RSICC Catalog

Online Catalog

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: REACTOR ACCIDENT
Package Name	Abstract	RSICC Tapelist	Title
APUD 3.0	Abstract	C00637 IBMPC 00	Code System for Analyzing, Predicting Consequences of, and Guiding the Response to Nuclear Emergencies.
BWR-LTAS	Abstract	C00485 I3033 01	A Boiling Water Reactor Long-Term Accident Simulation Code.
CARNAC	Abstract	C00238 I3691 00	Calculation of Flux and Neutron Spectra in the Case of Criticality Accident.
COBRA-EN	Abstract	P00507 MNYCP 01	Thermal-Hydraulic Transient Analysis of Reactor Cores.
CRAC2	Abstract	C00419 C0000 00	Code System for Calculating Reactor Accident Consequences.
CRAC2	Abstract	C00419 I3033 00	Code System for Calculating Reactor Accident Consequences.
DOSE-SGTR	Abstract	C00624 IBMPC 00	Code System to Calculate the Integrated Iodine Release to the Environment During a Steam Generator Tube Rupture in a PWR.
ESDORA	Abstract	C00183 U1108 00	Fission Product Inventory and Gamma-Ray Dose Rate from a Radioactive Cloud System.
EXPRESS	Abstract	C00622 MNYCP 00	Exact Preparedness Supporting System.
FONTA	Abstract	C00423 S4044 00	Code System For Calculating Individual And Collective Doses From Reactor Accidents Using Pasquill's Plume Model.
FRCRL2	Abstract	C00231 C6400 00	Calculation of Fission-Product Release in Reactor Accident Analyses.
GRSAC	Abstract	C00774 PCX86 00	Graphite Reactor Severe Accident Code.
HAARM-3	Abstract	P00401 CDCMF 00	Aerosol Behavior Log-Normal Distribution Model.
HABIT 1.1	Abstract	C00665 IBMPC 01	Code System for Evaluation of Control Room Habitability.
HORN	Abstract	C00568 I3083 00	A Computer Code To Analyze The Gas-Phase Transport of Fission Products In Reactor Cooling System Under Severe Accidents.
HOTSPOT 3.0.2	Abstract	M00009 IBMPC 03	Health Physics Code System for Evaluating Accidents Involving Radioactive Materials.
IRDAM	Abstract	C00524 IPCXT 00	Interactive Rapid Dose Assessment Model.
MARCH2	Abstract	P00473 CDCMF 00	Code System to Model LWR Meltdown Accident Response.
MTR_PC 2.6	Abstract	C00674 PC386 00	Modular Code System for Neutronics, Thermalhydraulics and Shielding Calculations.
PFPL	Abstract	C00607 D0VAX 00	Puff-Plume Atmospheric Deposition Model.
PLUDOS	Abstract	C00313 I0360 00	Calculator of Ground Level External Gamma-Ray Dose from a Radioactive Plume.
PREST	Abstract	C00355 I0360 00	Calculator of Pressure and Temperature Transient in Containment Studies.
RACER	Abstract	C00174 U1108 00	Calculation of Potential External Dose from Airborne Fission Products Following Postulated Reactor Accident.
RADOS	Abstract	C00088 I3675 00	Gamma-Ray Dose Estimation from Cloud of Radioactive Gases by Kernel Integration.
RADTRAD 3.03	Abstract	C00800 IBMPC 00	A Simplified Model for RADionuclide Transport and Removal And Dose Estimation.
RADTRAD 3.03-EXE	Abstract	C00800 IBMPC 01	A Simplified Model for RADionuclide Transport and Removal And Dose Estimation.
RASCAL 4.3	Abstract	C00783 PCX86 02	Radiological Assessment for Consequence Analysis.
RETRAC	Abstract	C00635 D0VAX 00	Code System for the Analysis of Material Test Reactor (MTR) Cores.
RRR	Abstract	C00196 I0360 00	Radiation Transport in Air-Analysis of Routine Releases of Short-Lived Radioactive Nuclides.
SACHET	Abstract	C00571 D8810 00	A Computer Program To Evaluate The Dynamic Fission Product Inventories in the Multiple Compartment System of PWR's.
SLIDERULE 1.0	Abstract	C00704 PC586 01	Nuclear Criticality Slide Rule.
SMART	Abstract	C00602 ALLCP 00	Code System for Calculating Early Offsite Consequences from Nuclear Reactor Accidents.
SPEEDI	Abstract	C00507 FM180 00	Code System for Real-Time Prediction of Radiation Dose to the Public Due to an Accidental Release from a Nuclear Power Plant.
SUBDOSA-II	Abstract	C00270 U1100 00	Calculation of External Gamma-Ray and Beta-Ray Doses from Accidental Atmospheric Releases of Radionuclides.
TACT-III	Abstract	C00447 I3033 00	Calculation of the Transport of Radioactivity from a Reactor Core.
TORAC	Abstract	P00459 C0170 00	Code System to Calculate Tornado-Induced Flow Material Transport.
WRAITH	Abstract	C00427 U1100 00	Code System for Calculating Internal and External Doses Resulting from an Atmospheric Release of Radioactive Material.

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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.