Conceptual Design of the Transformational Challenge Reactor

Betzler, Benjamin R.; Ade, Brian J.; Jain, Prashant; Wysocki, Aaron; Chesser, Phillip; Kirkland, William M.; Cetiner, Mustafa Sacit; Bergeron, A.; Heidet, Florent; Terrani, Kurt A.

doi:10.1080/00295639.2021.1996196

Cited by 12 publications

(5 citation statements)

References 30 publications

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“…Each hole is placed between two of the divaricate legs of the center coolant channel. The AM geometry studied in the current work is 1/6 th the size of the typical TCR fuel element prototype [ 17 ], [ 18 ]. The supplied geometry has a length of 203 mm and a diameter of 43.3 mm, making the piece the ideal size to establish a sliding fit with the experimental setup described in the next section.…”

Section: Test Geometriesmentioning

confidence: 99%

Effect of geometry on the evolution of DLOFC transients in high temperature helium loop

Sieh,

Bindra

2024

Progress in Nuclear Energy

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Section: Test Geometriesmentioning

confidence: 99%

Effect of geometry on the evolution of DLOFC transients in high temperature helium loop

Sieh,

Bindra

2024

Progress in Nuclear Energy

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“…In the field of nuclear engineering, numerous industry norms and standards prohibit the utilization of AM components. Consequently, a number of pressurized structure AM components, including miniature heat exchangers [ 21 , 22 ], storage tanks [ 23 , 24 ], and pump units [ 25 ], remain in the experimental phase. Nevertheless, in non-pressurized structures, AM technology has made significant advancements, with a particular focus on the production of fuel, cladding, and control components within the reactor core [ 26 , 27 , 28 ].…”

Section: Introductionmentioning

confidence: 99%

Microhardness and Tensile Strength Analysis of SS316L/CuCrZr Interface by Laser Powder Bed Fusion

Jin,

Hoo,

Jin

et al. 2024

Materials

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Metallic joints within tokamak devices necessitate high interface hardness and superior bonding properties. However, conventional manufacturing techniques, specifically the hot isostatic pressing (HIP) diffusion joining process, encounter challenges, including the degradation of the SS316L/CuCrZr interface and CuCrZr hardness. To address this, we explore the potential of laser powder bed fusion (LPBF) technology. To assess its viability, we fabricated 54 SS316L/CuCrZr samples and systematically investigated the impact of varied process parameters on the microhardness and tensile strength of the dissimilar metal interfaces. Through comprehensive analysis, integrating scanning electron microscopy (SEM) imagery, we elucidated the mechanisms underlying mechanical property alterations. Notably, within a laser volumetric energy density range of 60 J/mm3 to 90 J/mm3, we achieved elevated interface hardness (around 150 HV) and commendable bonding quality. Comparative analysis against traditional methods revealed a substantial enhancement of 30% to 40% in interface hardness with additive manufacturing, effectively mitigating CuCrZr hardness degradation.

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“…A more agile design approach that uses rapid prototyping to enable learning during the design and manufacture process before final product completion could reduce inherent risk and enable adaptability to changes in technologies and constraints [5,6]. For example, the Transformational Challenge Reactor (TCR) program sought to leverage recent advances in advanced manufacturing techniques such as additive manufacturing (AM) to develop a reactor with materials that ASME had already approved, such as SS316 [6,7]. The main goal of the TCR program was to design a reactor with enhanced passive safety controls and site-specific monitoring that could be easily manufactured, factory-assembled, and deployed to urban and remote locations [7,8].…”

Section: Introductionmentioning

confidence: 99%

“…For example, the Transformational Challenge Reactor (TCR) program sought to leverage recent advances in advanced manufacturing techniques such as additive manufacturing (AM) to develop a reactor with materials that ASME had already approved, such as SS316 [6,7]. The main goal of the TCR program was to design a reactor with enhanced passive safety controls and site-specific monitoring that could be easily manufactured, factory-assembled, and deployed to urban and remote locations [7,8]. Complex geometries could be identified, designed, and printed within 1 week and be ready for evaluation and testing [5,9].…”

Section: Introductionmentioning

confidence: 99%

Summary of Methodology for Mitigating Risks Associated with Licensing and Qualifying AM Nuclear Materials

Hyer¹,

Sweeney²,

Petrie³

2023

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The US Department of Energy's Advanced Materials and Manufacturing Technologies (AMMT) program focuses on accelerating the development, qualification, demonstration, and deployment of advanced materials and manufacturing technologies to enable reliable and economical nuclear energy. Laser powder bed fusion (LPBF) is one of the most popular additive manufacturing (AM) processes for fabricating components with intrinsically complex geometries. LPBF was extensively explored for nuclear applications under the previous Transformational Challenge Reactor program. Additionally, Oak Ridge National Laboratory developed and licensed the Peregrine software and larger digital platform that couples machine learning and in situ data collection during AM to detect anomalies and any evolved defects. The digital platform will be critical to (1) the qualification of AM components for nuclear applications that link location-specific data to macroscopic properties and (2) predict final component performance. Current in situ process monitoring tools are valuable for observing the formation of stochastic flaws, but additional data are needed to predict the resulting microstructures and associated material performance. Rapid cooling rates and large thermal gradients have caused large heterogeneities in the microstructure, which cause anisotropy in mechanical performance. The AMMT program is evaluating the best approaches for addressing these heterogeneities and their effect on component performance using a combination of multiscale modeling, enhanced in situ process monitoring, and highthroughput experimental testing. This report summarizes strategies for mitigating the risks associated with qualifying AM components, including developing new sensing capabilities for in situ process monitoring and characterizing melt pool solidification and residual stresses to inform multiscale modeling efforts.

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Conceptual Design of the Transformational Challenge Reactor

Cited by 12 publications

References 30 publications

Effect of geometry on the evolution of DLOFC transients in high temperature helium loop

Effect of geometry on the evolution of DLOFC transients in high temperature helium loop

Microhardness and Tensile Strength Analysis of SS316L/CuCrZr Interface by Laser Powder Bed Fusion

Summary of Methodology for Mitigating Risks Associated with Licensing and Qualifying AM Nuclear Materials

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