Document Type

Technical Report

Publication Date



Stainless steel 316L, titanium alloy grade 7, and alloy C22 are currently under consideration as candidate materials for use in various components associated with the spent nuclear fuel package, which must be designed to withstand structural deformation caused by static, thermal, and handling loads. In addition, it has to maintain its integrity in case of accidents, where it may be subjected to high loads over a very short period of time. Mechanical characteristics of these three materials under dynamic loading are not well documented. This paper describes the procedures and results obtained from experiments performed over a range of slow and moderate strain rates in the range of 0.0001 sec"1 - 200 sec"1. An MTS servohydraulic system was used for the slower tests and an Instron/Dynatup instrumented drop weight impact machine was used for the faster experiments. Experiments were conducted at room temperature, 175 °F, and 350 °F. Results show that the yield strength, ultimate strength, failure strain, and percentage of area reduction depend on strain rate and temperature to varying degrees for all three candidate materials.


Alloys – Testing; Chromium alloys – Testing; Metallurgy; Molybdenum alloys – Testing; Nevada – Yucca Mountain; Radioactive waste canisters; Radioactive wastes – Storage; Stainless steel – Testing; Titanium alloys – Testing; Tungsten alloys – Testing


Environmental Sciences | Materials Science and Engineering | Metallurgy | Nuclear | Physics




Prepared for the U.S. DOE/UCCSN Cooperative Agreement
Number: DE-FC08-98NV12081
Task 24
Document ID: TR-02-007 Revision: 0
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