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: STRESS ANALYSIS
Package NameAbstractRSICC TapelistTitle
FEMAXI 6 VER.1AbstractP00536 IBMPC 00Code System for Light Water Reactor Fuel Analysis.
FLANGE-ORNLAbstractP00566 I0360 00Flanged Pipe Joint Stress Analysis, Internal Pressure, Moment Loads, Temperature.
GAPCON-THERMALAbstractP00499 C7600 00Code System to Calculate Fuel Steady State & Transient Behavior.
HASSANAbstractP00593 I0370 00Time-Dependent Temperature Distribution and Stress and Strain in HTR Fuel Pins.
STABA,STAGT,STEGT,STIG,STIGMAAbstractP00575 MNYCP 00Stress Analysis of Dragon HTR Graphite Structure.
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.