Abstract
Additive manufacturing (AM) is viewed as a critical enabling technology for achieving superior performance and improved economics across many sectors. Although the past decade has seen increased application of AM methods to nuclear reactor cladding and structural materials, exploration of AM as applied to the uranium-bearing nuclear fuel forms has been limited. The two major families of nuclear fuel forms (monolithic, particle/dispersion) are utilized with their own set of core objectives in mind, and their differences require distinct fabrication infrastructures. These reference fabrication methods impose many limitations on nuclear fuels. Both currently operating reactors and future concepts have the potential for improved performance if these accepted limitations are relaxed or removed entirely. The primary limitations of reference fabrication processes for the common nuclear fuel forms are outlined in this paper. This groundwork is then used to identify avenues of fuel performance specific to each of these fuel architectures that could be exploited if the restrictions of conventional fuel fabrication are removed. Moreover, multiple targets for AM studies are laid out for each of the major nuclear fuel variants. Finally, key strategic components to guide research activities in AM of nuclear fuels are outlined, with an emphasis on use of modeling and simulation to motivate research aims and embrace of an accelerated testing methodology to screen and quality new fuel forms.
Original language | English |
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Article number | 104493 |
Journal | Progress in Nuclear Energy |
Volume | 155 |
DOIs | |
State | Published - Jan 2023 |
Funding
This manuscript has been authored by UT-Battelle LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ). This manuscript has been authored by UT-Battelle LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).This work was supported by the Transformational Challenge Reactor (TCR) and Advanced Materials and Manufacturing Technologies (AMMT) programs of the US DOE, Office of Nuclear Energy. The technical insights of Kurt Terrani, Ben Betzler, and may others involved with the TCR program are gratefully acknowledged. Paul Cantonwine, Jason Harp and Christian Petrie at ORNL performed a thorough review of the manuscript. The insights of Jacob Gorton regarding interpretation and comparison of fuel performance modeling data improved discussion. Finally, M. Dylan Richardson assisted with preparation of selected graphics. This work was supported by the Transformational Challenge Reactor ( TCR ) and Advanced Materials and Manufacturing Technologies ( AMMT ) programs of the US DOE, Office of Nuclear Energy. The technical insights of Kurt Terrani, Ben Betzler, and may others involved with the TCR program are gratefully acknowledged. Paul Cantonwine, Jason Harp and Christian Petrie at ORNL performed a thorough review of the manuscript. The insights of Jacob Gorton regarding interpretation and comparison of fuel performance modeling data improved discussion. Finally, M. Dylan Richardson assisted with preparation of selected graphics.
Funders | Funder number |
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AMMT | |
Advanced Materials and Manufacturing Technologies | |
DOE Public Access Plan | |
U.S. Department of Energy | |
Office of Nuclear Energy | |
UT-Battelle | DE-AC05-00OR22725 |
Keywords
- Accelerated qualification
- Additive manufacturing
- Nuclear fuel