Reactor Physics Considerations for Use of Yttrium Hydride Moderator

Ade, Brian J.; Betzler, Benjamin R.; Burns, Joseph R.; Chapman, Chris; Hu, Jianwei

doi:10.1080/00295639.2022.2035157

Cited by 9 publications

(2 citation statements)

References 29 publications

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“…This effect has been seen before in ZrH x in the Topaz reactor (Buden, 1993), and was predicted based on new thermal scattering laws for YH x in ENDF/B-VIII.0 (Zerkle and Holmes, 2017;Zerkle et al, 2021;Brown et al, 2018) and new experimental data on YH x scattering (Mehta, 2020;Mehta et al, 2022). The positive temperature coefficient of reactivity for YH x may have design implications for advanced reactors seeking to utilize this moderator (Ade et al, 2022).…”

Section: Hypatiamentioning

confidence: 57%

The National Criticality Experiments Research Center and its role in support of advanced reactor design

Thompson

Maldonado²,

Cutler³

et al. 2023

Front. Energy Res.

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The National Criticality Experiments Research Center (NCERC) located at the Nevada National Security Site (NNSS) in the Device Assembly Facility (DAF) and operated by Los Alamos National Laboratory (LANL) is the only general purpose critical experiments facility in the United States. Experiments from subcritical to critical and above prompt critical are carried out at NCERC on a regular basis. In recent years, NCERC has become more involved in experiments related to nuclear energy, including the Kilopower/KRUSTY demonstration and the recent Hypatia experiment. Multiple nuclear energy related projects are currently ongoing at NCERC. This paper discusses NCERC’s role in advanced reactor design and how that role may change in the future.

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Section: Hypatiamentioning

confidence: 57%

The National Criticality Experiments Research Center and its role in support of advanced reactor design

Thompson

Maldonado²,

Cutler³

et al. 2023

Front. Energy Res.

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show abstract

“…• Demonstrating an agile design process to leverage AM and rapidly converge on an optimized, advanced nuclear microreactor design [9][10][11][12][13][14][15] • Advancing new reactor materials such as an yttrium hydride moderator [16][17][18][19][20][21][22], AM 316 stainless steel (316SS) [23], AM silicon carbide (SiC) [24,25], and the novel integration of uranium nitride tristructural-isotropic fuel [26] densely packed in an AM SiC matrix [27] • Developing the digital platform necessary to certify and qualify AM materials for nuclear applications [28][29][30] • Integrating and embedding spatially distributed sensors within AM materials for nuclear applications [31][32][33][34] • Progressing toward semi-autonomous reactor operation [35,36] • Evaluating and understanding radiation effects on AM SiC [37,38], 316SS [39], and integral TCR fuel compacts [27,40] In fiscal year (FY) 2021, the TCR program priorities shifted away from a nuclear reactor demonstration, but the focus on advancing ceramic AM for nuclear applications and qualifying AM components remained. Eventually, the TCR program was merged into the AMMT program and focused on the broader adoption of AM for nuclear applications compliant with American Society of Mechanical Engineers (ASME) Nuclear Quality Assurance (NQA-1) standards.…”

Section: Introductionmentioning

confidence: 99%