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: CONTAINMENT
Package Name	Abstract	RSICC Tapelist	Title
ART MOD2	Abstract	P00611 PCX86 00	Fission Product Migration in Primary System and Containment
COGAP	Abstract	P00375 MNYCP 01	Nuclear Power Plant Containment Hydrogen Control System Evaluation Code.
CONTEMPT4	Abstract	P00397 MNYCP 00	Code System for PWR & BWR Multicompartment Containment Analysis.
CONTEMPT-LT28B USSO	Abstract	P00387 C7600 00	Code System to Predict Containment Pressure-Temperature Response To a Loss-Of-Coolant Accident.
GRSAC	Abstract	C00774 PCX86 00	Graphite Reactor Severe Accident Code.
MARCH2	Abstract	P00473 CDCMF 00	Code System to Model LWR Meltdown Accident Response.
NAUA-MOD5 NAUA-MOD5/M	Abstract	P00556 MNYCP 00	Aerosols in Reactor Containment During Meltdown.
NONSAP-C	Abstract	P00458 C7600 00	Code System for Analysis of 3-D Reinforced Concrete Structures.
SOFIRE-2	Abstract	P00570 I0370 00	Containment Temperature and Pressure During Na Pool Fire, 1-Cell or 2 Cell.

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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.