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: LOCA
Package NameAbstractRSICC TapelistTitle
BEACON MOD3AbstractP00402 CDCMF 00Code System for Thermal-Hydraulic Analysis of Nuclear Reactor Containments.
BLOCKAGE V2.5RAbstractP00377 IBMPC 00Code System to Calculate Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in a BWR.
COMPARE-MOD1AAbstractP00410 C7600 00Code System to Calculate Transient Flow With Heat Sinks & Doors.
COMPARE-MOD1AAbstractP00410 I3033 00Code System to Calculate Transient Flow With Heat Sinks & Doors.
CONTEMPT4AbstractP00397 MNYCP 00Code System for PWR & BWR Multicompartment Containment Analysis.
CONTEMPT-LT28B
USSO		AbstractP00387 C7600 00Code System to Predict Containment Pressure-Temperature Response To a Loss-Of-Coolant Accident.
MARCH2AbstractP00473 CDCMF 00Code System to Model LWR Meltdown Accident Response.
MORECAAbstractP00411 PC386 00Computer Code System for Simulating Modular High-Temperature Gas Cooled Reactor Core Heatup.
MOXY-MOD32AbstractP00385 I0360 00BWR Core Heat Transfer Code System.
ORINC
USSO		AbstractP00439 I0360 00Code System for 1-D Implicit Heat Conduction Solution.
ORMDIN
USSO		AbstractP00399 I3033 002-D Nonlinear Inverse Heat Conduction.
PC-PRAISEAbstractP00391 IBMPC 00Code System for Analysis of Piping Reliability Including Seismic Events.
PELE-1CAbstractP00461 C7600 00Code System for Fluid-Structure Interaction Analysis.
PMK2-VVER440-REPORTSAbstractM00012 MNYCP 00Results of the Experiments Performed in the PMK-2 Facility for VVER Safety Studies.
REFLUXAbstractP00403 I3033 00Code System to Predict LWR Reflood Heat Transfer.
RELAP5/MOD1/029_EXE
810		AbstractP00423 C0176 01Reactor System Transient Code.
SARA 4.16AbstractP00484 IBMPC 00System Analysis and Risk Assessment System.
SCDAP/RELAP5/MOD3.3-EXE
810		AbstractP00581 MNYCP 01A Best-Estimate Transient Simulation of Light Water Reactor Coolant Systems During a Severe Accident.
SCORE-EVETAbstractP00442 C7600 00Code System for Three-Dimensional Hydraulic Reactor Core Analysis.
SCRELAAbstractP00408 SUN05 00Code System for Supercritical Water Cooled Reactor LOCA Analysis.
SIMMER II
USSO		AbstractC00691 MFMWS 00Code System for Two-Dinensional Sn-Neutronics and Fluid Dynamics.
THYDE-B1/MOD2AbstractP00553 FM200 00Computer Code for PWR LOCA Thermohydraulic Transient Analysis.
THYDE-P2AbstractP00554 FV100 00Computer Code for PWR LOCA Thermohydraulic Transient Analysis.
WREM-TOODEE2AbstractP00469 ALLMF 002-D Time-Dependent Fuel Element, Thermal Analysis Code System.
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The Radiation Safety Information Computational Center (RSICC) collects, analyzes, maintains, and distributes software in the areas of radiation transport and safety. RSICC resides in the Nuclear Energy and Fuel Cycle Division (NEFCD) at Oak Ridge National Laboratory.