| 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. |