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Topic Title: INSC Material Properties Database
Topic Summary: International Nuclear Safety Center, Argonne National Lab.
Created On: 2/8/2007 5:06 PM

 2/8/2007 5:06 PM

Cathy Rohrer

Posts: 584
Joined: 2/6/2007

This resource offers transport and mechanical property data for nuclear materials including fuel, cladding, absorber materials, structural materials, coolants, concretes. Material properties incorporated into this database are intended to meet the needs of analysts using computer codes and doing experiments for safety evaluation of the world's commercial nuclear reactors. The focus is on the materials used in light water reactors (LWRs) with initial emphasis on high-priority properties of materials unique to Soviet nuclear reactor designs and reactors in eastern-Europe and developing countries. A list of properties for each material and the phases to be considered are determined based on a needs assessment. The longer-term goal is to include data that will meet future needs such as materials used in evolutionary reactor designs, properties of extended burnup fuel, and possibly properties of mixed oxide fuels

CITATION: INSC Material Properties Database, International Nuclear Safety Center, Argonne National Lab. Last updated July 2004.

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