Post-irradiation tensile properties of the first and second operational target modules at the Spallation Neutron Source

David A. McClintock, Bradley J. Vevera, Bernard W. Riemer, Franz X. Gallmeier, James W. Hyres, Phillip D. Ferguson

Research output: Contribution to journalArticlepeer-review

21 Scopus citations

Abstract

During neutron production the target module at the Spallation Neutron Source (SNS) is damaged by cavitation-induced erosion and the mechanical properties of the AISI 316L vessel material are altered by high-energy proton and neutron radiation. Recently the first and second operational target modules at the SNS reached the end of their useful lifetime, and disk shaped specimens were sampled from the beam entrance region of both targets. Tensile specimens ranging in dose from 3 to 7 displacements per atom (dpa) were fabricated from the disk specimens using wire electrical discharge machining and tested at room temperature. This paper presents the tensile properties of the irradiated 316L vessel material removed from the first and second operational SNS target modules. Results show an increase in tensile strength and decrease in elongation values similar to previous spallation irradiated 316L results. Abnormally large elongation, 57% total elongation, was observed in a specimen irradiated to 5.4 dpa and considerable scatter was observed in the uniform and total elongation data. One possible explanation for the abnormally large elongations and scatter observed in tensile test results is the so-called deformation wave phase transformation-induced plasticity effect. Microscopy characterization revealed the presence of large nonmetallic inclusions rich in Al, S, Ca, O, and Mg on the fracture surface, which may have also contributed to the scatter in the tensile elongation results. While all specimens exhibited radiation-induced hardening and a decrease in ductility, the predominate topographical morphology on all specimen fracture surfaces examined was ductile microvoid coalescence and all specimens experienced appreciable necking prior to fracture. These findings indicate that 316L retains sufficient ductility (10-20% total elongation) and fractures in a ductile manor after irradiation to approximately 6-7 dpa in the mixed proton/neutron radiation environment at the SNS.

Original languageEnglish
Pages (from-to)130-140
Number of pages11
JournalJournal of Nuclear Materials
Volume450
Issue number1-3
DOIs
StatePublished - Jul 2014

Funding

The authors would like to thank Justin Carmichael for assistance with figures presented in this paper. The SNS is sponsored by the Office of Science, U.S. Department of Energy, and managed by UT-Battelle, LLC for the U.S. Department of Energy under Contract DE-AC05-00OR22725.

FundersFunder number
U.S. Department of Energy
Office of Science
UT-BattelleDE-AC05-00OR22725

    Fingerprint

    Dive into the research topics of 'Post-irradiation tensile properties of the first and second operational target modules at the Spallation Neutron Source'. Together they form a unique fingerprint.

    Cite this