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| Packages with Subject: ISOTOPE GENERATION AND DECAY |
| Package Name | Abstract | RSICC Tapelist | Title |
| ACDOS3 | Abstract | C00442 C7600 00 | Calculation of Activities and Dose Rates Produced by Neutron Activation. |
| ACFA | Abstract | C00478 I3033 00 | A Versatile Activation Code for Coolant and Structural Materials. |
| ACT-ARA | Abstract | C00372 CYXMP 00 | Code System for the Calculation of Changes in Radiological Source Terms with Time. |
| ACTIV87 | Abstract | D00169 ALLCP 00 | Fast Neutron Activation Cross Section File. |
| AKTIV | Abstract | C00339 I0360 00 | An Evaluation of Activity, Afterheat and Biological Hazard Potential of Stainless Steel Structures in Fusion Reactor Blankets. |
| ANITA-2000 | Abstract | C00693 MNYCP 00 | Analysis of Neutron Induced Transmutation and Activation. |
| BISON-C | Abstract | C00659 MNYWS 00 | One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System. |
| BURP-2 | Abstract | C00237 C6600 00 | Calculation of Buildup and Decay of Radioactive Fission Products. |
| CACA-2 | Abstract | C00302 I0360 00 | Heavy Isotope and Fission-Product Concentration Calculation Code System. |
| CHAINS-PC | Abstract | C00604 IBMPC 00 | Code System to Compute Atom Density of Members of a Single Decay Chain. |
| CINDER 1.05 | Abstract | C00755 PC586 00 | Code System for Actinide Transmutation Calculations |
| 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. |
| DANTE | Abstract | P00185 I0370 00 | Unfolding Code System for Energy Spectra Evaluation for Dosimetry Purposes. |
| DCHAIN 1.3 | Abstract | C00640 MNYCP 01 | Code System for Radioactive Decay and Reaction Chain Calculations. |
| 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. |
| DEPLETOR | Abstract | P00523 MNYCP 00 | Code System to Provide Depletion Capability to the U.S. NRC PARCS Code |
| DIMEN | Abstract | P00341 IBMPC 00 | Code System for Isotope Identification by Gamma-Ray Analysis. |
| ELECSPEC | Abstract | D00100 DP010 00 | Electron Spectra from Decay of Fission Products. |
| EMERALD-NORMAL | Abstract | C00250 I0370 00 | Calculation of Activity Releases and Potential Doses from the Normal Operation of a Pressurized Water Reactor Plant. |
| 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. |
| FASTGRASS | Abstract | P00479 MNYCP 00 | Code System to Predict Fission Product Release in Ubase Fuels. |
| FDKR | Abstract | C00541 I4381 00 | Radioactivity and Dose Rate Calculation Code for Fission, Fusion and Hybrid Reactors. |
| 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. |
| FPGAM | Abstract | C00386 F2307 00 | Calculation of Fission-Product Gamma-Ray Spectra. |
| FPIP | Abstract | C00162 C6600 00 | Fission Product Inventory Code System. |
| FRCRL2 | Abstract | C00231 C6400 00 | Calculation of Fission-Product Release in Reactor Accident Analyses. |
| GAMIDENT | Abstract | P00154 C0000 00 | A Program to Aid in the Identification of Unknown Materials by Gamma-ray Spectroscopy. |
| GAMTAB | Abstract | D00032 I0360 00 | Radioactive-Decay Gamma-Rays Ordered by Energy and Nuclide. |
| GAMTOT78 | Abstract | D00109 CY00I 00 | Compilation of Radioactive Decay and Capture Gamma Rays. |
| GETOUT | Abstract | C00461 C0176 00 | A Computer Code System for Predicting One-Dimensional Radionuclide Decay Chain Transport through Geologic Media. |
| GIRAFFE | Abstract | P00304 I3033 00 | General Isotope Release Analysis For Failed Elements. |
| HARAD | Abstract | C00387 I0360 00 | Calculation of Daughter Concentrations in Air Following the Atmospheric Release of a Parent Radionuclide. |
| INAP | Abstract | C00235 U1108 00 | Improved Neutron Activation Prediction Code Systems. |
| INVENT | Abstract | C00540 D8810 00 | A Radionuclide Inventory and Hazard Index Code. |
| IONMIG | Abstract | C00526 ALLMF 00 | Code System for Radionuclide Migration Calculations. |
| ISOGEN II | Abstract | C00055 I3675 00 | Radioisotope Generator Code. |
| ISO-PC 2.1 | Abstract | C00636 IBMPC 01 | Kernel Integration Code System for General Purpose Isotope Shielding Analyses. |
| ITER-2 | Abstract | P00148 C0000 00 | Codes for Unfolding Activation Detector Data and Pulse Height Spectra. |
| LEAF | Abstract | C00312 C6600 00 | Fission Product Release Calculator-From a Reactor Containment Building for Arbitrary Radioactive Decay Chains. |
| LIONS | Abstract | C00247 I0360 00 | Calculation of Fission Product Inventory, Gamma-Ray Dose Rates and Gamma-Ray Doses by Kernel Integration. |
| MAGIK | Abstract | C00359 I0360 00 | A Monte Carlo Code System for Computing Induced Residual Activation Dose Rates. |
| MATADOR | Abstract | C00689 CDCMF 00 | Radionuclide Behavior in Containments. |
| NAC | Abstract | C00164 C0000 00 | Neutron Activation Analysis and Product Isotope Inventory Code System. |
| NAC | Abstract | C00164 IBMMF 00 | Neutron Activation Analysis and Product Isotope Inventory Code System. |
| NAC-PC | Abstract | C00164 IBMPC 00 | Neutron Activation Analysis and Product Isotope Inventory Code System. |
| NACT | Abstract | C00502 U1100 00 | Screening Program for Neutron Activation Products. |
| NAP | Abstract | C00101 I7090 00 | Multigroup Time-Dependent Neutron Activation Prediction Code. |
| NRCPAGE | Abstract | P00491 DVX11 00 | Code System to Detect Recurring Loss of Special Nuclear Materials. |
| NUCCON | Abstract | C00439 S7800 00 | A Code System for Calculation of Time-Dependent Nuclide Concentrations, Activity, Gamma-Ray Dose Rate and Biological Hazard Potential of Fusion Reactor Materials Due to Neutron Irradiation. |
| ORIGEN2.2 | Abstract | C00371 ALLCP 03 | Isotope Generation and Depletion Code - Matrix Exponential Method. |
| ORIP_XXI | Abstract | C00731 PC586 02 | Computer Programs for Isotope Transmutation Simulations. |
| ORYX-E | Abstract | D00038 I0360 00 | ORIGEN Yields and Cross Sections Nuclear Transmutation and Decay Data from ENDF/B-IV. |
| ORYX-E | Abstract | D00038 I0360 01 | ORIGEN Yields and Cross Sections Nuclear Transmutation and Decay Data from ENDF/B-IV. |
| OZMA | Abstract | C00406 I0370 00 | Calculation of Resonance Reaction Rates in Reactor Lattices Using Resonance Profile Tabulations. |
| PADLOC | Abstract | C00330 U0000 00 | A One-Dimensional, Time-Dependent Program for Calculating Coolant and Plateout Fission Product Concentrations in a Network of Pipes. |
| PATCH-7 | Abstract | C00243 C0074 00 | Three-Dimensional Kernel Integration Code-Explicit Single Scattering Option. |
| PEFPYD | Abstract | D00096 ALLMF 02 | Aggregate Fission-Product Decay Data Based on ENDF/B-IV and -V. |
| PICFEE | Abstract | C00175 I3675 00 | Fission Product Inventory Code System. |
| PREMOR | Abstract | C00369 I0360 00 | A Point Reactor Exposure Code System for Survey Nuclear Analysis of Power Plant Performance. |
| PURSE | Abstract | C00338 C6600 00 | A Plutonium Radiation Source Code System. |
| PWR-AXBUPRO-SNL | Abstract | D00201 MNYCP 00 | Axial Burnup Profile Database for Pressurized Water Reactors. |
| RACC | Abstract | C00388 CY000 00 | A Code System for Computing Radioactivity-Related Parameters for Fusion Reactor Systems. |
| RACC | Abstract | C00388 I3033 00 | A Code System for Computing Radioactivity-Related Parameters for Fusion Reactor Systems. |
| RACC-PULSE | Abstract | C00639 MNYWS 00 | RACC Code System for Computing Radioactivity-Related Parameters for Fusion Reactor Systems Modified for Pulsed/Intermittent Activation Analysis. |
| RAD 2 | Abstract | C00122 I7090 00 | Fission Product Radioactivities Calculation. |
| RADAC | Abstract | C00627 PC486 02 | Code System for Calculating Radioactive Decay and Accumulation of Decayed Products Using Integer-Array Arithmetic for Precise Evaluation of the Bateman Equations. |
| RASPA | Abstract | C00352 C7600 00 | A Code for the Calculation of Buildup and Decay of Fission Products and Actinides. |
| REAC*3 | Abstract | C00443 IBMPC 00 | Computer Code System for Activation and Transmutation. |
| REAC*3 | Abstract | C00443 MFMWS 00 | Computer Code System for Activation and Transmutation. |
| REST 1;2;3 | Abstract | C00225 I0360 00 | Fission Product Inventory Code System with Fission Product Escape Model. |
| RIBD-II | Abstract | C00137 C6600 00 | Radioisotope Buildup and Decay Code System. |
| RIBD-II | Abstract | C00137 I0360 00 | Radioisotope Buildup and Decay Code System. |
| RIBD-IRT | Abstract | C00382 U1100 00 | Radioisotope Buildup and Decay Code System. |
| RICECCC | Abstract | C00348 I0360 00 | A Reactor Nuclide Inventory Code for Calculating Actinides and Fission Products. |
| SAIPS | Abstract | P00203 E1040 00 | Information Processing System for Calculating Neutron Spectra from Measured Reaction Rates. |
| SAMPO-LRC | Abstract | P00186 C6600 00 | Gamma-Ray Spectrum Analysis Code. |
| SAND-II | Abstract | C00112 MNYCP 03 | Neutron Flux Spectra Determination by Multiple Foil Activation Method. |
| SCANS | Abstract | P00029 I3675 00 | Spectra Calculation from Activated Nuclide Sets. |
| SOSUM | Abstract | C00109 I3675 00 | Multigroup Beta and Gamma-Ray Energy Sources from Activities. |
| SPECTRA | Abstract | C00108 C0000 00 | Determination of Neutron Spectra from Activation. |
| SPECTRA | Abstract | C00108 C0073 00 | Determination of Neutron Spectra from Activation. |
| SPECTRA | Abstract | C00108 C3600 00 | Determination of Neutron Spectra from Activation. |
| THIDA-2 | Abstract | C00410 FM380 00 | Code System for the Calculation of Transmutation, Activation, Decay Heat and Dose Rate in Fusion Reactors. |
| TIBSO | Abstract | C00512 MNYCP 00 | Code System to Calculate Production and Migration of Radionuclides in Nuclear Reactor Systems. |
| TPASGAM 85 | Abstract | D00088 ALLCP 04 | Radioactive Decay Library of Gamma-Ray Energies, Branching Ratios, and Cross Sections. |
| WINDOWS | Abstract | P00136 I0360 00 | A Program for the Analysis of Spectral Data Foil Activation Measurements. |