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Nuclear Technology Volume 206, 2020 - Issue sup1: Special issue on the Kilopower Project, Kilowatt Reactor Using Stirling TechnologY (KRUSTY) Test
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Technical Papers – Selected papers from Kilopower/KRUSTY special issue

Results of the KRUSTY Warm Critical Experiments

David I. Postona Los Alamos National Laboratory, Los Alamos, New Mexico87545Correspondence[email protected]
ORCID Iconhttps://orcid.org/0000-0001-7642-2929
ORCID Icon,
Marc A. Gibsonb NASA Glenn Research Center, Cleveland, Ohio44135
,
Patrick R. McClurea Los Alamos National Laboratory, Los Alamos, New Mexico87545
&
Rene G. Sancheza Los Alamos National Laboratory, Los Alamos, New Mexico87545
Pages S78-S88 | Received 18 Dec 2019, Accepted 04 Feb 2020, Published online: 04 Jun 2020

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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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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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David Hayes, Todd Bredeweg, Theresa Cutler, Joetta Goda, Travis Grove, Jesson Hutchinson, Juliann Lamproe, George McKenzie, Alexander McSpaden, William Myers, Rene Sanchez & Jessie Walker. (2021) A New Era of Nuclear Criticality Experiments: The First 10 Years of Flattop Operations at NCERC. Nuclear Science and Engineering 195:sup1, pages S37-S54.
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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, Thomas Godfroy & Patrick R. McClure. (2020) KRUSTY Reactor Design. Nuclear Technology 206:sup1, pages S13-S30.
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Patrick R. McClure, David I. Poston, Steven D. Clement, Louis Restrepo, Robert Miller & Manny Negrete. (2020) KRUSTY Experiment: Reactivity Insertion Accident Analysis. Nuclear Technology 206:sup1, pages S43-S55.
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Articles from other publishers (9)

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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Zeqin Zhang, Chenglong Wang, Kailun Guo, Suizheng Qiu, G.H. Su & Wenxi Tian. 2024. Nuclear Power Reactor Designs. Nuclear Power Reactor Designs 309 347 .
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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Yugao Ma, Ruicheng Zhong, Hongxing Yu, Shanfang Huang, Changqing Tian, Xiaoqiang He, Zeyu Ouyang, Jiusong Liu, Yu Liu & Xiaoming Chai. (2022) Startup analyses of a megawatt heat pipe cooled reactor. Progress in Nuclear Energy 153, pages 104405.
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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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YuChuan Guo, ZeGuang Li, Kan Wang & ZiLin Su. (2021) A transient multiphysics coupling method based on OpenFOAM for heat pipe cooled reactors. Science China Technological Sciences.
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Yugao Ma, Changqing Tian, Hongxing Yu, Ruicheng Zhong, Zhuohua Zhang, Shanfang Huang, Jian Deng, Xiaoming Chai & Yunjia Yang. (2021) Transient heat pipe failure accident analysis of a megawatt heat pipe cooled reactor. Progress in Nuclear Energy 140, pages 103904.
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David I. Poston. 2021. Encyclopedia of Nuclear Energy. Encyclopedia of Nuclear Energy 266 279 .

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