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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: WASTE MANAGEMENT |
| Package Name | Abstract | RSICC Tapelist | Title |
| ACT-ARA | Abstract | C00372 CYXMP 00 | Code System for the Calculation of Changes in Radiological Source Terms with Time. |
| ALPHN | Abstract | C00612 IBMPC 00 | Code System for Calculating (alpha,n) Neutron Production in Canisters of High-Level Waste. |
| AT123D | Abstract | C00417 I0360 00 | Analytical Transient One-, Two-, and Three-Dimensional Simulation of Waste Transport in an Aquifer System. |
BLT-FEMWATER
USSO | Abstract | C00633 PC386 00 | Code System to Solve for Release and Transport of Contaminants through Saturated/Unsaturated Media. |
| CARL 2.3 | Abstract | C00743 PC586 01 | Code System to Calculate Radiotoxicity, Activity, Dose and Decay Power Calculations for Spent Fuel. |
CEMENT 1.02
USSO | Abstract | P00412 IBMPC 00 | Computer Code System for the Estimation of Long-Term Performance of Cement-Based Materials. |
| COBRA-SFS VERSION 6.3 | Abstract | P00614 MNYCP 03 | COBRA-SFS Thermal-Hydraulic Analysis of Multi-Assembly Spent Fuel Storage and Transportation Systems. |
| 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. |
| DPCT | Abstract | C00580 CYXMP 00 | A Deterministic-Probabilistic Model For Contaminant Transport. |
| DUST-BNL | Abstract | C00634 PC386 00 | Disposal Unit Source Term by One-Dimensional, Transient, Finite-Difference, Subsurface Release and Transport of Contaminants. |
| FE3DGW | Abstract | C00531 D0780 00 | Code System for Finite-Element, Three-Dimensional Ground-Water Flow Analysis. |
| FEMWASTE/FEMWATER | Abstract | C00451 C7600 00 | A Finite-Element Model of Waste and Water Transport through Porous Saturated-Unsaturated Media. |
| FEMWASTE/FEMWATER | Abstract | C00451 PC386 00 | A Finite-Element Model of Waste and Water Transport through Porous Saturated-Unsaturated Media. |
| FEWA-FEMA | Abstract | C00477 I3033 00 | A Finite Element Model of Water and Other Material through Aquifers. |
| GETOUT | Abstract | C00461 C0176 00 | A Computer Code System for Predicting One-Dimensional Radionuclide Decay Chain Transport through Geologic Media. |
| HYACINTH | Abstract | C00294 I0360 00 | Fast Heavy Isotope Point Burnup and Decay Code System - Analytical Solution. |
| INTRUDE-ANS | Abstract | C00539 D8810 00 | A Repository Intrusion Risk Evaluation Code. |
| IONMIG | Abstract | C00526 ALLMF 00 | Code System for Radionuclide Migration Calculations. |
| MARINRAD | Abstract | C00503 C1785 00 | Code System Model for Assessing the Consequences of Release of Radioactive Material into the Oceans. |
| MINTEQ | Abstract | P00494 DVX11 00 | Code System to Model Aqueous Geochemical Equilibria. |
| NUTRAN | Abstract | C00675 I0370 00 | Code System for Long-Term Repository Safety Analysis. |
| PAGAN | Abstract | C00621 IBMPC 00 | Code System for Performance Assessment Ground-water Analysis for Low-level Nuclear Waste. |
| PART61 | Abstract | C00499 IBMPC 01 | Low-Level Radioactive Waste Impacts Analysis System. |
| PREP/SPOP | Abstract | C00772 MNYCP 00 | Uncertainty and Sensitivity Analysis Monte Carlo Program and Input Preparation. |
| PRESTO-II | Abstract | C00504 I0360 00 | Code System for Low-Level Waste Environmental Transport and Risk Assessment. |
| RABFIN PARTS | Abstract | C00668 IBMPC 00 | Code System for Calculating Gaseous Effluent Dose Parameters. |
| 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. |
| RADSHIP-2 | Abstract | C00523 FM200 00 | Code System To Analyze Radiological Impact From Radwaste Transportation. |
RISKIND 2.0
FEDC | Abstract | C00623 IBMPC 02 | Radiological Risk Assessment Code System for Spent Nuclear Fuel Transportation. |
| SOURCES-4C | Abstract | C00661 MNYCP 04 | Code System for Calculating (alpha,n), Spontaneous Fission, and Delayed Neutron Sources and Spectra. |
| SWIFT | Abstract | C00679 C7600 00 | Code System to Calculate Waste-Isolation Flow and Transport. |
SWIFT2
USSO | Abstract | C00686 MNYCP 00 | Code System to Calculate Waste-Isolation Flow and Transport. |
| WHATIF-AQ | Abstract | C00561 B7800 00 | A Computer Program For Speciation Calculation. |