NSUF 16-CINR-10584: Irradiation Performance Testing of Specimens Produced by Commercially Available Additive Manufacturing Techniques

The proposed project will collect first-ever irradiation performance data for stainless steel and Inconelspecimens produced using a range of commercially available additive manufacturing techniques.Commercial suppliers will produce a set of standardized tensile bar specimens using a representativerange of currently-available additive manufacturing techniques and parameters. The Colorado School ofMines will conduct pre-irradiation thermo-mechanical testing (tensile strength, yield strength, elasticmodulus, ductility, thermal conductivity and thermal diffusivity) and micro-structural characterization ofthe specimens at the University’s facilities. A subset of the tensile bar specimens will be irradiated to arange of fast neutron fluences at typical light water reactor temperatures (~600 K) in the Advanced TestReactor (ATR). Thermo-mechanical testing and micro-structural characterization of the irradiatedspecimens will be conducted at the Advanced Test Reactor National Scientific User Facility (ATRNSUF)post-irradiation examination facilities. The remaining un-irradiated specimens will be thermallyaged at the University and subjected to post-aging thermo-mechanical testing and micro-structuralcharacterization. In addition to the required progress and final reports, the project will produce twoarchival journal articles and two conference papers describing the results of the test campaign. Acomparison of the physical properties and microstructure of the irradiated specimens to those of the asfabricatedand thermally-aged specimens will provide insight into the viability of additively manufacturedparts for nuclear reactor applications, identify key areas of concerns for further technology developmentefforts, and provide data for future computational model development.

Additional Info

Field Value
Abstract The proposed project will collect first-ever irradiation performance data for stainless steel and Inconelspecimens produced using a range of commercially available additive manufacturing techniques.Commercial suppliers will produce a set of standardized tensile bar specimens using a representativerange of currently-available additive manufacturing techniques and parameters. The Colorado School ofMines will conduct pre-irradiation thermo-mechanical testing (tensile strength, yield strength, elasticmodulus, ductility, thermal conductivity and thermal diffusivity) and micro-structural characterization ofthe specimens at the University’s facilities. A subset of the tensile bar specimens will be irradiated to arange of fast neutron fluences at typical light water reactor temperatures (~600 K) in the Advanced TestReactor (ATR). Thermo-mechanical testing and micro-structural characterization of the irradiatedspecimens will be conducted at the Advanced Test Reactor National Scientific User Facility (ATRNSUF)post-irradiation examination facilities. The remaining un-irradiated specimens will be thermallyaged at the University and subjected to post-aging thermo-mechanical testing and micro-structuralcharacterization. In addition to the required progress and final reports, the project will produce twoarchival journal articles and two conference papers describing the results of the test campaign. Acomparison of the physical properties and microstructure of the irradiated specimens to those of the asfabricatedand thermally-aged specimens will provide insight into the viability of additively manufacturedparts for nuclear reactor applications, identify key areas of concerns for further technology developmentefforts, and provide data for future computational model development.
Award Announced Date 2019-12-17T00:00:00
Awarded Institution Center for Advanced Energy Studies
Facility Microscopy and Characterization Suite
Facility Tech Lead Yaqiao Wu
Irradiation Facility None
PI Jeffrey King
PI Email [email protected]
Project Type CINR
RTE Number 3039