Online Catalog
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810 -- US DOE 10CFR810 Jurisdiction
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OECD -- Restricted/See Abstract
RUGA -- Restricted Use Government Authorized
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Packages with Keyword: WASTE MANAGEMENT
Package NameAbstractRSICC TapelistTitle
ACT-ARAAbstractC00372 CYXMP 00Code System for the Calculation of Changes in Radiological Source Terms with Time.
ALPHNAbstractC00612 IBMPC 00Code System for Calculating (alpha,n) Neutron Production in Canisters of High-Level Waste.
AT123DAbstractC00417 I0360 00Analytical Transient One-, Two-, and Three-Dimensional Simulation of Waste Transport in an Aquifer System.
AbstractC00633 PC386 00Code System to Solve for Release and Transport of Contaminants through Saturated/Unsaturated Media.
CARL 2.3AbstractC00743 PC586 01Code System to Calculate Radiotoxicity, Activity, Dose and Decay Power Calculations for Spent Fuel.
AbstractP00412 IBMPC 00Computer Code System for the Estimation of Long-Term Performance of Cement-Based Materials.
COBRA-SFS VERSION 6.0AbstractP00614 MNYCP 02COBRA-SFS Version 6.0 for Thermal-Hydraulic Analysis of Multi-Assembly Spent Fuel Storage and Transportation Systems
DIFMODAbstractC00572 I3083 00A Computer Program To Calculate The Leaching of Radionuclides and the Corrosion of Cemented Waste Forms in Water or Brine.
DPCTAbstractC00580 CYXMP 00A Deterministic-Probabilistic Model For Contaminant Transport.
DUST-BNLAbstractC00634 PC386 00Disposal Unit Source Term by One-Dimensional, Transient, Finite-Difference, Subsurface Release and Transport of Contaminants.
FE3DGWAbstractC00531 D0780 00Code System for Finite-Element, Three-Dimensional Ground-Water Flow Analysis.
FEMWASTE/FEMWATERAbstractC00451 C7600 00A Finite-Element Model of Waste and Water Transport through Porous Saturated-Unsaturated Media.
FEMWASTE/FEMWATERAbstractC00451 PC386 00A Finite-Element Model of Waste and Water Transport through Porous Saturated-Unsaturated Media.
FEWA-FEMAAbstractC00477 I3033 00A Finite Element Model of Water and Other Material through Aquifers.
GETOUTAbstractC00461 C0176 00A Computer Code System for Predicting One-Dimensional Radionuclide Decay Chain Transport through Geologic Media.
HYACINTHAbstractC00294 I0360 00Fast Heavy Isotope Point Burnup and Decay Code System - Analytical Solution.
INTRUDE-ANSAbstractC00539 D8810 00A Repository Intrusion Risk Evaluation Code.
IONMIGAbstractC00526 ALLMF 00Code System for Radionuclide Migration Calculations.
MARINRADAbstractC00503 C1785 00Code System Model for Assessing the Consequences of Release of Radioactive Material into the Oceans.
MINTEQAbstractP00494 DVX11 00Code System to Model Aqueous Geochemical Equilibria.
NUTRANAbstractC00675 I0370 00Code System for Long-Term Repository Safety Analysis.
PAGANAbstractC00621 IBMPC 00Code System for Performance Assessment Ground-water Analysis for Low-level Nuclear Waste.
PART61AbstractC00499 IBMPC 01Low-Level Radioactive Waste Impacts Analysis System.
PREP/SPOPAbstractC00772 MNYCP 00Uncertainty and Sensitivity Analysis Monte Carlo Program and Input Preparation.
PRESTO-IIAbstractC00504 I0360 00Code System for Low-Level Waste Environmental Transport and Risk Assessment.
RABFIN PARTSAbstractC00668 IBMPC 00Code System for Calculating Gaseous Effluent Dose Parameters.
RADACAbstractC00627 PC486 02Code System for Calculating Radioactive Decay and Accumulation of Decayed Products Using Integer-Array Arithmetic for Precise Evaluation of the Bateman Equations.
RADSHIP-2AbstractC00523 FM200 00Code System To Analyze Radiological Impact From Radwaste Transportation.
AbstractC00623 IBMPC 02Radiological Risk Assessment Code System for Spent Nuclear Fuel Transportation.
SOURCES-4CAbstractC00661 MNYCP 04Code System for Calculating (alpha,n), Spontaneous Fission, and Delayed Neutron Sources and Spectra.
SWIFTAbstractC00679 C7600 00Code System to Calculate Waste-Isolation Flow and Transport.
AbstractC00686 MNYCP 00Code System to Calculate Waste-Isolation Flow and Transport.
WHATIF-AQAbstractC00561 B7800 00A Computer Program For Speciation Calculation.
The Radiation Safety Information Computational Center (RSICC) is a Department of Energy Specialized Information Analysis Center (SIAC) authorized to collect, analyze, maintain, and distribute computer software and data sets in the areas of radiation transport and safety. RSICC resides in the Reactor and Nuclear Systems Division (RNSD) at Oak Ridge National Laboratory.