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Technical Papers – Selected papers from Kilopower/KRUSTY special issue

Kilowatt Reactor Using Stirling TechnologY (KRUSTY) Component-Critical Experiments

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Pages S56-S67 | Received 02 Oct 2019, Accepted 24 Jan 2020, Published online: 04 Jun 2020

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Read on this site (7)

Kristin N. Stolte, Jeffrey A. Favorite, George E. McKenzie, Theresa E. Cutler, Jesson D. Hutchinson, Nicholas W. Thompson & Rene G. Sanchez. (2022) Benchmark of the Kilowatt Reactor Using Stirling TechnologY (KRUSTY) Component Critical Configurations. Nuclear Technology 208:4, pages 625-643.
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Jesson Hutchinson, Jennifer Alwin, Alexander McSpaden, William Myers, Michael Rising & Rene Sanchez. (2021) Criticality Experiments with Fast 235U and 239Pu Metal and Hydride Systems During the Manhattan Project. Nuclear Technology 207:sup1, pages S62-S80.
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Nicholas Thompson, Rene Sanchez, Joetta Goda, Kelsey Amundson, Theresa Cutler, Travis Grove, David Hayes, Jesson Hutchinson, Cole Kostelac, George McKenzie, Alexander McSpaden, William Myers & Jessie Walker. (2021) A New Era of Nuclear Criticality Experiments: The First 10 Years of Comet Operations at NCERC. Nuclear Science and Engineering 195:sup1, pages S17-S36.
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Vedant K. Mehta, Michael W. D. Cooper, Robert B. Wilkerson, Dan Kotlyar, Dasari V. Rao & Sven C. Vogel. (2021) Evaluation of Yttrium Hydride (δ-YH2-) Thermal Neutron Scattering Laws and Thermophysical Properties. Nuclear Science and Engineering 195:6, pages 563-577.
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David I. Poston, Marc A. Gibson, Rene G. Sanchez & Patrick R. McClure. (2020) Results of the KRUSTY Nuclear System Test. Nuclear Technology 206:sup1, pages S89-S117.
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David I. Poston, Marc A. Gibson, Patrick R. McClure & Rene G. Sanchez. (2020) Results of the KRUSTY Warm Critical Experiments. Nuclear Technology 206:sup1, pages S78-S88.
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David I. Poston, Marc A. Gibson, Thomas Godfroy & Patrick R. McClure. (2020) KRUSTY Reactor Design. Nuclear Technology 206:sup1, pages S13-S30.
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Articles from other publishers (12)

D.Y. Cui, X.X. Li, Y. Dai, Y. Zou, J.G. Chen & X.Z. Cai. (2024) Accident scenario analysis and control scheme design for a micro Molten Salt Reactor. Progress in Nuclear Energy 172, pages 105208.
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Ziang Guo, Limin Liu, Ziyin Liu & Hanyang Gu. (2024) Development and application of a transient analysis code for heat pipe cooled reactor systems. Nuclear Engineering and Design 419, pages 112979.
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Yun Qi, Daming Sun & Jie Zhang. (2023) Study on the thermoacoustic characteristics and acoustic matching of a 15 We free-piston Stirling generator. Applied Thermal Engineering 235, pages 121357.
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Ming-dong Hou, Xiang-wen Zhou, Zefan Yan, Malin Liu & Bing Liu. (2023) Molecular dynamics study of the irradiation damage accumulation in beryllium oxide at different temperatures. Materialia 30, pages 101830.
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Ming-dong Hou, Xiang-wen Zhou & Bing Liu. (2023) Stress corrosion phenomenon of BeO at room temperature and its mechanism: Experimental and molecular dynamics study. Materials Today Communications 35, pages 106385.
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Nicholas W. Thompson, Alexis Maldonado, Theresa E. Cutler, Holly R. Trellue, Kelsey M. Amundson, Venkateswara Rao Dasari, Joetta M. Goda, Travis J. Grove, David K. Hayes, Jesson D. Hutchinson, Hadyn M. Kistle, Cole M. Kostelac, Juliann R. Lamproe, Christopher Matthews, George McKenzie, Garrett E. McMath, Alexander T. McSpaden, Rene G. Sanchez, Kristin N. Stolte, Jessie L. Walker, Robert Weldon & Nicholas H. Whitman. (2023) The National Criticality Experiments Research Center and its role in support of advanced reactor design. Frontiers in Energy Research 10.
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Ming-dong Hou, Xiang-wen Zhou & Bing Liu. (2022) Beryllium oxide utilized in nuclear reactors: Part I: Application history, thermal properties, mechanical properties, corrosion behavior and fabrication methods. Nuclear Engineering and Technology 54:12, pages 4393-4411.
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D.Y. Cui, X.X. Li, Y. Dai, G. Hu, X.Z. Cai, Y. Zou & J.G. Chen. (2022) An improved core design of a 50 kWth heat pipe cooled micro Molten Salt Reactor (micro-MSR). Progress in Nuclear Energy 151, pages 104326.
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Vedant K. Mehta, Jerawan Armstrong, Dasari V. Rao & Dan Kotlyar. (2022) Capturing multiphysics effects in hydride moderated microreactors using MARM. Annals of Nuclear Energy 172, pages 109067.
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Yugao Ma, Minyun Liu, Biheng Xie, Wenbin Han, Xiaoming Chai, Shanfang Huang & Hongxing Yu. (2022) Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs. Journal of Nuclear Engineering and Radiation Science 8:2.
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Yuchuan Guo, Zilin Su, Zeguang Li & Kan Wang. (2022) The Super Thermal Conductivity Model for High-Temperature Heat Pipe Applied to Heat Pipe Cooled Reactor. Frontiers in Energy Research 10.
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David I. Poston. 2021. Encyclopedia of Nuclear Energy. Encyclopedia of Nuclear Energy 266 279 .