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Click on RSICC Tapelist to view list of files distributed with package.
Note: RESTRICTIONS APPLY TO SOME PACKAGES -
810 -- US DOE 10CFR810 Jurisdiction
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| Packages with Keyword: ISOTOPE INVENTORY |
| Package Name | Abstract | RSICC Tapelist | Title |
| AARE-V1.0 | Abstract | C00846 MNYCP 00 | Activation in Accelerator Radiation Environments |
| ACAB-2008 | Abstract | C00758 MNYCP 01 | Activation Abacus Inventory Code System for Nuclear Applications. |
| ACT-ARA | Abstract | C00372 CYXMP 00 | Code System for the Calculation of Changes in Radiological Source Terms with Time. |
| AISITE II | Abstract | C00286 I0360 00 | Reactor Siting Code 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. |
| ALPHN | Abstract | C00612 IBMPC 00 | Code System for Calculating (alpha,n) Neutron Production in Canisters of High-Level Waste. |
| ANITA-2000 | Abstract | C00693 MNYCP 00 | Analysis of Neutron Induced Transmutation and Activation. |
| ANITA-4 | Abstract | C00606 MNYCP 01 | Analysis of Neutron Induced Transmutation and Activation. |
| BISON 1.5 | Abstract | C00464 HM200 00 | One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System. |
| BISON-C | Abstract | C00659 MNYWS 00 | One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System. |
| CACA-2 | Abstract | C00302 I0360 00 | Heavy Isotope and Fission-Product Concentration Calculation Code System. |
| CARMEN SYSTEM | Abstract | C00487 U1110 00 | A Code System for Neutronics PWR Calculation by Diffusion Theory with Space-Dependent Feedback Effects. |
| 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 |
| 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. |
| DKR | Abstract | C00323 CY000 00 | A Radioactivity and Dose Rate Calculation Code System for Fusion Reactors. |
| FDKR | Abstract | C00541 I4381 00 | Radioactivity and Dose Rate Calculation Code for Fission, Fusion and Hybrid Reactors. |
| FISPIN | Abstract | C00413 ICL00 00 | Nuclide Inventory Calculation System. |
| HARAD | Abstract | C00387 I0360 00 | Calculation of Daughter Concentrations in Air Following the Atmospheric Release of a Parent Radionuclide. |
| HYACINTH | Abstract | C00294 I0360 00 | Fast Heavy Isotope Point Burnup and Decay Code System - Analytical Solution. |
| INAP | Abstract | C00235 U1108 00 | Improved Neutron Activation Prediction Code Systems. |
| INREM II | Abstract | C00392 I3033 00 | Computer Implementation of Recent Models for Estimating the Dose Equivalent to Organs of Man from an Inhaled or Ingested Radionuclide. |
| ISOGEN II | Abstract | C00055 I3675 00 | Radioisotope Generator Code. |
| KORIGEN | Abstract | C00457 I3033 00 | A Modification of the Isotope Generation and Depletion Code System ORIGEN. |
| 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. |
| MARMER | Abstract | C00579 D8350 00 | A Flexible Point-Kernel Shielding Code System. |
| MARMER | Abstract | C00579 PC486 00 | A Flexible Point-Kernel Shielding Code System. |
| MTR_PC 2.6 | Abstract | C00674 PC386 00 | Modular Code System for Neutronics, Thermalhydraulics and Shielding Calculations. |
| MYRA | Abstract | C00056 C0000 00 | Calculation of Shipping Costs and Cask Designs for Irradiated Fuel Elements. |
| MYRA | Abstract | C00056 I7090 00 | Calculation of Shipping Costs and Cask Designs for Irradiated Fuel Elements. |
| 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. |
| NAP | Abstract | C00101 I7090 00 | Multigroup Time-Dependent Neutron Activation Prediction Code. |
| ORIGEN2.2 | Abstract | C00371 ALLCP 03 | Isotope Generation and Depletion Code - Matrix Exponential Method. |
| ORIGEN-JENDL32 | Abstract | C00703 MNYWS 00 | Isotope Generation and Depletion Code - Matrix Exponential Method. |
| 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. |
| 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. |
| 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. |
| 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. |
| SANDOR | Abstract | C00364 C7600 00 | Isotope Generation and Depletion Code Matrix Exponential Method. |
| SOSUM | Abstract | C00109 I3675 00 | Multigroup Beta and Gamma-Ray Energy Sources from Activities. |
| SOURCES-4C | Abstract | C00661 MNYCP 04 | Code System for Calculating (alpha,n), Spontaneous Fission, and Delayed Neutron Sources and Spectra. |
| SRAC95 | Abstract | C00716 MNYWS 00 | Thermal Reactor Code System for Reactor Design and Analysis. |
| SWAT | Abstract | C00714 MNYCP 01 | Step-Wise Burnup Analysis Code System to Combine SRAC-95 Cell Calculation Code and ORIGEN2. |
| THIDA-2 | Abstract | C00410 FM380 00 | Code System for the Calculation of Transmutation, Activation, Decay Heat and Dose Rate in Fusion Reactors. |
| VESTA 2.1.5-AURORA 1.0 | Abstract | C00769 PCX86 01 | A Generic Monte Carlo Code and Depletion Module Interface. |