Click on Package Name to get detailed information.
Click on Abstract to read the package abstract.
Click on RSICC Tapelist to view list of files distributed with package.
Note: RESTRICTIONS APPLY TO SOME PACKAGES -
810 -- US DOE 10CFR810 Jurisdiction
FEDC -- US Government Agencies and Their Contractors Only
OECD -- Restricted/See Abstract
RUGA -- Restricted Use Government Authorized
USSO -- US Distribution Only
USUNV -- US Universities Only
Packages with Keyword: ACTIVATION |
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. |
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. |
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. |
ANITA-4 | Abstract | C00606 MNYCP 01 | Analysis of Neutron Induced Transmutation and Activation. |
CARL 2.3 | Abstract | C00743 PC586 01 | Code System to Calculate Radiotoxicity, Activity, Dose and Decay Power Calculations for Spent Fuel. |
CINDER 1.05 | Abstract | C00755 PC586 00 | Code System for Actinide Transmutation Calculations |
COG11.1 | Abstract | C00829 MNYCP 00 | Multiparticle Monte Carlo Code System for Shielding and Criticality Use. |
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. |
FISPACT-II 5.0 | Abstract | C00836 MNYCP 03 | FISPACT-II 5.0 & TENDL-2019; TENDL-2017, -2015; ENDF/B-VIII.0, -VII.1; JENDL-4.0; JEFF-3.3, -3.2; CENDL-3.1; HEIR-0.1; HEAD-2009; and GEFY-6.1 libraries. |
FISPIN | Abstract | C00413 ICL00 00 | Nuclide Inventory Calculation System. |
INAP | Abstract | C00235 U1108 00 | Improved Neutron Activation Prediction Code Systems. |
MAGIK | Abstract | C00359 I0360 00 | A Monte Carlo Code System for Computing Induced Residual Activation Dose Rates. |
MENDL-2P | Abstract | D00207 MNYCP 00 | Proton Reaction Data Library for Nuclear Activation (Medium Energy Nuclear Data Library.) |
NAAPRO | Abstract | C00722 PC586 00 | Neutron Activation Analysis PRognosis and Optimization Code System. |
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. |
ORIP_XXI | Abstract | C00731 PC586 02 | Computer Programs for Isotope Transmutation Simulations. |
PADF-2007 | Abstract | D00259 PCX86 00 | Proton Activation Data File in ENDF-6 Format. |
PATCH-7 | Abstract | C00243 C0074 00 | Three-Dimensional Kernel Integration Code-Explicit Single Scattering Option. |
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. |
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. |
SHARDA | Abstract | C00521 C0740 00 | Sample Heat, Activity, Reactivity, and Dose Analysis for Safety Analysis of Irradiations in a Research Reactor. |
SOSUM | Abstract | C00109 I3675 00 | Multigroup Beta and Gamma-Ray Energy Sources from Activities. |
THIDA-2 | Abstract | C00410 FM380 00 | Code System for the Calculation of Transmutation, Activation, Decay Heat and Dose Rate in Fusion Reactors. |