| Package Name |
Abstract |
RSICC Tapelist |
Title |
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1DB-2DB-3DB
|
Abstract
|
C00741 PC586 00 |
One-Dimensional Diffusion Code System for Nuclear Reactor. |
1DX |
Abstract
|
P00096 I0360 00 |
A One-Dimensional Diffusion Code System for Producing Energy Group Collapsed and Self-Shielded Cross Sections. |
1DX |
Abstract
|
P00096 U1108 00 |
A One-Dimensional Diffusion Code System for Producing Energy Group Collapsed and Self-Shielded Cross Sections. |
3DDT
|
Abstract
|
C00605 C6600 00 |
Multigroup Diffusion Code System for Use in Fast Reactor Analysis. |
ABAREX |
Abstract
|
P00248 MNYCP 01 |
Neutron Spherical Optical-Statistical Model Code System. |
ABBN-90 |
Abstract
|
D00182 MNYCP 00 |
Multigroup Constant Set for Calculation of Neutron and Photon Radiation Fields and Functionals, Including the CONSYST2 Program. |
ABLEIT-TRANS |
Abstract
|
P00247 C0175 00 |
Error Propagation Analysis for Burnup Calculation. |
ACAB-2008
|
Abstract
|
C00758 MNYCP 00 |
ACtivation ABacus Inventory Code System for Nuclear Applications. |
ACAT |
Abstract
|
P00257 FM380 00 |
Monte Carlo Simulation of Atomic Collisions in Amorphous Targets in the Binary Collision Approximation. |
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. |
ACORNS |
Abstract
|
P00264 IBMPC 01 |
Analysis of Correlations Used in Neutron Spectrometry. |
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. |
ACTIV-PC |
Abstract
|
P00287 IBMPC 00 |
A Program to Process Gamma or X-ray Spectra. |
ACTIV87 |
Abstract
|
D00169 ALLCP 00 |
Fast Neutron Activation Cross Section File. |
ACTL82 |
Abstract
|
D00069 ALLCP 01 |
Evaluated Neutron Activation Cross-Section Library. |
ACTV-F/H |
Abstract
|
D00155 ALLCP 00 |
Neutron Activation Cross Section Library for Fusion Reactor Design. |
ACTV-FUS/INT |
Abstract
|
D00170 ALLCP 00 |
International Library of Neutron Activation Cross-Section Data for Fusion Reactor Application. |
ADASAGE |
Abstract
|
P00426 IBMPC 00 |
Ada Application Development System, Versions 4.02, 4.0 and 3.1. |
ADEFTA 4.0 |
Abstract
|
P00543 MNYCP 00 |
Atomic Densities for Transport Analysis Script. |
ADENA |
Abstract
|
P00190 C0000 00 |
Code System for Application of Adjusted Data in Calculating Fission-Product Decay Energies and Spectra. |
ADENA |
Abstract
|
P00190 I3033 00 |
Code System for Application of Adjusted Data in Calculating Fission-Product Decay Energies and Spectra. |
ADJMOM
|
Abstract
|
C00212 I3675 00 |
Adjoint Moments Method Gamma-Ray Transport Code System. |
ADLER III |
Abstract
|
P00058 I0360 00 |
A Program to Calculate Cross Sections from Adler-Adler Resonance Parameters. |
ADO
|
Abstract
|
C00189 I3675 00 |
Aerojet Discrete Ordinates Calculational System. |
AGDATA |
Abstract
|
D00127 I0360 00 |
Two Agricultural Production Data Libraries (AGDATC and AGDATG) for Dose and Risk Assessment Models. |
AIR DATA |
Abstract
|
D00014 I0360 00 |
Sample Input to ANISN for Calculation of Neutron and Secondary Gamma-Ray Transport in Air. |
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. |
AIRFEWG |
Abstract
|
D00049 I0360 00 |
Results of ANISN Multigroup Calculations of Gamma-Ray, Neutron, and Secondary Gamma-Ray Transport in Infinite Homogeneous Air Using DLC-31/(DPL-1/FEWG1) Cross Sections. |
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. |
ALARM-B2 |
Abstract
|
P00218 I0360 00 |
A Computer Code System for Analysis of a Large Break LOCA of a BWR. |
ALBEDO-DATA |
Abstract
|
D00224 MNYCP 00 |
KSU Neutron Albedo Data. |
ALBEMO
|
Abstract
|
C00268 C6600 00 |
Albedo Monte Carlo Code System. |
ALDOSE
|
Abstract
|
C00577 IBMPC 00 |
Dose Calculation for Alpha Disc Source. |
ALEPH-LIB-JEFF3.1 |
Abstract
|
D00230 MNYCP 00 |
ACE Format Neutron Cross Section Library based on JEFF3.1. |
ALGAM-97
|
Abstract
|
C00152 I3675 00 |
Monte Carlo Estimation of Internal Dose from Gamma-Ray Sources in a Phantom Man. |
ALICE-2008 |
Abstract
|
P00550 PC586 00 |
Statistical Model Code System to Calculate Particle Spectra from HMS Precompound Nucleus Decay. |
ALKASYS-PC
|
Abstract
|
C00558 IBMPC 00 |
A Computer Program For Studies of Rankine-Cycle Space Nuclear Power Systems. |
ALPHA-M |
Abstract
|
P00169 I0360 00 |
Least-Squares Resolution of Gamma-Ray Spectra in Environmental Samples. |
ALPHN
|
Abstract
|
C00612 IBMPC 00 |
Code System for Calculating (alpha,n) Neutron Production in Canisters of High-Level Waste. |
ALPS |
Abstract
|
P00144 F2307 00 |
Alpha Spectrum Analysis Code System. |
AMARA |
Abstract
|
P00079 I3675 00 |
Nuclear Data Adjustment Using Lagrange's Multipliers Method. |
AMC
|
Abstract
|
C00090 I3675 00 |
Monte Carlo Albedo Code for Neutron and Capture Gamma-Ray Distributions in Rectangular Concrete Ducts. |
AMPX 77 |
Abstract
|
P00315 CY000 00 |
Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B. |
AMPX-77 |
Abstract
|
P00315 ALLMF 01 |
Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B. |
AMPX01 |
Abstract
|
D00027 I3675 02 |
126-Group Coupled Neutron and Gamma-Ray Transport Cross-Section Data Generated by AMPX. |
AMUSE |
Abstract
|
P00028 C6600 00 |
Gamma-Ray Spectra Unfolding Code. |
ANA |
Abstract
|
P00356 IBMPC 00 |
Code System for Gamma-Ray Spectra Analyses. |
ANIPLO D50 |
Abstract
|
P00213 I0360 00 |
A Digital Computer Program for Plotting Results from Calculations with the Sn Computer Program ANISN. |
ANISN-ORNL
|
Abstract
|
C00254 MNYCP 02 |
One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering. |
ANISN-PC
|
Abstract
|
C00514 IBMPC 00 |
Multigroup One-Dimensional Discrete Ordinates Transport Code System with
Anisotropic Scattering. 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). |
ANL-BPB
| Abstract
|
M00004 MNYCP 00 |
Argonne National Laboratory Code Center: Benchmark Problem Book. |
ANS643 |
Abstract
|
D00129 IBMPC 02 |
ANS-6.4.3 Geometric Progression Gamma-Ray Buildup Factor Coefficients. |
ANSIFT |
Abstract
|
P00077 C6600 00 |
ANSI Standard Fortran Sifting Program. |
ANSIFT |
Abstract
|
P00077 I0360 00 |
ANSI Standard Fortran Sifting Program. |
ANSL-V |
Abstract
|
D00154 ALLCP 01 |
ENDF/B-V Based Multigroup Cross Section Libraries for Advanced Neutron Source (ANS) Reactor Studies. |
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. |
APPLE-2 |
Abstract
|
P00111 FM200 00 |
Plotter of Neutron and Gamma-Ray Spectra and Reaction Rates. |
APPLE-2 |
Abstract
|
P00111 I3081 00 |
Plotter of Neutron and Gamma-Ray Spectra and Reaction Rates. |
APSAI |
Abstract
|
P00065 I3691 00 |
Activity Calculations and Plotting of Neutron or Gamma-Ray Spectra Generated by Discrete Ordinates Code System ANISN. |
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. |
AREAD |
Abstract
|
P00088 I0360 00 |
Input Data Processor for Transport Codes. |
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. |
ATHENA_2D |
Abstract
|
P00431 MNYCP 00 |
Code System For Simulation Of Hypothetical Recriticality Accidents in a Thermal Neutron Spectrum. |
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. |
AUTOJOM-JOMREAD |
Abstract
|
P00008 C6600 00 |
Computer Programs to Generate or Check Coefficients for Quadratic Equations Describing 3D Geometries. |
AXMIX |
Abstract
|
P00075 CYXMP 00 |
ANISN Cross Section Code System. |
AXMIX |
Abstract
|
P00075 IRISC 01 |
ANISN Cross Section Code System. |
AXMIX-PC |
Abstract
|
P00297 IBMPC 00 |
ANISN Cross Section Mixing Code System. |
BABEL |
Abstract
|
D00104 I3033 00 |
Multi-Purpose Neutron and Gamma-Ray Cross Section Library for Fast Reactor Shielding Design. |
BALTORO
|
Abstract
|
C00479 C6600 00 |
Code for Coupling of Monte Carlo and Discrete Ordinates Radiation Transport Calculations. |
BARC-35 |
Abstract
|
D00124 IBMMF 00 |
35-Group Neutron Cross Sections and Resonance Self-Shielding Factors Generated in ISOTXS and BRKOXS Format from ENDF/B-IV Using MINX. |
BASACF |
Abstract
|
P00285 IBMPC 00 |
Bayesian Approach to Spectrum Adjustment with Covariance Filter. |
BAYES |
Abstract
|
P00205 DP010 00 |
User's Guide for A General-Purpose Computer Code System for Fitting a Functional Form to Experimental Data. |
BCG
|
Abstract
|
C00578 C0170 00 |
A Code For Calculating Pointwise Neutron Spectra and Criticality in Fast Reactor Cells. |
BEACON MOD3 |
Abstract
|
P00402 CDCMF 00 |
Code System for Thermal-Hydraulic Analysis of Nuclear Reactor Containments. |
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. |
BFR
USSO
|
Abstract
|
P00449 C0176 00 |
Code System for Common Cause Failure Data Analysis. |
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. |
BLOCKAGE V2.5R |
Abstract
|
P00377 IBMPC 00 |
Code System to Calculate Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in a BWR. |
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. |
BOB-7 SERIES |
Abstract
|
P00084 F2306 00 |
Theory and Use of Gamma-Ray Spectrum Analysis Codes for Ge(Li) Detectors. |
BOLD VENTURE IV
|
Abstract
|
C00459 I3033 00 |
A Reactor Analysis Code System. |
BON |
Abstract
|
P00173 I0360 00 |
A Code System for Unfolding Multisphere Spectrometer Neutron Measurements. |
BOT3P-5.2 |
Abstract
|
P00530 MNYCP 01 |
Code System for 2D and 3D Mesh Generation and Graphical Display of Geometry and Results for Radation Transport Codes. |
BPPC
|
Abstract
|
C00076 I7090 00 |
Proton Penetration Codes for Space Vehicles. |
BREESE-II |
Abstract
|
P00143 I3033 00 |
Auxiliary Routines for Implementing the Albedo Option in the MORSE Monte Carlo Code System. |
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. |
BRMSTK |
Abstract
|
P00044 C6600 00 |
CSEWG Integral Data Testing Shielding Experiment Code System. |
BRMSTK |
Abstract
|
P00044 I3691 00 |
CSEWG Integral Data Testing Shielding Experiment Code System. |
BSPRP2 |
Abstract
|
P00372 IRISC 00 |
Code System to Process DORT Boundary-Flux Files. |
BUCORST |
Abstract
|
P00339 PC386 00 |
A Code to Prepare Burnup-Dependent Multigroup Nuclear Reactor Source Terms. |
BUGLE-80 |
Abstract
|
D00075 PC386 01 |
Coupled 47 Neutron, 20 Gamma-Ray Group, P3, Cross Section Library for LWR Shielding Calculations by the ANS-6.1.2 Working Group on Multigroup Cross Sections. We recommend ENDF/B-VI derived data in DLC-185/BUGLE-96. |
BUGLE-80 |
Abstract
|
D00075 IBMPC 02 |
Coupled 47 Neutron, 20 Gamma-Ray Group, P3, Cross Section Library for LWR Shielding Calculations by the ANS-6.1.2 Working Group on Multigroup Cross Sections. We recommend ENDF/B-VI derived data in DLC-185/BUGLE-96. |
BUGLE-80 |
Abstract
|
D00075 IBMPC 03 |
Coupled 47 Neutron, 20 Gamma-Ray Group, P3, Cross Section Library for LWR Shielding Calculations by the ANS-6.1.2 Working Group on Multigroup Cross Sections. We recommend ENDF/B-VI derived data in DLC-185/BUGLE-96. |
BUGLE-96 |
Abstract
|
D00185 ALLCP 00 |
Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications. |
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. |
CAD |
Abstract
|
D00059 I0360 00 |
51 Neutron, 25 Gamma-Ray Group ALBEDO DATA Generated with DOT for Various Materials. |
CALENDF-2005 |
Abstract
|
P00539 MNYCP 00 |
Pointwise, Multigroup Neutron Cross-Sections and Probability Tables from ENDF/B Evaluations. |
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. |
CANDULIB-AECL |
Abstract
|
D00210 MNYCP 00 |
Burnup-Dependent ORIGEN-S Cross Section Libraries for CANDU Reactor Fuel Characterization. |
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. |
CARP-82 |
Abstract
|
P00131 I3033 00 |
Multigroup Albedo Data Using DOT Angular Flux Results. |
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. |
CASK |
Abstract
|
D00023 I3691 04 |
22 Neutron, 18 Gamma-Ray Group, P3, Cross Sections for Shipping Cask Analysis. |
CASK-81 |
Abstract
|
D00023 I0370 05 |
22 Neutron, 18 Gamma-Ray Group, P3, Cross Sections for Shipping Cask Analysis. |
CASK-81 |
Abstract
|
D00023 IBMPC 06 |
22 Neutron, 18 Gamma-Ray Group, P3, Cross Sections for Shipping Cask Analysis. |
CASKCODES |
Abstract
|
P00262 IBMPC 00 |
CAPSIZE, SCOPE, AND KWIKDOSE for Shipping Cask Optimization, Dose Calculation, Parameter Evaluation, and Shielding Requirements. |
CASTHY |
Abstract
|
P00316 F0230 00 |
Statistical Model Calculation for Neutron Cross Sections and Capture Gamma-Ray Spectra. |
CAVEAT
|
Abstract
|
C00169 I3675 00 |
General Purpose Monte Carlo Time-Dependent Radiation Transport Code in Complex Geometry. |
CCRMN |
Abstract
|
P00366 MNYCP 00 |
Monte Carlo Simulation of the Coupled Transport of Electrons and Photons. |
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. |
CEAR-PPU |
Abstract
|
P00528 PC586 00 |
Code System for Monte Carlo Simulation of Detector Pulse Pile Up. |
CECP-BWR |
Abstract
|
P00370 PC386 00 |
Estimating Boiling Water Reactor Decomissioning Costs. |
CECP-PWR |
Abstract
|
P00371 PC386 00 |
Estimating Pressurized Water Reactor Decomissioning Costs. |
CEM03.01 |
Abstract
|
P00532 MNYCP 00 |
Monte-Carlo Code System to Calculate Nuclear Reactions in the Framework of Improved Cascade-Exciton Model. |
CEMENT 1.02
USSO
|
Abstract
|
P00412 IBMPC 00 |
Computer Code System for the Estimation of Long-Term Performance of Cement-Based Materials. |
CEPXS/ONELD 1.0
|
Abstract
|
C00544 MNYCP 02 |
One-Dimensional Coupled Electron-Photon Multigroup Discrete Ordinates Code System. |
CERPI-CEREL |
Abstract
|
P00147 I0360 00 |
Code Systems for Automatic Analysis of Gamma-Ray Spectra Obtained with Ge(Li) Detectors. |
CGS 11.4 |
Abstract
|
P00243 MFMWS 03 |
Common Graphics System, Version 11.4. |
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. |
CHENDF 7.02 |
Abstract
|
P00333 MNYCP 05 |
Codes for Handling ENDF/B-V and ENDF/B-VI Data. |
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. |
CLAW-IV |
Abstract
|
D00036 I0360 02 |
Coupled 30 Neutron, 12 Gamma-Ray Group Cross Sections Based on ENDF/B-IV for Radiation Transport Calculations. |
CLAW-IV |
Abstract
|
D00036 I3033 03 |
Coupled 30 Neutron, 12 Gamma-Ray Group Cross Sections Based on ENDF/B-IV for Radiation Transport Calculations. |
CLEAR |
Abstract
|
D00042 I3691 00 |
126 Neutron, 36 Gamma-Ray Cross Sections in AMPX and CCCC Interface Formats for LMFBR Neutronics Calculations. |
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. |
COAG-II |
Abstract
|
P00070 I0360 00 |
Calculation of the Westcott Epithermal Index and the Westcott 2200 m/s Neutron Flux. |
COBB |
Abstract
|
D00016 I3675 01 |
123-Group Neutron Cross Section Data Generated from ENDF/B-II Data for Use in the XSDRN Discrete Ordinates Spectral Averaging Code. |
COBRA-EN |
Abstract
|
P00507 IBMPC 00 |
Code System for Thermal-Hydraulic Transient Analysis of Light Water Reactor Fuel Assemblies and Cores. |
COBRA-SFS CYCLE 3 |
Abstract
|
P00472 MNYCP 00 |
Code System for Thermal Hydraulic Analysis of Spent Fuel Casks. |
COBRA4I |
Abstract
|
P00419 MNYCP 00 |
Code Sytem to Calculate Rod-Bundle and Core Thermal-Hydraulics. |
CODAC (2) |
Abstract
|
P00073 I0360 00 |
For TIMOC 72, Monte Carlo Three-Dimensional Neutron Transport Code's Data Generator. |
COG 10
|
Abstract
|
C00724 MNYCP 00 |
Multiparticle Monte Carlo Code System for Shielding and Criticality Use. |
COGAP |
Abstract
|
P00375 MNYCP 01 |
Nuclear Power Plant Containment Hydrogen Control System Evaluation Code. |
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. |
COMAND |
Abstract
|
P00091 I0360 00 |
A Multigroup ANISN Cross Section Data Library Collapsing Code System. |
COMBINE-PC |
Abstract
|
P00286 IBMPC 00 |
Code System to Compute Neutron Spectra and ENDF/B Version 5 Based Multigroup Neutron Constants. |
COMIDA |
Abstract
|
P00343 MNYCP 00 |
Radionuclide Food Chain Model for Acute Fallout Deposition. |
COMMIX-1B
USSO
|
Abstract
|
P00393 DVX11 00 |
3-D Single-Phase Thermal Hydraulics |
COMMIX-1B
USSO
|
Abstract
|
P00393 I3033 00 |
3-D Single-Phase Thermal Hydraulics |
COMMIX-1C
USSO
|
Abstract
|
P00393 MNYCP 00 |
3-D Single-Phase Thermal Hydraulics |
COMNUC3B |
Abstract
|
P00302 CYXMP 00 |
A Compound Nucleus Analysis Program. |
COMPAR |
Abstract
|
P00240 C0170 00 |
Compares Multigroup Cross Sections Generated by NJOY, GROUPIE, FLANGE-II, ETOG-3 and XLACS. |
COMPARE-MOD1A |
Abstract
|
P00410 C7600 00 |
Transient Flow W/Sinks & Doors |
COMPARE-MOD1A |
Abstract
|
P00410 I3033 00 |
Code System to Calculate Transient Flow With Heat Sinks & Doors. |
COMPASS 1.0.0 |
Abstract
|
P00520 PC586 00 |
Computerization of MARSSIM for Planning and Assessing Site Surveys. |
COMPBRN3 |
Abstract
|
P00389 PC386 00 |
Code System for Modeling Compartment Fires. |
COMPLOT |
Abstract
|
P00259 IBMMF 00 |
Convert EXFOR Format Data to Computation Format and Plot Comparisons of EXFOR and ENDF/B Evaluated Data (Version 86-1). |
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. |
CONFOLD |
Abstract
|
P00053 C6600 00 |
Least-Structure Unfolding Code System for Measured Neutron and Gamma-Ray Spectra. |
CONFOLD |
Abstract
|
P00053 I0360 00 |
Least-Structure Unfolding Code System for Measured Neutron and Gamma-Ray Spectra. |
CONSTRIP V
|
Abstract
|
C00139 I3675 00 |
Vertical Barrier-Finite Source Plane Gamma-Ray Penetration Code System. |
CONTEMPT-LT28B
USSO
|
Abstract
|
P00387 C7600 00 |
Code System to Predict Containment Pressure-Temperature Response To a Loss-Of-Coolant Accident. |
CONTEMPT4 |
Abstract
|
P00397 MNYCP 00 |
Code System for PWR & BWR Multicompartment Containment Analysis, Versions MOD5 & MOD6. |
CONVERT |
Abstract
|
P00036 C6600 00 |
An IBM-to-CDC Program Conversion Code. |
COOL-C |
Abstract
|
P00017 I0360 00 |
Spectra Unfolding Codes. |
CORTES |
Abstract
|
P00404 I0360 00 |
Code System for Thermal & Mechanical Analysis of Tees. |
COVERV |
Abstract
|
D00077 I0360 01 |
Compilation of Multigroup Cross-section Covariance Matrices in COVERX Format for Several Important Materials (Generated from ENDF/B-V Data using PSR-093/PUFF2). |
COVERX |
Abstract
|
D00044 I0360 02 |
Compilation of Multigroup Cross-Section Covariance Matrices in COVERX Format for Several Important Materials. |
COVFILS |
Abstract
|
D00091 I0360 00 |
A 30-Group Covariance Library Based on ENDF/B-V. |
COVFILS-2 |
Abstract
|
D00137 ALLCP 00 |
Neutron Data and Covariances for Sensitivity and Uncertainty Analysis. |
CRAC2
|
Abstract
|
C00419 C0000 00 |
Code System for Calculating Reactor Accident Consequences. |
CRAC2
|
Abstract
|
C00419 I3033 00 |
Code System for Calculating Reactor Accident Consequences. |
CRECTJ5 |
Abstract
|
P00250 D0780 00 |
A Computer Program for Compilation of Evaluated Nuclear Data in ENDF/B Format. |
CRESO |
Abstract
|
P00184 I3081 00 |
Resonance Data-Handling Code System. |
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. |
CRRS |
Abstract
|
P00376 DALPU 01 |
Conference Room Reservation System. |
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. |
CTR DATA |
Abstract
|
D00028 I3675 01 |
73-Group P3 Coupled Neutron and Gamma-Ray Cross Sections for Fusion Reactor Calculations. |
CUPED |
Abstract
|
P00032 I3675 00 |
Scintillation Spectrometer Polyenergetic Gamma Photon Experimental Distributions Unfolding Code. |
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. |
D2O |
Abstract
|
P00398 PC486 00 |
Code System for Computing Thermodynamic and Transport Properties of D2O. |
DABL69 |
Abstract
|
D00130 I0360 01 |
Defense Nuclear Applications Broad-Group Library based on ENDF/B-V in ANISN Format. |
DACRIN
|
Abstract
|
C00273 U1100 00 |
Airborne Radionuclide Organ Dose Calculational System. |
DANCOFF-MC |
Abstract
|
P00509 MNYCP 00 |
Code System for Monte Carlo Calculation of Dancoff Factors in Irregular Geometries. |
DANCOFF3 |
Abstract
|
P00279 D8810 00 |
Calculates Dancoff Correction. |
DANTE |
Abstract
|
P00185 I0370 00 |
Unfolding Code System for Energy Spectra Evaluation for Dosimetry Purposes. |
DASH-FP
|
Abstract
|
C00366 C0000 00 |
A One-Dimensional Analytic-Numerical Solution to the Problem of Multicomponent Time-Dependent Diffusion of Fission Products. |
DASQHE |
Abstract
|
P00278 D8810 00 |
Calculates Dancoff Corrections Factors. |
DATINIT |
Abstract
|
P00258 DGMV1 00 |
Interactive Program To Access Photon Interaction Data. |
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. |
DDXLIB |
Abstract
|
D00123 FM380 01 |
125-Neutron Group Double Differential Cross Section Library. |
DECAYREM |
Abstract
|
D00030 I0360 02 |
Radioactive Decay Spectra in EXREM Format. |
DECDC 1.0 |
Abstract
|
D00213 MNYCP 00 |
Nucear Decay Data Files for Radiation Dosimetry Calculations. |
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. |
DENIS |
Abstract
|
P00082 I0360 00 |
Monte Carlo Simulation of the Capture and Detection of Neutrons with Large Liquid Scintillators. |
DEPLETOR |
Abstract
|
P00523 MNYCP 00 |
Code System to Provide Depletion Capability to the U.S. NRC PARCS Code |
DEPOSITION
FEDC
|
Abstract
|
P00420 IBMPC 00 |
Code System to Calculate Particle Penetration Through Aerosol Transport Lines. |
DETAN 95 |
Abstract
|
P00361 MNYCP 00 |
Code System to Calculate Spectrum-Averaged Cross Sections and Detector Responses in Neutron Spectra. |
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. |
DIFBAS |
Abstract
|
P00334 MNYCP 00 |
A Bayesian Approach to Unfolding a Neutron Spectrum from a Spectrum of Recoiled Protons. |
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. |
DIMEN |
Abstract
|
P00341 IBMPC 00 |
Code System for Isotope Identification by Gamma-Ray Analysis. |
DINT |
Abstract
|
P00049 C6600 00 |
Multigroup Coherent-Incoherent Cross Section Data Generator for Photon Transport Calculations. |
DINT |
Abstract
|
P00049 I0360 00 |
Multigroup Coherent-Incoherent Cross Section Data Generator for Photon Transport Calculations. |
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. |
DOMINO |
Abstract
|
P00064 I0360 00 |
A General Purpose Code System for Coupling Discrete Ordinates and Monte Carlo Radiation Transport Calculations. |
DOMINO-II |
Abstract
|
P00162 I3033 00 |
General Purpose Code System for Coupling DOT-IV Discrete Ordinates and Monte Carlo Radiation Transport Calculations. |
DOMUS |
Abstract
|
P00301 IPCXT 00 |
A Program for Decomposing A Two-Dimensional Spectrum. |
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. |
DOQDP |
Abstract
|
P00110 I0360 00 |
Discrete Ordinates Quadrature Generator. |
DORGLIB |
Abstract
|
P00181 I0360 00 |
An Interactive Program for Displaying Nuclide Decay and Generation Data Based on ORIGEN Data Library. |
DORIAN |
Abstract
|
P00425 IBMPC 00 |
Code System to Implement Bayes Method for Plant Aging Risk Analysis. |
DOSCOV |
Abstract
|
D00090 I0360 00 |
24-Group Covariance Data. |
DOSDAM77-81 |
Abstract
|
D00081 C6400 00 |
620 Group, SAND-II Formatted, Neutron Cross Sections Based on ENDF/B-IV and Other Sources for Spectral, Integral, and Damage Analyses. |
DOSDAM81-82 |
Abstract
|
D00097 C0000 00 |
Multigroup Cross Sections in SAND-II Format for Spectral, Integral, and Damage Analyses. |
DOSDAM84 |
Abstract
|
D00131 IBMMF 00 |
Multigroup Cross Sections in SAND-II Format for Spectral, Integral, and Damage Analyses. |
DOSDAT II-81 |
Abstract
|
D00079 I0370 00 |
Dose-Rate Conversion Factors for External Exposure to Photons and Electrons. |
DOSDAT-DOE |
Abstract
|
D00144 ALLMF 00 |
Dose-Rate Conversion Factors for External Exposure to Photons and Electrons. |
DOSDAT-DOE |
Abstract
|
D00144 IBMPC 01 |
Dose-Rate Conversion Factors for External Exposure to Photons and Electrons. |
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. |
DPL-400 GEDT1 |
Abstract
|
D00031 I0360 08 |
Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format. |
DPL-401 NEDT |
Abstract
|
D00031 I0360 09 |
Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format. |
DPL-402A/GPDT1 |
Abstract
|
D00031 I0360 10 |
Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format. |
DPL-402B/GPDT1 |
Abstract
|
D00031 I0360 11 |
Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format. |
DRAGON3.05D
|
Abstract
|
C00647 MNYWS 03 |
Lattice Cell Code System. |
DRALIST |
Abstract
|
D00080 ALLCP 00 |
Radioactive Decay Data for Application to Radiation Dosimetry and Radiological Assessments. |
DSNQUAD |
Abstract
|
P00251 IPCXT 00 |
Calculates Angular Quadrature Weights and Cosines. |
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. |
DUFOLD |
Abstract
|
P00042 I0360 00 |
Derivative Unfolding Code - Determination of Neutron Spectra from NE-213 Pulse Height Data. |
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. |
DWBA07/DWBB07 |
Abstract
|
P00338 MNYCP 01 |
Code System for Inelastic and Elastic Scattering with Nucleon-Nucleon Potential |
DWNWND
|
Abstract
|
C00383 DP010 00 |
Interactive Gaussian Plume Atmospheric Transport Model. |
DWUCK-CHUCK |
Abstract
|
P00546 MNYCP 00 |
Nuclear Model Code System for Distorted Wave Born Approximation and Coupled Channel Calculations. |
E-DEP-1
|
Abstract
|
C00275 D0VAX 00 |
Heavy Ion Energy Deposition Code System. |
E3LWR |
Abstract
|
D00098 C0000 00 |
45 Neutron, 16 Gamma-Ray and 15 Neutron, 5 Gamma-Ray Group LWR Cross Section Libraries Derived from EURLIB-III using the AGRUKO Optimized Collapsing Scheme. |
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. |
ECIS-06 |
Abstract
|
P00227 MNYCP 01 |
Code System to Solve the Coupled Differential Equations Arising in Nuclear Model Calculations. |
ECPL82 |
Abstract
|
D00106 ALLCP 00 |
Evaluated Charged-Particle Data Library. |
EDISTR |
Abstract
|
P00191 I3033 00 |
Prepares a Nuclear Decay Data Base for Internal Radiation Dosimetry Calculations. |
EDITOR |
Abstract
|
P00035 I0360 00 |
Alters Mode, Copies, Merges, Punches, Edits, or Adds to ENDF/B-Formatted Data on Tapes or Cards. |
|
