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: CONTAINMENT
Package NameAbstractRSICC TapelistTitle
ART MOD2AbstractP00611 PCX86 00Fission Product Migration in Primary System and Containment
COGAPAbstractP00375 MNYCP 01Nuclear Power Plant Containment Hydrogen Control System Evaluation Code.
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.
GRSACAbstractC00774 PCX86 00Graphite Reactor Severe Accident Code.
MARCH2AbstractP00473 CDCMF 00Code System to Model LWR Meltdown Accident Response.
NAUA-MOD5 NAUA-MOD5/MAbstractP00556 MNYCP 00Aerosols in Reactor Containment During Meltdown.
NONSAP-CAbstractP00458 C7600 00Code System for Analysis of 3-D Reinforced Concrete Structures.
SOFIRE-2AbstractP00570 I0370 00Containment Temperature and Pressure During Na Pool Fire, 1-Cell or 2 Cell.
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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.