Assessing the viability of a new subsize tensile specimen geometry for evaluation of structural nuclear and additively manufactured materials

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Abstract

The use of subsize specimens in nuclear materials testing has been a subject of ongoing interest due to radiation safety concerns and resource conservation needs. It is also of interest in additive manufacturing (AM), also known as 3D-printing, as subsize specimens can more accurately represent the behavior of the small, intricate geometries often produced using AM. A novel, extremely small geometry, called the Subsize Teeny (SST) was recently developed and is of interest for implementation. Given its extraordinarily small size and the complexities associated with subsize specimen testing, adequate vetting of this geometry is necessary to ensure data quality. A variety of unirradiated nuclear structural materials were tested in the SST geometry and compared against the well-established SSJ3 geometry. In addition, two case studies implementing the SST as a screening geometry for AM materials were also conducted. The question of SST viability was found to be highly nuanced and will often be dependent on the context or application in question. It was determined, however, that the SST is a largely invalid geometry for exceptionally coarse-grained materials or in cases where the physical defect volume equals or exceeds 0.1 % or where the specimen machining parameters result in significant surface alterations. On the other hand, it was determined that the SST may be employed with confidence if the test material is nearly or totally free of physical defects, isotropic, demonstrates homogeneous plastic deformation, and possesses a fine-grained, nearly or totally homogeneous microstructure with at least twelve slip systems.

Original languageEnglish
Article number155831
JournalJournal of Nuclear Materials
Volume612
DOIs
StatePublished - Jun 2025

Funding

This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). Part of this work was supported by the DOE Office of Nuclear Energy Advanced Fuels Campaign (AFC) and the Advanced Materials and Manufacturing Technologies (AMMT) programs. Part of work was supported by Light Water Reactor Sustainability (LWRS) Program. The authors would like to thank Fred List III for the optical photographs of relevant additively manufactured components, as well as Jim Horenburg for metallography support. The authors would also like to acknowledge Ryan Duncan, Kyle Everett, and Daniel Fleming for miniature specimen machining efforts.

Keywords

  • Additive manufacturing
  • Grain size
  • Nuclear materials
  • Size effect
  • Subsize specimens
  • Tensile properties

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