract
|
Multigroup One-Dimensional Transport Code System, Collision Probability Method. |
C00289 IBMPC 01 |
SKYIII-PC
|
Abstract
|
Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air. |
C00289 D0VAX 00 |
SKYSHINE-III
|
Abstract
|
Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air. |
C00290 U1108 00 |
TRIGON
|
Abstract
|
Two-Dimensional Multigroup Diffusion Code System-Trigonal or Hexagonal Mesh. |
C00291 C6600 00 |
BMC-MG
|
Abstract
|
Multigroup Monte Carlo Neutron and Gamma-Ray Shielding Code System for Plutonium. |
C00292 I0360 00 |
TIMED
|
Abstract
|
Calculation of Cumulated Activity of a Radionuclide in the Organs of the Human Body at a Given Time After Deposition. |
C00293 C7600 00 |
TRIDENT
|
Abstract
|
Two-Dimensional Multigroup Discrete Ordinates Transport Code System-(x,y) and (r,z) Geometries. |
C00293 I0360 00 |
TRIDENT
|
Abstract
|
Two-Dimensional Multigroup Discrete Ordinates Transport Code System-(x,y) and (r,z) Geometries. |
C00294 I0360 00 |
HYACINTH
|
Abstract
|
Fast Heavy Isotope Point Burnup and Decay Code System - Analytical Solution. |
C00295 C6600 00 |
ELGATL
|
Abstract
|
Calculation of Energy Spectra from Coupled Electron-Photon Slowing Down. |
C00296 I0360 00 |
APARNA-II
|
Abstract
|
Integral Transport Theory Code System Based on Discrete Ordinate Representation in Space and Direction-Slab Geometry. |
C00297 U1106 00 |
ARMYL-G
|
Abstract
|
Calculation of Transmission Factors for Gamma Rays from Nuclear Explosions. |
C00298 U1106 00 |
ARMYL-N
|
Abstract
|
Calculation of Transmission Factors for Neutrons from Nuclear Explosions. |
C00299 I0360 00 |
REBEL 3
|
Abstract
|
Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms. |
C00299 C6600 00 |
REBEL-2
|
Abstract
|
Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms. |
C00299 ICL00 00 |
REBEL-2
|
Abstract
|
Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms. |
C00300 FM380 00 |
RADHEAT-V4
|
Abstract
|
A Code System To Generate Multigroup Constants and Analyze Radiation Transport for Shielding Safety Evaluation. |
C00301 I0360 00 |
ELPHO
|
Abstract
|
Three-Dimensional Monte Carlo Electromagnetic Transport Code System. |
C00302 I0360 00 |
CACA-2
|
Abstract
|
Heavy Isotope and Fission-Product Concentration Calculation Code System. |
C00303 I0360 00 |
INDRA
|
Abstract
|
A Modular System for Calculating the Neutronics and Photonics Characteristics of a Fusion Reactor Blanket. |
C00305 C0073 00 |
ERPEX
|
Abstract
|
Monte Carlo Distributions of Energetic Proton Ranges in Silicon. |
C00306 ALLMF 00 |
DINT-YAEC
|
Abstract
|
Evaluator of I1 and I2 Integrals as Used in Long-Term External Gamma-Ray Doses from Routine Atmospheric Releases. |
C00309 C6600 00 |
EPRI-CINDER
|
Abstract
|
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. |
C00310 I0360 00 |
SFACTOR
|
Abstract
|
Dose Equivalent to a Target Organ Calculator. |
C00311 D8810 00 |
MARC-PN
|
Abstract
|
A Neutron Diffusion Code System with Spherical Harmonics Option. |
C00311 I3081 00 |
MARC-PN
|
Abstract
|
A Neutron Diffusion Code System with Spherical Harmonics Option. |
C00312 C6600 00 |
LEAF
|
Abstract
|
Fission Product Release Calculator-From a Reactor Containment Building for Arbitrary Radioactive Decay Chains. |
C00313 I0360 00 |
PLUDOS
|
Abstract
|
Calculator of Ground Level External Gamma-Ray Dose from a Radioactive Plume. |
C00315 C0073 00 |
SAMSY
|
Abstract
|
A One-Dimensional Multilayer Multigroup Neutron Removal-Diffusion and Gamma-Ray Point Kernel Calculator. |
C00316 DGMV1 00 |
XOQDOQ-82
|
Abstract
|
Radiological Assessment Code System - Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations. |
C00316 I3033 00 |
XOQDOQ-82
|
Abstract
|
Radiological Assessment Code System - Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations. |
C00316 IPCAT 00 |
XOQDOQ-82
|
Abstract
|
Radiological Assessment Code System - Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations. |
C00317 I3033 00 |
CYGAS
|
Abstract
|
A Gamma-Ray Attenuation Code System for Large Gamma-Ray Sources Shielded by Coaxial Cylinders. |
C00318 I0370 00 |
RASC-2D
|
Abstract
|
Two-Dimensional Removal Diffusion Code Reactor Shielding Design Code System. |
C00321 C7600 00 |
STREAM
|
Abstract
|
A Three-Dimensional Cylindrical-Geometry Monte Carlo Ray Tracing Code for Computing Light Transmission. |
C00322 C6600 00 |
S3
|
Abstract
|
Kernel Integration Code System--Multigroup Gamma-Ray Scattering. |
C00322 DVX11 00 |
S3
|
Abstract
|
Kernel Integration Code System--Multigroup Gamma-Ray Scattering. |
C00322 IBMPC 00 |
S3
|
Abstract
|
Kernel Integration Code System--Multigroup Gamma-Ray Scattering. |
C00323 CY000 00 |
DKR
|
Abstract
|
A Radioactivity and Dose Rate Calculation Code System for Fusion Reactors. |
C00324 C0000 00 |
OOSII
|
Abstract
|
Calculation 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. |
C00325 I0370 00 |
KAMCCO
|
Abstract
|
Three-Dimensional Time Dependent Monte Carlo Code System for Fast Neutron Physics Problems. |
C00326 C0000 00 |
TREEDE
|
Abstract
|
Monte Carlo Neutron Transport Code System Based on the Track Rotation Estimator. |
C00327 I0360 00 |
PHOEL-2
|
Abstract
|
A Monte Carlo Calculation of Initial Energy of Photoelectrons and Compton Electrons Produced by Photons in Water. |
C00329 I3033 00 |
MODEL
|
Abstract
|
Models of Trapped Proton and Electron Environments for Solar Maximum and Minimum. |
C00330 U0000 00 |
PADLOC
|
Abstract
|
A One-Dimensional, Time-Dependent Program for Calculating Coolant and Plateout Fission Product Concentrations in a Network of Pipes. |
C00331 MNYCP 00 |
EGS4
|
Abstract
|
Monte Carlo Simulation of the Coupled Transport of Electrons and Photons. |
C00332 I0360 00 |
COMRADEX4
|
Abstract
|
Evaluator of Potential Radiological Doses in the Near (< 10 km) Environment of Radioactive Release. |
C00333 I0360 00 |
BUSH
|
Abstract
|
A Code to Calculate Radiation Doses Inside Buildings from Routine Releases of Radionuclides to the Atmosphere. |
C00334 C0000 00 |
FORSS
|
Abstract
|
A Sensitivity and Uncertainty Analysis Code System. |
C00334 I0360 00 |
FORSS
|
Abstract
|
A Sensitivity and Uncertainty Analysis Code System. |
C00335 U1100 00 |
GALE BWR
|
Abstract
|
Boiling Water and Pressurized Water Reactors Gaseous and Liquid Effluents Radiological Assessment Code System. |
C00335 I3033 00 |
GALE PWR & BWR
|
Abstract
|
Boiling Water and Pressurized Water Reactors Gaseous and Liquid Effluents Radiological Assessment Code System. |
C00336 H0000 00 |
ASFIT-VARI
|
Abstract
|
Gamma-Ray Transport Code System for One-Dimensional Finite Systems. |
C00336 IBMPC 00 |
ASFIT-VARI
|
Abstract
|
Gamma-Ray Transport Code System for One-Dimensional Finite Systems. |
C00338 C6600 00 |
PURSE
|
Abstract
|
A Plutonium Radiation Source Code System. |
C00339 I0360 00 |
AKTIV
|
Abstract
|
An Evaluation of Activity, Afterheat and Biological Hazard Potential of Stainless Steel Structures in Fusion Reactor Blankets. |
C00340 B6700 00 |
FEMB
|
Abstract
|
A Two-Dimensional Diffusion Theory Finite Element Program. |
C00341 DP010 00 |
AIRSCAT
|
Abstract
|
Calculation of Dose Rate for Gamma-Rays Scattered in Air. |
C00342 F2307 00 |
FEMRZ
|
Abstract
|
A Finite-Element Method Two-Dimensional Multigroup Neutron Transport Code System, (r,z) Geometry. |
C00343 C0000 00 |
LEOPARD
|
Abstract
|
A Spectrum-Dependent Non-Spatial Fuel Depletion Code System. |
C00343 IBMPC 00 |
LEOPARD
|
Abstract
|
A Spectrum-Dependent Non-Spatial Fuel Depletion Code System. |
C00344 I0360 00 |
LASER
|
Abstract
|
A One-Dimensional, Neutron-Thermalization, Lattice-Cell Program Based on MUFT and THERMOS. |
C00345 I0360 00 |
SEDONE
|
Abstract
|
A Simulator of Tidal Transient Hydrodynamic Sediment Concentrations Conditions in Controlled Rivers and Estuaries. |
C00346 C0000 00 |
QAD-BSA
|
Abstract
|
Point-Kernel Shielding Code System. |
C00347 I0360 00 |
REDIFFUSION
|
Abstract
|
One-Dimensional Neutron Removal-Diffusion and Gamma-Ray Kernel Integration or Diffusion Theory Calculator. |
C00348 I0360 00 |
RICECCC
|
Abstract
|
A Reactor Nuclide Inventory Code for Calculating Actinides and Fission Products. |
C00349 F2307 00 |
MEDUSA-PIJ
|
Abstract
|
One-Dimensional Laser Fusion Analyzer (Including Neutron Heating Effect) Collision Probability Method. |
C00350 I3033 00 |
BRHGAM
|
Abstract
|
Monte Carlo Estimation of Absorbed Dose from X-Ray Sources in Phantom Man. |
C00352 C7600 00 |
RASPA
|
Abstract
|
A Code for the Calculation of Buildup and Decay of Fission Products and Actinides. |
C00353 C0000 00 |
SNEX
|
Abstract
|
A One-Dimensional Single Group Discrete Ordinates Transport Code System. |
C00354 I0360 00 |
ACRO
|
Abstract
|
Calculation of Organ Dose from Acute or Chronic Inhalation and Ingestion of Radionuclides. |
C00355 I0360 00 |
PREST
|
Abstract
|
Calculator of Pressure and Temperature Transient in Containment Studies. |
C00356 I0360 00 |
PLUMEX
|
Abstract
|
A Computer Program to Evaluate External Exposures to a Gaussian Plume by Point Kernel Integration. |
C00358 I3033 00 |
SOFIP
|
Abstract
|
Evaluator of Space Radiation Environment Encountered by Geocentric Satellites. |
C00359 I0360 00 |
MAGIK
|
Abstract
|
A Monte Carlo Code System for Computing Induced Residual Activation Dose Rates. |
C00360 C6600 00 |
AIRDIF
|
Abstract
|
A Two-Dimensional Atmospheric Radiation Diffusion Code. |
C00361 C0000 00 |
SANDYL
|
Abstract
|
A Monte Carlo Three-Dimensional Code System for Calculating Combined Photon-Electron Transport in Complex Systems. |
C00362 I3033 00 |
TRD-3
|
Abstract
|
Two-Dimensional Removal-Diffusion Neutron Shielding Code System. |
C00363 C7600 00 |
LADTAP II
|
Abstract
|
Code System for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents. |
C00363 D0780 00 |
LADTAP II
|
Abstract
|
Code System for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents. |
C00363 I3033 00 |
LADTAP II
|
Abstract
|
Code System for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents. |
C00364 C7600 00 |
SANDOR
|
Abstract
|
Isotope Generation and Depletion Code Matrix Exponential Method. |
C00365 I0360 00 |
IODES
|
Abstract
|
A Code System for Calculating the Estimation of Dose to the World Population from Releases of Iodine-129 to the Environment. |
C00366 C0000 00 |
DASH-FP
|
Abstract
|
A One-Dimensional Analytic-Numerical Solution to the Problem of Multicomponent Time-Dependent Diffusion of Fission Products. |
C00368 I0370 00 |
MORSE-B
|
Abstract
|
General Purpose Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. We recommend C00474/ALLCP/02 MORSE-CGA. |
C00369 I0360 00 |
PREMOR
|
Abstract
|
A Point Reactor Exposure Code System for Survey Nuclear Analysis of Power Plant Performance. |
C00370 PC486 00 |
DCHAIN2
|
Abstract
|
A Code System for Calculation of Transmutation of Nuclides. |
C00371 ALLCP 03 |
ORIGEN2.2
|
Abstract
|
Isotope Generation and Depletion Code - Matrix Exponential Method. New ORIGEN users are advised to get CCC-750/SCALE6 and run the ORIGEN-ARP code system in that package. |
